Facility: Oconee Scenario No.: Op-Test No.: 1 SRO OATC BOP · OP/1/A/1106/001 Encl 4.8 Crew...

Appendix D Scenario Outline Form ES D-1 ILT16-1 NRC Exam

Facility: Oconee Scenario No.: 1 Op-Test No.: 1 Examiners: ________________________ Operators: ________________________SRO

________________________ ________________________OATC

________________________ ________________________BOP

Initial Conditions: Reactor Power = 100%

Turnover:

SASS is in Manual

AMSAC/DSS is bypassed

‘C’ GWD tank release is in progress

Event No.

Malfunction No. Event Type*

Event Description

0a Override AMSAC/DSS Bypassed

0b Override SASS in Manual

1 N: BOP, SRO Place Voltage Regulator in Auto and Decrease VARs

2 Override I: BOP, SRO (SLC) 1RIA-37/38 Fail to Terminate GWR

3 MPS090 C: OATC, SRO 1HP-120 Fails Closed

4 Override C: BOP, SRO Failure of Unit 2 AS Controller

5 MCS004 I: OATC, SRO Controlling Narrow Range Tave Fails High

6 MPS020

MPS020D R: OATC, SRO (TS)

21 gpm Primary to Secondary Leak in 1B SG (Requires Manual Shutdown)

7 MPS020D M: ALL

Spurious Turbine Trip, 1B SGTR

One Stuck Control Rod

1HP-26 (1A HP Injection) Fails Closed

* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Required Operator Actions Form ES-D-2 ILT16-1 NRC Exam

of 52

Scenario 1

Event Summary

Event 1: When the crew takes the shift, the voltage regulator will be in manual and the crew

will be directed to reduce generator VARs to ≈ 150 MVARs with the voltage regulator in automatic

Event 2: A GWD tank release will be in progress when the crew takes the shift. 1RIA-37 counts will begin to increase and reach the RIA alarm setpoint. The GWD tank release will fail to terminate due to the RIA reaching the alarm setpoint which will require an operator to manually terminate the release. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 3: 1HP-120 will fail closed which will cause RCS makeup to be lost. Pressurizer level will begin to decrease and Letdown Storage Tank level will begin to increase. Once the crew responds to the event to stabilize RCS makeup and letdown, 1HP-120 will be repaired and the crew will place the valve back in automatic and restore normal operation.

Event 4: The Auxiliary Steam (AS) Header will be initially supplied by Unit 2. The AS controller on Unit 2 will fail to properly control AS Header pressure. The crew will be required to align AS from Unit 1 to supply the AS header.

Event 5: Controlling Tave will fail High causing ICS to insert control rods and increase feedwater flow. The crew should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to MANUAL and stabilize the plant before the reactor trips

Event 6: The unit will experience a SG tube leak of ≈ 21 gpm. The crew will enter the primary to secondary leakage AP which will require the crew to rapidly shutdown the unit with ICS in manual. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 7: Once Reactor power has been reduced > 10% and auxiliary power has been transferred to CT-1, the Main Turbine will experience a spurious trip which will cause the Reactor to trip. There will be one control rod that will not fully insert into the core which will require aligning the BWST to compensate for the stuck control rod. 1HP-26 will not open when trying to inject borated water into the RCS which will require opening 1HP-410. The SG tube leak will evolve into a SG tube rupture of ≈ 200 gpm. The crew will then be required to minimize SCM (lower RCS pressure) in order to reduce the tube leak size and minimize the release of radioactivity to the environment. The crew will then cooldown the RCS to a band of 525°F - 532°F and isolate the 1B SG.


of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 1 Page 1 of 1 Event Description: Place Voltage Regulator in Auto and Decrease VARs (N: BOP, SRO)

Time Position Applicant’s Actions or Behavior

SRO

SRO/BOP

OP/1/A/1106/001 Encl 4.8 Crew response:

SRO directs the BOP to reduce Generator MVARs to 150 ± 10 MVARs in accordance with OP/1/A/1106/001 Enclosure 4.8. OP/1/A/1106/001 Encl. 4.8 Rev 131

CAUTION

Do NOT exceed limits as shown on Enclosure 4.5 (Capability Curve).

NOTE

Minimum of 18.05 Generator kV must be maintained.

Operation with leading PF is acceptable.

2.1. Notify other online units of VAR change.

2.2. Select VARS on WATT/VAR TRANSFER Switch.

2.3. Ensure MVARS are indicated on MWATT/MVAR meter.

2.4. IF VOLTAGE REGULATOR MODE will be swapped between AUTO & MANUAL, notify System Operating Center (SOC) that VOLTAGE REGULATOR MODE will be swapped.

2.5. IF AUTO adjustment is required, perform the following:

NOTE

VOLTAGE REGULATOR MODE Ready Light (Amber light) should be ON.

CRD AC Power Fault ‘A’ and/or ‘B’ alarms along with CRD Global System Fault may be received during generator voltage changes.

2.5.1. Ensure VOLTAGE REGULATOR MODE in AUTO.

2.5.2. Use VOLTAGE ADJUST to slowly modify Generator voltage to increase/decrease MVARS.

2.6. IF MANUAL adjustment is required, perform the following: N/A

This event is complete when MVARs have been adjusted to 150 ± 10 MVARs, or when directed by the Lead Examiner.


of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 2 Page 1 of 5 Event Description: 1RIA-37/38 Fail to Terminate GWR (I: BOP, SRO) (SLC) Time Position Applicant’s Actions or Behavior

SRO/BOP

SRO/BOP

Plant response:

1SA-9/A-4 (GWD DISCH RADIATION INHIBIT)

1SA-8/B-9 (RM PROCESS MONITOR HIGH) 1SA-8/D-9 (RM REACTOR BUILDING PURGE DISCH RAD INHIBIT)

1SA-09/A-4

Crew response:

The BOP refers to Statalarm 1SA-9/A-4 (GWD DISCH RADIATION INHIBIT)

2. Automatic Action

2.1 IF high alarm is received, 1RIA-37 and/or 1RIA-38 will close valves 1GWD-4, 5, 6, and 7 and GWD-206, 207 and stop the WG Exhauster.

3. Manual Action

3.1 Ensure automatic action has taken place. (they have not)

3.2 Refer to OP/1-2/A/1104/18 (Gaseous Waste Disposal System) for direction on continuing or terminating release

1SA-08/B-9

Crew response:

The BOP refers to Statalarm 1SA-8/B-9 (RM PROCESS MONITOR HIGH) 2. Automatic Action

MONITOR DESCRIPTION AUTOMATIC FUNCTIONS

1RIA-37 Waste Gas Effluent Monitor

Closes valves 1GWD-4, -5, -6, -7, GWD-206, 207 if high setpoint is reached

Stop the W. G. Exhauster if high setpoint is reached

1RIA-38 Waste Gas Effluent Monitor

1RIA-45 Norm Vent Gas Stops RB Purge Fan and Mini-Fan if high setpoint is reached

Isolates RB Purge System if high setpoint is reached

This event is complete when GWD Tank C is isolated (GWD-206 closed) in Step 4.4, or as directed by the Lead Examiner.


of 52


SRO/BOP

SRO/BOP

ARG 1SA-08/B-9 Crew response:

3. Manual Action

3.1 Perform one of the following:

3.1.1 Determine radiation monitors in alarm

3.1.2 IF Radiation Monitoring data from the PMC System is NOT in service, refer to OP/1/A/1103/026, (Loss of Sorrento Radiation Monitor). (does NOT apply)

3.2 IF 1SA-08/B-10 (Process Monitor Fault) has occurred for the same nomtor, Go To ARG for 1SA-08/B-10 (Process Monitor Fault). (N/A)

3.3 IF 1RIA-40 alarms, Go To the appropriate procedure (N/A)

3.4 IF any of the following RIAs have valid alarms, Go To AP/1/A/1700/018 (Abnormal Release of Radioactivity) (page 8)

√ RIA

RIA-31

1RIA-35

1RIA-39

1RIA-41

1RIA-42

1RIA-45, 46

1RIA-49A

1RIA-50

Note: Steps 3.5 through 3.10 do NOT apply

3.11 IF 1RIA-37 OR 1RIA-38 alarms during GWD tank release, Go To OP/1-2/A/1104/018 (GWD System) for applicable guidance.

The BOP refers to Statalarm 1SA-9/A-4 (GWD DISCH RADIATION INHIBIT)

2. Automatic Action

2.1 IF high alarm is received, 1RIA-37 and/or 1RIA-38 will close valves 1GWD-4, 5, 6, and 7 and GWD-206, 207 and stop the WG Exhauster.

3. Manual Action

3.1 Ensure automatic action has taken place. (they have not)

3.2 Refer to OP/1-2/A/1104/18 (Gaseous Waste Disposal System) for direction on continuing or terminating release.

This event is complete when GWD Tank C is isolated (GWD-206 closed) in Step 4.4 of OP/1-2/A/1104/018, or as directed by the Lead Examiner.


of 52


SRO/BOP

OP/1-2/A/1104/018 Encl 4.9 Crew Response:

Booth Cue: When the BOP goes to secure the GWD tank release, FIRE TIMER 3 to initiate Event 3.

OP/1-2/A/1104/018 (GWD System) Encl 4.9 (GWD Tank Release) rev 077

Complete Encl. 4.9 of OP/1-2/A/1104/018 (GWD Tank Release)

3.19 IF AT ANY TIME desired to terminate release, perform the following:

3.19.1 Close GWR DISCHARGE FLOW CONTROL

3.19.2 Go To Section 4 (GWR Termination)

3.34 IF 1RIA-37 High Alarm is received, perform the following:

3.34.1 Close GWR DISCHARGE FLOW CONTROL (GWD-206)

3.34.2 Record maximum readings for the following in Narrative Log:

1RIA-37 ________ cpm

1RIA-38 ________ cpm

3.34.3 IF NOT desired to continue release, Go To Section 4 (GWR Termination).

3.34.4 Verify desired to continue GWD Tank release.

Note: It is NOT desired to continue GWD tank release.

3.35 IF 1RIA-38 High alarm is received, perform the following:

3.35.1 Close GWR DISCHARGE FLOW CONTROL (GWD-206)

3.35.2 Record maximum readings for the following in Narrative Log:

1RIA-37 ________ cpm

1RIA-38 ________ cpm

3.35.3 Go To Section 4 (GWR Termination) Section 4. GWR Termination:

4.1 Record “Stop GWR # _______” in Narrative Log

4.2 IF GWD Tank ‘A’ released, perform the following: (does not apply)

4.3 IF GWD Tank ‘B’ released, perform the following: (does not apply)



of 52


SRO/BOP

SRO

OP/1-2/A/1104/018 Encl 4.9 Crew Response:

Section 4. GWR Termination:

4.4 IF GWD Tank ‘C’ released, perform the following:

4.4.1 Isolate GWD Tank ‘C’ as follows:

Close GWD-204 (Tank 1C Discharge Block)

Close GWD-100 (Decay Tanks Discharge Header Block)

Place GWD-206 (C Interim GWD Tank Discharge) switch in CLOSED

4.4.2 Check GWD Tank ‘C’ for accumulation of water as follows:

Throttle open GWD-197

Throttle open GWD-198

4.4.3 WHEN no water passes through sight-glass, position the following:

Close GWD-197

Close GWD-198

4.5 IF GWD Tank ‘D’ released, perform the following: (does not apply)

4.6 Drain GWD Filters as follows:

Throttle LWD-242 (Waste Gas Absolute Filter Drain)

Throttle LWD-243 (Waste Gas Charcoal Filter Drain)

4.7 After one minute, perform the following:

Close LWD-242 (Waste Gas Absolute Filter Drain)

Close LWD-243 (Waste Gas Charcoal Filter Drain)

4.8 Perform purge on 1RIA-37 and 1RIA-38 per Enclosure 4.16 (1RIA-37 and 38 Purge).

SLC 16.11.3 (Radioactive Effluent Monitoring Instrumentation) Condition C One or more required gaseous effluent monitoring instrument

channels inoperable. Required Action: Enter the Condition referenced in Table 16.11.3-2 for the

function (Immediately)

Restore the instrument(s) to OPERABLE status (30 days) Condition I As required by Required Action C.1 in Table 16.11.3-2 Required Action: Suspend release of radioactive effluents (Immediately)



of 52


SRO/BOP

AP/1/A/1700/018 Crew Response:

The SRO will enter AP/1/A/1700/018 (Abnormal Release of Radioactivity) 4.1 Perform the following:

__ At the discretion of the CRS, make a PA announcement of the event including any necessary precautions to be observed

__ Notify the SM to reference the following:

RP/0/A/1000/001 (Emergency Classification) NSD-202 (Reportability) OMP 1-14 (Notifications)

4.2 GO TO appropriate sections for any monitors in High of Alert alarm:

√ Section Monitor

4G 1RIA-45 or 1RIA-46

AP/1/A/1700/018 Section 4G

1. IAAT 1RIA-45 or 1RIA-46 reaches the High set point, THEN ensure automatic actions occurred:

A. RB PURGE FAN secured

B. 1PR-2 closed

C. 1PR-3 closed

D. 1PR-4 closed

E. 1PR-5 closed

2. Verify monitor spike was caused by normal startup of RB Purge System

RNO: GO TO Step 4

4. Verify RB Equipment Hatch is closed

5. Notify RP of RIAs in alarm

6. Stop all station GWRs using in-progress procedures until RP has determined that release limits will maintain compliance with Tech Spec and SLC limits

7. WHEN conditions permit, THEN:

A. Notify appropriate personnel to continue GWRs as necessary

B. EXIT

Booth Cue: If asked, Unit 2 is busy and can NOT perform actions from AP/18.



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 3 Page 1 of 4 Event Description: 1HP-120 Fails Closed (C: OATC, SRO) Time Position Applicant’s Actions or Behavior

SRO/BOP

Booth Cue: If necessary, when the BOP goes to secure the GWD tank

release, FIRE TIMER 3 to initiate Event 3.

Plant Response:

RCS makeup flow goes to ≈ 8 – 10 gpm (HPI Warming Flow)

PZR level begins to decrease

LDST level begins to increase

Valve position demand for 1HP-120 will increase to the 100% demand value and valve position indication will indicate closed (green light)

1SA-02/ B-1 (HP LETDOWN TANK LEVEL HIGH/LOW) will illuminate after several minutes

Crew Response:

Examiner Note: If the 1HP-120 failure is recognized before the LDST Statalarm actuates, the SRO will make a direct entry into AP/14 (next page). Otherwise the crew may perform the ARG and OP below and enter AP/14 when the SRO determines the entry conditions are met.

ARG 1SA-02/B-1

The crew may refer to ARG 1SA-02/B-1 (HP LETDOWN TANK LEVEL HIGH/LOW) and perform the required actions. rev 033

3.1 Instrument Failed:

3.1.1 Compare alternate channels to verify alarm validity:

O1A1042 LDST LEVEL 1

O1A1043 LDST LEVEL 2

3.2 Verify LDST pressure does not exceed LDST level/pressure operability requirement per OP/0/A/1108/001 (Curves and General Information).

3.3 IF High Level alarm is received:

3.3.1 Bleed as required by OP/1/A/1103/004 (Soluble Poison Concentration Control).

This event is complete when Step 4.186 of AP/14 is complete, or as directed by the Lead Examiner.


of 52


SRO/OATC

OP/1/A/1103/004 Crew Response:

Examiner Note: The crew may perform Enclosure 4.8 as necessary to reduce inventory. Enclosure 4.6 is performed to makeup/batch.

OP/1/A/1103/004 Enclosure 4.8 (Reducing RCS Inventory) rev 105

2.1 Verify HPI System operating.

2.2 Ensure open 1CS-26 (LETDOWN TO RC BHUT).

2.3 Ensure open 1CS-41 (1A RC BHUT INLET).

2.4 Position 1HP-14 (LDST BYPASS) to “BLEED”.

2.5 WHEN desired LDST level achieved, position 1HP-14 to “NORMAL”.

Examiner Note: The crew may initiate EOP Encl 5.5 for RCS inventory

control due LDST level increase (page 42)

AP/1/A/1700/014

AP/1/A/1700/014 (Loss of Normal Makeup and/or RCP Seal Injection) rev 18

3.1 IAAT RCP seal injection flow is lost, AND Component Cooling is lost, THEN perform the following:

A. Trip the Rx

B. Stop all RCPs

C. Initiate AP/25 (SSF EOP)

3.2 IAAT loss of suction to operating HPI pumps is indicated:

Motor amps low or cycling

Discharge pressure low or cycling

Abnormal LDST level trend

THEN GO TO Step 3.3

RNO: GO TO Step 4.7

4.7 Announce AP entry using PA System

4.8 Verify any HPI pump operating



of 52


SRO/OATC


4.9 Verify RCP seal injection or HPI makeup line leak indicated by any of the following:

Report of line leak

Abnormal LDST level decrease

1RIA-32 (AUX BLDG GAS)

1RIA-45 (NORM VENT GAS)

RB RIAs in alarm

Abnormal RBNS level increase

Abnormal LAWT or HAWT level increase

RNO: GO TO Step 4.11

4.11 Verify RCP seal injection flow exists to any RCP

4.12 Verify 1HP-120 operable in AUTO

RNO: 1. Attempt to operate 1HP-120 in HAND (will NOT operate)

2. IF 1HP-120 fails to operate, THEN GO TO Step 4.176

4.176 Perform the following as necessary to maintain Pzr level > 200”

Close 1HP-6

Throttle 1HP-7

Throttle 1HP-26

4.177 Place 1HP-120 in HAND and close

4.178 Notify SPOC to investigate and repair 1HP-120

4.179 WHEN 1HP-120 is repaired, THEN slowly re-establish flow through 1HP-120

Booth Cue: Notify the crew as FIN-24 that 1HP-120 has been repaired



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 3 Page 4 of 4

Event Description: 1HP-120 Fails Closed (C: OATC, SRO)

Time Position Applicant’s Actions or Behavior

SRO/OATC


4.180 Place 1HP-120 in AUTO.

4.181 Close 1HP-26.

4.182 Verify 1HP-122 (RC VOLUME CONTROL BYPASS) throttled.


4.184 Verify 1HP-5 open.

Examiner Note: 1HP-6 may be open or closed based on the actions taken in Step 4.176.

4.185 Verify 1HP-6 open.

RNO: 1. Throttle 1HP-7 for ≈ 20 gpm letdown flow.

2. Open 1HP-6.

4.186 Adjust 1HP-7 for desired letdown

4.187 WHEN conditions permit, THEN EXIT this procedure.



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 4 Page 1 of 3 Event Description: Failure of Unit 2 AS Controller (C: BOP, SRO) Time Position Applicant’s Actions or Behavior

SRO/BOP

1SA-06/C-10 Plant Response:

1SA-06/C-10 (AS HDR PRESS LOW) will actuate

1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller will indicate AS pressure < 300 psig and decreasing

Crew Response:

Booth Cue: While the crew is referring to the ARG, call Unit 1 control room to notify them that Unit 2 AS Controller has failed and Unit 3 cannot take control. The SM is directing you as Unit 1 to take control of AS system pressure.

ARG 1SA-06/C-10

3.1 IF excessive steam flow exists, reduce AS load or locate and isolate leak.

3.2 Verify proper operation of MS/AS controller on Unit supplying Auxiliary Steam Header (U2). (not controlling properly)

3.3 IF necessary, transfer AS Header to another Unit per OP/1/A/1106/22 (Auxiliary Steam System).

3.4 IF necessary, start auxiliary boiler per OP/0/A/1106/04 (Aux Boiler)

OP/1/A/1106/022 Encl 4.2

OP/1/A/1106/022 Encl 4.2 rev 041

Initial Conditions

1.1 Verify Unit 1 in Mode 1 or 2.

1.2 Verify all conditions of SLC 16.10.9 will be met with Unit 1 supplying the Aux Steam Header.

Examiner Note: All conditions of SLC 16.10.9 are met

NOTE: If ICS is in Manual, supplying Aux Steam Header from MS has the potential to affect core reactivity by changing RCS temperature.

1.3 Verify Unit 1 ICS in "AUTO". (R.M.)

1.4 Verify Unit 1 has ≥ 100 EFPD Core burnup.

This event is complete when the Unit 1 AS controller is in AUTO and AS pressure is ≈ 300 psig, or when directed by the Lead Examiner.


of 52


SRO/BOP

OP/1/A/1106/022 Encl 4.2 Crew Response:

1.5 Notify Secondary chemist that the AS header will be transferred

________________________ _____

Person Notified Date

1.6 Review Limits and Precautions.

Procedure

2.1 IF AP/0/A/1700/025 (SSF EOP) NOT in progress, notify Unit 2 to reduce setpoint on AS controller.

Booth Cue: No actions from booth are required since pressure is below setpoint due to the failure. Notify the crew that Unit 2 has reduced the AS controller setpoint.

2.2 Ensure 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller in “MANUAL”.

2.3 Ensure closed 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS).

2.4 IF AP/0/A/1700/025 (SSF EOP) NOT in progress, verify Unit 2 has reduced setpoint on AS controller.

Booth Cue: No actions from booth are required since pressure is below setpoint due to the failure. Notify the crew that Unit 2 has reduced the AS controller setpoint.

2.5 Perform one of the following:

__ Open 1MS-24 (1A MS TO AS HDR)

__ Open 1MS-33 (1B MS TO AS HDR)

2.6 Manually throttle open 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) to increase Aux Steam Header pressure.

2.7 Continue to throttle 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) to increase Aux Steam Header pressure to ≈ 300 psig.


NOTE: 1MS-24 is preferred source of MS to AS.

NOTE: MS to Aux Steam flow should NOT exceed 240,000 lbm/hr on any single unit.


of 52


SRO/BOP


2.8 WHEN Aux Steam Header is ≈ 300 psig:

2.8.1 Compare 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller setpoint to Aux Steam Header pressure.

2.8.2 IF 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller setpoint matches AS header pressure, place 1MS-126 & 1MS-129 controller to “AUTO”.

2.8.3 IF 1MS-126 & 1MS-129 controller setpoint does NOT match AS header pressure, notify SPOC.

2.8.4 IF required, adjust 1MS-126 & 1MS-129 controller setpoint to ≈ 300 psig.

2.9 Shut down other sources of AS

IF required, shut down Aux Boiler per OP/0/A/1106/004

IF required, notify U2 CR to secure MS to AS per procedure

IF required, notify U3 CR to secure MS to AS per procedure

2.10 IF Aux Steam will remain being supplied from Unit 1, align Condensate Returns to Unit 1 per OP/0/A/1104/37 (Plant Heating).

Examiner Note: The SRO may announce that SLC 16.10.9 would apply to Unit 2 while Unit 2 is supplying the AS header. Also, the crew may announce that the TD EFDW pump is inoperable on AS only (Main Steam is still available so the pump is still operable).



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 5 Page 1 of 3 Event Description: Controlling NR Tave Fails High (I: OATC, SRO) Time Position Applicant’s Actions or Behavior

OATC

CT-1

BOP

SRO

Plant Response:

Controlling NR Tave digital display reads ≈ 587.1F

Controlling Tave Chessell display reads ≈ 587.1F

1SA-2/A12 ICS Tracking

1SA-2/C11 ICS Loss of OAC CTP Signal

Control Rods will insert and FDW flow will increase

RCS pressure will decrease

Crew Response:

When the Statalarms are received, the candidates should utilize the “Plant Transient Response” (PTR) process to stabilize the plant.

OATC should:

Communicate to the CRS the initial alarm (if applicable) followed by reactor power level and direction.

Place the appropriate ICS stations in manual (Diamond and both FDW Masters in this case) in manual if any of the following occur:

o NI power increasing above the pre-transient power level

o Failed instrument is diagnosed

o Invalid input exists and the CRS directs the ICS be placed in manual

Remain focused on reactor power level and FDW response during the transient

Note: The OATC will have to reduce FDW in order to stabilize power below the pre-transient level.

The BOP should:

Determine if a valid ICS runback exists and inform the CRS

Monitor plant response and verify operating limits NOT exceeded

If ICS is placed in Manual, remain focused on RCS pressure, SG outlet pressure and RCS inventory

The CRS should:

Refer to AP/28 (ICS Instrument Failures)

Ensure FIN-24 (SPOC) is contacted to repair the failed instrument.

This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.


of 52


SRO/OATC


AP/1/A/1700/028 (ICS Instrument Failures) rev 20

4.1 Provide control bands as required. (OMP 1-18 Att. I)

OMP 1-18 Attachment I:

1. Plant Conditions Stable or TPB ≤ Pre-transient Conditions

1.1 The following bands are to be established during manual control of plant conditions (as needed) but may be adjusted by the CRS if required

1.1.1 NI Power ± 1% not to exceed the pre-transient or allowable power. If at the pre-transient or allowable level, band is NI Power – 1%

1.1.2 Current Tave ± 2°F

1.1.3 Current SG Outlet Pressure ± 10 PSIG (N/A)

1.1.4 Delta Tc 0oF ± 2°F

4.2 Initiate notification of the following:

__ OSM to reference the following:

OMP 1-14 (Notifications)

Emergency Plan

__ STA

4.3 Verify a power transient ≥ 5% has occurred.

RNO: GO TO Step 4.5.

4.4 Notify Rx Engineering and discuss the need for a maneuvering plan.

4.5 Use the following, as necessary, to determine the applicable section from table in Step 4.6:

OAC alarm video

OAC display points

Control Board indications

SPOC assistance, as needed

4.6 GO TO the applicable section per the following table:

√ Section Failure

4A RCS Temperature



of 52


SRO/OATC

AP/1/A/1700/028 Section 4A Crew Response:

AP/1/A/1700/028 Section 4A (RCS Temperature Failure)

NOTE If Tave instrument circuit failed high, the following may have occurred

depending on initial ICS station status:

Unit to TRACK due to Rx Cross Limits

Control Rod insertion

Feedwater flow increase

If Tave instrument circuit failed low, the following may have occurred depending on initial ICS station status:


Control Rod withdrawal

Feedwater flow decrease

Feedwater re-ratio

1. Ensure the following in HAND:

__ 1A FDW MASTER

__ 1B FDW MASTER

2. Ensure DIAMOND in MANUAL.

3. Notify SPOC to perform the following:

__ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).

__ Investigate and repair the failed RCS temperature instrumentation.

4. PERFORM an instrumentation surveillance using applicable table in Encl 5.2 (ICS Instrument Surveillances) for the failed instrument. (next page)

5. Verify instrumentation surveillance in Encl 5.2 (ICS Instrument Surveillances was performed satisfactorily as written.

RNO: Initiate a Surveillance Evaluation in accordance with PT/1/A/0600/001 (Periodic Instrument Surveillance) and OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).

Examiner Note: Crew Brief opportunity.



of 52


of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 1 of 9 Event Description: 21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO) Time Position Applicant’s Actions or Behavior

SRO

AP/1/A/1700/031 Plant Response:

1SA-8/A-9 (RM AREA MONITOR RADIATION HIGH)

1SA-8/E-10 (N-16 RM PRIMARY TO SECONDARY TUBE LEAK)

1SA-8/D-10 (RM CSAE EXHAUST RADIATION HIGH)

1SA-8/B-9 (RM PROCESS MONITOR RADIATION HIGH)

1RIA-40 in alarm

1RIA 60 in alarm and indicating 20 gpm Crew Response:

SRO will enter AP/1/A/1700/031 (Primary To Secondary Leakage) AP/1/A/1700/031 (Primary to Secondary Leakage) rev 021

NOTE The total primary to secondary leak rate can be determined by the following means: OAC point O1P1599 (EST TOTAL PRI TO SEC LEAKRATE) if OAC

primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFF-GAS BLOWER operating).

Sum of 1RIA-59 and 1RIA-60 readings if both operable and reactor power > 40%.

Allowable leakage per Tech Spec 3.4.13 is 150 gpd through any one SG. Estimated SGTR leak rate formula:

Leak rate = ____ + ____ - ____ - ____ = ____ MU SI LD TSR Where: MU = Makeup Flow SI = Seal Inlet Hdr Flow LD = Letdown TSR = Total Seal Return Flow

If the EOP is NOT already in progress, entry will be directly to the SGTR tab. RIA-59 / 60 and RIA-16 / 17 on the unaffected SG may indicate up to 2% of the value of the detector on the affected SG due to radiation shine from the steam line carrying radioactive steam from the SG with the tube leak.

This event is complete when Reactor power has been reduced > 10% and auxiliaries have been transferred, or when directed by the Lead Examiner.


of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 2 of 9 Event Description: 21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO) Time Position Applicant's Actions or Behavior

SRO

OATC/BOP


4.1 IAAT primary to secondary leak rate is ≥ 25 gpm (≥ 36,000 gpd), THEN GO TO Unit 1 EOP.

4.2 IAAT either of the following exists for 1RIA-54:

__ is in High alarm

__ inoperable

THEN perform Steps 4.3 - 4.4.

RNO: GO TO Step 4,5




Emergency Plan

__ STA

NOTE 1RIA-59 and 1RIA-60 are considered inoperable below 40% power.

4.6 IAAT notified by Chemistry that 1RIA-40 is inoperable because the minimum detection limit is too high, AND 1RIA-59 or 1RIA-60 is inoperable, THEN perform Encl 5.9 (1RIA-40 Inoperable Due to Failure to Meet Minimum Detectable Limit).

4.7 IAAT primary to secondary leakage exceeds 30 gpd, THEN perform Steps 4.8 – 4.9.

[Pri-Sec leak rate ≈ 21 gpm] 4.8 Dispatch AO to reroute Unit 1 CSAE drains to the CST per

OP/1-2/A/1106/016 (Condenser Vacuum System).

4.9 Initiate Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination).(page 28)

4.10 IAAT tube leakage is large enough to be indicated by an increase in normal RC makeup flow or a decrease in Pzr level, THEN GO TO Step 4.86.

4.86 Verify OAC primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFFGAS BLOWER operating).



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 3 of 9 Event Description: 21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO) Time Position Applicant's Actions or Behavior

SRO

OATC/BOP


4.87 Determine primary to secondary leakage rate using OAC point O1P1599 (EST TOTAL PRI TO SEC LEAK RATE).

4.88 GO TO Step 4.93.

4.93 Initiate log readings from the following every 15 minutes in the Auto Log:

1RIA-16

1RIA-17

1RIA-40

1RIA-59 (when Rx power > 40 %)

1RIA-60 (when Rx power > 40 %)

4.94 Initiate a unit shutdown to meet requirements of Encl 5.1 (Unit Shutdown Requirements) using the following, as applicable:

AP/29 (Rapid Unit Shutdown) (Page 24)

OP/1/A/1102/004 (Operation at Power)

OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown)

Examiner Note: Focus Brief opportunity.

Examiner Note: Per Encl 5.1, if the leak rate is > 150 gpd, the requirement is to be < 50% in one hour and Mode 3 in three hours.

Booth Cue: If asked, Unit 2 will continue actions in AP/31 after the SRO enters AP/29

Booth Cue: If the crew chooses to use the OP to shut down the unit, call as the SM and direct the crew to use AP/29 to shut down the Reactor.

4.95 IAAT primary to secondary leakage increases, THEN modify shutdown as required by Encl 5.1 (Unit Shutdown Requirements).

4.96 Notify OSM to refer to Tech Spec. 3.10.1 Basis to determine SSF operability.



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 6 Page 4 of 9 Event Description: 21 gpm Primary to Secondary Leak in 1B SG (R: OATC, SRO)

Time Position Applicant's Actions or Behavior

SRO

OATC/BOP

SRO


4.97 Notify plant personnel, using the PA system, to stay clear of the affected MS line and the Powdex.

4.98 Notify Radwaste to stop all liquid releases in progress until sample results assures release rates within limits.

4.99 Stop all gaseous releases in progress until sample results assure release rates within limits.

4.100 IAAT all the following exist:

__ Primary to secondary leak rate < 100 gpd (< 0.0694 gpm)

__ 1RIA-40 inoperable

__ Rx Power ≤ 40 %

THEN notify RP and Primary Chemistry to sample CSAE off-gas and RCS every 4 hours.

4.101 Make up to the UST only as necessary to maintain UST level > 7.5’

4.102 Notify the following that a shutdown is in progress due to primary to secondary leakage:

__ RP

__ Primary Chemistry

__ Secondary Chemistry

4.103 Verify affected SG identified.

4.104 Verify entry into this procedure was due to one of the following:

__ Tube leakage large enough to be indicated by an increase in normal RC makeup flow or a decrease in Pzr level

__ Tritium sample indicating ≥75 gpd primary to secondary leak

TS 3.4.13 RCS OPERATIONAL LEAKAGE

Condition B due to Primary to Secondary LEAKAGE > 150 gpd

Required Action: Be in Mode 3 in 12 hours and Mode 5 in 36 hours

TS 3.4.9 Pressurizer

Condition A anytime Pressurizer exceeds 260” in Mode 1 or 2

Required Action: Restore level to within limits within 1 hour



of 52



AP/1/A/1700/029 Crew Response: AP/1/A/1700/029 Rapid Unit Shutdown rev 13

NOTE The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.

4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown)

(Page 26)

4.2 Announce AP entry using the PA system

4.3 IAAT both of the following apply:

__ It is desired to stop power decrease

__ CTP > 18 %

THEN perform Steps 4.4 - 4.7

RNO: GO TO Step 4.8

4.4 Verify ICS in AUTO

RNO: 1. Stop manual power reduction

2. GO TO Step 4.6

NOTE Due to the power decrease initiated in this AP, the current plant configuration must be compared to the normal plant configuration in OP/1/A/1102/004 (Operation at Power) power reduction enclosure. Equivalent steps performed by this AP should be signed off as intent met. Any steps NOT performed by this AP must be evaluated in preparation for power increase or continued shutdown.

4.6 Initiate OP/1/A/1102/004 (Operation at Power) power reduction

enclosure

4.7 WHEN conditions permit, THEN perform one of the following:

__ Depress MAXIMUM RUNBACK to resume power reduction

__ GO TO appropriate operating procedure for continued operation

4.8 Verify ICS in AUTO

RNO: 1. Initiate manual power reduction to desired power level

2. GO TO Step 4.10



of 52



SRO/BOP


4.10 Verify both Main FDW pumps running.

NOTE

1B Main FDW Pump is the preferred pump to be shutdown first.

To lower 1B Main FDW Pump suction flow, bias is adjusted counter-clockwise.

To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise.

4.11 Adjust bias for first Main FDW pump desired to be shutdown until Suction flow is ≈ 1 x 106 lbm/hr less than remaining Main FDW pump suction flow.

4.12 WHEN core thermal power is < 65% FP, THEN continue.

4.13 IAAT both Main FDW pumps running, AND both of the following exist:

__ 1B Main FDW Pump is first pump to be shut down

__ Any of the following alarms actuate and remain in alarm:

FWP B FLOW MINIMUM (1SA-16/A-3)

FWP B FLOW BELOW MIN (1SA-16/A-4)

THEN trip 1B Main FDW Pump.


__ 1A Main FDW Pump is first pump to be shut down


FWP A FLOW MINIMUM (1SA-16/A-1)

FWP A FLOW BELOW MIN (1SA-16/A-2)

THEN trip 1A Main FDW Pump.

4.15 Verify Turbine-Generator shutdown is required.

4.16 Start the TURBINE TURNING GEAR OIL PUMP.



of 52



BOP


4.17 Start 1A through 1E TURBINE BRNG OIL LIFT PUMPS.

4.18 Start the TURBINE MOTOR SUCTION PUMP.

4.19 IAAT both of the following apply: __ ICS in automatic __ NI power is ≤ 18% THEN deselect MAXIMUM RUNBACK.


4.21 WHEN NI power ≤ 18%, THEN depress turbine TRIP pushbutton.

4.22 Verify all TURBINE STOP VALVES closed.

AP/1/A/1700/029 Encl 5.1

AP/29 Enclosure 5.1 (Support Actions During Rapid Unit Shutdown)

1. Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid Unit Shutdown).

2. Start the following pumps:

__ 1A FDWP SEAL INJECTION PUMP

__ 1A FDWP AUXILIARY OIL PUMP

__ 1B FDWP AUXILIARY OIL PUMP

__ 1B FDWP SEAL INJECTION PUMP

3. WHEN CTP is ≤ 80%, THEN continue.

4. Stop 1E1 HTR DRN PUMP.

5. Place 1HD-254 switch to OPEN.



8. Verify Turbine-Generator shutdown is required.



of 52



SRO/BOP

AP/1/A/1700/029 Encl. 5.1 Crew Response:

9. Place the following transfer switches to MAN:

__ 1TA AUTO/MAN

__ 1TB AUTO/MAN

10. Close 1TA SU 6.9 KV FDR.

11. Verify 1TA NORMAL 6.9 KV FDR opens.

12. Close 1TB SU 6.9 KV FDR.

13. Verify 1TB NORMAL 6.9 KV FDR opens.


__ MFB1 AUTO/MAN

__ MFB2 AUTO/MAN

15. Close E11 MFB1 STARTUP FDR.

16. Verify N11 MFB1 NORMAL FDR opens.



19. Notify CR SRO that Unit auxiliaries have been transferred.

20. IAAT 1SSH-9 is NOT closed, AND CTP is ≤ 75%, THEN throttle 1SSH-9 to Maintain Steam Seal Header pressure 2.5 - 4.5 psig.

21. WHEN CTP ≤ 65%, THEN place the following in MANUAL and close:

__ 1FDW-53

__ 1FDW-65

22. IAAT load is ≤ 550 MWe, THEN perform Steps 23 - 24.

TS 3.10.1 STANDBY SHUTDOWN FACILITY

Conditions A-E are applicable due to Reactor power being < 85% which makes the SSF inoperable

Required Action: Restore SSF systems to OPERABLE status (7 days)



of 52



SRO/BOP

AP/1/A/1700/031 Encl. 5.2 Crew Response:

AP/31 Encl 5.2

1. Verify AS header being supplied by Unit 2 or 3

RNO: Initiate Encl 5.33 (Swapping Aux Steam Header to Another Unit) of the Unit 1 EOP

Examiner Note: The remaining steps in AP/31 Encl 5.2 are performed

outside the control room by an Auxiliary Operator so they were not included.

EOP Encl 5.33 (Swapping Aux Steam Header to Another Unit)

1. Notify Secondary Chemist of AS header transfer

2. Adjust 1MS-126 & 1MS-129 controller setpoint to ≈ 280 psig

3. Notify unit CR that will be supplying AS of Unit 1 header setpoint reduction

4. Notify unit CR that will be supplying AS to perform transfer per the appropriate AS system procedure

5. WHEN notified by other unit to secure MS to AS, THEN continue

6. Ensure 1MS-126 & 1MS-129 controller in MANUAL

7. Reduce 1MS-126 & 1MS-129 valve position demand to zero

8. Close 1MS-24

9. Close 1MS-33

10. EXIT this enclosure



of 52

Op-Test No.: ILT16-1 Scenario No.: 1 Event No.: 7 Page 1 of 12 Event Description: Spurious Turbine Trip, 1B SGTR (M: All)


SRO

OATC

BOP

Plant Response:

Reactor trips

1SA-8/B-9 RM Process Monitor Radiation High

1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH) Crew Response:

SRO will direct the OATC to perform IMAs and the BOP to perform a symptom check.

The SRO will declare Emergency Dose Limits in effect once the transfer to the SGTR tab is made.

IMAs

EOP Immediate Actions

3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress the turbine TRIP pushbutton

3.4 Verify all turbine stop valves closed.

3.5 Verify RCP seal injection available.

SYMPTOM CHECK

The BOP will verify the following:

Power Range NIs NOT < 5%

Power Range NIs NOT decreasing

Rule 1, ATWS/Unanticipated Nuclear Power Production

Any SCM < 0°F Rule 2, Loss Of SCM

Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW)

Rule 3, Loss of Main or Emerg FDW

Rule 4, Initiation of HPI Forced Cooling (Inability to feed SGs and > 2300 psig, NDT limit reached, or PZR level > 375")

Uncontrolled Main steam line(s) pressure decrease

Rule 5, Main Steam Line Break

CSAE Offgas alarms

Process monitor alarms (RIA-40, 59,60),

Area monitor alarms (RIA-16/17)

None (SGTR Tab is entered when identified SG Tube Leakage > 25 gpm)

This event is complete when the 1B SG is isolated, or when directed by the Lead Examiner.


of 52



Subsequent Actions Tab Crew Response:

Examiner Note: The crew may not recognize the SGTL has degraded into a SGTR initially so steps in the SA tab were included. When the crew recognizes the SGTR, they should transfer to the SGTR tab (Page 33) as directed by the Subsequent Actions, Parallel Action Page (Page 50).

4.1 Verify all control rods in Groups 1 – 7 fully inserted.

RNO: 1. Open:

__ 1HP-24

__ 1HP-25

2. Secure makeup to LDST

3. IF CRDs are energized, THEN:

A. Initiate regulating control rod insertion to the IN LIMIT

B. Dispatch one operator to open 600V CRD breakers:

__ 1X9-5C (U1 CRD NORM FDR BKR) (U1 Equip Rm)

__ 2X1-5B (U1 CRD ALT FDR BKR) (T3/Dd-28)

4.2 Verify Main FDW in operation.

4.3 Verify either:

__ Main FDW overfeeding causing excessive temperature decrease.

__ Main FDW underfeeding causing SG level decrease below setpoint.


4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8.


4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs)



of 52




4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating.

4.11 GO TO Step 4.14.

4.14 Verify both are closed:

__ 1MS-17

__ 1MS-26

4.15 Verify ES is required.

RNO: 1. Initiate Encl 5.5 (Pzr and LDST Level Control).(Page 42)

2. GO TO Step 4.17.

4.17 Open:

__ PCB 20

__ PCB 21

4.18 Verify Generator Field Breaker open.

4.19 Verify EXCITATION is OFF.

4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure ≥ 90 psig.

4.21 Verify ICS/NNI power available.

4.22 Verify all 4160V switchgear (1TC, 1TD & 1TE) energized.

4.23 Verify both SGs > 550 psig.

4.24 Verify Main FDW operating.

4.25 Verify any RCP operating.

4.26 Verify AP/0/A/1700/025 (SSF EOP) Encl (Unit 1 OATC Actions During Fire) in progress or complete.

RNO: Ensure SGs approaching 25″ - 35″ [55″ - 65″ acc] S/U level.



of 52




4.27 Place switches in CLOSE:

__ 1FDW-31

__ 1FDW-40

4.28 Verify SFP Cooling: {42}

__ SFP Cooling in service

__ SFP level normal

4.29 Verify all SCMs > 0°F.

4.30 Verify both SGs intentionally isolated to stop excessive heat transfer.


4.32 Verify heat transfer exists.

4.33 Verify primary to secondary heat transfer has been excessive.


4.35 Verify indications of SGTR ≥ 25 gpm.

4.36 GO TO SGTR tab.

Examiner Note: The crew should recognize that the SGTL has degraded to a SGTR at this point.



of 52



CT-2

SGTR Tab Crew Response:

1. Verify Rx tripped.

2. Maintain Pzr level 140″ - 180″ [175″ - 215″ acc] by initiating Encl 5.5 (Pzr and LDST Level Control). (Page 42)

Examiner Note: 1HP-26 has failed in the closed position.

3. Ensure Parallel Actions Page reviewed.

NOTE The remainder of this page may be given to an RO. The Procedure Director may continue.

4. Start:

__ A OUTSIDE AIR BOOSTER FAN

__ B OUTSIDE AIR BOOSTER FAN

5. Notify Unit 3 to start:

__ 3A OUTSIDE AIR BOOSTER FAN

__ 3B OUTSIDE AIR BOOSTER FAN

6. Perform the following:

A. Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.

B. Inform SRO of results.

7. Dispatch an operator to open:

__ 1XD-R3C (A Turb Bldg Sump Pump Bkr) (T-1, G-27)

__ 1XE-R3D (B Turb Bldg Sump Pump Bkr) (T-1, J-27)

8. Notify RP to survey both MS lines for radiation.

9. GO TO Step 28.

28. Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector, etc.).

29. Verify Main FDW or EFDW controlling properly.

30. Open:

__ 1HP-24

__ 1HP-25



of 52




31. Secure makeup to LDST.

32. Maintain both SG pressures < 950 psig using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of the ADVs)

33. IAAT all the following exist:

__ All SCMs > 0°F

__ ES Bypass Permit satisfied

__ RCS pressure controllable

THEN perform Steps 34 - 35.

34. Bypass applicable ES:

To Bypass HPI:

__ Bypass HPI CH A, B, C

To Bypass LPI:

__ Bypass LPI CH A, B, C

35. Bypass applicable Diverse ES:

To Bypass HPI:

__ Bypass Diverse HPI

To Bypass LPI:

__ Bypass Diverse LPI

NOTE

Leak rate prior to reducing SCM is input to Cool Down Plateau at Steps 103 and 203.

36. Estimate SGTR leak rate:

_____ + _____ - _____ - _____ = _____ gpm MU SI LD TSR LR

Where: MU = Makeup Flow

SI = Seal Inlet Hdr Flow

LD = Letdown Flow

TSR = Total Seal Return Flow

LR = Leak Rate



of 52



CT-3


37. Verify any RCP operating.

38. Maintain RCP NPSH during the reduction of SCM:

OAC

Encl 5.18 (P/T Curves)

NOTE

If normal pzr spray is available, efforts should be made to minimize core SCM ≤ 15°F IF allowed by RCP NPSH requirements.

If normal pzr spray is NOT available, minimize core SCM as low as safely achievable.

39. Reduce and maintain core SCM at minimum using any/all of the following methods:

__ De-energize all Pzr heaters

__ Use Pzr spray

__ Maintain Pzr level 140″ - 180″ [175″ - 215″ acc]

NOTE

The rate of fill of the SG with the tube rupture should be considered when deciding to use alternate depressurization methods.

Pzr spray, if available, is preferred to maintain SCM at minimum after using the PORV. This will prevent repetitive cycling of the PORV.

40. IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 41 - 43.

NOTE

BWST temperature should be used in determining Pzr spray nozzle ΔT. Computer point O1P3367 provides Pzr spray nozzle ΔT information.

41. Verify Pzr spray nozzle ΔT ≥ 410°F.

42. Close:

__ 1LWD-1

__ 1LWD-2

43. Cycle PORV as necessary.



of 52



SGTR Tab

Crew Response:

44. Verify 1SA-2/C-8 (AFIS HEADER A INITIATED) lit.

RNO: Select OFF for both digital channels on AFIS HEADER A.

45. Verify 1SA-2/D-8 (AFIS HEADER B INITIATED) lit.

RNO: Select OFF for both digital channels on AFIS HEADER B.

46. Verify RCS temperature > 532°F.

NOTE

Close monitoring of RCS pressure is essential during the cooldown if ES has not been bypassed. Slowing the cooldown and stopping Pzr spray momentarily may be needed as ES Bypass Permit is approached to avoid ES actuation.

47. Initiate a cooldown as follows:

__ Decrease SG pressure to 835 - 845 psig using any of the following:

TBV setpoint adjusted to 710 - 720 psig

TBVs in manual

ADVs

__ Maximize cooldown rate limited only by the ability to maintain Pzr level > 100″ [180″ acc].

48. WHEN SG pressure is 835 - 845 psig, THEN adjust SG pressure as necessary to maintain an RCS temperature band of 525°F - 532°F.

49. IAAT any affected SG approaches overfill:

Any SCM ≤ 0°F: LOSCM setpoint

All SCMs > 0°F: 285″ [315″ acc] XSUR


RNO: GO TO Step 53.

50. Verify TBVs available for steaming affected SGs.

51. Open on all affected SGs:

1A SG 1B SG

1MS-17 1MS-26



of 52




NOTE

Steaming a SG to prevent overfill should continue even if Tech Spec cooldown rates are exceeded.

52. Steam affected SGs to prevent overfill.

53. Verify at least one open:

__ 1MS-24

__ 1MS-33

54. Verify a SG without a tube leak is available to supply the Aux Steam header.

55. Open on the SG without a tube leak:

1A SG 1B SG

1MS-24 1MS-33

56. Close on the SG with a tube leak:

1A SG 1B SG

1MS-24 1MS-33

57. Open 1AS-40 while closing 1MS-47.

58. Close on all affected SGs:

1A SG 1B SG

1MS-79 1MS-76

1MS-82 1MS-84

1MS-35 1MS-36

59. Close 1SSH-9.

60. Verify one SG isolated due to steam leak.

RNO: GO TO Step 68.

68. Verify all SCMs > 0°F.



of 52



CT-4


69. GO TO applicable step based on number of RCPs operating:

Number of RCPs Operating

Applicable Step

4 70

1,2 or 3 71

None 91

70. Stop one RCP in B loop

71. Verify steaming both SGs.

72. Verify SG to be isolated is being steamed to prevent overfill per Steps 49-52

RNO: 1. Place the following in HAND and reduce demand to 0% on SG with largest tube rupture

√ 1A SG √ 1B SG

1A TBVs 1B TBVs

2. GO TO Step 74

74. Verify ADVs being used to steam

RNO: GO TO Step 76

76. Place in HAND and reduce demand to 0% on SG with largest tube rupture:

√ 1A SG √ 1B SG

1FDW-35 1FDW-44

1FDW-32 1FDW-41



of 52




77. Place in MANUAL and close on SG with largest tube rupture

√ 1A SG √ 1B SG

1FDW-315 1FDW-316

78. Verify SG to be isolated is being steamed to prevent overfill per Steps 49-52

RNO: 1. Close on the SG with the largest tube rupture:

√ 1A SG √ 1B SG

1MS-17 1MS-26

2. GO TO Step 80

80. Verify ADVs being used to steam

RNO: GO TO Step 82

82. Place control switch in CLOSE on SG with largest tube rupture:

√ 1A SG √ 1B SG

1FDW-31 1FDW-40

1FDW-33 1FDW-42

83. Place control switch in OFF on SG with largest tube rupture:

√ 1A SG √ 1B SG

1A MDEFDWP

1B MDEFDWP



of 52




84. Close on SG with largest tube rupture:

√ 1A SG √ 1B SG

1FDW-372 1FDW-382

1FDW-36 1FDW-45

1FDW-38 1FDW-47

1FDW-368 1FDW-369

1SD-2 1SD-5

1SD-27 1SD-290

1SD-358

1SD-418 1SD-420

1SD-419 1SD-421

85. Dispatch an operator to perform Encl 5.28 (Local SG Isolation) to complete isolation of SG with largest tube rupture

86. Verify both are closed:

__ 1MS-24

__ 1MS-33

87. Initiate AP/31 (Primary to Secondary Leakage) Encl 5.2 (Reduction of Secondary Leakage and Cross-Unit Contamination).

88. GO TO applicable step based on number of RCPs operating:

Number Of RCPs Operating

Applicable Step

4 89

1, 2, or 3 191

None 91



of 52

Rule 6

HPI

HPI Pump Throttling Limits • HPI must be throttled to prevent violating the RV-P/T limit.

• HPI pump operation must be limited to two HPIPs when only one BWST suction valve (1HP-24 or 1HP-25) is open.

• HPI must be throttled ≤ 475 gpm/pump (including seal injection for A header) when only one HPI pump is operating in a header.

• Total HPI flow must be throttled ≤ 950 gpm including seal injection when 1A and 1B HPI pumps are operating with 1HP-409 open.

• Total HPI flow must be throttled < 750 gpm when all the following exist:

- LPI suction is from the RBES

- piggyback is aligned

- either of the following exist:

• only one piggyback valve is open (1LP-15 or 1LP-16)

• only one LPI pump operating

• HPI may be throttled under the following conditions:

HPI Forced Cooling in Progress:

HPI Forced Cooling NOT in Progress:

All the following conditions must exist: • Core SCM > 0

• CETCs decreasing

All the following conditions must exist: • All WR NIs ≤ 1%

• Core SCM > 0

• Pzr level increasing

• CRS concurrence required if throttling following emergency boration

HPI Pump Minimum Flow Limit

• Maintain ≥ 170 gpm indicated/pump. This is an instrument error adjusted value that ensures a real value of ≥ 65 gpm/pump is maintained. HPI pump flow less than minimum is allowed for up to 4 hours.


of 52

Enclosure 5.5

Pzr and LDST Level Control

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE

Maintaining Pzr level >100″ [180″ acc] will ensure Pzr heater bundles remain covered.

1. __ Utilize the following as necessary to maintain desired Pzr level:

• 1A HPI Pump

• 1B HPI Pump

• 1HP-26

• 1HP-7

• 1HP-120 setpoint or valve demand

• 1HP-5

__ IF 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain desired Pzr level.

2. __ IAAT makeup to the LDST is desired, THEN makeup from 1A BHUT.

3. __ IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A BHUT.

4. __ IAAT it is desired to bleed letdown flow to 1A BHUT, THEN perform the following:

A. Open:

1CS-26

1CS-41

B. Position 1HP-14 to BLEED.

C. Notify SRO.

5. __ IAAT letdown bleed is NO longer desired, THEN position 1HP-14 to NORMAL.


of 52

Enclosure 5.5 Pzr and LDST Level Control


6. __ IAAT 1C HPI PUMP is required,


__ GO TO Step 10.

7. Open:

• 1HP-24

• 1HP-25

1. __ IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN perform the following:

A. Start 1A LPI PUMP.

B. Start 1B LPI PUMP.

C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7

D. __ IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.

E. __ Dispatch an operator to open 1HP-363 (Letdown Line To LPI Pump Suction Block) (A-1-119, U1 LPI Hatch Rm, N end).

F. GO TO Step 8.

2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN perform the following:

A.__ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.

B.__ IF < 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C. GO TO Step 9.


of 52


ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. Start 1C HPI PUMP.

__ IF at least two HPI pumps are operating, THEN throttle 1HP-409 to maintain desired Pzr level.

9. Throttle the following as required to maintain desired Pzr level:

__ 1HP-26

1HP-27

1. IF at least two HPI pumps are operating, AND 1HP-26 will NOT open, THEN throttle 1HP-410 to maintain desired Pzr level.

2. __ IF 1A HPI PUMP and 1B HPI PUMP are operating, AND 1HP-27 will NOT open, THEN throttle 1HP-409 to maintain desired Pzr level.


of 52


ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10. __ IAAT LDST level CANNOT be

maintained, THEN perform Step 11.

__ GO TO Step 12.


• Open 1HP-24.

• Open 1HP-25.

• Close 1HP-16.




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7



F. __ GO TO Step 13.

2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, AND three HPI pumps are operating, THEN secure 1B HPI PUMP.

NOTE

Maintaining Pzr level > 100” [180” acc] will ensure Pzr heater bundles remain covered.

12.__ Operate Pzr heaters as required to maintain heater bundle integrity.


of 52


ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13. __ IAAT additional makeup flow to LDST

is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 (1A BHUT Recirc) (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).

14. __ IAAT two Letdown Filters are desired, THEN perform the following:

Open 1HP-17.

Open 1HP-18

15. IAAT all of the following exist:

Letdown isolated

LPSW available

Letdown restoration desired

THEN perform Steps 16 - 34. {41}

GO TO Step 35.

16. Open:

__ 1CC-7

__ 1CC-8

1. __ Notify CR SRO that letdown CANNOT be restored due to inability to restart the CC system.

2. __ GO TO Step 35.

17. __ Ensure only one CC pump running.

18. __ Place the non-running CC pump in AUTO.

19. Verify both are open:

__ 1HP-1

__ 1HP-2

1. __ IF 1HP-1 is closed due to 1HP-3 failing to close, THEN GO TO Step 21.


20. GO TO Step 23.

NOTE Verification of leakage requires visual observation of East Penetration Room.

21. Verify letdown line leak in East Penetration Room has occurred.

GO TO Step 23.

22. GO TO Step 35.


of 52


ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23. __ Monitor for unexpected conditions

while restoring letdown.

24. Verify both letdown coolers to be placed in service.

1. __ IF 1A letdown cooler is to be placed in service, THEN open:

1HP-1

1HP-3

2. __ IF 1B letdown cooler is to be placed in service, THEN open:

1HP-2

1HP-4


25. Open:

1HP-1

1HP-2

1HP-3

1HP-4

26. __ Verify at least one letdown cooler is aligned.

Perform the following:

A. __ Notify CR SRO of problem.

B. __ GO TO Step 35.

27. __ Close 1HP-6.

28. __ Close 1HP-7.

29. __ Verify letdown temperature < 125°F. 1. __ Open 1HP-13.

2. Close:

1HP-8

1HP-9&11

3. __ IF any deborating IX is in service, THEN perform the following:

A. Select 1HP-14 to NORMAL.

B. Close 1HP-16.

4. __ Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.


of 52


ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30. Open 1HP-5.

31. Adjust 1HP-7 for ≈ 20 gpm letdown.

32. WHEN letdown temperature is < 125°F, THEN place LETDOWN HI TEMP INTLK BYP switch to NORMAL.

33. Open 1HP-6.

34. __ Adjust 1HP-7 to control desired letdown flow.

NOTE

AP/32 (Loss of Letdown) provides direction to cool down the RCS to offset increasing pressurizer level.

35. __ IAAT it is determined that letdown is unavailable due to equipment failures or letdown system leakage, THEN notify CR SRO to initiate AP/32 (Loss of Letdown).

36. __ IAAT > 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:

A. __ Obtain SRO concurrence to reduce running HPI pumps.

B. Secure the desired HPI pumps.

C. __ Place secured HPI pump switch in AUTO, if desired.

37. IAAT all the following conditions exist:

Makeup from BWST NOT required

LDST level > 55″

All control rods inserted

Cooldown Plateau NOT being used

THEN close:

1HP-24

1HP-25


of 52


ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38. Verify 1CS-48 (1A BHUT Recirc) has

been closed to provide additional makeup flow to LDST.

__ GO TO Step 40.

39. __ WHEN 1CS-48 (1A BHUT Recirc) is NO longer needed to provide additional makeup flow to LDST, THEN perform the following:

A. __ Stop 1A BLEED TRANSFER PUMP.

B. __ Locally position 1CS-48 (1A BHUT Recirc) one turn open (A-1-107, Unit 1 RC Bleed Transfer Pump Rm.).

C. Close 1CS-46.

D. __ Start 1A BLEED TRANSFER PUMP.

E. __ Locally throttle 1CS-48 (1A BHUT Recirc) to obtain 90 - 110 psig discharge pressure.

F. __ Stop 1A BLEED TRANSFER PUMP.

40. Verify two Letdown Filters in service, AND only one Letdown filter is desired.

__ GO TO Step 42.

41. Perform one of the following:

Place 1HP-17 switch to CLOSE.


42. __ WHEN directed by CR SRO, THEN EXIT this enclosure.


of 52

Subsequent Actions EP/1/A/1800/001

Parallel Actions Page 1 of 1

CONDITION ACTIONS

1. PR NIs ≥ 5% FP

OR

NIs NOT decreasing

GO TO UNPP tab.

UNPP

2. All 4160V SWGR de-energized

{13}

GO TO Blackout tab. BLACKOUT

3. Core SCM indicates superheat GO TO ICC tab. ICC

4. Any SCM = 0°F GO TO LOSCM tab. LOSCM

5. Both SGs intentionally isolated to stop excessive heat transfer

GO TO EHT tab.

LOHT 6. Loss of heat transfer (including

loss of all Main and Emergency FDW)

GO TO LOHT tab.

7. Heat transfer is or has been excessive

GO TO EHT tab.

EHT

8. Indications of SGTR ≥ 25 gpm GO TO SGTR tab. SGTR

9. Turbine Building flooding NOT caused by rainfall event

GO TO TBF tab.

TBF

10. Inadvertent ES actuation occurred Initiate AP/1/A/1700/042 (Inadvertent ES Actuation).

ES

11. Valid ES actuation has occurred or should have occurred

Initiate Encl 5.1 (ES Actuation).

ES

12. Power lost to all 4160V SWGR and any 4160V SWGR re-energized

• Initiate AP/11 (Recovery from Loss of Power).

• IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

ROP

13. RCS leakage > 160 gpm with letdown isolated

Notify plant staff that Emergency Dose Limits are in affect using PA system.

EDL

14. Individual available to make notifications

• Announce plant conditions using PA system.

• Notify OSM to reference the Emergency Plan and AD-LS-ALL-0006.

NOTIFY


of 52

CRITICAL TASKS

CT-1 ICS must be taken to HAND and FDW adjusted to prevent tripping the reactor on RPS

Low Pressure (1810 psig) or RPS Variable Low Pressure. Adjustment will be dependent on how much time it takes to place ICS in HAND.

CT-2 Outside Air Booster Fans are started to minimize radiation exposure to control room

personnel. (Within 30 minutes of SGTR) TCA #20

CT-3 Decrease SCM (≈ 5-20°F) to decrease leak size prior to SG overfill (water in MS Line)

CT-4 Isolate steaming of the 1B SG within 20 minutes of RCS temperature decreasing

below 532°F

SAFETY: Take a Minute

UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No

UNIT STATUS (CR SRO)

Unit 1 Simulator Other Units

Mode: 1 Unit 2 Unit 3

Reactor Power: 100% Mode: 1 Mode: 1

Gross MWE: 894 100% Power 100% Power

RCS Leakage: 0.01 gpm

No WCAP Action EFDW Backup: Yes EFDW Backup: Yes

RBNS Rate: 0.01 gpm

Technical Specifications/SLC Items (CR SRO) Component/Train OOS

Date/Time Restoration

Required Date/Time

TS/SLC #

AMSAC/DSS 0300 7 Days 16.7.2

Shift Turnover Items (CR SRO)

Primary

Due to unanalyzed condition, the SSF should be considered INOP for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%).

1RIA-3 and 5 removed from RB. SASS is in Manual for calibration ‘C’ GWD tank release is in progress per OP/1-2/A/1104/018 Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to

‘1 PRV System Filter Discharge’. IF 1SA-8/B-9 is due to RIA-32 - ‘1 PRV System Filter Discharge’, it can be considered an expected alarm

Secondary

AMSAC/DSS bypassed for calibration

Unit 2 is supplying the AS header

The Voltage Regulator is in Manual and ready to be placed back in Auto. BOP is to perform OP/1/A/1106/001 Encl 4.8 to lower MVARs to 150 ± 10 MVARs with the

Voltage Regulator in AUTO.

1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.

Reactivity Management (CR SRO)

RCS Boron 83 ppmB Gp 7 Rod Position: 92% Withdrawn

Batch additions as required for volume control.

Human Performance Emphasis (OSM)

Procedure Use and Adherence



________________________ ________________________OATC

________________________ ________________________BOP


Turnover:

SASS is in Manual

AMSAC/DSS is Bypassed


Event No.


Event Description



1 Override C: BOP, SRO (TS) Pump RBNS (1LWD-1 Fails to Close)

2 MSS200

MSS200D C: BOP, SRO (TS) Condenser Vacuum Leak

3 MPI050 MPI080

I: OATC, SRO Loop B RCS Flow Fails Low

4 R: OATC, SRO Oil Leak on Main Turbine Requires Manual Power Reduction

5 N: BOP, SRO Swap Auxiliaries Due to Oil Leak on ‘B’ LP Turbine

6 MEL220 MPI290 MPI300

C: OATC, SRO 1TB Lockout Causes a Loss of 1A2 and 1B2 RCPs Requiring a Manual Reactor Trip

7 MPS400 M: ALL

Large Break LOCA

1A LPI Pump Fails

1B LPI Pump Fails to Start on ES (1B LPIP can be started manually)

Switch Will Not Stop 1A1 RCP When Securing Per Rule 2



Page 2 of 60

Scenario 2

Event Summary

Event 1: When the crew takes the shift, they will be required to pump the Reactor Building Normal Sump due to high level. When the operator begins to secure the alignment, LWD-1 will fail to close. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 2: The condenser will experience a vacuum leak and will require the crew to start the

Main Vacuum Pumps prior to the unit tripping on low condenser vacuum. After the crew dispatches operators to look for vacuum leaks, a report will be made to the control room and the SRO will be required to direct the AO to isolate the source of the leak. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 3: The Loop ‘B’ RCS flow signal will fail low causing ICS to automatically re-ratio FDW. The crew should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to manual and re-ratio FDW to stabilize the plant.

Event 4: A report will be made to the control room that there is a large oil leak on the Main Turbine and there is no way to isolate the leak without shutting down the oil system. The SRO will enter an Abnormal Procedure to rapidly shut down the unit with ICS in manual in order to take the turbine offline.

Event 5: During the power reduction from Event 4, the BOP operator will be required to swap auxiliary power to the startup transformer (CT-1) before the generator is taken offline.

Event 6: Once Reactor power has been decreased > 10% and auxiliary power has been transferred to CT-1, switchgear 1TB will lockout which will cause the loss of two RCPs. The Reactor will fail to automatically trip which will require an operator to manually trip the Reactor during Immediate Manual Actions.

Event 7: Shortly after the Reactor is tripped, an RCS leak will develop which will evolve into a Large Break LOCA within a short period of time. While performing Rule 2 due to the Loss of SCM, the 1A1 RCP will fail to trip from the control switch which will require the operator to de-energize the switchgear to remove power from the pump. The 1A LPI Pump will fail and the 1B LPI Pump will fail to receive an ES start signal which will require the operator to manually start the 1B LPI Pump to maintain core cooling.


Page 3 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 1 Page 1 of 2 Event Description: Pump RBNS (LWD-1 Fails to Close) (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior

SRO/BOP


SRO directs the BOP to pump the Reactor Building Normal Sump in accordance with OP/1/A/1104/007 Enclosure 4.1. OP/1/A/1104/007, Encl. 4.1 (Pumping RBNS to ≥ 1 inch) rev 30

2.1 Verify required to lower RBNS to ≥ 1”

3.1 Verify MWHUT level adequate to receive waste volume.

3.2 Position the following:

Ensure open 1LWD-1 (RB NORMAL SUMP ISOLATION)


3.3 Start one or both of the following:

1A RB NORM SUMP PUMP

1B RB NORM SUMP PUMP

NOTE

Changes in LAWT levels may occur during pumping.

RIA Alarms may be indicative of gas leakage.

If RBNS level was above 14" when pumps were started, a level increase following securing the RBNS pumps may occur.

During outages, it is desirable to maintain RBNS > 6” for shielding to decrease dose rates in RBNS area.

3.4 WHEN RBNS is at desired level OR at 1" (low level alarm), ensure the following:

1A RB NORMAL SUMP PUMP "OFF".

1B RB NORMAL SUMP PUMP "OFF".

Examiner Note: 1LWD-1 will NOT close.

3.5 IF required to close the valves, position the following:

Close 1LWD-1 (RB NORMAL SUMP ISOLATION)


This event is complete when the SRO has referred to Tech Specs, or as directed by the Lead Examiner


Page 4 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 1 Page 2 of 2 Event Description: Pump RBNS (LWD-1 Fails to Close) (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior

Crew response:

Examiner Note: The crew should diagnose the failure of 1LWD-1 and the SRO will refer to Tech Specs. Since 1LWD-1 is a Containment Isolation Valve, the applicable Tech Spec is 3.6.3. Since this path has 2 Containment Isolation Valves, Condition A applies and the Completion Time is 4 hours.

Booth Cue: If directed by the control room, SPOC will investigate the problem with 1LWD-1. Troubleshooting/repair of the valve will be turned over to the WCC and the valve is not expected to be returned to service on this shift.

TS 3.6.3 CONTAINMENT ISOLATION VALVES

Condition A (4 hours) Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured

AND

(Once per 31 days) Verify the affected penetration flow path is isolated for isolation devices outside containment.

This event is complete when the SRO has referred to Tech Specs, or as directed by the Lead Examiner


Page 5 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 2 Page 1 of 2 Event Description: Condenser Vacuum Leak (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior

CT-1


1SA-3/A-6 (Condenser Vacuum Low) will alarm at 25” Hg

Crew Response:

The SRO may direct the BOP to refer to the Alarm Response Guide for 1SA-3/A-6

The SRO will enter AP/1/A/1700/027 (Loss of Condenser Vacuum)

1SA-3/A-6 (Condenser Vacuum Low) rev 061

3.1 Refer to AP/1/A/1700/027 (Loss of Condenser Vacuum) AP/1/A/1700/027 (Loss of Condenser Vacuum) rev 007

4.1 Announce AP entry using the PA system.


__ Condenser vacuum ≤ 22″ Hg

__ MODE 1 or 2

THEN trip the Rx.

4.3 Dispatch operators to perform the following:

__ Perform Encl 5.1 (Main Vacuum Pump Alignment)

__ Look for vacuum leaks

4.4 Ensure all available Main Vacuum Pumps operating (A, B, & C).

Booth Cue: After all MVPs are running, using TIME COMPRESSION, call the Control Room to notify the operator that the Main Vacuum Pumps are aligned to Unit 1.

4.5 Ensure 1V-186 is closed.

4.6 Ensure Steam to Steam Air Ejector A, B, C > 255 psig.

4.7 Verify Steam Seal Header Press > 1.5 psig.

This event is complete when SRO reaches Step 4.10 of AP/27, or as directed by the Lead Examiner.


Page 6 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 2 Page 2 of 2 Event Description: Condenser Vacuum Leak (C: BOP, SRO) (TS) Time Position Applicant's Actions or Behavior

OATC


4.8 Ensure all available CCW pumps operating.

Examiner Note: When the 4th CCW Pump is started, the LPSW Leakage Accumulator will alarm on the OAC requiring entry into TS 3.7.7 Condition B (7 days) Restore the LPSW WPS to OPERABLE status.

Booth Cue: Call Control Room as the AO sent out to look for vacuum leaks and report that a leak was found on the 1B Main FDW Pump pumping trap sight glass. The leak will be removed after the control room directs the AO to isolate the sight glass.

4.9 Verify Condensate flow ≥ 2300 gpm

4.10 Verify 1SSH-1 is closed

4.11 WHEN condenser vacuum is stable, AND Encl 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure

Booth Cue: IF/when asked about the status of Encl. 5.1, respond that using time compression, Encl. 5.1 is complete.

TS 3.7.7 LOW PRESSURE SERVICE WATER

Condition B (7 days) Restore the LPSW WPS to OPERABLE status.

This event is complete when SRO reaches Step 4.10 of AP/27, or as directed by the Lead Examiner.


Page 7 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 3 Page 1 of 3 Event Description: Loop ‘B’ RCS Flow Fails Low (I: OATC, SRO) Time Position Applicant's Actions or Behavior

OATC

BOP

SRO


1SA-1/A-3 (1A Flux/Flow/Imb Trip)

1SA-2/A-4 (RC Loop A Flow Low)

1SA-2/A-5 (RC Total Flow Low)

1SA-2/C-11 (ICS Loss of OAC CTP Signal)

1SA-5/A-5 through D-5 (1A-1D RPS Trouble)

ICS will re-ratio FDW Crew Response:

When the Statalarms are received, the candidates should utilize the “Plant Transient Response” process to stabilize the plant.

OATC should:







Note: The OATC will have to re-ratio and maintain total FDW flow ≤ pre-transient in order to stabilize power below the pre-transient level.

The BOP should:




The CRS should:



This event is complete when the CRS reaches step 6 (WHEN) in AP/28 Section 4E, or as directed by the Lead Examiner.


Page 8 of 60


SRO/BOP


AP/1/A/1700/028 (ICS Instrument Failures) Rev 20












Emergency Plan

__ STA





OAC alarm video

OAC display points




√ Section Failure

4E RCS Flow



Page 9 of 60


SRO/OATC

AP/1/A/1700/028 Section 4E Crew Response:

AP/1/A/1700/028, Section 4E (RCS Flow Failure)

NOTE

The following will occur when an ICS RCS flow loop signal fails: ICS RUNBACK

Controlling Tave swaps to RCS loop with higher flow

Delta Tc station re-ratios loop feedwater flows


__ 1A FDW MASTER

__ 1B FDW MASTER



__ Select a valid RCS flow input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).

__ Investigate and repair the failed RCS flow instrumentation.

4. PERFORM an instrumentation surveillance using applicable table in Encl 5.2 (ICS Instrument Surveillances) for the failed instrument. (see next page)



Booth Cue: If asked, Unit 2 will initiate the surveillance evaluation in accordance with PT/1/A/0600/001.

6. WHEN notified by SPOC that a valid RCS flow input has been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).




Page 10 of 60


Page 11 of 60


Event Description: Oil Leak on Main Turbine Requires Manual Power Reduction (R: OATC, SRO)


SRO/OATC

Booth Cue: To initiate this event, call the Control Room on 4911 and

inform them as follows: "This is the WCC SRO. There is an oil leak on the north end of the Unit 1 B LP turbine. There is not a way to isolate the leak without shutting down the oil system".

Booth Cue: If needed, state that there is a significant amount of oil leaking from the LP turbine.

Booth Cue If asked for Unit 2 to handle the Spill Response procedure, respond that "Unit 2 will handle the Spill Response procedure".

The SRO will initiate AP/29 (Rapid Unit Shutdown) to direct power reduction

AP/1A/1700/029 (Rapid Unit Shutdown) rev 013

4.1 Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown) (page 13)

4.2 Announce AP entry using the PA system.


__ It is desired to stop power decrease.

__ CTP > 18%

THEN perform Steps 4.4 – 4.7

RNO: GO TO Step 4.8

4.8 Verify ICS in AUTO (ICS is NOT in Auto)


RNO: 1. Initiate manual power reduction to desired power level.

2. GO TO Step 4.10

Note: OATC reduces power by first reducing feedwater and then inserting control rods as necessary.

4.10 Verify both Main FDW pumps running:


NOTE 1B Main FDW Pump is the preferred pump to be shutdown first. To lower 1B Main FDW Pump suction flow, bias is adjusted counter-

clockwise. To lower 1A Main FDW Pump suction flow, bias is adjusted clockwise.

This event is complete when Reactor power has been reduced > 10% and Auxiliaries have been transferred, or as directed by the Lead Examiner.


Page 12 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 4 Page 2 of 2 Event Description: Oil Leak on Main Turbine Requires Manual Power Reduction (R: OATC, SRO) Time Position Applicant's Actions or Behavior

BOP/SRO

AP/1/A/1700/029 AP/1/A/1700/029 (Rapid Unit Shutdown)

4.11 Adjust bias for first Main FDW pump desired to be shutdown (1B) until its suction flow is ≈ 1 X 106 lbm/hr less than remaining Main FDW pump suction flow.

4.12 WHEN core thermal power is < 65% FP, THEN continue.


__ 1B Main FDW Pump is first pump to be shut down.


FWP B FLOW MINIMUM (1SA-16/A-3)

FWP B FLOW BELOW MIN (1SA-16/A-4)

THEN trip 1B Main FDW Pump.

4.14 IAAT both Main FDW pumps running, AND both of the following exists:

__ 1A Main FDW pump is the first pump to be shut down


FWP A FLOW MINIMUM (1SA-16/A-1)

FWP A FLOW BELOW MIN (1SA-16/A-2)

THEN trip 1A Main FDW Pump


4.16 Start the TURBINE TURNING GEAR OIL PUMP.

4.17 Start 1A through 1E TURBINE BRNG OIL LIFT PUMPS.

4.18 Start the TURBINE MOTOR SUCTION PUMP.


__ ICS in automatic

__ NI power is ≤ 18%

THEN deselect MAXIMUM RUNBACK. (does NOT apply)

4.20 Verify Turbine-Generator shutdown is required (it is required)

4.21 WHEN NI power ≤18% THEN depress turbine TRIP pushbutton

This event is complete when Reactor power has been reduced > 10% and Auxiliaries have been transferred, or as directed by the Lead Examiner.


Page 13 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 5 Page 1 of 2 Event Description: Swap Auxiliaries Due To Oil Leak on Main Turbine (N: BOP, SRO) Time Position Applicant's Actions or Behavior

SRO/BOP

AP/1/A/1700/029 Encl 5.1

AP/1/A/1700/029 Encl. 5.1 (Support Actions During Rapid Unit Shutdown)

1. Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid Unit Shutdown).

2. Start the following pumps:

1A FDWP SEAL INJECTION PUMP

1A FDWP AUXILIARY OIL PUMP

1B FDWP AUXILIARY OIL PUMP

1B FDWP SEAL INJECTION PUMP

3. WHEN CTP is ≤ 80%, THEN continue.





8. Verify Turbine-Generator shutdown is required. (It is required)


1TA AUTO/MAN

1TB AUTO/MAN

10. Close 1TA SU 6.9 KV FDR.

11. Verify 1TA NORMAL 6.9 KV FDR opens.

12. Close 1TB SU 6.9 KV FDR.

13. Verify 1TB NORMAL 6.9 KV FDR opens.

14 Place the following transfer switches to MAN:

MFB1 AUTO/MAN

MFB2 AUTO/MAN




18. Verify N21 MFB2 NORMAL FDR opens

This event is complete when Auxiliaries have been transferred, or as directed by the Lead Examiner.


Page 14 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 5 Page 2 of 2 Event Description: Swap Auxiliaries Due To Oil Leak on Main Turbine (N: BOP, SRO) Time Position Applicant's Actions or Behavior

SRO/BOP

AP/1/A/1700/029 Encl 5.1

19. Notify CR SRO that Unit auxiliaries have been transferred

20. IAAT 1SSH-9 is NOT closed, AND CTP is ≤ 75%, THEN throttle 1SSH-9 to maintain Steam Seal Header pressure 2.5 – 4.5 psig

21. WHEN CTP ≤ 65% THEN place the following in MANUAL

__ 1FDW-53

__ 1FDW-65

22. IAAT load is ≤ 550 MWe, THEN perform Steps 23-24

23. Ensure the following are stopped:

__ 1A MSRH DRN PUMP

__ 1B MSRH DRN PUMP

24. Place 1HD-37 and 1HD-52 in DUMP:

25. WHEN CTP is ≤ 60%, THEN ensure 1SSH-9 closed

26. IAAT load is ≤ 450 MWe, THEN perform Steps 27-30

27. Verify the 1C CBP operating

28. Stop the 1A and 1B CBPs

29. Place the control switch for one shutdown CBP in AUTO

30. Ensure CBP LOAD SHED DEFEAT switch to a running CBP

31. WHEN ≤ 400 MWe, THEN stop the following pumps

__ 1D1 HTR DRN PUMP

__ 1D2 HTR DRN PUMP

32. WHEN ≤ 325 MWe, THEN verify ≤ two HWPs operating

33. WHEN ≤ 225 MWe, THEN stop all but one HWP

34. Place control switch for one idle HWP in AUTO

35. Ensure HWP LOAD SHED DEFEAT switch is positioned to a running HWP

36. WHEN CTP DEMAND is < 20%, THEN Close 1MS-76 and 1MS-79

37. WHEN directed by CR SRO, THEN EXIT this enclosure

This event is complete when Auxiliaries have been transferred, or as directed by the Lead Examiner.


Page 15 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 6 Page 1 of 1 Event Description: 1TB Lockout Causes a Loss of 1A2 and 1B2 RCPs Requiring a Manual

Reactor Trip (C: OATC, SRO) Time Position Applicant's Actions or Behavior

SRO/OATC

BOP

SRO

Plant Response:

1TB lockout will occur. This will cause a loss of 6900V power to the 1A2 and 1B2 RCPs. RPS alarms will occur indicating that the Reactor should have tripped, but it will remain at power.

Crew Response:

Recognize the Reactor should have tripped (< 3 RCPs operating with Reactor power > 2% - OMP 1-18 Att. A), therefore manually trip the Reactor and then perform Immediate Manual Actions of the EOP.

3.1 Depress REACTOR TRIP pushbutton

3.2 Verify reactor power < 5% FP and decreasing

3.3 Depress turbine TRIP pushbutton

3.4 Verify all turbine stop valves closed

3.5 Verify RCP seal injection available The BOP will perform a symptom check.










CSAE Offgas alarms




The SRO will transfer to the Subsequent Actions Tab after IMAs and Symptoms Check are complete (page 16).

This event is complete when the SRO reaches Step 4.10 of the Subsequent Actions tab, or as directed by the Lead Examiner.


Page 16 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 6 Page 1 of 1 Event Description: 1TB Lockout Causes a Loss of 1A2 and 1B2 RCPs Requiring a Manual

Reactor Trip (C: OATC, SRO) Time Position Applicant's Actions or Behavior

SRO/OATC

SRO/BOP


EOP Subsequent Actions Tab

4.1 Verify all control rods in Groups 1-7 fully inserted

4.2 Verify Main FDW in operation

4.3 Verify either:

__ Main FDW overfeeding causing excessive temperature decrease

__ Main FDW underfeeding causing SG level decrease below setpoint

RNO: GO TO Step 4.5

4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the operating range, THEN perform Steps 4.6 – 4.8

RNO: GO TO Step 4.9

4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs NOT intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24 (Operation of ADVs)

4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating

4.11 GO TO Step 4.14

4.14 Verify 1MS-17 and 1MS-26 are closed

RNO: Dispatch an operator with Encl 5.29 to verify all MSRVs have reseated

4.15 Verify ES is required

RNO: 1. Initiate Encl 5.5 (Pzr and LDST Level Control)

2. GO TO Step 4.17

4.17 Open PCB-20 and PCB-21

4.18 Verify Generator Field Breaker open

4.19 Verify EXCITATION is OFF

4.20 Verify Aux Bldg and Turbine Bldg Instrument Air pressure ≥ 90 psig

4.21 Verify ICS/NNI power available

4.22 Verify all 4160V switchgear (1TC, 1TD, & 1TE) energized

4.23 Verify both SGs > 550 psig

4.24 Verify Main FDW operating

This event is complete when the SRO reaches Step 4.10 of the Subsequent Actions tab, or as directed by the Lead Examiner.


Page 17 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 1 of 10 Event Description: Large Break LOCA (M: ALL) Time Position Applicant's Actions or Behavior

SRO/BOP

Crew Response:

The SRO will direct the BOP to perform a Symptoms Check (OMP 1-18)










CSAE Offgas alarms




After verifying IMAs, the SRO will transfer to the Subsequent Actions Tab and review the Parallel Action page. (Page 56) Examiner Note: Core SCM will indicate 0°F or superheated during this

transient depending on when CFTs and LPI flow injects into the core. When the SRO reaches the decision point in the SA parallel action page, if superheated he should transfer to the Inadequate Core Cooling (ICC) tab (Page 18) or if saturated, he should transfer to the Loss of Subcooling Margin (LOSCM) tab (Page 20).

The SRO will direct one of the ROs to perform Enclosure 5.1 (ES Actuation) (Page 28)

This event is complete when the SRO has transferred to the LOCA CD Tab or as directed by the Lead Examiner.


Page 18 of 60


SRO/OATC

CT-4

ICC Tab Crew Response:

ICC Tab (ICC Parallel Actions on Page 57)

CAUTION

ICC conditions should not exist unless multiple equipment and system failures have occurred. Some of the equipment used in this section may be the same equipment that has failed. It is expected that attempts to restore equipment operations will continue throughout this section. It is also expected that transition to OSAG will occur whenever conditions requiring the transition exist..

1. IAAT CETCs > 1200oF, AND TSC is ready to provide mitigation

guidance, THEN:

A. Notify TSC to enter the OSAG.

B. EXIT this procedure.

2. Ensure full HPI and control per Rule 6 (HPI). (Page 27)

3. IAAT RCS pressure is ≤ 550 psig, OR RB pressure is ≥ 3 psig, THEN perform Steps 4-8.

4. Open:

1LP-21

1LP-17

5. Start 1A LPI pump. (The 1A LPI pump will fail to start.)

RNO: 1. IF 1C LPI Pump is operating, THEN GO TO Step 8.

2. Close 1LP-17.

6. Open:

1LP-22

1LP-18

7. Start 1B LPI pump. (1B LPI pump will start manually).

RNO: 1. IF 1C LPI Pump is operating, THEN GO TO Step 8.

2. Close 1LP-18



Page 19 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 3 of 10 Event Description: Large Break LOCA (M: ALL) Time Position Applicant’s Actions or Behavior

ICC Tab Crew Response:

8. Verify two LPI pumps operating.

RNO: IF LPI/HPI piggyback is aligned, THEN maximize total LPI flow by throttling HPI flow as follows:

1C LPI pump only < 2900 gpm

1A or 1B LPI pump only < 3100 gpm

9. IAAT all exist:

1C LPI Pump off

1C LPI Pump available

LPI required

ECCS pump suction aligned to BWST

1A LPI Pump unavailable

1B LPI Pump unavailable

THEN perform Steps 10-13.

RNO: GO TO Step 14

14. Open:

1CF-1

1CF-2

15. IAAT core SCM is ≥ 0°F, THEN GO TO LOCA CD tab (page 23)

Note: Core SCM will return to 0°F shortly after LPI flow has been established.

16. Verify any injection sources available:

HPI

LPI

CFTs

17. Open:

1RC-4

PORV



Page 20 of 60


SRO

LOSCM Tab Crew Response:

LOSCM Tab

1. Ensure Rule 2 (Loss of SCM) is in progress or complete.

2. Verify LOSCM caused by excessive heat transfer.

RNO: GO TO Step 4.

4. IAAT either exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B ≥ 3400 gpm

Only one LPI header in operation with header flow ≥ 2900 gpm.

THEN GO TO LOCA CD tab. (page 23)

5. Verify SSF activated per AP/25 with SSF RC Makeup required.

RNO: GO TO Step 7.

7. Verify all exist:

NO RCPs operating

HPI flow in both HPI headers

Adequate total HPI flow per Figure 1 (Total Required HPI Flow).



Page 21 of 60



LOSCM tab (continued)

8 GO TO Step 104.


105. Verify HPI forced cooling in progress.

RNO: Close 1RC-4

106. Close 1GWD-17, 1HP-1, 1HP-2, and 1RC-3

107. Verify either:

Core superheated

Rx vessel head level at 0″

RNO: GO TO Step 109

109. IAAT BWST level is ≤ 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

CAUTION

If TDEFDWP is being used for SG feed, reducing SG pressure below 250 psig can result in reduced pumping capability

110. Maintain SG pressure < RCS pressure utilizing either:

__ TBVs

__ ADVs

111. Verify any SG available for feeding/steaming.

112. Initiate Encl 5.16 (SG Tube-to-Shell T Control).

113. Verify indications of SGTR exist.

RNO: GO TO Step 116


RNO: GO TO Step 118



Page 22 of 60



NOTE If in boiler condenser cooling, the CETCs may have a saw tooth pattern, sometimes increasing and sometimes decreasing. The overall trend should be used to make this determination.

118. Verify CETCs trend decreasing.

119. Verify primary to secondary heat transfer is excessive.

RNO: GO TO Step 121

121. Verify indications of SGTR 25 gpm.

RNO: GO TO Step 123

123. Verify required RCS makeup flow within normal makeup capability.

RNO: GO TO LOCA CD tab (page 23)



Page 23 of 60

Op-Test No.: ILT16-1 Scenario No.: 2 Event No.: 7 Page 7 of 10 Event Description: Large Break LOCA (M: ALL)


LOCA Cooldown Tab Crew Response:

LOCA COOLDOWN Tab

1. IAAT BWST level is ≤ 19’, THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

2. Verify ES actuated.

3. GO TO Step 7.


Ensure all RBCUs in low speed.

Open 1LPSW-18

Open 1LPSW-21

Open 1LPSW-24

8. Initiate Encl 5.35 (Containment Isolation).

9. Start all RB Aux fans.

10. IAAT either of the following exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B ≥ 3400gpm

Only one LPI header in operation with header flow ≥ 2900 gpm

THEN GO TO Step 11.

11. Stop all RCPs

12. Dispatch an operator to perform the following:

__ Remove white tag and close 1XO-F5C (1A CFT Outlet)

__ Remove white tag and close 1XP-F5C (1B CFT Outlet)

__ Close 1XS2-F3D (1LP-104 Bkr (Post LOCA Boron Dilute))

13. IAAT breakers for 1CF-1 AND 1CF-2 are closed, THEN close 1CF-1 and 1CF-2

14. Dispatch an operator to perform Encl 5.28 (Local SG Isolation) to isolate both SGs

15. IAAT Spent Fuel Cooling indicates:

__ Abnormal temperature increase

__ Abnormal level change

__ Abnormal SFC flow

THEN initiate AP/35

16. Verify 1MS-24 and 1MS-33 are closed



Page 24 of 60



CT-2

Rule 2 Crew Response:

Rule 2 LOSCM

1. IAAT all exist:

Any SCM ≤ 0°F

Rx power ≤ 1%

≤ 2 minutes elapsed since loss of SCM

THEN perform Steps 2 and 3.

2. Stop all RCPs. 1A1 RCP will NOT trip using the switch

RNO: 1. Place 1TA AUTO/MAN switch in MAN.

2. Place 1TB AUTO/MAN switch in MAN.

3. Open 1TA SU 6.9 KV FDR.

4. Open 1TB SU 6.9 KV FDR.

3. Notify CR SRO of RCP status.

4. Verify Blackout exists.

RNO: GO TO Step 6.

6. Open:

1HP-24

1HP-25

7. Start all available HPI pumps.

8. GO TO Step 13.

13. Open:

1HP-26

1HP-27

14. Verify at least two HPI pumps are operating using two diverse indications.

15. IAAT ≥ 2 HPI pumps operating, AND HPI flow in any header is in the Unacceptable Region of Figure 1 THEN perform Steps16-21.

RNO: GO TO Step 17



Page 25 of 60



SRO/BOP

Rule 2 16. Open in the affected header:

1A Header 1B Header

1HP-410 1HP-409

17. IAAT flow limits are exceeded,

Pump Operation Limit

1HPI pump/hdr 475 gpm (incl. seal injection for A hdr)

1A & 1B HPI pumps operating with 1HP-409 open

Total flow of 950 gpm (incl. seal injection)

THEN perform Steps 18-20.

RNO: GO TO Step 21.

18. Place Diverse HPI in BYPASS.



Page 26 of 60



SRO

OATC

BOP

Rule 2 19. Perform both:

Place ES CH 1 in MANUAL.


20. Throttle HPI to maximize flow ≤ flow limit.

21. Notify CR SRO of HPI status.

22. Verify RCS pressure > 550 psig.



Only one LPI header in operations with header flow ≥ 2900 gpm

THEN GO TO Step 24.

RNO: GO TO Step 35.


Place 1FDW-315 in MANUAL and close.

Place 1FDW-316 in MANUAL and close.

Place 1FDW-35 in HAND and close.

Place 1FDW-44 in HAND and close.

25. Notify crew that performance of Rule 3 is NOT required due to LBLOCA.

26. WHEN directed by CR SRO, THEN EXIT.



Page 27 of 60

Rule 6 HPI

HPI Pump Throttling Limits

• HPI must be throttled to prevent violating the RV-P/T limit.
















• Core SCM > 0


• SRO concurrence required if throttling following emergency boration




Page 28 of 60

EOP Enclosure 5.1 (ES Actuation)


1. __ Determine all ES channels that should have actuated based on RCS pressure and RB pressure:

2. __ Verify all ES channels associated with actuation setpoints have actuated.

NOTE

Voter OVERRIDE extinguishes the TRIPPED light on the associated channels that have auto actuated. Pressing TRIP on channels previously actuated will reposition components that may have been throttled or secured by this Enclosure.

__ Depress TRIP on affected ES logic channels that have NOT previously been actuated.

3. __ IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1 - 2.

4. __ Place Diverse HPI in BYPASS. __ Place Diverse HPI in OVERRIDE.

5. Perform both:

__ Place ES CH 1 in MANUAL.


NOTE

Voter OVERRIDE affects all channels of the affected ODD and/or EVEN channels.

In OVERRIDE, all components on the affected ODD and/or EVEN channels can be manually operated from the component switch.

1. __ IF ES CH 1 fails to go to MANUAL, THEN place ODD voter in OVERRIDE.

2. __ IF ES CH 2 fails to go to MANUAL, THEN place EVEN voter in OVERRIDE.

Actuation Setpoint

(psig)

Associated ES Channel

1600 (RCS) 1 & 2 550 (RCS) 3 & 4 3 (RB) 1, 2, 3, 4, 5, & 6 10 (RB) 7 & 8


Page 29 of 60


6. __ IAAT all exist:

__ Voter associated with ES channel is in OVERRIDE

__ An ES channel is manually actuated

__Components on that channel require manipulation

THEN depress RESET on the required channel.

7. __ Verify Rule 2 in progress or complete. __ GOTO Step 74.

8. __ Verify any RCP operating. __ GOTO Step 10.

9. Open:

__ 1HP-20

__ 1HP-21

10. __ IAAT any RCP is operating, AND ES Channels 5 and 6 actuate, THEN perform Steps 11 - 15.

__ GOTO Step 16.

11. Perform all:



NOTE





12. __ Verify any RCP is operating __ GO TO Step 16

13. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6

14. __ Ensure only one CC pump operating.

15. __ Ensure Standby CC pump in AUTO.


Page 30 of 60


16. __ IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 17.

__ GO TO Step 54.

17. __ Place Diverse LPI in BYPASS. __ Place Diverse LPI in OVERRIDE.

18. Perform both:



NOTE





CAUTION

LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head. {6}

19. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22}

20. __ IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 21 - 22.

__ GOTO Step 23.


__ Open 1LP-17.

__ Start 1A LPI PUMP.

1. __ Stop 1A LPI PUMP.

2. __ Close 1LP-17.


__ Open 1LP-18.

__ Start 1B LPI PUMP. (CT-4)

1. __ Stop 1B LPI PUMP.

2. __ Close 1LP-18.


Page 31 of 60


23. __ IAAT 1A and 1B LPI PUMPs are off / tripped, AND all exist:

__ RCS pressure < LPI pump shutoff head

__ 1LP-19 closed

__ 1LP-20 closed


__ GO TO Step 26.

24. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22

25. __ Start 1C LPI PUMP.

26. __ IAAT 1A LPI PUMP fails while operating, AND 1B LPI PUMP is operating, THEN close 1LP-17.

27. __ IAAT 1B LPI PUMP fails while operating, AND 1A LPI PUMP is operating, THEN close 1LP-18.

28. Start:



(CT- 3)





Page 32 of 60


30. Verify open:

__ 1CF-1 __ 1CF-2

__ IF CR SRO desires 1CF-1 and 1CF-2 open, THEN open:

__ 1CF-1 __ 1CF-2

31. __ Verify 1HP-410 closed. 1. __ Place 1HP-120 in HAND.

2. __ Close 1HP-120.

32. __ Secure makeup to the LDST.

33. __ Verify all ES channel 1 - 4 components are in the ES position.

1. __ IF 1HP-3 fails to close, THEN close 1HP-1.


3. __ IF 1HP-20 fails to close, AND NO RCPs operating, THEN close:

__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230

4. __ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.

34. __ Verify Unit 2 turbine tripped. __ GOTO Step 37.

35. __ Close 2LPSW-139.

36. __ Verify total LPSW flow to Unit 2 LPI coolers 6000 gpm.

__ Reduce LPSW to Unit 2 LPI coolers to obtain total LPSW flow 6000 gpm.

37. __ Close 1LPSW-139.

38. Place in FAIL OPEN:

__ 1LPSW-251 FAIL SWITCH


39. __ Start all available LPSW pumps.


Page 33 of 60


40. Verify either:

__ Three LPSW pumps operating

__ Two LPSW pumps operating when Tech Specs only requires two operable

__ GOTO Step 42.

41. Open:

__ 1LPSW-4 __ 1LPSW-5

__ IF both are closed:

__ 1LPSW-4

__ 1LPSW-5

THEN notify SRO to initiate action to open at least one valve prior to BWST level 19'.

42. __ IAAT BWST level 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

1. __ Display BWST level using OAC Turn-on Code "SHOWDIG O1P1600".

2. __ Notify crew of BWST level IAAT step.

43. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS)

44. __ Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.

45. __ IAAT ES channels 5 & 6 have actuated, THEN perform Step 46.

__ GOTO Step 47.

NOTE

RBCU transfer to low speed will NOT occur until 3 minute time delay is satisfied.

46. __ Verify all ES channel 5 & 6 components are in the ES position.

__ Notify SRO to evaluate components NOT in ES position and initiate action to place in ES position if desired.


Page 34 of 60


47. __ IAAT ES channels 7 & 8 have actuated, THEN perform Steps 48 - 49.

__ GOTO Step 50.

48. Perform all:



NOTE







50. __ Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open.

51. __ Ensure any turnover sheet compensatory measures for ES actuation are complete as necessary.

52. __ IAAT conditions causing ES actuation have cleared, THEN initiate Encl 5.41 (ES Recovery).

53. __ WHEN CR SRO approves, THEN EXIT.

END


Page 35 of 60


Unit Status

ES Channels 3 & 4 have NOT actuated.

54. Start:



CT-3




56. Verify open:

__ 1CF-1

__ 1CF-2


__ 1CF-1

__ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



61. __ Close 2LPSW-139.



63. __ Close 1LPSW-139.


Page 36 of 60






66. Verify either:



__ GOTO Step 68.

67. Open:

__ 1LPSW-4

__ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5





69. __ Dispatch an operator to perform Encl 5.2 (Placing RB Hydrogen Analyzers In Service). (PS )





END


Page 37 of 60


74. Open:

__ 1HP-24

__ 1HP-25

1. __ IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN:

A. __ Start 1A LPI PUMP.

B. __ Start 1B LPI PUMP.

C. Open:

__ 1LP-15

__ 1LP-16

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7



F. __ GOTO Step 75.

2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN:

A. __ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.

B. __ IF< 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C. __ GO TO Step 76.


Page 38 of 60


75. __ Ensure at least two HPI pumps are operating.

76. Verify open:

__ 1HP-26

__ 1HP-27

1. __ IF HPI has been intentionally throttled, THEN GOTO Step 77.

2. Open:

__ 1HP-26

__ 1HP-27


Page 39 of 60


77. __ IAAT at least two HPI pumps are operating, AND HPI flow in any header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header:

Figure 1

Required HPI Flow Per Header

HPI Pump

Runout Region For 1

Pump In Header

(including seal

injection for A

header)

Unacceptable Region (excluding seal

injection)

1A Header 1B Header

1HP-410 1HP-409


Page 40 of 60



79. Open:

__ 1HP-20

__ 1HP-21


__ GOTO Step 86.

81. Perform all:



NOTE





82. __ Verify any RCP operating __ GO TO Step 86

83. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6




Page 41 of 60



__ GO TO Step 124.


88. Perform both:



NOTE





CAUTION


89. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps.{6, 22}


Page 42 of 60



__ GOTO Step 93.


__ Open 1LP-17.



2. __ Close 1LP-17.


__ Open 1LP-18.

__ Start 1B LPI PUMP. (CT-4)


2. __ Close 1LP-18.



__ 1LP-19 closed

__ 1LP-20 closed

THEN perform Steps 94 -95.

__ GO TO Step 96.

94. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22





Page 43 of 60


98. Start:






100. Verify open:

__ 1CF-1

__ 1CF-2


__ 1CF-1

__ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



105. __ Close 2LPSW-139.



107. __ Close 1LPSW-139.


Page 44 of 60






110. Verify either:



__ GOTO Step 112.

111. Open:

__ 1LPSW-4

__ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5








__ GOTO Step 117.

NOTE





Page 45 of 60


117. __ IAAT ES channels 7 & 8 have actuated, THEN perform Step 118 - 119.

__ GOTO Step 120.

118. Perform all:



NOTE












Page 46 of 60

Unit Status


124. Start:






126. Verify open:

__ 1CF-1

__ 1CF-2


__ 1CF-1 __ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



131. __ Close 2LPSW-139.



133. __ Close 1LPSW-139.


Page 47 of 60






136. Verify either:



__ GOTO Step 138.

137. Open:

__ 1LPSW-4

__ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5










END


Page 48 of 60

Enclosure 5.5



NOTE



• 1A HPI Pump

• 1B HPI Pump

• 1HP-26

• 1HP-7


• 1HP-5





A. Open:

1CS-26

1CS-41


C. Notify SRO.



Page 49 of 60





__ GO TO Step 10.

7. Open:

• 1HP-24

• 1HP-25




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7



F. GO TO Step 8.




C. GO TO Step 9.


Page 50 of 60





__ 1HP-26

1HP-27




Page 51 of 60




__ GO TO Step 12.


• Open 1HP-24.

• Open 1HP-25.

• Close 1HP-16.




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7





NOTE




Page 52 of 60





Open 1HP-17.

Open 1HP-18


Letdown isolated

LPSW available



GO TO Step 35.

16. Open:

__ 1CC-7

__ 1CC-8






__ 1HP-1

__ 1HP-2



20. GO TO Step 23.



GO TO Step 23.

22. GO TO Step 35.


Page 53 of 60






1HP-1

1HP-3


1HP-2

1HP-4


25. Open:

1HP-1

1HP-2

1HP-3

1HP-4





27. __ Close 1HP-6.

28. __ Close 1HP-7.


2. Close:

1HP-8

1HP-9&11



B. Close 1HP-16.



Page 54 of 60





33. Open 1HP-6.


NOTE









LDST level > 55″



THEN close:

1HP-24

1HP-25


Page 55 of 60




__ GO TO Step 40.




C. Close 1CS-46.





__ GO TO Step 42.






Page 56 of 60



CONDITION ACTIONS

1. PR NIs ≥ 5% FP

OR

NIs NOT decreasing

GO TO UNPP tab.

UNPP


{13}





GO TO EHT tab.



GO TO LOHT tab.


GO TO EHT tab.

EHT



GO TO TBF tab.

TBF


ES



ES




ROP



EDL



• Notify OSM to reference the Emergency Plan and NSD 202 (Reportability).

NOTIFY


Page 57 of 60

ICC EP/1/A/1800/001


CONDITION ACTIONS

1. All 4160V SWGR de-energized after ICC tab is entered {13}

GO TO Blackout tab.

BLACKOUT


ES



ES




ROP



• Notify OSM to reference the Emergency Plan and NSD 202 (Reportability).

• Notify plant staff that

Emergency Dose Limits are in affect using PA system.

NOTIFY and EDL


Page 58 of 60

CRITICAL TASKS

CT-1 Ensure the Main Vacuum Pumps are operating prior to the low vacuum Turbine

trip of 21.75 inches hg. CT-2 (BWOG CT-1) Trip all RCPs

RCPs must be secured within 2 minutes of RCS SCM reaching zero per Rule 2. CT-3 (BWOG CT-27) Implementation of Control Room Habitability Guidance

Start the Outside Air Booster Fans within 30 minutes of a LOCA. Not performing this action could result in Control Room habitability issues.

CT-4 Start 1B LPI Pump prior to reaching 700°F CETCs.


UNIT 0 (OSM)

SSF Operable: No KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No








RBNS Rate: 0.01 gpm



Required Date/Time

TS/SLC #

AMSAC/DSS 0300 7 Days SLC 16.7.2

SSF 0400 7 Days TS 3.10.1


Primary

Due to unanalyzed condition, the SSF should be considered INOPERABLE for Unit 1 if power levels are reduced below 85%. Evaluations must be performed prior to declaring the SSF operable following a return to power (after going below 85%).

1RIA-3 and 5 removed from RB.

Rx power ≈ 50% and holding per dispatcher request with no plans to increase power this shift.

SASS is in Manual for calibration

‘C’ GWD tank release is in progress per OP/1-2/A/1104/018

Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to ‘1 PRV System Filter Discharge’. IF 1SA-8/B-9 is due to RIA-32 - ‘1 PRV System Filter Discharge’, it can be considered an expected alarm

The BOP is to pump the RBNS per OP/1/A/1104/007 Encl 4.1 due to high level

Secondary


Unit 2 is supplying the AS header

1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.







Page 1 of 51


________________________ ________________________OATC

________________________ ________________________BOP


Turnover:

SASS is in Manual

AMSAC/DSS is Bypassed


Event No.


Event Description



1 Override C: BOP, SRO HPSW Jockey Pump Trips

2 Override C: OATC, SRO (TS) Inadvertent DPLIAS Actuation

3 MPI500 MPI171

I: OATC, SRO 1A THOT Fails High

4 MPS110 C: BOP, SRO (TS) 1HP-5 Fails Closed (Restore Letdown)

5 MPS247 R: OATC, C: BOP, SRO (TS)

1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

6 N: BOP, SRO Support Activities During Power Decrease and Securing 1B1 RCP

7

MSS010

MSS020

MSS260

MSS270

MSS330

M: ALL

LOHT Requiring CBP Feed

Turbine Fails to Trip When Performing IMAs Requiring EHC Pump Lockout

EFDW Restored From Unit 2



Page 2 of 51

Scenario 3

Event Summary

Event 1: This event will start with the HPSW Jockey Pump tripping off and the BOP will refer to

the Alarm Response Guide for 1SA-9/D-8 (HPSW Jockey Pump Off). Once an operator is dispatched to investigate the cause of the trip, a report will be made to the crew that a scaffold builder accidentally bumped the Jockey Pump breaker. They will also be told that the pump breaker is closed and there is no damage to the Jockey Pump or it’s breaker. The crew will then restart the pump per the ARG.

Event 2: The crew will respond to 1SA-01/E-11 (Diverse LPI Trip) which will direct them to initiate AP/42 (Inadvertent ES Actuation). The crew will bypass Diverse LPI , secure the 1A and 1B LPI pumps, and close 1LP-17 and 1LP-18 (LPI Injection Valves). This will require the SRO to evaluate TS/SLC and enter the appropriate conditions

Event 3: The 1A Loop THOT instrument will fail high which will cause FDW flow to increase and control rods to insert. They should perform Plant Transient Response and take the ICS Diamond and Feedwater Loop Masters to manual and re-ratio FDW to stabilize the plant before the Reactor trips

Event 4: 1HP-5 will fail closed causing a loss of RCS letdown. The crew will enter AP/32 for a Loss of Letdown and minimize charging flow and seal injection to help control RCS inventory. The crew will restore letdown by dispatching an operator to manually open 1HP-5 locally which is a containment isolation valve. This requires an operator stationed locally at the valve in communication with the control room. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions

Event 5: The 1B1 RCP lower seal will fail and crew will refer to Alarm Response Guides which will direct entry into AP/16 (Abnormal RCP Operation). AP/16 will direct the crew to initiate a manual power reduction since ICS will be in manual. Once Reactor power is < 70%, the 1B1 RCP will be secured. Once the RCP is secured, the OATC will have to manually re-ratio FDW to control ΔTc within a band of ± 2°F. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions

Event 6: Once power has been reduced to < 70% in event 5, the BOP will secure the 1E1 and 1E2 Heater Drain Pumps and then secure the 1B1 RCP due to the seal failure.

Event 7: Both Main FDW Pumps will trip which will cause the Reactor to trip. During the performance of Immediate Manual Actions, the turbine will fail to trip which will require the OATC to secure the EHC pumps in order to close the Turbine Stop Valves. The 1A and 1B Motor Driven EFDW Pumps do not start on low SG level and the Turbine Driven EFDW Pump will trip on overspeed. Rule 3 (Loss of Main/Emergency FDW) will be initiated following a Symptoms Check which will establish Condensate Booster Pump feed to manually control RCS temperature and pressure. The SRO will transfer to the LOHT tab of the EOP to direct mitigation activities. Once RCS temperature and pressure are stabilized and Emergency FDW is aligned from Unit 2, the crew will initiate EFDW flow and feed the SGs per Rule 7 which will begin to establish a level in both SGs.


Page 3 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 1 Page 1 of 2 Event Description: HPSW Jockey Pump Trips (C: BOP, SRO)


SRO/BOP

Plant Response:

1SA-9/A-8 HPSW Header A/B PRESS LOW

1SA-9/D-8 HPSW JOCKEY PUMP OFF

OAC Alarm – O1D2146 (HPSW Jockey Pump) OFF

HPSW header pressure decreases due to Jockey Pump trip

Crew Response:

Refer to ARG 1SA-9/D-8

3.1 Verify automatic action until jockey pump is restarted.

3.2 IF there is NO evidence of breaker and/or pump motor problem, attempt to restart jockey pump one time. If restart is unsuccessful, notify Maintenance Department.

Booth Cue: Once dispatched to investigate the Jockey Pump motor/breaker, wait two minutes and call back to report "A scaffold builder bumped the Jockey Pump BKR with a scaffold pole. There is no damage to the breaker and the breaker is closed". If asked about the status of the Jockey Pump, state that there are no problems evident with the Jockey Pump motor.

The crew may refer to ARG 1SA-9/A-8

3.1 Verify proper jockey pump operation

3.2 Refer to SLC 16.9.8a

3.3 Verify HPSW pumps start (start manually if NOT already in operation per OP/0/A/1104/011) when preset levels in EWST are reached

3.4 IF both HPSW Pumps NOT available, Go To EP/1/A/1800/001 Enclosure 5.31 for method of back charging the HPSW system.

3.5 IF HPSW Header Pressure continues to decrease AND Elevated Storage Tank Level is NOT dropping; i.e., altitude valve stuck closed and jockey pump not providing adequate supply, manually start a HPSW Pump.

Refer to OP/0/A/1104/011 (High Pressure Service Water).

3.6 Refer to AP/1-2/A/1700/030 (Aux Building Flood)

3.7 Investigate and correct reason for excessive HPSW usage

3.8 Verify BASE and STANDBY HPSW Pumps stop at 80,000 gals

This event is complete when the Jockey Pump has been restarted, or as directed by the Lead Examiner.


Page 4 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 1 Page 2 of 2 Event Description: HPSW Jockey Pump Trips (C: BOP, SRO)


SRO/BOP

Crew response:

3.9 IF manually started, return HPSW Pumps when NO longer needed

3.9.1 Ensure ‘B’ HPSW Pump in “BASE”

3.9.2 Ensure ‘A’ HPSW Pump in “STANDBY”

The crew may refer to the ARG for O1D2146 (HPSW Jockey Pump)

1. IF there is NO evidence of breaker and/or pump motor problem, THEN attempt to restart jockey pump one time. If restart is unsuccessful, contact SPOC.

2. Refer to OP/0/A/1104/011 (High Pressure Service Water)

This event is complete when the Jockey Pump has been restarted, or as directed by the Lead Examiner.


Page 5 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 2 Page 1 of 5 Event Description: Inadvertent DLPIAS Actuation (C: OATC, SRO) (TS)


BOP

SRO/OATC


1SA-01/E-11, Diverse LPI Trip

1SA-07/D-3, ES ODD VOTERS TROUBLE

1SA-07/E-3, ES EVEN VOTERS TROUBLE

DLPIAS tripped red light Illuminated

LPI Pumps start

LPI injection aligned

LPSW Pumps start

Crew Response:

ARG: 1SA-01/E-11 (Diverse LPI Trip)

3.1 Determine if DLPIAS condition exists (RCS pressure ≤ 462 psig).

3.2 IF RCS pressure is ≤ 462 psig, Go To EP/1/A/1800/001 (Emergency Operating Procedure).

3.3 IF ES condition does NOT exist, Initiate AP/1/A/1700/042 (Inadvertent ES Actuation).

3.4 Refer to OP/1/A/1105/014 (Control Room Instrumentation Operation And Information).

AP/1/A/1700/042 (Inadvertent ES Actuation) rev 004

4.1 Verify any of the following have inadvertently actuated:

Diverse HPI

ES Channel 1

ES Channel 2

RNO: GO TO Step 4.4


ES Channel 5

ES Channel 6

RNO: 1. IF ES Channel 1, ES Channel 2, or Diverse HPI have inadvertently actuated, AND it is desired to restore letdown, THEN initiate AP/42 Encl 5.2 (Letdown Restoration).

2. GO TO Step 4.10.

This event is complete when Enclosure 5.1 is completed and TS/SLCs have been addressed IAW step 4.25, or as directed by the Lead Examiner.


Page 6 of 51



SRO/OATC


4.10 Close the following:

1HP-24

1HP-25

NOTE If personnel are available, progression should continue while Encl 5.1 (Required Operator Actions) is in progress.

4.11 Ensure AP/42 Encl 5.1 (Required Operator Actions) is in progress. (Page 8)


Diverse LPI

ES Channel 3

ES Channel 4

4.13 Verify Diverse LPI has inadvertently actuated.

Examiner Note: Placing Diverse LPI in BYPASS will actuate Statalarm 1SA-01/E-10. This is an expected alarm.

4.14 Ensure DIVERSE LPI BYPASS is in BYPASS

4.15 Perform the following on all inadvertently actuated system(s):

Ensure ES CH-3 is in MANUAL (does not apply)

Ensure ES CH-4 is in MANUAL (does not apply)

4.16 Verify LPI was aligned in decay heat removal mode prior to ES actuation.

RNO: 1. Stop the following:

1A LPI PUMP

1B LPI PUMP

2. Simultaneously close the following:

1LP-17

1LP-18

4.17 Verify the Rx is critical.



Page 7 of 51



SRO/OATC


CAUTION Do NOT add demin water to counter the boration until RCS boron concentration stabilizes to prevent a positive reactivity event.

Note: The crew may initiate EOP Encl 5.5 for inventory control. These steps are included beginning on (page 42) if necessary.

NOTE ICS in Auto means ICS is in control of Tave and Rx power.

4.18 Verify ICS in Auto

4.19 Verify control rods are outside the desired control band (they are not)



ES Channel 1

Diverse HPI


4.24 Notify SPOC to investigate and repair the cause of the inadvertent ES actuation, as necessary.

4.25 Initiate logging TS/SLC Entry/Exit, as applicable, in accordance with Encl 5.4 (TS/SLC Requirements). (see page 9)

4.26 WHEN all the following exist:

Reason for inadvertent ES Channel or Diverse HPI/LPI actuation has been resolved

ES Channel or Diverse HPI/LPI reset is desired

OSM concurs

THEN continue.



Page 8 of 51



SRO/BOP

AP/1/A/1700/042 Encl 5.1

Crew Response:

AP/1/A/1700/042 Encl 5.1 (Required Operator Actions)

1 Initiate announcement of AP Entry using the PA system.

NOTE If channels are bypassed or in override, 1SA-1/A-10 (ES 1 Trip) and 1SA-1/B-10 (ES 2 Trip) will be off even though the channel may have actuated.

2 Verify any of the following have inadvertently actuated:

Diverse HPI

ES Channel 1

ES Channel 2

RNO: GO TO Step 5


ES Channel 7

ES Channel 8

RNO: GO TO Step 9

9 Perform the following:

A. Open the following to restore RB RIAs:

1PR-7

1PR-8

1PR-9

1PR-10

B. From the ENABLE CONTROLS screen on the RIA View Node, perform the following:

1) Select OFF for RB RIA sample pump.

2) Start the RB RIA sample pump.


Diverse HPI

ES Channel 1

RNO: GO TO Step 12

12 EXIT this enclosure.



Page 9 of 51



SRO

Crew Response:

Examiner Note: SLC 16.7.6 will apply due to the automatic actuation logic being blocked if any Diverse Actuation system is in OVERRIDE or BYPASS.

SLC 16.7.6 (Diverse Actuation Systems)

Condition A (7 days) Restore DLPIAS to FUNCTIONAL status.

Examiner Note: If OAC alarm is received for LPSW leakage accumulator,

TS 3.7.7 will apply.

TS 3.7.7 (LPSW System)


Examiner Note: The RB RIA sample pump will be stopped and started by the BOP per AP/42 Encl 5.1 Step 9. TS 3.4.15 will apply while the sample pump is OFF.

TS 3.4.15 (RCS Leakage Detection Instrumentation)

Condition B (Once per 24 hours) Analyze grab samples of the containment atmosphere

OR

(Once per 24 hours) Perform SR 3.4.13.1

AND

(30 days) Restore required containment atmosphere radioactivity monitor to OPERABLE status



Page 10 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 3 Page 1 of 4 Event Description: 1A Thot Fails High (I: OATC, SRO)


OATC

CT-1

BOP

SRO

Plant Response:

1A Th will fail HIGH

Tave will indicate HIGH

Feedwater flow will increase

Control Rods will insert

1SA-2/B-3 (RC Hot Leg Temp High)

1SA-2/B-4 (RC Average Temperature High/Low)

1SA-2/A-12 (ICS Tracking) Crew Response:

When the Statalarms are received, the candidates should utilize the “Plant Transient Response” process to stabilize the plant.

OATC should:







Note: The OATC will have to reduce FDW in order to stabilize power below the pre-transient level.

The BOP should:




The CRS should:



This event is complete when the SRO reaches Step 6 (WHEN) in AP/28 Section 4A, or as directed by the Lead Examiner.


Page 11 of 51



BOP


AP/1/A/1700/028 (ICS Instrument Failures) Rev 20












Emergency Plan

__ STA






Page 12 of 51



SRO/OATC

AP/1/A/1700/028 Encl 4A Crew Response:


OAC alarm video

OAC display points




√ Section Failure

4A RCS Temperature

AP/1/A/1700/028 Section 4A

AP/1/A/1700/028, Section 4A (RCS Temperature Failure)

NOTE If Tave instrument circuit failed high, the following may have occurred

depending on initial ICS station status:


Control Rod insertion

Feedwater flow increase

If Tave instrument circuit failed low, the following may have occurred depending on initial ICS station status:


Control Rod withdrawal

Feedwater flow decrease

Feedwater re-ratio



Page 13 of 51



SRO/OATC

AP/1/A/1700/028 Section 4A Crew Response:


__ 1A FDW MASTER

__ 1B FDW MASTER



__ Select a valid RCS Tave and Delta Tc input to ICS per AM/1/A/0326/020 (Control of Unit 1 Star Module Signal Selection Function).

__ Investigate and repair the failed RCS temperature instrumentation.

4. PERFORM an instrumentation surveillance using applicable table in Encl 5.2 (ICS Instrument Surveillances) for the failed instrument. (see next page)



Booth Cue: If the crew asks, Unit 2 will perform the surveillance evaluation.

6. WHEN notified by SPOC that a valid RCS Tave and Delta Tc input have Been restored to ICS, THEN GO TO OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).


Examiner Note: If RCS pressure decreases below 2125 psig, TS 3.4.1 will

apply if Reactor power stabilizes at ≥ 96 (inside the steady state band of 4%) during Plant Transient Response.

TS 3.4.1 RCS Pressure, Temperature, & Flow DNB Limits

Condition A (2 hours) One or more RCS DNB parameters not within limits

Required Action: Restore RCS DNB parameter(s) to within limit



Page 14 of 51


Page 15 of 51


Event Description: 1HP-5 Fails Closed (Restore Letdown) (C:BOP, SRO) (TS)


SRO/BOP


OAC alarm: HPI LETDOWN FLOW

Letdown flow = 0 gpm

1HP-5 indicates closed Crew Response:

SRO should enter AP/1/A/1700/032 (Loss of Letdown) AP/1/A/1700/032 (Loss of Letdown) rev 006

NOTE This AP may be performed by an RO if the EOP is also in progress. The Procedure Director should resume directing the actions of this AP as soon as EOP actions allow.

4.1 Place 1HP-120 in HAND and reduce demand to zero.

4.2 Position the standby HPI pump switch to OFF.

CAUTION RCP individual seal return valves will close if seal injection is < 22 gpm with CC flow < 575 gpm.

4.3 Throttle 1HP-31, preferably in AUTO, to establish SEAL INLET HDR FLOW to the appropriate value:

√ CC TOTAL FLOW

Throttle HPI Seal flow to:

> 575 gpm 12-15 gpm

≤ 575 gpm 24-25 gpm

NOTE The running HPI pump may operate below 65 gpm for up to 4 hours. HPI pump time of operation below minimum flow is cumulative.

4.4 Verify HPI pump flow ≥ 65 gpm. Note: Flow will be < 65 gpm. 30 + ___ +___ = ___ gpm Recirc + SI + MU

RNO: Log beginning time for HPI pump flow below minimum.

4.5 Initiate makeup to LDST as required.

This event is complete when the Standby HPI pump is placed in AUTO, or as directed by the Lead Examiner.


Page 16 of 51




SRO/OATC


4.6 Initiate notification of the following :



Emergency Plan

__ STA

4.7 Verify 1HP-5 closed.

4.8 Dispatch an operator to 1HP-5 (Letdown Isolation) (East Pen Rm) to establish communication with Control Room.

NOTE

Tech Spec 3.4.9 applies when indicated Pzr level > 260” (corrected value for 285”).

Conditions where it is known that letdown CANNOT be restored do not require waiting until 260” to begin a Rapid Shutdown.

4.9 IAAT either of the following exist:

Pzr level > 260”, AND letdown CANNOT be established

Plant conditions exist such that letdown will NOT be restored

THEN initiate unit shutdown per AP/29 (Rapid Unit Shutdown).

4.10 IAAT Pzr level ≥ 375”, THEN trip Rx. 4.11 Determine the cause of loss of letdown AND GO TO designated

mitigation Step:

√ Reason for Loss of Letdown

GO TO

Step

1HP-5 failed closed 4.12 Actual LD Temp high

LD interlock failure

LD line leak

Both LD Coolers isolated

Other

4.28

4.12 Close 1HP-6.



Page 17 of 51




SRO/OATC

AP/1/A/1700/032

Crew Response:

4.13 Close 1HP-7.

4.14 Open 1HP-5 (1HP-5 will NOT open from the control room).

RNO: 1. Notify operator dispatched to 1HP-5 to:

A. Manually open 1HP-5 (LETDOWN ISOLATION)(East Pen Rm).

Booth Cue: When notified to open 1HP-5, FIRE TIMER 13 to manually open 1HP-5. Wait at least 15 seconds and report back that 1HP-5 is manually open.

B. Maintain continuous communication with Control Room.

2. IF 1HP-5 is manually open, THEN enter TS 3.6.3. (see page 18)

4.15 Place the CC system in operation.

4.16 Verify letdown temperature < 135°F.

4.17 Throttle open 1HP-7 to establish ≈ 20 gpm.

4.18 WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.

4.19 Open 1HP-6

4.20 Adjust 1HP-7 to control desired letdown flow.

4.21 Re-establish normal makeup through 1HP-120.

Examiner Note: Normal makeup may include placing 1HP-120 in AUTO.

4.22 Verify any purification IX in service.

4.23 Notify SPOC to initiate repairs on 1HP-5.

4.24 Re-establish normal RCP seal injection flow.

4.25 Position the standby HPI pump switch to AUTO.

4.26 WHEN repairs are compete on 1HP-5 (LETDOWN ISOLATION) (East Pen Rm), THEN perform the following:

A. Locally turn 1HP-5 handwheel fully clockwise.

B. EXIT TS 3.6.3.

4.27 EXIT

Examiner Note: 1HP-5 will not be repaired for this scenario.



Page 18 of 51




SRO

TS 3.6.3 CONTAINMENT ISOLATION VALVES

Condition A (4 hours) Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, one closed and de-activated non-automatic power operated valve, closed manual valve, blind flange, or check valve with flow through the valve secured

AND

(Once per 31 days) Verify the affected penetration flow path is isolated.

Note: Penetration flow paths except for 48 inch purge valve penetration flow paths may be un-isolated intermittently under administrative controls.

TS 3.6.3 Bases, Administrative Controls: The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following:

(1) stationing an operator, who is in constant communication with control room, at the valve controls,

(2) instructing this operator to close these valves in an accident situation, and

(3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment (Ref. 5).

Examiner Note: If pressurizer level exceeds 260 inches, TS 3.4.9 would

also be entered.

TS 3.4.9 PRESSURIZER

Condition A (1 hour) Restore Pressurizer water level to within limit

Examiner Note: If RCS pressure decreases below 2125 psig, TS 3.4.1 will

apply if Reactor power stabilizes at ≥ 96 (inside the steady state band of 4%) during Plant Transient Response in Event 3.

TS 3.4.1 RCS Pressure, Temperature, & Flow DNB Limits

Condition A (2 hours) Restore RCS DNB parameter(s) to within limit



Page 19 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 5/6 Page 1 of 10 Event Description: 1B1 RCP Lower Seal Failure (Requires Manual Power Reduction)

(R: OATC, C:BOP, SRO) (TS)


SRO/BOP

Plant Response:

1SA-06/C-5 (RC PUMP 1B1 SEAL CAVITY PRESS HI/LOW)

OAC Alarm RCP 1B1 LOWER SEAL CAVITY PRESSURE HI HI

OAC Alarm RCP 1B1 UPPER SEAL CAVITY PRESSURE HI HI

OAC Alarm 1B1 UPPER & LOWER SEAL ΔP

Crew response:

Refer to the ARGs

3.1 Upper/Lower Seal Cavity Pressure High

3.1.1 Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action

3.2 Upper/Lower Seal Cavity Pressure Low

3.2.1 IF in Mode 1 or 2, Go To AP/1/A/1700/016, Abnormal RCP Operation, for limits and required action

AP/1/A/1700/016 (Abnormal RCP Operation) rev 033

4.1 IAAT any RCP meets immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria), THEN perform Steps 4.2 - 4.11. (Immediate trip criteria will NOT be met)


4.12 IAAT either of the following apply:

__ Any RCP approaching immediate trip criteria of Encl 5.1 (RCP Immediate Trip Criteria)

__ There is an immediate need to stop a RCP at this time

THEN perform Steps 4.13 - 4.15.

RNO: GO TO Step 4.16 (see page 22)

Examiner Note: It is acceptable for the SRO to take either procedure path to secure the 1B1 RCP. Step 4.16 is page 20.

4.13 Verify Rx Power > 70%

4.14 Initiate Encl 5.2 (Rapid Power Reduction) (see page 25)

4.15 WHEN Rx Power is ≤ 70%, THEN GO TO Step 4.2

This event is complete when 1B1 RCP is secured and ΔTc is within 0 ± 2°F, or as directed by the Lead Examiner.


Page 20 of 51




SRO/BOP


4.2 Verify MODE 1 or 2

4.3 Verify Rx power is ≤ 70% as indicated on all NIs

4.4 Verify three RCPs will remain operating after affected RCP is tripped

4.5 Verify any SG on Low Level Limits

RNO: GO TO Step 4.8

4.8 Verify FDW masters in Auto

RNO: 1. Stop affected pump

2. Manually adjust FDW masters to achieve desired ΔTc

3. GO TO Step 4.29

4.29 IAAT any of the following indicate external RCP seal leakage:

__ RB RIAs increasing or in alarm

__ RCS Tave constant with LDST level decreasing more than normal

__ Quench Tank level rate increasing

__ RB Normal Sump rate increasing

__ Visual confirmation

THEN initiate AP/02 (Excessive RCS Leakage).

4.30 Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (Page 26)

4.31 IAAT either of the following conditions is met:

__ a RCP has been shut down for ≥ 3 hours

__ a RCP with high oil level has been shut down

THEN close the associated RCP motor cooler inlet/outlet valve:

__ 1LPSW-7&8 (1A1 RCP)

__ 1LPSW-9&10 (1B1 RCP)

__ 1LPSW-13&14 (1A2 RCP)

__ 1LPSW-11&12 (1B2 RCP)


CAUTION Total FDW flow should be maintained constant to prevent changes in core reactivity


Page 21 of 51




SRO/BOP

AP/1/A/1700/016

4.32 IAAT either of the following has exceeded 260°F including transient situations:

__ O1A1253 - O1A1256 (RCP UPPER SEAL HOUSING TEMP)

__ O1A1910 - O1A1913 (RCP SEAL RETURN TEMP)

THEN closely monitor seal parameters for degradation until an Engineering evaluation is completed due to potential for seal ring and elastomer damage.

NOTE Operating experience has shown that failure of RC Pump components located internal to the RCS can create loose debris which can lead to fuel clad failures. These type RC Pump failures may cause Loose Parts Monitor alarms immediately and increased RCS radioactivity later.

4.33 Verify 1RIA 57 or 1RIA 58 have increased.


4.35 IAAT a RCP has been tripped due to exceeding Immediate Trip Criteria on a RCP motor, THEN contact RCP engineer prior to restart.

4.36 IAAT both are met:

__ There has been a failure of the DELTA Tc controller

__ The DELTA Tc controller has been repaired

THEN initiate OP/1/A/1102/004 A Encl (Placing ICS Stations To Auto).

4.37 Verify any RCP that was shut down had a high vibration alarm.

4.38 Initiate a PIP for Engineering to document potential vibration effects on RCS piping.

4.39 WHEN conditions permit, THEN EXIT this procedure.



Page 22 of 51




SRO/BOP

AP/1/A/1700/016

Alternate Path from Step 4.12

4.16 Announce AP entry using the PA system

4.17 Notify OSM to request evaluation by RCP Component Engineer

4.18 IAAT the failure is identified, THEN GO TO the applicable section per the following table:

√ Section Failure

4A Seal Failure

4B Abnormal Vibration

4C High or Low Oil Pot Level

4D Loss of Seal Return

4E Abnormal RCP Temperatures

AP/1/A/1700/016 Section 4A (RCP Seal Failure)

1. IAAT any RCP meets immediate trip criteria of Encl 5.1, THEN perform Steps 2-11 (Immediate trip criteria will NOT be met)

RNO: GO TO Step 12

12. IAAT any of the following indicate external RCP seal leakage:

RB RIAs increasing or in alarm

RCS Tave constant with LDST level decreasing more than normal

Quench Tank level rate increasing

RB Normal Sump rate increasing

Visual confirmation

THEN initiate AP/02 (Excessive RCS Leakage)

13. Verify the following are open:

__ 1HP-20

__ 1HP-21



Page 23 of 51




SRO/BOP

AP/1/A/1700/016

14. Verify the following is open for the affected RCP:

1HP-232 (1B1 RCP)

15. IAAT either of the following conditions apply to an operating RCP:

√ RCS Pressure ∆P across any seal

> 1000 psig ≤ 100 psid

≤ 1000 psig ≤ 35 psid

OR shut down of an RCP is desired, THEN perform Steps 16-26 to shut down the affected RCP.

16. Verify MODE 1 or 2

17. Verify three RCPs will remain operating after affected RCP is tripped

18. Verify Rx power is ≤ 70% as indicated on all Nis

Examiner Note: Focus Brief opportunity

RNO: 1. Direct an RO to initiate Encl 5.2 (Rapid Power Reduction) (see page 25)

2. WHEN Rx power is ≤ 70% on all NIs, THEN continue this procedure

19. Verify any SG on Low Level Limits

RNO: GO TO Step 22


NOTE

A single failed seal can transport debris to the other seals and damage them. A RCP with a failed seal should be secured as quickly as plant conditions allow.

Use diverse indications, such as changes in other seal pressures, to ensure abnormal parameter is not a single instrument failure. For any seal failure, upper and lower seal cavity pressures should change from normal value.


Page 24 of 51




BOP OATC

AP/1/A/1700/016

22. Verify FDW masters in Auto


RNO: 1. Stop the affected pump

2. Manually adjust FDW masters to achieve desired ∆Tc

3. GO TO Step 25

25. Initiate Encl. 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 (Operation at Power). (see page 26)

26. Initiate the following notifications:

__ Notify OSM to make required notifications of OMP 1-14 (Notifications).

__ Notify Rx Engineering and request a power maneuver plan, if needed.

__ Notify SOC if load reduction was required.

__ Notify Chemistry to take RCS boron samples on a 1 hour frequency.

27 IAAT a RCP has been shut down for ≥ 3 hours THEN close the associated RCP motor cooler inlet/outlet valve:

__ 1LPSW-7&8 (1A1 RCP)

__ 1LPSW-9&10 (1B1 RCP)

__ 1LPSW-13&14 (1A2 RCP)

__ 1LPSW-11&12 (1B2 RCP)

28 IAAT either of the following has exceeded 260°F including transient situations:

__ O1A1253 - O1A1256 (RCP UPPER SEAL HOUSING TEMP)

__ O1A1910 - O1A1913 (RCP SEAL RETURN TEMP)

THEN closely monitor seal parameters for degradation until an Engineering evaluation is completed due to potential for seal ring and elastomer damage.


CAUTION Total FDW flow should be maintained constant to prevent changes in core reactivity


Page 25 of 51




SRO/OATC

BOP

AP/1/A/1700/016 Encl 5.2

AP/16 Enclosure 5.2 (Rapid Power Reduction)

1. Verify ICS in AUTO

RNO: 1. Notify SRO to provide target power level, average power reduction rate, and control bands, as required

2. Initiate manual power reduction to ≤ 70%

3. WHEN Rx Power ≤ 70% as indicated by all Nis , THEN notify CRS

4. Stop the following pumps:

__ 1E1 HTR DRN PUMP

__ 1E2 HTR DRN PUMP

5. GO TO Step 7

7. Verify Rx Power was reduced ≥ 15% within a 1 hour period

8. Notify Primary Chemistry to perform Tech Spec SR 3.4.11.2 as required

9. EXIT this enclosure Examiner Note: Once Reactor power is reduced to below 85%, the

SSF must be declared inoperable and therefore Tech Spec 3.10.1 applies.

TS 3.10.1 STANDBY SHUTDOWN FACILITY (SSF)

Conditions A-E (7 Days) Restore to OPERABLE status



Page 26 of 51




OP/1/A/1102/004 Encl 4.3

OP/1/A/1102/004 (Operations At Power) Encl 4.3 (Special Instructions For < 4 RCP Operations) Rev 147

2.1 IF conditions permit, log the current quadrant power tilt and the position of the ΔTC controller prior to securing a RCP during power operations.

NOTE Instructions for performing OAC trends are located in Working With

Trends enclosure of OP/0/A/1103/020 A (Operator Aid Computer Use).

Only the first 6 points will be displayed initially; press "Page Down" key to see second 6 points.

2.2 Using turn-on code T6 3RCP, digitally trend the following data at one minute intervals:

Point ID Description O1P0889 CORE THERMAL POWER BEST O1P0877 INCORE IMBALANCE O1E3335 API GROUP AVE FOR GROUP 7 O1E3336 API GROUP AVE FOR GROUP 8 O1P0737 INCORE TILT QUADRANT W-X O1P0738 INCORE TILT QUADRANT X-Y O1P0739 INCORE TILT QUADRANT Y-Z O1P0740 INCORE TILT QUADRANT Z-W O1I0828 RC COLD LEG A1 TEMP O1I0829 RC COLD LEG A2 TEMP O1I0830 RC COLD LEG B1 TEMP O1I0831 RC COLD LEG B2 TEMP

2.3 After steady state conditions are attained, perform the following:

2.3.1 Check NI calibration.

2.3.2 IF NI calibration is NOT within requirements of Limit and Precaution Step 2.2.6, calibrate NIs to Thermal Power Best.

NOTE: The 100% Power Imbalance curves also apply for runs at reduced power.

2.4 Maintain Control Rod position and Power Imbalance within COLR limits.



Page 27 of 51




OP/1/A/1102/004 Encl 4.3

NOTE: The Maximum Allowed Power Setpoint (Pmax) is reduced when operating for extended periods with a 3 RC Pump Configuration as a conservative action.

2.5 Perform the following:

2.5.1 IF expected to operate for an extended period of time with only 3 RCPs operating, notify I&E to adjust Flux/Imbalance /Flow trip setpoints for 3 RCP operation per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions). (R.M.) ________________________ _____ Person Notified Date

2.5.2 IF AT ANY TIME Quadrant Power Tilt problems exist, notify I&E

to Adjust Flux/Imbalance/Flow trip setpoints as required to comply with TS 3.2.3 per AM/1/A/0315/017 (TXS RPS Channels A, B, C, And D Parameter Changes For Abnormal/Normal Operating Conditions). (R.M.) ________________________ _____ Person Notified Date

NOTE

Operations Management/Reactor Engineering Group should be consulted for value to use for high flux alarm setpoint.

Instructions for Adjusting Alarm Setpoints On The NI Recorder are in OP/0/A/1108/001 (Curves And General Information).

2.6 Adjust high flux alarm setpoint per Operations Management/Reactor Engineering Group recommendations. (Alarm setpoint is adjusted on the NI Recorder). (R.M.)

NOTE: 'D' bleed pressure may NOT be high enough to run the FDWP turbines.

2.7 Maintain Auxiliary Steam available to the FDWP turbines.



Page 28 of 51




OP/1/A/1102/004 Encl 4.3

2.8 IF 1SSH-9 (SSH DISCH CTRL BYPASS) is being used to control Steam Seal Header pressure, throttle 1SSH-9 as required to maintain desired SSH pressure during the load reduction to secure an RCP.

NOTE RCS pressure decrease in the loop with two RCPs running is expected. This may cause acceptance criteria of PT/1/A/0600/001 (Periodic Instrument Surveillance) NOT to be met.

2.9 Place note on CR turnover sheet indicating the following:

"Be aware of the effect of the indicated pressure on the margin to trip setpoint for the Reactor Protective System trips associated with RCS pressure."



Page 29 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 1 of 9 Event Description: LOHT Requiring CBP Feed (M: All)


SRO

OATC

CT-2

BOP

Plant Response:

Both MFWPs trip

Reactor Trips

MD EFDWPs do NOT start

TD EFDWP overspeeds and trips

Crew Response:

SRO directs the OATC to perform IMAs and the BOP to perform a Symptom Check

IMAs EOP Immediate Actions

3.1 Depress REACTOR TRIP pushbutton

3.2 Verify reactor power < 5% FP and decreasing

3.3 Depress turbine TRIP pushbutton

3.4 Verify all turbine stop valves closed

RNO: Place both EHC pumps in PULL TO LOCK

3.5 Verify RCP seal injection available SYMPTOM CHECK

The BOP will perform a Symptom Check:










CSAE Offgas alarms




BOP will perform Rule 3 due to a loss of ALL Feedwater: (Page 33)

This event is complete when EFDW is established from Unit 2, or as directed by the Lead Examiner.


Page 30 of 51



LOHT Tab Crew Response:

SRO will transfer to the Subsequent Actions tab of the EOP.

SRO will refer to Subsequent Actions Parallel Actions Page and transfer to the LOHT tab.. (see page 40)

SRO will refer to the LOHT Parallel Actions Page and direct an RO to announce plant conditions and notify the SM to reference the Emergency Plan and AD-LS-ALL-0006 (page 41)

Loss of Heat Transfer Tab (LOHT)

1. Ensure Rule 3 is in progress or complete

2. IAAT the RCS heats to the point where core SCM = 0°F, THEN GO TO Step 4.

3. IAAT NO SGs can be fed with FDW (Main/CBP/Emergency/PSW), AND any of the following exist:

__ RCS pressure reaches 2300 psig OR NDT limit

__ PZR level reaches 375" (340" acc)

THEN GO TO Step 4

NOTE: 1A1 RCP provides the best Pzr spray.

RNO: 1. Reduce operating RCPs to one pump/loop.

2. WHEN any exists:

__ EFDW or PSW SG feed flow has been re-established by existing Rules/Enclosures

__ EFDW aligned from another unit

__ Operator performing Rule 3 or Encl. 5.27 reports EFDW available

THEN GO TO Step 50

50. Verify EFDW or PSW flow has been re-established to any SG per Rule 3 or Encl. 5.27 (it has not).

RNO: GO TO step 52.


NOTE

Transfer to LOSCM tab is NOT required if RCS heats to the point where core SCM = 0F.


Page 31 of 51



BOP


52. Verify Unit 1 EFDW available.

RNO: GO TO step 56.

56. Confirm ability to feed any intact SG:

A. Throttle EFDW control valve on each intact SG until flow confirmed

B. WHEN flow confirmed, THEN close valve on each intact SG

57. Perform a brief to discuss operator roles for restoring EFDW flow to the SGs.

58. Verify all:

Tcold > 510°F

TBVs available

59. Verify Tcold ≤ 547°F

Examiner Note: The crew will perform Step 59 based on where they stabilize RCS temperature during CBP feed.

RNO: 1. Set THP setpoint at ≈ 885 psig

2. GO TO step 62

60. Determine Psat for existing RCS temperature (RCS Psat)

61. Adjust THP setpoint to RCS Psat minus 140 psi:

Setpoint = RCS Psat (psia) - 140 psi = ______ psig

62. Place TBVs in AUTO for available SGs.

63. Initiate feed to available SGs per Rule 7 (SG Feed Control) (p. 38)

64. IAAT heat transfer is established in any SG, THEN GO TO Step 75.

75. Control feeding and steaming of available SGs to maintain SG level at setpoint and cooldown rate within Tech Spec limits:

Tcold ≥ 270°F: ≤ 50°F / 1/2 hour

Tcold < 270°F: ≤ 25°F / 1/2 hour

76. Close all loop high point vents: (already closed)

1RC-155

1RC-156

1RC-157

1RC-158



Page 32 of 51




77. WHEN all SCMs are > 0°F, OR HPI flow is established, THEN continue.

78. Verify indications of SGTR ≥ 25 gpm.

RNO: GO TO step 80


81. Verify either:

Any SG isolated

Any SG has an unisolable steam leak

RNO: GO TO step 83.

83. GO TO Subsequent Actions.

EOP Subsequent Actions EOP Subsequent Actions

4.1 Verify all control rods in Groups 1–7 fully inserted.

4.2 Verify Main FDW in operation.

RNO: 1. Ensure Rule 3 is in progress or complete.

2. GO TO Step 4.5

4.5 IAAT Main FDW is operating, AND level in any SG is > 96% on the Operating Range, THEN perform Steps 4.6 - 4.8.


4.9 IAAT TBVs CANNOT control SG pressure at desired setpoint, AND TBVs not intentionally isolated, THEN manually control pressure in affected SGs using either:

__ TBVs

__ Dispatch two operators to perform Encl 5.24

4.10 Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating.

4.11 GO TO Step 4.14

4.14 Verify 1MS-17 and 1MS-26 are closed

RNO: Dispatch an operator with Encl 5.29 (MSRV Locations) to verify all MSRVs have reseated



Page 33 of 51



Rule 3

Crew Response:

Rule 3 (Loss of Main or Emergency FDW)

1. Verify loss of Main FDW and/or EFDW was due to TBF.

RNO: GO TO Step 3


RCS pressure reaches 2300 psig or NDT limit.

PZR level reaches 375” (340” acc)

THEN PERFORM Rule 4 (HPI Forced Cooling)

4. Start operable EFDW pumps, as required, to feed all intact SGs.

5. Verify any EFDW pump operating.

RNO: GO TO Step 7

7. Place 1FDW-315 and 1FDW-316 in MANUAL and closed.

8. Verify both:

Any CBP operating

TBVs available on an intact SG

9. Select OFF for both digital channels on AFIS HEADER A.

10. Select OFF for both digital channels on AFIS HEADER B.

11. Place 1FDW-33 and 1FDW-42 switches in OPEN

12. Simultaneously position 1FDW-35 and 1FDW-44 (Startup Control Valves) to 10 – 20% open.


Place 1FDW-31 and 1FDW-40 switches in CLOSE.

Close 1FDW-32 and 1FDW-41.



Page 34 of 51



CT-3


14. Verify Rule 4 (HPI Forced Cooling) in progress.

RNO: 1. Lower SG pressure in available SGs to ≈ 500 psig

2. Control FDW flow to stabilize RCS P/T by throttling the SU CVs and TBVs as necessary

3. Notify CRS that CBP feed is in progress

4. Place 1FDW-38 and 1FDW-47 switches to OPEN

5. Place 1FDW-36 and 1FDW-45 switches to CLOSE

6. GO TO Step 16

16. Verify 1TD EFDW Pump is operable and available for manual start.

17. Dispatch an operator to perform Encl. 5.26 (Manual Start of TD) (PS)

18. Verify cross-tie with Unit 2 is desired.

19. Dispatch an operator to open 2FDW-313 & 2FDW-314.

20. Dispatch an operator to 1FDW-313 and have them notify the CR when in position.

21. Notify alternate unit to:

Place both EFDW control valves in MANUAL and closed.

Start their TD EFDW Pump

22. IAAT SGs are NOT being fed from any source AND PSW SG Feed available, THEN establish SG feed from PSW using Encl. 5.45 (PSW Feed and RCP Seals).

23. WHEN either exists:

Operator is in position at 1FDW-313

Unit 1 TD EFDW Pump has been manually started

THEN continue.

Booth Cue: Notify crew that AO is in position at 1FDW-313.

Examiner Note: EFDW will be cross-connected with Unit 2.


CAUTION Until SGs are dry, lower SG pressure slowly to prevent overcooling.


Page 35 of 51




24. IAAT an operator is in position at 1FDW-313, AND Unit 1 TDEFDW Pump is NOT operating, THEN notify the operator to open:

1FDW-313 (1A EFDW Line Disch to 1A S/G X-conn)

1FDW-314 (1B EFDW Line Disch to 1B S/G X-conn)

Booth Cue: Once an AO is directed to open 1FDW 313 & 1FDW-314, FIRE TIMER 15 and notify crew 1FDW-313/314 and 2FDW-313/314 are open.

25. Verify either exists:

HPI Forced Cooling is maintaining core cooling

CBP feed providing SG feed (applies)

26. WHEN either exists:

Unit 1 TDEFDW Pump running

Alignment complete from alternate unit

THEN notify CRS of the following:

Source of EFDW availability

Rule 3 actions are continuing

27. IAAT CBPs were feeding the SGs, AND CBP feed has been lost, THEN:

Position TBVs as desired by CRS

Close 1FDW-35

Close 1FDW-44

28. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform steps 29 - 33.

RNO: GO TO Step 34

34. Verify any SCM ≤ 0°F.

RNO: IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control), THEN throttle EFDW , as necessary. (see page 38)


NOTE Procedure must continue while cross connects are being opened.


Page 36 of 51



SRO/OATC

BOP


35. Notify the alternate unit to:

Monitor EFDW parameters

Maintain UST level > 7.5'.

Enter appropriate TS/SLC for EFDW valves closed in manual.

36. IAAT Unit 1 EFDW is in operation, THEN initiate Encl. 5.9 (Extended EFDW Operation). (applies if Unit 1 TDEFDW Pump running).

37. WHEN directed by CRS, THEN EXIT.

EOP Encl 5.9 Encl. 5.9 (Extended EFDW Operation)

1. Monitor EFDW parameters on EFW graphic display.

2. IAAT UST level is < 4', THEN GO TO Step 120.

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform Steps 4 - 7.

RNO: GO TO step 8.

8. Perform as required to maintain UST level > 7.5':

Makeup with demin water.

Place CST pumps in AUTO.

9. IAAT all exist:

Rapid cooldown NOT in progress

__ MD EFDWP operating for each available SG

__ EFDW flow in each header < 600 gpm

THEN place 1 TD EFDW PUMP switch in PULL TO LOCK.



Page 37 of 51

Op-Test No.: ILT16-1 Scenario No.: 3 Event No.: 7 Page 9 of 9 Event Description:


EOP Encl 5.9

Crew Response:

10. Verify 1 TD EFDW PUMP operating.

RNO: GO TO step 12.

11. Start TD EFDWP BEARING OIL COOLING PUMP.

NOTE Loss of the condensate system for ≥ 25 minutes results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CRS deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 is 10% open. If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.

12. Notify CR SRO to set priority based on the NOTE above and EOP activities.

Examiner Note: The CRS will most likely direct the RO to suspend

Encl. 5.9 at this point due to higher priorities.



Page 38 of 51

Rule 7 Feed Flow Rates


Page 39 of 51

Rule 6 HPI


















• Core SCM > 0






Page 40 of 51



CONDITION ACTIONS

1. PR NIs ≥ 5% FP

OR

NIs NOT decreasing

GO TO UNPP tab.

UNPP


{13}





GO TO EHT tab.



GO TO LOHT tab.


GO TO EHT tab.

EHT



GO TO TBF tab.

TBF


ES



ES




ROP



EDL



• Notify OSM to reference the Emergency Plan and AD-LS-ALL-0006 (Reportability).

NOTIFY


Page 41 of 51

LOHT EP/1/A/1800/001


CONDITION ACTIONS

1. PR NIs ≥ 5% FP

OR

NIs NOT decreasing

GO TO UNPP tab.

UNPP


{13}



4. All of the following exist:

Any SCM = 0°F

HPI forced cooling NOT in progress

Condition other than RCS heat-up is the cause of loss of subcooling

GO TO LOSCM tab.

LOSCM


ES



ES


Initiate AP/11 (Recovery from Loss of Power).

IF Encl 5.1 (ES Actuation) has been initiated, THEN reinitiate Encl 5.1.

ROP


OR

SGTR > 25 gpm


EDL


Announce plant conditions using PA system.

Notify OSM to reference the Emergency Plan and AD-LS-ALL-0006 (Reportability).

NOTIFY


Page 42 of 51

Enclosure 5.5



NOTE



• 1A HPI Pump

• 1B HPI Pump

• 1HP-26

• 1HP-7


• 1HP-5





A. Open:

1CS-26

1CS-41


C. Notify SRO.



Page 43 of 51





__ GO TO Step 10.

7. Open:

• 1HP-24

• 1HP-25




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7



F. GO TO Step 8.




C. GO TO Step 9.


Page 44 of 51





__ 1HP-26

1HP-27




Page 45 of 51




__ GO TO Step 12.


• Open 1HP-24.

• Open 1HP-25.

• Close 1HP-16.




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7





NOTE




Page 46 of 51





Open 1HP-17.

Open 1HP-18


Letdown isolated

LPSW available



GO TO Step 35.

16. Open:

__ 1CC-7

__ 1CC-8






__ 1HP-1

__ 1HP-2



20. GO TO Step 23.



GO TO Step 23.

22. GO TO Step 35.


Page 47 of 51






1HP-1

1HP-3


1HP-2

1HP-4


25. Open:

1HP-1

1HP-2

1HP-3

1HP-4





27. __ Close 1HP-6.

28. __ Close 1HP-7.


2. Close:

1HP-8

1HP-9&11



B. Close 1HP-16.



Page 48 of 51





33. Open 1HP-6.


NOTE









LDST level > 55″



THEN close:

1HP-24

1HP-25


Page 49 of 51




__ GO TO Step 40.




C. Close 1CS-46.





__ GO TO Step 42.






Page 50 of 51

CRITICAL TASKS

CT-1 ICS must be taken to HAND and FDW adjusted to prevent tripping the reactor on RPS Low Pressure (1810 psig) or RPS Variable Low Pressure. Adjustment will be dependent on how much time it takes to place ICS in HAND.

CT-2 Lockout EHC pumps to manually trip the turbine prior to reaching Rule 8 (PTS) entry

conditions (400°F) CT-3 Establish CBP feed prior to reaching 2300 psig RCS pressure or 375 inches Pressurizer

level


UNIT 0 (OSM)

SSF Operable: Yes KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No








RBNS Rate: 0.01 gpm



Required Date/Time

TS/SLC #

AMSAC/DSS 0300 7 Days 16.7.2


Primary


1RIA-3 and 5 removed from RB. SASS is in Manual for calibration ‘C’ GWD tank release is in progress per OP/1-2/A/1104/018 Just after or during a GWD release, 1SA-8/B-9 may alarm from RIA-32 sample point selected to

‘1 PRV System Filter Discharge’. IF 1SA-8/B-9 is due to RIA-32 - ‘1 PRV System Filter Discharge’, it can be considered an expected alarm

Secondary


Unit 2 is supplying the AS header 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are

closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.








________________________ ________________________OATC

________________________ ________________________BOP

Initial Conditions: Reactor Power = 3.5%

Turnover:

SASS is in Manual

Event No.


Event Description

0a Override SASS in Manual

0b Override Standby LPSW Pump Auto Start Circuit Disabled

1 N: OATC, SRO Makeup to LDST 100 Gallons

2 Override C: BOP, SRO 1C Hotwell Pump Casing Water Level Low

3 Override C: BOP, SRO (TS) ‘A’ LPSW Pump Trips and ‘C’ LPSW Pump Fails to Auto Start

4 MSS470 C: BOP, SRO (TS) 1C RBCU Cooler Rupture

5 MPI150 I: OATC, SRO (TS) PZR ‘A’ RTD Fails Low

6 MCR061 C: OATC, SRO Continuous Rod Withdrawal

7 MPS400

MPS400D M: ALL

Small Break LOCA

1A MDEFDW Pump fails to start

ES Channel 3 Fails to go to Manual



Page 2 of 59

Scenario 4

Event Summary

Event 1: As soon as the crew takes the shift, the OATC will perform OP/1/A/1103/004 Enclosure 4.6 (RCS Makeup From 1A and 1B BHUT) to add approximately 100 gallons to the LDST for RCS inventory control.

Event 2: The crew will receive alarms indicating that 1C Hotwell Pump casing water level is

low. The associated Alarm Response Guides will require the BOP to start a standby HWP and secure the 1C HWP. The BOP will also bypass the Powdex System as directed by the ARG.

Event 3: The ‘A’ LPSW Pump will trip. This will result in several alarms to alert the operator of the failure since the standby LPSW Pump will not auto start. The associated Alarm Response Guides will direct entry into AP/1/A/1700/024 (Loss of LPSW). AP guidance will be used to restore normal LPSW system parameters by manually starting the ‘C’ LPSW Pump. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 4: Once the ‘C’ LPSW pump is started, a cooling water line for the 1C Reactor Building Cooling Unit (RBCU) will rupture inside containment. The BOP will use guidance provided in the associated Alarm Response Guide to secure the 1C RBCU and isolate cooling water to stop the leak. If time permits, the crew may decide to begin pumping the RBNS (due to the LPSW leakage from the 1C RBCU Cooler). If so, they will use OP/1/A/1104/007 Enclosure 4.1 (Pumping RBNS to ≥ 1"). This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 5: The ‘A’ PZR RTD will fail low causing PZR levels 1 & 2 to indicate low. With SASS in manual, this will cause 1HP-120 to begin throttling open in an attempt to restore the indicated PZR level. Actual PZR level will start to increase and LDST level will begin to decrease. The OATC is expected to place 1HP-120 in Hand and stabilize PZR level. The crew will refer to OP/1/A/1105/014 which will direct them to select PZR Level Channel 3 as the controlling channel. The OATC should then return 1HP-120 to AUTO. This will require the SRO to evaluate Tech Specs and enter the appropriate conditions.

Event 6: Control Rods will begin to withdraw and Reactor power will begin to increase. The crew will perform Plant Transient Response (PTR) to evaluate plant response and determine the cause of the associated transient. The OATC will either place the Diamond in manual and insert Control Rods to stabilize Reactor power or trip the Reactor due to the power increase. If the crew promptly diagnoses the failure and does not trip the Reactor, the scenario will continue by initiating Event 7.


Page 3 of 59

Scenario 4

Event Summary

Event 7: Once the event is initiated, RCS pressure will begin to rapidly decrease and ES

Channels 1 & 2 will actuate on low RCS pressure. Once ES Channels 1 and 2 have actuated, the SRO will direct an operator to perform EOP Enclosure 5.1 (ES Actuation). After a few minutes ES Channels 3-6 will also actuate. EOP Enclosure 5.1 will require all actuated ES Channels to be placed in manual but ES Channel 3 will fail to go to manual which will require the operator to place the Odd Voters in override. Shortly after ES Channels 1 & 2 actuate, the crew will observe at least one SCM indication ≤ 0°F which will require performing Rule 2 (Loss of SCM) and entry into the EOP LOSCM tab. Rule 2 requires the operator to stop all RCPs within 2 minutes of any SCM indication ≤ 0°F. While performing Rule 2, the 1A Motor Driven EFDW Pump will not start which will require the Turbine Driven EFDW Pump to be started. Rule 3 (Loss of Main or Emergency FDW) is performed as directed by Rule 2 to raise SG levels to the loss of SCM setpoint. EOP Enclosure 5.9 (Extended EFDW Operation) will be performed when directed by Rule 3.


Page 4 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 1 Page 1 of 5 Event Description: Makeup To LDST 100 Gallons (N: OATC, SRO)


SRO

OATC


SRO directs the OATC to use the in progress procedure OP/1/A/1103/004 (Soluble Poison Control) Enclosure 4.6 (RCS Makeup From 1A and 1B BHUT) beginning at Step 2.1 to makeup to the RCS from 1A and 1B BHUT. OP/1/A/1103/004, Encl. 4.6 (RCS Makeup From 1A and 1B BHUT) rev 105

Examiner Note: Steps 3.1 -3.3 are complete and the crew will start at Step 3.4 below.

2.1 Perform appropriate section(s) to achieve desired results:

Perform Section 3 (Makeup From 1A and 1B BHUT) for RCS Makeup

3.1 Determine required RCS Makeup volume by performing the following:

3.1.1 IF desired, utilize Enclosure 4.1 (RCS Boron Change Calculation)

3.1.2 IF two Letdown Filters are available, perform the following:

A. Review Component Boron Log for out-of-service Letdown Filter boron

B. Make appropriate adjustments to Makeup volumes for placing second Letdown Filter in service

3.1.3 Perform the following:

A. Review Component Boron Log for 1A RC Bleed Storage Header boron. {18}

B. Make appropriate adjustments to Makeup volumes based on 1A RC Bleed Storage Header boron {18}

3.1.4 Record required Makeup volume: 100 gallons (≈ 70 gals 1A BHUT and ≈ 30 gals DW)

3.2 Ensure required RCS Makeup volume and source acceptable. (R.M.)

3.3 IF predicted change in boron concentration per shift is expected to be ≥ 10 ppm, notify Primary Chemistry of the following:

Total Makeup volume to be added

Expected Boron change from the addition

3.4 IF two Letdown Filters are available, perform the following:

Open 1HP-17 (1A LETDOWN FILTER INLET)

Open 1HP-18 (1B LETDOWN FILTER INLET)

3.5 Ensure open 1HP-16 (LDST MAKEUP ISOLATION).

This event is complete when Step 3.27 is complete, or as directed by the Lead Examiner.


Page 5 of 59



OATC


Note: The crew may choose to perform the makeup with 1HP-15 in AUTO or MANUAL.

3.6 IF Makeup with 1HP-15 in "AUTO" desired, perform the following:

3.6.1 Select "S" on 1HP-15 Controller.

3.6.2 Enter batch size on 1HP-15 Controller. (R.M.)

3.6.3 Place 1HP-15 Controller in "AUTO".

3.6.4 Ensure "P" on 1HP-15 Controller.

3.7 WHILE making up to Unit 1 LDST from 1A and 1B BHUT, monitor the following indications: (R.M.)

Appropriate ranged NIs

Primary tank levels

Neutron error (if applicable)

CRD position (if applicable)

3.8 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup, perform the following: (RM)

3.8.1 Stop 1A BLEED TRANSFER PUMP.

3.8.2 IF RCS Makeup stopped due to alarm(s) OR abnormal indication(s), notify CRS.

3.8.3 WHEN conditions allow RCS Makeup to continue, perform one of the following:

Start 1A BLEED TRANSFER PUMP.

Go To Step 3.13 to terminate the addition.

3.9 Start 1A BLEED TRANSFER PUMP.

3.10 Open 1CS-46 (1A RC BLEED XFER PUMP DISCH).

3.11 IF increased Makeup flow required, perform the following: (AB-1, Unit 1-BTP Room).

Throttle 1CS-48 (1A BHUT Recirc) to establish desired flow.

Ensure 90 - 125 psig on 1CS-PG-0084.

3.12 WHEN required volume is added, ensure stop 1A BLEED TRANSFER PUMP.

3.13 Close 1CS-46 (1A RC BLEED XFER PUMP DISCH). (R.M.)



Page 6 of 59



OATC


3.14 Perform one of the following: (R.M.)

Verify correct volume added

Notify CRSRO of incorrect volume added.

3.15 Reset 1HP-15 Controller for Normal Operation.

3.16 Record 1A BHUT boron in Component Boron Log for 1A RC Bleed Storage Header

Note: The crew may choose to perform the makeup with 1HP-15 in AUTO or MANUAL.

3.17 IF Makeup with 1HP-15 in "AUTO" desired, perform the following:

3.16.1 Select "S" on 1HP-15 Controller.

3.16.2 Enter batch size on 1HP-15 Controller. (R.M.)

3.16.3 Place 1HP-15 Controller in "AUTO".

3.16.4 Ensure "P" on 1HP-15 Controller.


NOTE: • If during RCS Makeup the wrong volume is added, an CRS shall evaluate affect on reactivity and take action to minimize reactivity management events..

• 1HP-15 Controller volume will be different from volume based on LDST level change.

1. Select “STOP” on 1HP-15 Controller

2. Select “START” on 1HP-15 Controller

3. Ensure 1HP-15 Controller Start/Stop set to “START”

4. Ensure 1HP-15 Controller mode selector set to “MANUAL”

5. Ensure 1HP-15 Controller valve position set to 100% open

6. Ensure 1HP-15 Controller display selector set to “P”

7. Ensure 1HP-15 Controller display indicates “0”


Page 7 of 59



OATC


3.18 Ensure open 1HP-16 (LDST MAKEUP ISOLATION)

3.19 IF AT ANY TIME abnormal condition(s) require stopping RCS Makeup, perform the following: (RM)

3.19.1 Stop 1B BLEED TRANSFER PUMP.

3.19.2 IF RCS Makeup stopped due to alarm(s) OR abnormal indication(s), notify CRS.

3.19.3 WHEN conditions allow RCS Makeup to continue, perform one of the following:

Start 1B BLEED TRANSFER PUMP.

Go To Step 3.22 to terminate the addition.

3.20 Start 1B BLEED TRANSFER PUMP.

3.21 Open 1CS-56 (1B RC BLEED XFER PUMP DISCH).

3.22 IF increased Makeup flow required, perform the following: (AB-1, Unit 1-BTP Room).

Throttle 1CS-58 (1A BHUT Recirc) to establish desired flow.

Ensure 90 - 125 psig on 1CS-PG-0085.

3.23 WHEN required volume is added, stop 1B BLEED TRANSFER PUMP.

3.24 Close 1CS-56 (1B RC BLEED XFER PUMP DISCH). (R.M.)

3.25 Perform one of the following: (R.M.)

Verify correct volume added

Notify CRS of incorrect volume added.

3.26 Reset 1HP-15 Controller for Normal Operation. (see page 6)

3.27 Close 1HP-16 (LDST MAKEUP ISOLATION).


NOTE: If feed and bleed occurred during first makeup, 1HP-16 closed when the addition batched out (does NOT apply)


Page 8 of 59



OATC


3.28 Record RCS batch volume in narrative log.

3.29 IF desired to remove one Letdown Filter from service, perform the following: (Continue)

3.29.1 Verify > 10 minutes since LDST Makeup was secured. {8} (R.M.)

Examiner Note: Notify the crew that 10 minutes have elapsed.

3.29.2 Position one of the following:

Close 1HP-17 (1A LETDOWN FILTER INLET)

Close 1HP-18 (1B LETDOWN FILTER INLET)

3.29.3 Record RCS boron for out-of-service Letdown Filter in Component Boron Log

3.30 IF RCS sample for boron required, notify Chemistry to sample

3.31 IF increased Makeup flow from 1A BHUT was required, perform the following:

3.31.1 Start 1A BLEED TRANSFER PUMP

3.31.2 IF discharge pressure is NOT 90-110 psig, throttle 1CS-48 to obtain 90 – 110 psig on 1CS-PG-0084

3.31.3 Stop 1A BLEED TRANSFER PUMP

3.32 IF increased Makeup flow from 1B BHUT was required, perform the following:

3.32.1 Start 1B BLEED TRANSFER PUMP

3.32.2 IF discharge pressure is NOT 90-110 psig, throttle 1CS-58 to obtain 90 – 110 psig on 1CS-PG-0085

3.32.3 Stop 1B BLEED TRANSFER PUMP


NOTE: • 1B Letdown Filter is preferred filter to leave in service for ALARA.

• Only one Letdown Filter should be in service to prevent clogging both filters during startup.


Page 9 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 2 Page 1 of 1 Event Description: 1C Hotwell Pump Casing Water Level Low (C: BOP, SRO)


SRO

BOP

1SA-9/E-5 Plant Response:

1SA-9/E-5 (HWP C CASING WATER LEVEL LOW)

Crew Response:

The SRO should direct the BOP to refer to ARG 1SA-9/E-5 Alarm Response Guide 1SA-9/E-5 (HWP C Casing Water Level Low) rev 047

3.1 IF '1C' HWP is in operation, then immediately:

Start a standby HWP.

Trip '1C' HWP.

Note: When the 1C HWP is tripped, OAC alarm “1C HWP LOCA/LS OFF” will actuate and the crew may place the LOCA Load Shed switch to an operating Hotwell pump per the OAC alarm response guide.

Bypass Powdex. [Open 1C-14/1C-15]

Decrease load.

3.2 Monitor hotwell level.

3.3 Determine cause of low level alarm (possible suction filter clogging) and initiate corrective action necessary to return pump to normal operation.

Examiner Note: The crew may use OP/1/A/1106/002 (Condensate and

FDW System) to bypass Powdex OP/1/A/1106/002 Enclosure 4.19 (Placing Powdex In/Out of Service) rev 169

3.1 IF Powdex is to be removed from service for an extended period of time AND condensate system will NOT be shutdown, perform the following:

3.1.1 Ensure MSDD System in service

3.1.2 Notify Chemist that Powdex will be removed from service for an extended period of time

3.2 Ensure Open 1C-14/1C-15 (POL DEMIN BYPASS CONTROL)

3.3 Place note on Turnover sheet that Powdex has been removed from service

3.4 Notify Chemist that Powdex has been removed from service

This event is complete when the standby HWP has been started, or as directed by the Lead Examiner.


Page 10 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 3 Page 1 of 3 Event Description: ‘A’ LPSW Pump Trips and ‘C’ LPSW Pump Fails to Auto Start

(C: BOP, SRO) (TS)


SRO/BOP

BOP

OATC

Plant response:

Statalarm 1SA-9/A-9 (LPSW Header A Press Low)

OAC Alarm LPSW HDR Pressure LO LO

OAC Alarm LPSW leakage accumulator level

OAC Alarm LO LO RCP MTR Cooler Inlet HDR LPSW

LPSW Header A/B Pressure Gauge indicates low Crew Response:

The SRO should direct the BOP to refer to ARG 1SA-9/A-9

The OATC may refer to the OAC alarm response

ARG 1SA-9/A-9 (LPSW Header A Press Low) rev 047

3.1 Refer to AP/1/A/1700/024 (Loss of LPSW) (next page)

3.2 Have Unit 2 refer to AP/2/A/1700/024 (Loss of LPSW).

OAC Alarm Response

1. Refer to AP/24 (Loss of LPSW) (next page)

2. Notify engineering

3. Refer to TS 3.7.7

OAC Alarm Response

1. If Standby LPSW pump doesn’t start automatically, then start manually.

2. Refer to AP/1/A/1700/024 (Loss of LPSW)

3. Notify Engineering

4. Refer to Tech Spec 3.7.7 Examiner Note: The SRO may direct an RO to start the ‘C’ LPSW pump

per OMP 1-18 prior to entering AP/24. Examiner Note: The SRO may direct an RO to start the ‘C’ LPSW pump

per OAC alarm response prior to entering AP/24.

This event is complete when the ‘C’ LPSW pump is started, or as directed by the Lead Examiner.


Page 11 of 59


(C: BOP, SRO) (TS)


SRO/BOP


AP/1/A/1700/024 (Loss of LPSW) rev 028

4.1 Verify Unit 1 is going to handle LPSW system operations.

4.2 IAAT any LPSW pump is cavitating, THEN perform Steps 4.3 – 4.4

RNO: GO TO Step 4.5

4.5 Verify LPSW pressure ≤ 70 psig

4.6 Ensure Unit 1/2 Standby LPSW Pump Auto Start Circuit in Disable

4.7 IAAT a non-operating LPSW pump is available AND pump start is desired, THEN start the available pump (C LPSW Pump will start).

Examiner Note: When the C LPSW pump is manually started, TIMER 4 will auto actuate after 5 seconds to initiate Event 4.

4.8 IAAT LPSW to all RBCUs has been isolated, AND LPSW header pressure is > 25 psig, THEN perform Step 4.9


4.10 Verify normal LPSW System operation is restored.

NOTE

1LPSW-1054, 1055, 1061, and 1062 will close to isolate RB Auxiliary Coolers on low LPSW pressure.

If RB Auxiliary Coolers are aligned for outage cooling with the portable chiller, sliding links have been positioned such that 1LPSW-1054, 1055, 1061, and 1062 will NOT close.


NOTE Unit 1 normally handles LPSW System operation unless otherwise directed by the CRS

NOTE If an LPSW pump is stopped due to cavitation, it is NOT available until filled and vented.


Page 12 of 59


(C: BOP, SRO) (TS)


SRO/BOP

SRO


4.11 Verify that RB Auxiliary Coolers have isolated:

1LPSW-1054 closed

1LPSW-1055 closed

1LPSW-1061 closed

1LPSW-1062 closed


4.14 EXIT this procedure

TS 3.7.7 (LOW PRESSURE SERVICE WATER SYSTEM)

Condition A (72 hours) Restore required LPSW pump to OPERABLE status.


TS 3.3.28 (LPSW PUMP AUTO START CIRCUITRY)

Condition A (7 days) Restore LPSW standby pump auto-start circuitry to OPERABLE status.



Page 13 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 4 Page 1 of 3 Event Description: 1C RBCU Cooler Rupture (C: BOP, SRO) (TS)


SRO/BOP

Plant Response:

1SA-9/D-9 (LPSW RBCU C Cooler Rupture)

1SA-9/A-6 (RB Normal Sump Level High/Low)

RB normal sump level will increase

1C RBCU LPSW flow indicator indicates low on 1VB2

Crew Response:

ARG for 1SA-9/D-9 (RBCU C Cooler Rupture) rev 047

3.1 Verify alarm is valid by checking RBCU 1C Inlet Flow and RBCU 1C delta flow.

3.2 Verify 1LPSW-24 (RBCU 1C Outlet) throttled

3.3 Verify adequate LPSW flow is available; check LPSW pump operation

3.3.1 Verify 1LPSW-22 (1C RBCU INLET) is open.

3.3.2 IF 1LPSW-22 (1C RBCU INLET) is NOT open, refer to Technical Specifications and Selected Licensee Commitments

3.4 Monitor RBNS Level for any unexplained increase

3.5 IF RBNS Level is increasing AND ES has actuated, notify Chemistry to sample the RBNS for boron concentration to determine if a cooler rupture has occurred based on sample results.

3.6 IF RBCU 1C Cooler rupture or line break is indicated, then:

NOTE: This sequence prevents having to call LPSW and Containment inoperable per SLC 16.9.12.

3.6.1 Isolate the 1C RBCU Cooler as follows:

A. Close 1LPSW-22 (1C RBCU INLET).

B. Close 1LPSW-24 (RBCU 1C OUTLET).

C. Evaluate TS 3.6.3 Condition C (does NOT apply)

D. Evaluate TS 3.6.5 for inoperable RBCU (page 15)

E. Continue to monitor RBNS level for increase.

F. IF RBNS level is still increasing, notify Engineering to evaluate further isolation of 1C RBCU.

This event is complete when the 1C RBCU rupture is isolated and the SRO has referred to TS, or as directed by the Lead Examiner.


Page 14 of 59



BOP

BOP

SRO

Crew Response:

ARG 1SA-9 / D-9 (RBCU C Cooler Rupture) (cont.):

3.6.2 Refer to Technical Specifications

3.6.3 Refer to SLC 16.9.12 (Does NOT apply)

3.6.4 Refer to OP/1/A/1104/010 (LPSW)

3.6.5 Refer to OP/1/A/1104/015 (RB Cooling System)

Examiner Note: The crew may decide to pump the RB Normal Sump. If so, see the steps below from OP/1/A/1104/007 (LWD System) Enclosure 4.1 (Pumping RBNS to ≥ 1")

OP/1/A/1104/007 Enclosure 4.1 (Pumping RBNS ≥ 1 Inch) rev 030

3.1 Verify MWHUT level adequate to receive waste volume.

3.2 Position the following:



3.3 Start one or both of the following:

1A RB NORM SUMP PUMP

1B RB NORM SUMP PUMP

3.4 WHEN RBNS is at desired level OR at 1" (low level alarm), ensure the following:

1A RB NORMAL SUMP PUMP "OFF".

1B RB NORMAL SUMP PUMP "OFF".

3.5 IF required to close the valves, position the following:





Page 15 of 59



SRO

Crew Response:

Note: TS 3.6.3 Condition C does not apply since no Containment

Isolation Valves are inoperable.

TS 3.6.5 REACTOR BUILDING SPRAY AND COOLING SYSTEMS

Condition B (7 days and 14 days from discovery of failure to meet LCO) Restore reactor building cooling train to OPERABLE status.

TS 3.4.15 (RCS LEAKAGE DETECTION INSTRUMENTATION)

Condition A (Once per 24 hours) Perform SR 3.4.13.1

AND

(30 days) Restore required containment sump level indication to OPERABLE status



Page 16 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 5 Page 1 of 2 Event Description: PZR ‘A’ RTD Fails Low (I: OATC, SRO) (TS)


BOP/SRO

Booth Cue: If needed, call the BOP to request the following: “This

is Secondary Chemistry. I need you to report steam flow to Unit 1 E Heaters as read on the gauge on 1VB1". This will help to ensure the OATC will take actions for the PZR RTD failure.

Plant Response:

OAC alarm (RC PZR level 1&3 mismatch)

OAC alarm (RC PZR level 2&3 mismatch)

Statalarm 1SA-02/C-3 (RC Pressurizer Level High/Low)

PZR level 1 and 2 indicates ≈ 95 inches

PZR level 3 indicates ≈ 120 inches and slowly increasing

Crew Response:

Refer to ARG 1SA-02/C-3 (RC Pressurizer Level High/Low): rev 033

3.1 Check alternate PZR level indications..

3.2 Check for proper Makeup/Letdown flows and adjust to restore proper level.

Examiner Note: The RO may take 1HP-120 to MANUAL to control Pzr level. If so, they should place it in AUTO after the failure is addressed.

Examiner Note: The SRO may direct the OATC to select PZR level 3 prior to referencing OP/1/A/1105/014.

3.1 Refer to the following procedures as required:

AP/1/A/1700/002 (Excessive RCS Leakage)

AP/1/A/1700/014 (Loss of Normal HPI M/U and/or RCP SI)

AP/1/A/1700/032 (Loss of Letdown)

3.4 Refer to Technical Specification 3.4.9 (Pressurizer) (does not apply)

3.5 Refer to Technical Specification 3.3.8 (PAM Instrumentation) (Page 17)

3.6 Refer to OP/1/A/1105/014 Control Room Instrumentation Operation And Information.

This event is complete when PZR level 3 has been selected, 1HP-120 is in Auto, and the SRO has referred to TS, or as directed by the Lead Examiner.


Page 17 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 5 Page 2 of 2 Event Description: PZR ‘A’ RTD Fails Low (I: OATC, SRO) (TS)


SRO/OATC

SRO

Crew Response:

OP/1/A/1105/014 Enclosure 4.11 (SASS Information) rev 042

3.2 SASS (Smart Automatic Signal Selector) Manual Operation

3.2.1 IF "MISMATCH" light is on and "TRIP ‘A’" or "TRIP ‘B’" light is on, a SASS trip has occurred.

A. Controlling signal will be signal selected from CR keyswitch (for parameters in ICS Cabinet #8).

B. Select valid signal as controlling signal by positioning CR keyswitch or pushbutton for Pzr level to valid signal (for parameters in ICS Cabinet #8).

3.2.2 IF "MISMATCH" light is on, a mismatch has occurred

A. Controlling signal will be signal selected from CR keyswitch (for parameters in ICS Cabinet #8).

B. Select valid signal as controlling signal by positioning CR keyswitch or pushbutton for Pzr level to valid signal (for parameters in ICS Cabinet #8). (Select Pzr Level #3)

3.2.3 Initiate a Work Request to repair faulty signal

TS 3.3.8 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION

Condition A (30 days) Restore required channel to OPERABLE status.

This event is complete when PZR level 3 has been selected, 1HP-120 is in Auto, and the SRO has referred to TS, or as directed by the Lead Examiner.


Page 18 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 6 Page 1 of 1 Event Description: Continuous Rod Withdrawal (C: OATC, SRO)


SRO/OATC

Plant response:

Control Rods withdrawing without operator action

NI-5 thru NI-8 indicate increasing reactor power

SURs on Wide Range NIs increasing Crew Response:

The candidates should utilize the “Plant Transient Response” process to stabilize the plant and recognize that control rods are withdrawing without a valid signal.

The OATC should:

Verbalize to the SRO reactor power level and direction of movement

Place the Diamond and both FDW Masters in MANUAL and insert control rods to stabilize the plant

Remain focused on reactor power level during the transient in order to stabilize reactor power ≤ pre-transient power level

The BOP should:

Determine if a valid ICS runback signal exists and report no valid (ICS) runback and then monitor RCS pressure and inventory

Contact FIN-24 (SPOC) to investigate the continuous rod withdrawal

Examiner Note: The OATC may elect to trip the Reactor during this transient per OMP 1-18 Attachment J (Plant Transient Response).

OMP 1-18 Attachment J states the following:

2. During abnormal operating conditions a manual reactor trip shall be initiated if any of the following conditions occur:

Reactor power level approaches any operating limit

Reactor power level exceeds the pre-transient power level by greater than 5% AND the cause of the power change is NOT understood, OR is NOT controllable

Any time plant conditions are considered uncontrollable or unsafe

Examiner/Booth Cue: If the crew does NOT manually trip the Reactor, then once they have completed PTR, FIRE TIMER 7 to initiate Event 7 when directed by the Lead Examiner.

This event is complete once the Reactor has tripped or as directed by the Lead Examiner.


Page 19 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 1 of 9 Event Description: Small Break LOCA (M: ALL)


SRO/OATC

SRO/BOP

OATC/BOP

BOP/OATC

Plant response:

1SA-2/D-3 (RC PRESS HI/LOW)

RCS pressure and PZR level decreasing

ES 1-6 actuate

RCS subcooling margin will indicate 0°F

Reactor Building level increasing Crew response:

The SRO will direct the OATC to perform IMAs.

3.1 Depress REACTOR TRIP pushbutton.

3.2 Verify reactor power < 5% FP and decreasing.

3.3 Depress the turbine TRIP pushbutton

3.4 Verify all turbine stop valves closed.

3.5 Verify RCP seal injection available. The SRO will direct the BOP to perform a Symptoms Check.










CSAE Offgas alarms




SRO will transfer from the Subsequent Actions Tab to the LOSCM tab (page 20) from the Parallel Actions Page (page 57) to direct crew activities. Once the RCS saturates, one of the ROs will perform Rule 2 (page 23). The RO not performing Rule 2 will begin performing Enclosure 5.1 due to ES actuation (page 28).

This event is complete when the SRO transfers to the LOCA CD Tab, or as directed by the Lead Examiner.


Page 20 of 59




LOSCM tab

1. Ensure Rule 2 (Loss of SCM) is in progress or complete.

2. Verify LOSCM caused by excessive heat transfer

RNO: GO TO Step 4




THEN GO TO LOCA CD tab.

5. Verify SSF activated per AP/25 with SSF RC Makeup required.

RNO: GO TO Step 7

7. Verify all exist:

NO RCPs operating

HPI flow in both HPI headers

Adequate total HPI flow per Figure 1 (Total Required HPI Flow)

8. GO TO Step 104.



Page 21 of 59



SRO


LOSCM tab (continued)



RNO: Close 1RC-4

106. Close 1GWD-17, 1HP-1, 1HP-2, and 1RC-3

107. Verify either:

Core superheated

Rx vessel head level at 0″

RNO: GO TO Step 109

109. IAAT BWST level is ≤ 19', THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

CAUTION

If TDEFDWP is being used for SG feed, reducing SG pressure below 250 psig can result in reduced pumping capability

110. Maintain SG pressure < RCS pressure utilizing either:

__ TBVs

__ ADVs

111. Verify any SG available for feeding/steaming.

112. Initiate Encl 5.16 (SG Tube-to-Shell T Control).

113. Verify indications of SGTR exist.

RNO: GO TO Step 116


RNO: GO TO Step 118

118. Verify CETCs trend decreasing.

119. Verify primary to secondary heat transfer is excessive.

RNO: GO TO Step 121

121. Verify indications of SGTR 25 gpm.

RNO: GO TO Step 123


RNO: GO TO LOCA CD tab (page 22)



Page 22 of 59



CT-2

LOCA Cooldown Tab Crew Response:

LOCA Cooldown Tab

1. IAAT BWST level is ≤ 19’, THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).

2. Verify ES actuated.

3. GO TO Step 7.

4. Verify two LPI pumps operating.

RNO: IF any HPI pump is operating, AND LPI/HPI piggyback is aligned, THEN maximize total LPI flow < 3100 gpm by throttling HPI flow.

5. Notify Unit 3 to start the following:

3A Outside Air Booster Fan

3B Outside Air Booster Fan

6. Start the following: (should already be started in Encl. 5.1 step 28) (Page 31)

A Outside Air Booster Fan

B Outside Air Booster Fan


Ensure all RBCUs in low speed.

Open 1LPSW-18

Open 1LPSW-21

Open 1LPSW-24

8. Initiate Encl 5.35 (Containment Isolation).

9. Start all RB Aux fans.

10. IAAT either of the following exists:

LPI FLOW TRAIN A plus LPI FLOW TRAIN B ≥ 3400gpm


THEN GO TO Step 11.

RNO: GO TO Step 43

43 Initiate Encl 5.36 (Equipment Alignment For Plant Shutdown)



Page 23 of 59



OATC/BOP

CT-1


Rule 2 (Loss of SCM)

1. IAAT all the following exist:

Any SCM ≤ 0°F

Rx power ≤ 1%

≤ 2 minutes elapsed since loss of SCM

THEN perform steps 2 & 3

2. Stop all RCPs

3. Notify CRS of RCP status.

4. Verify Blackout exists.

RNO: GO TO Step 6

6. Open 1HP-24 & 25

7. Start all available HPI Pumps

8. GO TO step 13.

13. Open 1HP-26 & 27

14. Verify at least two HPI pumps are operating using two diverse indications.

15. IAAT > 2 HPI pumps operating and HPI flow in any header is in Unacceptable Region of Fig. 1, THEN perform Steps 16-21.

RNO: GO TO step 17

17. IAAT flow limits are exceeded THEN perform Steps 18 - 20

RNO: GO TO Step 21

18. Place Diverse HPI in BYPASS.

19. Perform both:



20. Throttle HPI to maximize flow flow limit.



Page 24 of 59

Op-Test No.: ILT16-1 Scenario No.: 4 Event No.: 7 Page 6 of 9 Event Description: Small Break LOCA (M: ALL) Time Position Applicant's Actions or Behavior

BOP/OATC


Rule 2 ( Loss of SCM) (Continued)

21. Notify CRS of HPI status.

22. Verify RCS pressure >550 psig




THEN GO TO Step 24.

RNO: GO TO Step 35

35. IAAT TBVs are unavailable, THEN

A. Dispatch two operators to perform Encl 5.24 (Operation of ADVs)

B. Notify CRS the ADVs are being aligned for use.

36. Select OFF for both Digital Channels on AFIS HEADER A

37. Select OFF for both Digital Channels on AFIS HEADER B


RNO: Place 1FDW 315 and 1FDW-316 in MANUAL and close.

39. Start MD EFDW pumps on all intact SGs:

1A MD EFDWP (1A MD EFDWP will not start)

1B MD EFDWP

RNO: Start 1 TD EFDW PUMP


41. Verify both SGs intact.

42. Establish 300 gpm EFDW flow to each SG

43. Verify both MD EFDWPs operating. (the 1A MD EFDWP did not start)

RNO: 1. IF 1TD EFDW PUMP is operating, OR NO Main FDW pumps operating, GO TO Step 45

2. GO TO Step 47

45. Trip both Main FDW pumps.



Page 25 of 59


Event Description: Small Break LOCA (M: ALL)



Rule 2 ( Loss of SCM) (Continued)

46. Place FDW block valve switches in CLOSE:

1FDW-33

1FDW-31

1FDW-42

1FDW-40

47. Utilize Rule 7 (SG Feed Control) to feed all intact SGs to the appropriate SG Level Control Point using available feed sources; EFDW/Main FDW.

48. IAAT SG Level Control Point is reached, THEN maintain SG Level Control Point by feeding and steaming as necessary.

49. Notify CRS of SG feed status.

CAUTION If 1 TD EFDW PUMP is being used for SG feed and Unit 1 is supplying the Auxiliary Steam header, reducing SG pressure below ≈ 250 psig can result in reduced pumping capability.

50. IAAT SG pressure is > RCS pressure, THEN reduce SG pressure <

RCS pressure using either:

TBVs

Dispatch two operators to perform Encl 5.24 (operation of the ADVs)

51. Verify any Main FDW pump operating.

RNO: GO TO Step 58.

58. Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete. (page 26)




Page 26 of 59



SRO/OATC


Rule 3 (Loss of Main or Emergency Feedwater)

1. Verify loss of Main FDW/EFDW is due to TBF.

RNO: GO TO Step 3


RCS pressure reaches 2300 psig or NDT limit.

PZR level reaches 375” (340” acc)

THEN PERFORM Rule 4 (HPI Forced Cooling)

4. Start operable EFDW pumps, as required, to feed all intact SGs.


6. GO TO Step 38

38. IAAT an EFDW valve CANNOT control in AUTO, OR manual operation of EFDW valve is desired to control flow/level, THEN perform Steps 39 - 43.

RNO: GO TO Step 44

44. Verify any SCM 0F

RNO: IF overcooling OR exceeding limits in Rule 7, THEN throttle EFDW as necessary.

45. IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation).




Page 27 of 59



EOP Encl 5.9 Crew Response:

EOP Encl 5.9 (Extended EFDW Operation)

1. Monitor EFDW parameters on EFW graphic display.

2. IAAT UST level is < 4', THEN GO TO Step 120

3. IAAT feeding both SGs with one MD EFDWP is desired, THEN perform steps 4 - 7.

RNO: GO TO Step 8

8. Perform as required to maintain UST level > 7.5':

Makeup with demin water.

Place CST pumps in AUTO.

9. IAAT all exist:

__ Rapid cooldown NOT in progress

__ MD EFDWP operating for each available SG

__ EFDW flow in each header < 600 gpm

THEN place 1 TD EFDW PUMP switch in PULL TO LOCK

10. Verify 1 TD EFDW PUMP operating.

RNO: GO TO Step 12

11. Start TD EFDWP BEARING Oil Cooling Pump.

NOTE

Loss of the condensate system for 25 minutes results in cooling down to LPI using the ADVs. If NO HWPs are operating, continuing this enclosure to restore the condensate system is a priority unless the CR SRO deems EOP activities higher priority. The 25 minute criterion is satisfied when a HWP is started and 1C-10 is 10% open.

If the condensate system is operating, the remaining guidance establishes FDW recirc, monitors and maintains UST, and transfers EFDW suction to the hotwell if required.

12. Notify CR SRO to set priority based on the NOTE above and EOP activities.

Note: The SRO should determine that continuing in Encl 5.9 is not a priority at this time and direct the RO from the LOSCM Tab of the EOP.



Page 28 of 59

EOP Enclosure 5.1 (ES Actuation)


1. __ Determine all ES channels that should have actuated based on RCS pressure and RB pressure:

2. __ Verify all ES channels associated with actuation setpoints have actuated.

NOTE

Voter OVERRIDE extinguishes the TRIPPED light on the associated channels that have auto actuated. Pressing TRIP on channels previously actuated will reposition components that may have been throttled or secured by this Enclosure.

__ Depress TRIP on affected ES logic channels that have NOT previously been actuated.

3. __ IAAT additional ES actuation setpoints are exceeded, THEN perform Steps 1 - 2.

4. __ Place Diverse HPI in BYPASS. __ Place Diverse HPI in OVERRIDE.

5. Perform both:



NOTE





Actuation Setpoint

(psig)

Associated ES Channel

1600 (RCS) 1 & 2 550 (RCS) 3 & 4 3 (RB) 1, 2, 3, 4, 5, & 6 10 (RB) 7 & 8


Page 29 of 59


6. __ IAAT all exist:

__ Voter associated with ES channel is in OVERRIDE

__ An ES channel is manually actuated

__Components on that channel require manipulation

THEN depress RESET on the required channel.

7. __ Verify Rule 2 in progress or complete. __ GOTO Step 74.


9. Open:

__ 1HP-20

__ 1HP-21


__ GOTO Step 16.

11. Perform all:



NOTE





12. __ Verify any RCP is operating __ GO TO Step 16

13. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6




Page 30 of 59



__ GO TO Step 54.


18. Perform both:



NOTE





CAUTION


19. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. {6, 22}

CT-3


__ GOTO Step 23.


__ Open 1LP-17.



2. __ Close 1LP-17.


__ Open 1LP-18.

__ Start 1B LPI PUMP.


2. __ Close 1LP-18.


Page 31 of 59




__ 1LP-19 closed

__ 1LP-20 closed


__ GO TO Step 26.

24. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22




28. Start:



CT- 2





Page 32 of 59


30. Verify open:

__ 1CF-1 __ 1CF-2


__ 1CF-1 __ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



35. __ Close 2LPSW-139.



37. __ Close 1LPSW-139.






Page 33 of 59


40. Verify either:



__ GOTO Step 42.

41. Open:

__ 1LPSW-4 __ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5








__ GOTO Step 47.

NOTE





Page 34 of 59


47. __ IAAT ES channels 7 & 8 have actuated, THEN perform Steps 48 - 49.

__ GOTO Step 50.

48. Perform all:



NOTE











END


Page 35 of 59


Unit Status


54. Start:



CT-2




56. Verify open:

__ 1CF-1

__ 1CF-2


__ 1CF-1

__ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



61. __ Close 2LPSW-139.



63. __ Close 1LPSW-139.


Page 36 of 59






66. Verify either:



__ GOTO Step 68.

67. Open:

__ 1LPSW-4

__ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5










END


Page 37 of 59


74. Open:

__ 1HP-24

__ 1HP-25

1. __ IF both BWST suction valves (1HP-24 and 1HP-25) are closed, THEN:

A. __ Start 1A LPI PUMP.

B. __ Start 1B LPI PUMP.

C. Open:

__ 1LP-15

__ 1LP-16

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7



F. __ GOTO Step 75.

2. __ IF only one BWST suction valve (1HP-24 or 1HP-25) is open, THEN:

A. __ IF three HPI pumps are operating, THEN secure 1B HPI PUMP.

B. __ IF< 2 HPI pumps are operating, THEN start HPI pumps to obtain two HPI pump operation, preferably in opposite headers.

C. __ GO TO Step 76.


Page 38 of 59


75. __ Ensure at least two HPI pumps are operating.

76. Verify open:

__ 1HP-26

__ 1HP-27

1. __ IF HPI has been intentionally throttled, THEN GOTO Step 77.

2. Open:

__ 1HP-26

__ 1HP-27


Page 39 of 59


77. __ IAAT at least two HPI pumps are operating, AND HPI flow in any header that has NOT been intentionally throttled is in the Unacceptable Region of Figure 1, THEN open the following in the affected header:

Figure 1

Required HPI Flow Per Header

HPI Pump

Runout Region For 1

Pump In Header

(including seal

injection for A

header)

Unacceptable Region (excluding seal

injection)

1A Header 1B Header

1HP-410 1HP-409


Page 40 of 59



79. Open:

__ 1HP-20

__ 1HP-21


__ GOTO Step 86.

81. Perform all:



NOTE





82. __ Verify any RCP operating __ GO TO Step 86

83. Open:

__ 1CC-7

__ 1CC-8

__ 1LPSW-15

__ 1LPSW-6




Page 41 of 59



__ GO TO Step 124.


88. Perform both:



NOTE





CAUTION


89. __ IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps.{6, 22}


Page 42 of 59



__ GOTO Step 93.


__ Open 1LP-17.



2. __ Close 1LP-17.


__ Open 1LP-18.

__ Start 1B LPI PUMP.


2. __ Close 1LP-18.



__ 1LP-19 closed

__ 1LP-20 closed

THEN perform Steps 94 -95.

__ GO TO Step 96.

94. Open:

__ 1LP-9

__ 1LP-10

__ 1LP-6

__ 1LP-7

__ 1LP-17

__ 1LP-18

__ 1LP-21

__ 1LP-22





Page 43 of 59


98. Start:






100. Verify open:

__ 1CF-1

__ 1CF-2


__ 1CF-1

__ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



105. __ Close 2LPSW-139.



107. __ Close 1LPSW-139.


Page 44 of 59






110. Verify either:



__ GOTO Step 112.

111. Open:

__ 1LPSW-4

__ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5








__ GOTO Step 117.

NOTE





Page 45 of 59


117. __ IAAT ES channels 7 & 8 have actuated, THEN perform Step 118 - 119.

__ GOTO Step 120.

118. Perform all:



NOTE












Page 46 of 59

Unit Status


124. Start:






126. Verify open:

__ 1CF-1

__ 1CF-2


__ 1CF-1 __ 1CF-2


2. __ Close 1HP-120.






__ 1HP-228

__ 1HP-226

__ 1HP-232

__ 1HP-230



131. __ Close 2LPSW-139.



133. __ Close 1LPSW-139.


Page 47 of 59






136. Verify either:



__ GOTO Step 138.

137. Open:

__ 1LPSW-4

__ 1LPSW-5


__ 1LPSW-4

__ 1LPSW-5










END


Page 48 of 59

Rule 6 HPI


















• Core SCM > 0






Page 49 of 59

Enclosure 5.5



NOTE



• 1A HPI Pump

• 1B HPI Pump

• 1HP-26

• 1HP-7


• 1HP-5





A. Open:

1CS-26

1CS-41


C. Notify SRO.



Page 50 of 59





__ GO TO Step 10.

7. Open:

• 1HP-24

• 1HP-25




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7



F. GO TO Step 8.




C. GO TO Step 9.


Page 51 of 59





__ 1HP-26

1HP-27




Page 52 of 59




__ GO TO Step 12.


• Open 1HP-24.

• Open 1HP-25.

• Close 1HP-16.




C. Open:

1LP-15

1LP-16

1LP-9

1LP-10

1LP-6

1LP-7





NOTE




Page 53 of 59





Open 1HP-17.

Open 1HP-18


Letdown isolated

LPSW available



GO TO Step 35.

16. Open:

__ 1CC-7

__ 1CC-8






__ 1HP-1

__ 1HP-2



20. GO TO Step 23.



GO TO Step 23.

22. GO TO Step 35.


Page 54 of 59






1HP-1

1HP-3


1HP-2

1HP-4


25. Open:

1HP-1

1HP-2

1HP-3

1HP-4





27. __ Close 1HP-6.

28. __ Close 1HP-7.


2. Close:

1HP-8

1HP-9&11



B. Close 1HP-16.



Page 55 of 59





33. Open 1HP-6.


NOTE









LDST level > 55″



THEN close:

1HP-24

1HP-25


Page 56 of 59




__ GO TO Step 40.




C. Close 1CS-46.





__ GO TO Step 42.






Page 57 of 59



CONDITION ACTIONS

1. PR NIs ≥ 5% FP

OR

NIs NOT decreasing

GO TO UNPP tab.

UNPP


{13}





GO TO EHT tab.



GO TO LOHT tab.


GO TO EHT tab.

EHT



GO TO TBF tab.

TBF


ES



ES




ROP



EDL



• Notify OSM to reference the Emergency Plan and AD-LS-ALL-0006 (Notification/Reportability Evaluation).

NOTIFY


Page 58 of 59

CRITICAL TASKS

CT-1 (BWOG CT-1) Trip all RCPs

RCPs must be secured within 2 minutes of RCS SCM reaching zero per Rule 2. CT-2 (BWOG CT-27) Initiate Control Room Outside Air Booster Fans

Start the Outside Air Booster Fans within 30 minutes of a LOCA. Not performing this action could result in Control Room habitability issues.

CT-3 Secure LPI pumps within 30 minutes of pump start on ES actuation to prevent

pump damage due to overheating.


UNIT 0 (OSM)

SSF Operable: No KHU's Operable: U1 - OH, U2 - UG LCTs Operable: 2 Fuel Handling: No




Reactor Power: 3.5% Mode: 1 Mode: 1




RBNS Rate: 0.01 gpm



Required Date/Time

TS/SLC #

SSF Yesterday 0000 6 Days TS 3.10.1


Primary


1RIA-3 and 5 removed from RB. SASS is in Manual for calibration. Reactor power is being held at ≈ 3% for Reactor Engineering to update the maneuvering plan. OP/1/A/1102/001 Encl 4.7 is in progress up to Step 3.44 R1 Reactivity Management controls have been established per AD-OP-ALL-0203 After taking the shift, the OATC is to makeup to the LDST 100 gal (70 gal 1A BHUT & 30 gal 1B

BHUT) per OP/1/A/1103/004 Encl 4.6 beginning at step 3.4

Secondary

Unit 2 is supplying the AS header 1AS-35 throttled per Secondary Chemist to provide steam to ‘E’ heaters for secondary O2

removal. Temporary OAC alarms for FDW Loop A/B Composite Valve Demand set at 9.8% per the

Startup Procedure. When in MODE 2, evaluate or restrict evolutions involving MS, FDW, EFDW to minimize

changes to RCS temperature and reactor power. 1SSH-1, 1SSH-3, 1SD-2, 1SD-5, 1SD-140, 1SD-303, 1SD-355, 1SD-356 and 1SD-358 are

closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event.



Batch additions per the maneuvering plan.



AO-501 i Page 1 of 11

REGION II JOB PERFORMANCE MEASURE

AO-501

PLACE THE REACTOR BUILDING HYDROGEN ANALYZER IN SERVICE

Alternate Path: No Alt Path Failure: Time Critical: No Time Critical Criteria:

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II

JOB PERFORMANCE MEASURE

Task Title : Place the 1A Reactor Building Hydrogen Analyzer In Service Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s): System: 028 K/A: G2.1.30 Rating: 4.4/4.0 Task Standard: Reactor Building Hydrogen Analyzers are placed in service by procedure within 90 minutes. References: EP/1/A/1800/001 EOP Enclosure 5.2, “Placing RB Hydrogen Analyzers in Service” Tools/Equipment/Procedures Needed: EOP Enclosure 5.2 “Placing RB Hydrogen Analyzers in Service” rev. 001 ===================================================================================== Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ___________________________________/_________ NAME SIGNATURE DATE =====================================================================================

Comments


SIMULATOR OPERATOR JPM SETUP INSTRUCTIONS

None


NOTE: Student is expected to know that this procedure is pre-staged at the

Hydrogen Analyzers and be able to locate the procedure. (Not Critical)

READ TO OPERATOR

DIRECTION TO TRAINEE I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS

A LOCA has occurred on Unit 1.

Engineered Safeguards Channels 1 and 2 have actuated.

Enclosure 5.1 (ES Actuation) of the EOP is in progress.

The 1A and 1B RB Hydrogen Analyzer Trains are aligned in the standby mode. INITIATING CUES

The Control Room SRO directs you to place both trains of the RB Hydrogen Analyzers in service on Unit 1 per EOP Enclosure 5.2, (Placing RB Hydrogen Analyzers in Service).


START TIME: _______

SEQ STEP

PROC STEP DESCRIPTION

1 1

NOTE Hydrogen analyzer (RP) panels are located in A-6-602, Vent Equipment Rm, col Q73 West.

At 1A H2 ANALYZER (RP), perform the following: __ Ensure POWER ON light is on __ Position H2 DUAL RANGE SW to H2 0 -10% Range __ Position FUNCTION SELECTOR switch to SAMPLE

Depress the OFF button for the following: __ 1PR-83 (BYP TO POST AC 1SV220) __ 1PR-86 (BYP TO POST AC 1SV221) STANDARD: Red "Power On" light on remote panel is verified to be ON

at the Remote RB Hydrogen Analyzer Panel (Train “A”).

Cue: Indication is as you see it.

H2 DUAL RANGE Sw. on the Remote Panel is verified to be positioned to the "0-10%" scale.


FUNCTION SELECTOR SWITCH on the Remote Panel is verified to be positioned in the "SAMPLE" position.


At the remote panel, the "OFF" button is pushed for the following valves:

__ 1PR-83 (BYP TO POST AC 1SV220) __ 1PR-86 (BYP TO POST AC 1SV221)

Cue: OFF button is depressed and indications are as you see them.

COMMENTS:

___ SAT

___ UNSAT


2 2

At 1B H2 ANALYZER (RP), perform the following: __ Ensure POWER ON light is on __ Position H2 DUAL RANGE SW to H2 0 -10% Range __ Position FUNCTION SELECTOR switch to SAMPLE

Depress the OFF button for the following: __ 1PR-89 (BYP TO POST AC 1SV222) __ 1PR-92 (BYP TO POST AC 1SV223) STANDARD: Red "Power On" light on remote panel is verified to be ON

at the Remote RB Hydrogen Analyzer Panel (Train “B”).


H2 DUAL RANGE Sw. on the Remote Panel is verified to be positioned to the "0-10%" scale.


FUNCTION SELECTOR SWITCH on the Remote Panel is verified to be positioned in the "SAMPLE" position.


At the remote panel, the "OFF" button is pushed for the following valves:

__ 1PR-89 (BYP TO POST AC 1SV222) __ 1PR-92 (BYP TO POST AC 1SV223)

Cue: OFF button is depressed and indications are as you see them.

COMMENTS:

___ SAT

___ UNSAT

3 3

Notify the Control Room to perform the following:

__ Open 1PR-81 and 1PR-84

__ Open 1PR-87 and 1PR-90

STANDARD: Unit 1 Control Room personnel are notified to open 1PR-81, 1PR-84, 1PR-87, and 1PR-90 to align the Reactor Building Hydrogen Analyzer to the Reactor Building.

Cue: After notification has been made, indicate to student that the red OPEN indication lights for all four valves located at the Remote Panel are ON and green lights are off.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


4 4

NOTE When ANALYZE is selected, the indication will go up scale, possibly causing a HIGH HYDROGEN ALARM in the Analyzer Panel, the Remote Panel, and the Control Room. It should return down scale to the correct reading in ≈ 3 minutes.

At 1A H2 ANALYZER (RP), perform the following:

__ Position SAMPLE VALVE SEL SW to PR-71 (Top Of Containment Sample).

__ Position OFF / STANDBY / ANALYZE switch to ANALYZE.

__ Depress REMOTE SELECTOR pushbutton to ensure control is from the Remote Panel.

STANDARD: The SAMPLE VALVE SEL switch is positioned to PR-71.

Cue: Point to the Sample Valve Selector Switch and state switch is in the PR-71 position and the red light is illuminated.

The OFF / STANDBY / ANALYZE switch is placed to the ANALYZE position.

Cue: Point to the Off/Standby/Analyze Switch and state the switch is in Analyze position. The Hydrogen Concentration Meter reads approximately 3% hydrogen and the Yellow COMMON ALARM Light and Yellow HIGH HYDROGEN ALARM Lights are ON.

The REMOTE SELECTOR Pushbutton is depressed.

Cue: Pushbutton is depressed.

Cue: Inform candidate that using time compression approximately three minutes have elapsed.

Cue: Inform the candidate that the Hydrogen Concentration Meter indicating 0% hydrogen concentration.

Cue: Inform the candidate that the High alarm is extinguished and the Common alarm is still illuminated.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT


5 5

NOTE When ANALYZE is selected, the indication will go up scale, possibly causing a HIGH HYDROGEN ALARM in the Analyzer Panel, the Remote Panel, and the Control Room. It should return down scale to the correct reading in ≈ 3 minutes.

At 1B H2 ANALYZER (RP), perform the following:

__ Position SAMPLE VALVE SEL SW to PR-76 (Top Of Containment Sample).

__ Position OFF / STANDBY / ANALYZE switch to ANALYZE.

__ Depress REMOTE SELECTOR pushbutton to ensure control is from the Remote Panel.

STANDARD: The SAMPLE VALVE SEL switch is positioned to PR-76.

Cue: Point to the Sample Valve Selector Switch and state switch is in the PR-76 position and the red light is illuminated.

The OFF / STANDBY / ANALYZE switch is placed to the ANALYZE position.

Cue: Point to the Off/Standby/Analyze Switch and state the switch is in Analyze position. The Hydrogen Concentration Meter reads approximately 3% hydrogen and the Yellow COMMON ALARM Light and Yellow HIGH HYDROGEN ALARM Lights are ON.

The REMOTE SELECTOR Pushbutton is depressed.

Cue: The Remote Selector Pushbutton is depressed.

Cue: Inform candidate that using time compression approximately three minutes have elapsed.

Cue: Inform the candidate that the Hydrogen Concentration Meter is indicating 0% hydrogen concentration.

Cue: Inform the candidate that the High alarm is extinguished and the Common alarm is still illuminated.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT


6 6

IAAT either RB Hydrogen Analyzer Train indicates < 2.25% Hydrogen, AND the meter reading stabilizes, THEN push the ALARM RESET pushbutton to reset the COMMON ALARM on appropriate train: __ 1A RB Hydrogen Analyzer Train __ 1B RB Hydrogen Analyzer Train STANDARD: The ALARM RESET Pushbutton is depressed for both

trains.

Cue: Indicate that the Hydrogen reading is ≈ 0 percent on both trains. Cue: Indicate to student that both yellow alarm lights are out after the

ALARM RESET Pushbutton is depressed for each train.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT

7 7

WHEN HIGH HYDROGEN alarm has been reset on both 1A and 1B RB Hydrogen Analyzer Trains, THEN notify Unit 1 Control Room that 1A and 1B Hydrogen Analyzer Trains are in service.

STANDARD: Phone/radio is located and control room personnel are

notified that the RB Hydrogen Analyzers are in service.

COMMENTS:

___ SAT ___ UNSAT

8 8

EXIT this enclosure.

STANDARD: The enclosure is exited.

COMMENTS:

END TASK

___ SAT ___ UNSAT

TIME STOP: ________


CRITICAL STEP EXPLANATIONS

SEQ STEP #

Explanation

3 This step opens the block valves to the 1A and 1B H2 analyzers. 4 This step starts the Analyzer pump and the sampling process for the 1A H2 Analyzer. 5 This step starts the Analyzer pump and the sampling process for the 1B H2 Analyzer. 6 This step is required to enable the Control Room to detect an increase in H2 concentration.

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS

A LOCA has occurred on Unit 1.

Engineered Safeguards Channels 1 and 2 have actuated.

Enclosure 5.1 (ES Actuation) of the EOP is in progress.

The 1A and 1B RB Hydrogen Analyzer Trains are aligned in the standby mode. INITIATING CUES

The Control Room SRO directs you to place both trains of the RB Hydrogen Analyzers in service on Unit 1 per EOP Enclosure 5.2, (Placing RB Hydrogen Analyzers in Service).

AO-803 j Page 1 of 8


AO-803

SUPPLY SSW BY THE FIRE HOSE STATION


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Supply SSW by the Fire Hose Station Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 20 min K/A Rating(s): System: 075 K/A: G2.1.30 Rating: 4.4/4.0 Task Standard: Align HPSW to supply the SSW system using a fire hose in accordance with AP/1/A/1700/033 (Loss of SSW) Enclosure 5.6 (Supply of SSW by the Fire Hose Station). References: AP/1/A/1700/033 (Loss of SSW) Rev. 007 Tools/Equipment/Procedures Needed: AP/1/A/1700/033 (Loss of SSW) Enclosure 5.6 (Supply of SSW by the Fire Hose Station) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



None


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS

Unit 1 Reactor power = 100%

Two of the operating CCW pumps have low bearing seal water flow

Both SSW headers are intact and aligned for normal operation

AP/1/A/1700/033 (Loss of SSW) is in progress INITIATING CUES

The Control Room SRO directs you to perform AP/1/A/1700/033 (Loss of SSW), Enclosure 5.6, (Supply of SSW by the Fire Hose Station) to supply the SSW header by the Fire Hose Station.


START TIME: _______

SEQ STEP


1 1

NOTE • The fire hose, pipe wrench and spanner wrench required to perform this

enclosure are in a bag in the Emergency Equipment Cabinet located T-3/M-54/55.

• All valves are located in the ESV bldg.

To supply SSW from HPSW-921 (HPSW TO SSW MANUAL CONN (VIA EAST ESVB FIRE HOSE)) fire hose station perform the following: A. * Close SSW-18 (B SSW HEADER STRAINER ISOLATION) (2' SW of B

SSW Hdr Strainer). B. Close SSW-14 (A/B SSW HEADER X-CONN) (3' NW of B SSW Hdr

Strainer). C. * Remove the fitting from HPSW-921 (HPSW TO SSW MANUAL CONN

(VIA EAST ESVB FIRE HOSE)) (North side of East personnel access door).

D. * Remove the pipe cap from SSW-10 (A/B SSW HEADER X-CONN FIRE HOSE CONNECTION) (W of B SSW Hdr Strainer).

E. * Connect the fire hose from HPSW-921 (HPSW TO SSW MANUAL CONN (VIA EAST ESVB FIRE HOSE)) to SSW-10 (A/B SSW HEADER X-CONN FIRE HOSE CONNECTION).

F. * Open HPSW-921 (HPSW TO SSW MANUAL CONN (VIA EAST ESVB FIRE HOSE)).

G. * Open SSW-10 (A/B SSW HEADER X-CONN FIRE HOSE CONNECTION).

STANDARD: *Candidate closes SSW-18 by rotating the valve handle

until it is perpendicular (90°) to the pipe. Candidate verifies SSW-14 is closed by verifying the valve

handle is perpendicular (90°) to the pipe. *Candidate removes the fitting from HPSW-921 by rotating

it in the counterclockwise direction. *Candidate removes the pipe cap from SSW-10 by using a

pipe wrench to rotate the pipe cap in the counterclockwise direction until it is removed.

*Candidate connects the fire hose from HPSW-921 to SSW-10 by rotating the fitting on each end in the clockwise direction until each comes to a hard stop.

*Candidate opens HPSW-921 by rotating the handwheel in the counterclockwise direction until it comes to a hard stop.

*Candidate opens SSW-10 by rotating the handle until it is parallel to the pipe.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT


2 2

Notify Unit 1 CR SSW is being supplied from HPSW-921 (HPSW TO SSW MANUAL CONN (VIA EAST ESVB FIRE HOSE)) fire hose station.

STANDARD: Candidate notifies Unit 1 control room that SSW is being supplied from HPSW-921 fire hose station.

COMMENTS:

___ SAT

___ UNSAT

3 3

EXIT this enclosure.

STANDARD: Candidate exits the enclosure.

COMMENTS:

END TASK

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1A This step is required to properly align the flow path from the fire hose station to the ‘B’

SSW header.

1C This step is required to allow the fire hose to be connected to HPSW-921 connection.

1D This step is required to allow the fire hose to be connected to HPSW-921 connection.

1E This step is required to provide the flow path from the HPSW system to the SSW system.

1F This step is required to properly align the flow path from the fire hose station to the ‘B’

SSW header.

1G This step is required to properly align the flow path from the fire hose station to the ‘B’ SSW header.

CANDIDATE CUE SHEET


INITIAL CONDITIONS

Unit 1 Reactor power = 100%

Two of the operating CCW pumps have low bearing seal water flow

Both SSW headers are intact and aligned for normal operation

AP/1/A/1700/033 (Loss of SSW) is in progress INITIATING CUES

The Control Room SRO directs you to perform AP/1/A/1700/033 (Loss of SSW), Enclosure 5.6, (Supply of SSW by the Fire Hose Station) to supply the SSW header by the Fire Hose Station.

AO-S402 k Page 1 of 11


AO-S402

RESET AN EMERGENCY FDW PUMP TURBINE


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Reset an Emergency FDW Pump Turbine Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 10 min K/A Rating(s): System: 061 K/A: A2.04 Rating: 3.4/3.8 Task Standard: Emergency Feedwater Pump Turbine is reset correctly by procedure References: OP/2/A/1106/006 (Emergency FDW System) Rev. 115 Tools/Equipment/Procedures Needed: OP/2/A/1106/006 (Emergency FDW System) Enclosure 4.2 (Resetting TD EFDWP) OP/2/A/1106/006 (Emergency FDW System) Enclosure 4.10 (TD EFDWP Control Mechanism) OP/2/A/1106/006 (Emergency FDW System) Enclosure 4.12 (Full Closed Position Indication For 2MS-95) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



None


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 2 is operating at 100% power. Some workers in the area have inadvertently bumped the Hand Trip Lever on 2MS-94 (TD EFDWP Stop Valve). The EMERGENCY FEEDWATER TURBINE TRIP Statalarm is lit in the Control Room. INITIATING CUE Control Room Supervisor directs you to reset the Turbine Driven Emergency Feedwater Pump on Unit 2 per OP/2/A/1106/006 Enclosure 4.2, (Resetting TD EFDWP), beginning at Step 2.2.


START TIME: _______

SEQ STEP


1 2.2.1

Push RESET LEVER toward turbine shaft until it engages.

STANDARD: Candidate pushes RESET LEVER toward turbine shaft until

it engages

Cue: Indicate to candidate that the Reset Lever is engaged

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

2 2.2.2

Rotate SPINDLE fully clockwise.

STANDARD: Candidate rotates Trip/throttle valve SPINDLE fully CLOCKWISE

Cue: Indicate to candidate that the SPINDLE is in its fully clockwise position.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

3 2.2.3

Verify the following: __ LATCH BLOCK protruding ≈ 1 inch out of valve housing. __ HAND TRIP LEVER traveled to full up position.

STANDARD: Candidate observes Latch Block protruding ≈ 1 inch out of

the valve housing.

Cue: Indicate to candidate that the LATCH BLOCK is ≈ 1 inch out of valve housing.

Candidate observes HAND TRIP LEVER traveled to full up position.

Cue: Indicate to candidate that the HAND TRIP LEVER is in the full up position.

COMMENTS:

___ SAT

___ UNSAT


4 2.2.4

Rotate SPINDLE counterclockwise to open valve.

STANDARD: Candidate rotates Trip/throttle valve SPINDLE fully counterclockwise.

Cue: Indicate to candidate that the Trip/throttle valve spindle is in its full counterclockwise position.

COMMENTS:

___ SAT ___ UNSAT

5 2.2.5

Verify SPRING PLATE traveled up.

STANDARD: Candidate observes spring plate in its full up position.

Cue: Indicate to candidate that the SPRING PLATE is in its full up position.

COMMENTS:

___ SAT ___ UNSAT

6 2.2.6

Rotate SPINDLE clockwise 1/4 turn.

STANDARD: Candidate rotates Trip/throttle valve SPINDLE clockwise 1/4 turn.

Cue: Indicate that the SPINDLE is ¼ turn from full counterclockwise position.

COMMENTS:

___ SAT ___ UNSAT


7 2.2.7

Verify the following: __ 2SA-18/D-12 (TD EFDW PUMP TRIPPED) NOT in alarm __ O2D1886 "2MS-94 EFWPT Trip Valve" indicates "OPEN"

STANDARD: Candidate contacts the control room to verify that Statalarm 2SA-18/D-12 is NOT is alarm and OAC Computer point O2D1886 indicates “OPEN”.

Cue: When the candidate simulates contacting the control room, indicate that 2SA-18/D-12 is not in alarm and O2D1886 indicates “OPEN”

COMMENTS:

___ SAT ___ UNSAT

8 2.2.8

NOTE RESET LEVER will only disengage for an overspeed trip condition. If RESET LEVER is NOT engaged, then the TD EFDWP has NO overspeed trip protection.

To ensure positive latching of 2MS-94 RESET LEVER, perform the following: A. Trip HAND TRIP LEVER. B. Verify 2MS-94 tripped as follows:

• 2SA-18/D-12 (TD EFDW PUMP TRIPPED) alarm locked in • O2D1886 “2MS-94 EFWPT Trip Valve” indicates “NOT OPEN”

C. Verify RESET LEVER does NOT disengage. STANDARD: Candidate pushes down on the Hand Trip Lever

Candidate contacts the control room to verify that 2SA-18/D-12 alarm is locked in and OAC Computer point O2D1886 indicates “NOT OPEN”.

Candidate verifies the Reset Lever does NOT disengage.

Cue: Indicate that the Hand Trip Lever is tripped.

Cue: When the candidate simulates contacting the control room, indicate that 2SA-18/D-12 alarm is locked in and O2D1886 indicates “NOT OPEN”.

Cue: Indicate that the Reset Lever is engaged.

COMMENTS:

___ SAT ___ UNSAT


9 2.2.9

Rotate SPINDLE fully clockwise.

STANDARD: Candidate rotates Trip/throttle valve SPINDLE fully

CLOCKWISE Cue: Indicate to candidate that the SPINDLE is in its fully clockwise

position.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

10 2.2.10

Verify the following: __ LATCH BLOCK protruding ≈ 1 inch out of valve housing. __ HAND TRIP LEVER traveled to full up position.

STANDARD: Candidate observes Latch Block protruding ≈ 1 inch out of

the valve housing.

Cue: Indicate to candidate that the LATCH BLOCK is ≈ 1 inch out of valve housing.

Candidate observes HAND TRIP LEVER traveled to full up position.

Cue: Indicate to candidate that the HAND TRIP LEVER is in the full up position.

COMMENTS:

___ SAT

___ UNSAT

11 2.2.11

Rotate SPINDLE counterclockwise to open valve.

STANDARD: Candidate rotates Trip/throttle valve SPINDLE fully counterclockwise.

Cue: Indicate to candidate that the Trip/throttle valve spindle is in its full counterclockwise position.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT


12 2.2.12

Verify SPRING PLATE traveled up.

STANDARD: Candidate observes spring plate in its full up position.

Cue: Indicate to candidate that the SPRING PLATE is in its full up position.

COMMENTS:

___ SAT ___ UNSAT

13 2.2.13

Rotate SPINDLE clockwise 1/4 turn.

STANDARD: Candidate rotates Trip/throttle valve SPINDLE clockwise 1/4 turn.

Cue: Indicate that the SPINDLE is ¼ turn from full counterclockwise position.

COMMENTS:

END TASK

___ SAT ___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1 This step is required to reset 2MS-94 2 This step is required to reset 2MS-94 9 This step is required to latch 2MS-94 so the valve can be opened

11 This step is required to open 2MS-94 so the TDEFWP can start when given a start signal

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 2 is operating at 100% power. Some workers in the area have inadvertently bumped the Hand Trip Lever on 2MS-94 (TD EFDWP Stop Valve). The EMERGENCY FEEDWATER TURBINE TRIP Statalarm is lit in the Control Room. INITIATING CUE Control Room Supervisor directs you to reset the Turbine Driven Emergency Feedwater Pump on Unit 2 per OP/2/A/1106/006 Enclosure 4.2, (Resetting TD EFDWP), beginning at Step 2.2.

RO-103a a Page 1 of 9


RO-103a

WITHDRAWAL OF SAFETY RODS GROUP 1 TO 50%

Alternate Path: Yes Alt Path Failure: Time Critical: No Time Critical Criteria:

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Withdrawal of Safety Rods Group 1 to 50% Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 15 min K/A Rating(s): System: 001 K/A: G2.2.2 Rating: 4.6/4.1 Task Standard: Begin withdrawal Of Safety Rod Group 1 To 50% and manually trip the reactor when CRD temperature limits are exceeded per OMP 1-18. References: OP/1/A/1105/019 (Control Rod Drive System) Encl. 4.3 (Withdrawal Of Safety Rod Group 1 To 50%) rev 26

OMP 1-18 Implementation Standards During Abnormal and Emergency Events rev 37 Tools/Equipment/Procedures Needed: OP/1/A/1105/019 (Control Rod Drive System) Encl. 4.3 (Withdrawal Of Safety Rod Group 1 To 50%) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 211 2. IMPORT RO-103a Simulator files

3. Go To RUN

4. Select SR/WR on NI Recorder


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 startup is in progress RCS temperature = 332ºF RCS pressure = 475 psig INITIATING CUE The Control Room SRO directs you to: 1. Withdraw CRD Group 1 to 50% per OP/1/A/1105/019 (Control Rod Drive System)

Enclosure 4.3 (Withdrawal Of Safety Rod Group 1) beginning at Step 2.1.

a. Perform an Automatic Latch of Group 1 Control Rods when directed.


START TIME: _______

SEQ STEP


1 3.1

Perform the following: (R.M.) • Ensure RUN is ON. • Ensure SINGLE SELECT SWITCH to ALL.

STANDARD: Determine control rod speed switch is selected to RUN by

observing light indication on the Diamond.

Determine SINGLE SELECT SWITCH is selected to ALL on the Diamond.

Examiner Note: If asked about Concurrent Verification, state that the verifier agrees with whatever actions you decide to take.

COMMENTS:

___ SAT

___ UNSAT

2 3.2

WHILE CRDs are moving, monitor the following indications: • CRD position • Appropriate ranged NIs • Startup Rate

STANDARD: As CRDs are withdrawn, monitor the above indications. COMMENTS:

___ SAT

___ UNSAT


3 3.3

Perform Latch and PI alignment of Group 1, as follows: (R.M.) 3.3.1 Ensure GROUP SELECT SWITCH to 1. 3.3.2 Verify only Group 1 CONTROL ON lights are ON. (PI panel) 3.3.3 IF Manual Latch and PI Alignment desired, perform the following: (Per the initiating cue, Manual Latch is NOT desired)

NOTE: When LATCH AUTO is selected, the following automatically occurs: • Group inserts to latch rods (CRD TRAVEL "In" light ON) • Group withdraws to test for latching (CRD TRAVEL "Out" light ON) • Group inserts (CRD TRAVEL "In" light ON) • RPI resets • Group In Limit light on Diamond will momentarily extinguish then

illuminate

3.3.4 IF Auto Latch and PI Alignment desired, perform the following: (R.M.) A. Select LATCH AUTO B. WHEN Auto Latch is complete, perform the following:

• Verify LATCH AUTO is OFF. • Verify all 0% lights ON for Group 1. (PI Panel) • Verify Group 1 API/RPI indications agree. (PI Panel)

STANDARD: *Rotate GROUP SELECT SWITCH to 1.

Determine that only Group 1 CONTROL ON lights are “ON” on the PI panel.

*Depress the LATCH AUTO pushbutton.

WHEN Auto Latch is complete: Verify LATCH AUTO is OFF. Verify Group 1 0% lights are ON. (PI Panel) Verify Group 1 API/RPI indications agree using the

position switch on the PI Panel. COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT

4 3.4

Select FAULT RESET.

STANDARD: Depress FAULT RESET pushbutton on the diamond panel.

COMMENTS:

___ SAT

___ UNSAT


5 3.5

Select Group 1, as follows: (R.M.) 3.5.1 Ensure GROUP SELECT SWITCH to 1. 3.5.2 Ensure only Group 1 CONTROL ON lights are ON. (PI panel) 3.5.3 Ensure Group 1 at 50%. (R.M.) 3.5.4 Place GROUP SELECT SWITCH to OFF. STANDARD: Ensure GROUP SELECT SWITCH to 1. Determine that only Group 1 CONTROL ON lights are ON

on the PI panel. *Begin withdrawing Group 1 Control Rods to 50% Note: As control rods are withdrawn, CRD temperatures will begin to

increase.

Examiner Note: If asked about Concurrent Verification, state that the verifier agrees with whatever actions you decide to take.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT

6

[ALTERNATE PATH] Manually Trip the Reactor when two or more CRDM stator temperatures are ≥ 180°F in accordance with OMP 1-18 Attachment A (Licensed Operator Memory Items).

STANDARD: Candidate Manually Trips the Reactor when two or more

CRDM stator temperatures are ≥ 180°F IAW OMP 1-18 Attachment A (Licensed Operator Memory Items).

Note: At ≈ 10% withdrawn, CRD stator temperatures will begin to increase. At ≈ 18% withdrawn, CRD stator temperatures will reach the OAC alarm set point. Once any two CRD stator temperatures reach 180°F, the candidate should trip the Reactor. The Critical Step is satisfied if the Reactor is manually tripped before Group 1 Control Rods reach 50% withdrawn and the candidate decides the task is completed.

OMP 1-18 Attachment A states the following: 1.17 Initiate a manual Rx trip if any of the following conditions exist:

• Two or more CRDM stator temperatures ≥ 180°F COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

3 This step is required to withdraw group 1 control rods. 5 This step is required to withdraw group 1 control rods. 6 This step is required to manually trip the reactor when CRD temperature limits are

exceeded.

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 1 startup is in progress RCS temperature = 332ºF RCS pressure = 475 psig INITIATING CUE The Control Room SRO directs you to: 1. Withdraw CRD Group 1 to 50% per OP/1/A/1105/019 (Control Rod Drive System)

Enclosure 4.3 (Withdrawal Of Safety Rod Group 1) beginning at Step 2.1. a. Perform an Automatic Latch of Group 1 Control Rods when directed.

RO-203 d Page 1 of 9


RO-203

PRESSURE MAKEUP TO CFT


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Pressure Makeup to CFT Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 10 min K/A Rating(s): System: 006 K/A: A1.13 Rating: 3.5/3.7 Task Standard: Use OP/1/A/1104/001 (Core Flooding System) to increase 1A CFT pressure to ≈ 605 psig. References: OP/1/A/1104/001 (Core Flooding System) rev 079 Tools/Equipment/Procedures Needed: OP/1/A/1104/001 (Core Flooding System) Enclosure 4.7 (Pressure Makeup to CFTs Using Nitrogen) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 212 2. IMPORT files for RO-203

3. Go to RUN


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 is operating at 100% power Core Flood Tank low pressure Statalarm actuated OP/1/A/1104/001 (Core Flooding System) Enclosure 4.7 (Pressure Makeup To CFTs Using Nitrogen) is in progress INITIATING CUES The CR SRO directs you to complete the pressurization of the affected CFT by pressurizing to ≈ 600 psig beginning at Step 2.1 of Enclosure 4.7


START TIME: _______

SEQ STEP


1 2.1

Notify operator to open 1N-137 (CFTs Supply). (A-2-Hallway)

STANDARD: The candidate directs an AO to open 1N-137, communicate

when the valve is open, and standby for further instruction.

Booth Cue: When contacted, use Manual Valves to open 1N-137 and inform student that 1N-137 is OPEN and you are standing by for further instructions.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

2 2.2

IF required to increase pressure in 1A CFT:

STANDARD: Determine that 1A CFT is has low pressure by observing either:

The computer point for Core Flood Tank “1A” on the Operator Aid Computer.

OR “1A” Core Flood Tank pressure gauge located on 1VB2. OR Statalarm 1SA-8/A-11 (CF TANK A PRESS HIGH/LOW) Continue to step 2.2.1 COMMENTS:

___ SAT

___ UNSAT


3 2.2.1

NOTE: TS 3.6.3 Condition 'B' requires penetration flow path to be isolated within one hour. A check valve with flow secured through the valve is considered operable.

Enter Technical Specification 3.6.3 Condition 'A' and 'B'.

STANDARD: Candidate notifies the CRS to enter Technical Specification

3.6.3 Condition 'A' and 'B'.

Cue: Inform candidate that Tech Spec 3.6.3 Conditions ‘A’ and ‘B’ have been entered and step 2.2.1 is complete and signed off

COMMENTS:

___ SAT

___ UNSAT

4 2.2.2

Open 1N-298 (N2 FILL CORE FLOOD TANK 1A).

STANDARD: Open 1N-298 the “1A” Core Flood Tank nitrogen fill valve,

located on 1VB2. Verify RED OPEN indicating light lit; Green CLOSE light off.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

5 2.2.3

IF 1N-128 (CFT 1A Supply) is closed, throttle 1N-128 (CFT 1A Supply) for a rate of ≤ 100 psig per 15 minutes (≈ 6.6 psig/min). (A-4-409)

STANDARD: Determine 1N-128 is NOT closed. Continue to Step 2.2.4.

Cue: If asked, inform candidate that 1N-128 is NOT closed

COMMENTS:

___ SAT

___ UNSAT


6 2.2.4

Monitor 1A CFT pressure.

STANDARD: Observe computer point or pressure gauge for “1A” Core

Flood Tank on 1VB2 and verify Core Flood Tank pressure is increasing.

COMMENTS:

___ SAT

___ UNSAT

7 2.2.5

IF AT ANY TIME ES actuation occurs, close 1N-298 (N2 FILL CORE FLOOD TANK 1A).

STANDARD: Determine ES actuation has not occurred by observing:

Statalarm Panel 1SA-1 Alarms 10 and 11 on rows A thru D NOT in alarm

COMMENTS:

___ SAT

___ UNSAT

8 2.2.6

IF AT ANY TIME 1N-298 fails to close, notify operator to close 1N-137 (CFTs Supply). (A-2-Hallway).

STANDARD: Acknowledges the IAAT step to notify an operator to close

1N-137 if 1N-298 fails to close. COMMENTS:

___ SAT

___ UNSAT

9

WHEN pressurization of 1A CFT complete, close 1N-298 (N2 FILL CORE FLOOD TANK 1A).

STANDARD: Close the 1N-298 located on 1VB2 when Core Flood Tank

pressure is approximately 605 psig (600 psig to 610 psig). Verify CFT pressure stops increasing.

COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1 1N-137 must be opened to supply Nitrogen to pressurize the CFT. 4 1N-298 must be opened to supply Nitrogen to pressurize the CFT. 9 1N-298 must be closed to prevent over pressurizing the CFT.

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 1 is operating at 100% power Core Flood Tank low pressure Statalarm actuated OP/1/A/1104/001 (Core Flooding System) Enclosure 4.7 (Pressure Makeup To CFTs Using Nitrogen) is in progress INITIATING CUES The CR SRO directs you to complete the pressurization of the affected CFT by pressurizing to ≈ 600 psig beginning at Step 2.1 of Enclosure 4.7

RO-305a b Page 1 of 10


RO-305a

PERFORM REQUIRED ACTIONS FOR A FAILED LPI TRAIN

Alternate Path: Yes Alt Path Failure: Both LPI pumps fail to start requiring the 1C LPI pump to be aligned and

started Time Critical: Yes Time Critical Criteria: The 1C LPI pump must be started within 60 minutes from the failure of

the second LPI pump

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Perform Required Actions For a Failed LPI Train Task Number : N/A Alternate Path: Yes Time Critical: Yes Validation Time: 15 min K/A Rating(s): System: EPE 011 K/A: EA1.04 Rating: 4.4/4.4 Task Standard: 1C LPI pump is aligned and started in accordance with EOP Enclosure 5.1. Time critical clock starts when the second LPI pump fails to start and stops when 1C LPI pump is started. The 1C LPI pump must be started within 60 minutes from the failure of the second LPI pump. References: EP/1/A/1800/001 (Unit 1 Emergency Operating Procedure) Tools/Equipment/Procedures Needed: EOP Enclosure 5.1 (ES Actuation) rev. 001 ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 213 2. IMPORT files for RO-305a

3. Go to RUN when directed by the Lead Examiner


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS A LOCA has been in progress that initially stabilized RCS pressure at ≈ 1200 psig. ES Channels 1-8 have actuated on high RB pressure. LOCA CD Tab in progress. Rule 2 (Loss of SCM) is complete. All actions have been taken in Enclosure 5.1 for ES Channels 1-8 actuation. Enclosure 5.1 (ES Actuation) has been completed up to Step 52. The LPI pumps were secured as directed by Enclosure 5.1 (ES Actuation) to prevent pump damage from operating against a shutoff head. Steam Generator levels are being raised to the Loss of Subcooling Margin setpoint by the OATC. CURRENT CONDITIONS RCS pressure has decreased rapidly and Reactor Building pressure has increased. INITIATING CUES The Control Room SRO directs you to continue in Enclosure 5.1 (ES Actuation) at Step 52. THIS JPM IS TIME CRITICAL


START TIME: _______

SEQ STEP


1

REFER TO Enclosure 5.1 IAAT Steps prior to Step 52.

STANDARD: Candidate checks the IAAT steps to determine if any of

them apply.

Candidate determines that IAAT Step 20 now applies.

Candidate continues to Step 20 COMMENTS:

___ SAT

___ UNSAT

2 20

IAAT RCS pressure is < LPI pump shutoff head, THEN perform Steps 21 - 22. STANDARD: Candidate determines that RCS pressure is < LPI pump

shutoff head and continues to Step 21. COMMENTS:

___ SAT

___ UNSAT

3 21

Perform the following: __ Open 1LP-17. __ Start 1A LPI PUMP. STANDARD: Candidate determines that 1LP-17 is open by observing the

Red open light is lit and green closed light is off located on 1UB2.

Candidate places 1A LPI pump switch to START and determines that the 1A LPI pump does not start by observing red lights remain off and white light remains on.

Candidate continues to Step 21 RNO.

Note: The 1A LPI pump fails to start. COMMENTS:

___ SAT

___ UNSAT


4 21

RNO

1. Stop 1A LPI PUMP.

2. Close 1LP-17. STANDARD: Candidate determines that the1A LPI pump is stopped by

observing the white off light lit Candidate closes 1LP-17 located on 1UB2 by rotating the

switch to the close position and observes the green close light on and the red open light off.

Continue to Step 22. COMMENTS:

___ SAT

___ UNSAT

5 22

Perform the following: __ Open 1LP-18. __ Start 1B LPI PUMP. STANDARD: Candidate determines that 1LP-18 is open by observing the

Red open light is lit and green closed light is off located on 1UB2.

Candidate places 1B LPI pump switch to START and determines that the 1B LPI pump does not start by observing red lights remain off and white light remains on.

Candidate continues to Step 22 RNO.

Note: The 1B LPI pump fails to start. The Time Critical completion time is 60 minutes from the failure of the second LPI pump.

TIME CRITICAL clock starts: ______________ COMMENTS:

___ SAT

___ UNSAT


6 22

RNO

1. Stop 1B LPI PUMP. 2. Close 1LP-18. STANDARD: Candidate determines that the1B LPI pump is stopped by

observing the white off light lit.

Candidate closes 1LP-18 located on 1UB2 by rotating the switch to the close position and observes the green close light on and the red open light off.

Return to Step 52 and determine that IAAT Step 23 now applies

Continue to Step 23. COMMENTS:

___ SAT

___ UNSAT

7 23

[ALTERNATE PATH]

IAAT 1A and 1B LPI PUMPs are off / tripped, AND all exist: __ RCS pressure < LPI pump shutoff head __ 1LP-19 closed __ 1LP-20 closed THEN perform Steps 24 - 25. STANDARD: Candidate determines the following:

• 1A and 1B LPI pumps are off / tripped • RCS pressure is < LPI pump shutoff head (≈ 180 psig)

by observing the RCS pressure gauge on 1UB1 • 1LP-19 and 1LP-20 are both closed by observing the

green closed lights lit and the red open lights off on 1UB2

Candidate continues to Step 24. COMMENTS:

___ SAT

___ UNSAT


8 24

Open: __ 1LP-9 and 1LP-10 __ 1LP-6 and 1LP-7 __ 1LP-17 and 1LP-18 __ 1LP-21 and 1LP-22

STANDARD: Candidate opens the following valves (located on 1UB2)

and observes the red open lights lit and the green closed lights off. • *1LP-9 and 1LP-10 • *1LP-6 and 1LP-7 • *1LP-17 and 1LP-18

Candidate determines that 1LP-21 and 1LP-22 are open by observing the red open lights lit and the green closed lights off (located on 1UB2).

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT

9 25

Start 1C LPI PUMP. STANDARD: Candidate starts the 1C LPI pump located on 1UB2 and

verifies the red on light are lit, the white off light is off, and verifies the pump develops discharge pressure and flow.

TIME CRITICAL clock stops: ______________

Note: The 1C LPI pump must be started within 60 minutes of the 1B LPI pump failure to start.

COMMENTS:

Cue: Another operator will continue with this procedure.

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

8 This step is necessary to align a suction source and a discharge flow path for the

1C LPI pump since 1A and 1B LPI pumps fail to start. 9 This step is necessary to start the 1C LPI pump to provide LPI flow to the core (must be

completed within 60 minutes of 1A and 1B LPI pump failure).

CANDIDATE CUE SHEET


INITIAL CONDITIONS A LOCA has been in progress that initially stabilized RCS pressure at ≈ 1200 psig. ES Channels 1-8 have actuated on high RB pressure. LOCA CD Tab in progress. Rule 2 (Loss of SCM) is complete. All actions have been taken in Enclosure 5.1 for ES Channels 1-8 actuation. Enclosure 5.1 (ES Actuation) has been completed up to Step 52. The LPI pumps were secured as directed by Enclosure 5.1 (ES Actuation) to prevent pump damage from operating against a shutoff head. Steam Generator levels are being raised to the Loss of Subcooling Margin setpoint by the OATC. CURRENT CONDITIONS RCS pressure has decreased rapidly and Reactor Building pressure has increased. INITIATING CUES The Control Room SRO directs you to continue in Enclosure 5.1 (ES Actuation) at Step 52. THIS JPM IS TIME CRITICAL

RO-504a f Page 1 of 10


RO-504a

PERFORM EOP ENCLOSURE 5.35

Alternate Path: Yes Alt Path Failure: 1HP-3 fails to close requiring 1HP-1 to be closed in order to

isolate containment Time Critical: No Time Critical Criteria:

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Perform EOP Enclosure 5.35 Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 10 min K/A Rating(s): System: 103 K/A: G2.1.23 Rating: 4.3/4.4 Task Standard: Perform EOP Encl 5.35 (Containment Isolation) correctly. References: EP/1/A/1800/001 (Unit 1 Emergency Operating Procedure) Tools/Equipment/Procedures Needed: EOP Enclosure 5.35 (Containment Isolation) rev. 0 ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 215 2. IMPORT RO-504a simulator files

3. On the initial setup, recall IC-41 and set breaker flags to match plant conditions 4. Go to RUN and acknowledge alarms 5. Go to FREEZE 6. Go to RUN when directed by the Lead Examiner


READ TO OPERATOR


INITIAL CONDITIONS Unit 1 Reactor tripped from 100% power due to a spurious Main Turbine trip. RCS leak of 190 gpm occurs as result of the trip. EOP LOCA CD tab is in progress. ES Actuation has NOT occurred. INITIATING CUE The Control Room SRO directs you to perform EOP Enclosure 5.35 (Containment Isolation).


START TIME: _______

SEQ STEP


1 1

Verify Encl 5.1 (ES Actuation) is in progress or complete. STANDARD: Candidate determines that ES has NOT actuated from the

Initial Conditions and continues to Step 1 RNO. COMMENTS:

___ SAT

___ UNSAT

2 1

RNO

1. Close the following ES operated RB isolation valves:

√ ES Chan 1 √ ES Chan 2

1HP-3 1HP-5 1HP-4* 1GWD-12 1GWD-13 1LWD-1 1LWD-2 1CS-5 1CS-6 1PR-1 1PR-2 1PR-6 1PR-3 1PR-4 1PR-5 1PR-7* 1PR-8* 1PR-9* 1PR-10* 1RC-5 1RC-7 1RC-6 1FDW-105 1FDW-106 1FDW-107 1FDW-108 1FDW-103 1FDW-104

STANDARD: Candidate closes the valves listed above and determines

that 1HP-3 will not close.

Note: 1HP-3 will NOT close. COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT


3 1

RNO

[ALTERNATE PATH] 2. IF 1HP-3 fails to close, THEN close 1HP-1. STANDARD: Candidate determines that 1HP-3 is open by observing the

red open light on and green closed light off. Candidate positions 1HP-1 switch in the closed position and

verifies the green closed light is on and the red open light is off.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

4 1

RNO

3. IF 1HP-4 fails to close, THEN close 1HP-2. STANDARD: Candidate determines that 1HP-4 is closed by observing the

red light off and green light on. COMMENTS:

___ SAT

___ UNSAT

5 1

RNO

4. IF 1HP-5 fails to close, THEN close: __ 1HP-7 __ 1HP-6

STANDARD: Candidate determines that 1HP-5 is closed by observing the

red light off and green light on. COMMENTS:

___ SAT

___ UNSAT


6 2

Verify all RCPs off. STANDARD: Candidate determines that all RCPs are operating by

observing red on light lit and RCP amps indicate normal.

Candidate continues to Step 2 RNO. COMMENTS:

___ SAT

___ UNSAT

7 2

RNO

GO TO Step 5. STANDARD: Candidate continues to Step 5 COMMENTS:

___ SAT

___ UNSAT

8 5

Rotate switches to the closed position for the following components: __ 1LPSW-1054 __ 1LPSW-1055 __ 1LPSW-1061 __ 1LPSW-1062

STANDARD: Candidate rotates the above switches to the closed position

located on 1VB3.

Note: Either 1LPSW-1054 or 1LPSW-1055 and 1LPSW-1061 or 1LPSW-1062 must be closed to satisfy the critical step.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


9 6

Verify the following components indicate closed: __ 1LPSW-1054 __ 1LPSW-1055 __ 1LPSW-1061 __ 1LPSW-1062

STANDARD: Candidate verifies the above valves indicate closed by

observing the green closed lights are on and red open lights are off located on 1VB3.

COMMENTS:

___ SAT

___ UNSAT

10 7

EXIT this enclosure. STANDARD: Candidate exits the enclosure COMMENTS:

END TASK

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

2 This step is critical to isolate the Reactor Building. 3 This step is critical since 1HP-3 is failed open 1HP-1 isolates this pathway. 8 This step is critical to isolate the Reactor Building.

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 1 Reactor tripped from 100% power due to a spurious Main Turbine trip. RCS leak of 190 gpm occurs as result of the trip. EOP LOCA CD tab is in progress. ES Actuation has NOT occurred. INITIATING CUE The Control Room SRO directs you to perform EOP Enclosure 5.35 (Containment Isolation).

RO-603a g Page 1 of 14


RO-603a

ENERGIZE MFBs FROM CT-5

Alternate Path: Yes Alt Path Failure: Both Keowee Units fail to start when required Time Critical: No Time Critical Criteria:

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Energize MFBs From CT-5 Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 15 min K/A Rating(s): System: EPE 055 K/A: EA1.07 Rating: 4.3/4.5 Task Standard: Energize Main Feeder Busses from CT-5 in accordance with EOP Enclosure 5.38. References: EP/1/A/1800/001 (Unit 1 Emergency Operating Procedure) Tools/Equipment/Procedures Needed: EOP Enclosure 5.38 (Restoration of Power) rev. 0 ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 216 (password in ALL CAPS) 2. IMPORT RO-603a simulator files

3. Place simulator in RUN so the lights go out, then go to FREEZE.

4. Place simulator in RUN when directed by the Lead Examiner


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 1 has experienced a lockout on CT-1 followed by a Reactor trip. The Blackout tab of the EOP in progress. The Blackout tab directs the initiation of Enclosure 5.38 (Restoration of Power). INITIATING CUES The Control Room SRO directs you to initiate EOP Enclosure 5.38 (Restoration of Power) to regain power to the Main Feeder Buses.


START TIME: _______

SEQ STEP


1 1

Verify power has been restored. STANDARD: Candidate determines that power has NOT been restored

by observing MFB voltage on 1AB1 and continues to Step 1 RNO.

COMMENTS:

___ SAT

___ UNSAT

2 1

RNO

GO TO Step 3. STANDARD: Candidate continues to Step 3. COMMENTS:

___ SAT

___ UNSAT

3 3

Place 1HP-31 in HAND and reduce demand to 0. STANDARD: Candidate places 1HP-31 in HAND and reduces demand to

zero using the toggle switch located on 1UB1. COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


4 4

Close 1HP-21. STANDARD: Candidate closes 1HP-21 by rotating the switch to the

closed position located on 1UB2. COMMENTS:

___ SAT

___ UNSAT

5 5

Verify any of the following energized: __ MFB1 __ MFB2

STANDARD: Candidate Observes that zero (0) volts are indicated on

both MFBs meters located on 1AB1 and continues to Step 5 RNO.

COMMENTS:

___ SAT

___ UNSAT

6 5

RNO


___ SAT

___ UNSAT

7 8

Verify CT-1 indicates ≈ 4160 volts. STANDARD: Candidate observes that zero (0) volts is indicated on CT-1

on 1AB1 and continues to Step 8 RNO. COMMENTS:

___ SAT

___ UNSAT


8 8

RNO


___ SAT

___ UNSAT

9 18

Verify both Standby Bus #1 and Standby Bus #2 are de-energized (0 volts). STANDARD: Candidate observes that zero (0) volts is indicated both

Standby Buses located on 2AB3. COMMENTS:

___ SAT

___ UNSAT

10 19

Verify both Keowee units operating. STANDARD: Candidate determines that both Keowee units are

Emergency Locked Out (not operating) by observing the Statalarms 2SA-17/A-1 and 2SA-18/A-1 or by observing KHU-1 & KHU-2 output voltage/frequency (0 volts/0 Hz) or by observing KHU-1 & KHU-2 gate position (0%) located on 2AB3 and continues to Step 19 RNO.

COMMENTS:

___ SAT

___ UNSAT


11 19

RNO

[ALTERNATE PATH] 1. Emergency start Keowee units:

__ KEOWEE EMER START CHANNEL A __ KEOWEE EMER START CHANNEL B

2. __ IF NO Keowee units are operating, THEN perform the following: A. __ Notify Keowee operator to restore a Keowee unit to operable

status. B. __ GO TO Step 38.

STANDARD: Candidate places both KEOWEE EMER START CHANNEL

switches to start located on 1UB1. Candidate determines that neither Keowee unit is operating

and notifies the Keowee operator to restore a Keowee unit to operable status.

Candidate continues to Step 38

Note: Since both Keowee units are locked out, the candidate may decide to not operate the emergency start switches.

COMMENTS:

___ SAT

___ UNSAT

12 38

IAAT CT-5 indicates ≈ 4160 volts, THEN GO TO Step 53. STANDARD: Candidate observes that approximately 4160 volts is

indicated on the CT-5 voltage meter located on 1AB1 and continues to Step 53.

COMMENTS:

___ SAT

___ UNSAT


13 53

Place the following switches in MAN: __ MFB1 AUTO/MAN __ MFB2 AUTO/MAN __ STANDBY 1 AUTO/MAN __ STANDBY 2 AUTO/MAN

STANDARD: Candidate rotates the AUTO/MAN selector switch to the

MANUAL position for each of the switches listed above. COMMENTS:

___ SAT

___ UNSAT

14 54

Open the following breakers: __ N11 MFB1 NORMAL FDR __ N21 MFB2 NORMAL FDR __ E11 MFB1 STARTUP FDR __ E21 MFB2 STARTUP FDR

STANDARD: Candidate verifies each of the above breakers is OPEN by

observing the white breaker open lights are lit on 1AB1. COMMENTS:

___ SAT

___ UNSAT

15 55

Place the following switches in MAN: __ CT4 BUS 1 AUTO/MAN __ CT4 BUS 2 AUTO/MAN __ CT5 BUS 1 AUTO/MAN (already in MAN) __ CT5 BUS 2 AUTO/MAN (already in MAN)


MANUAL position for each of the switches listed above located on 2AB3.

COMMENTS:

___ SAT

___ UNSAT


16 56

Open the following breakers: __ SK1 CT4 STBY BUS 1 FEEDER __ SK2 CT4 STDY BUS 2 FEEDER

STANDARD: Candidate verifies each of the above breakers is OPEN by

observing the white breaker open lights are lit on 2AB3. COMMENTS:

___ SAT

___ UNSAT

17 57

Close the following breakers: __ SL1 CT5 STBY BUS 1 FEEDER __ SL2 CT5 STBY BUS 2 FEEDER

STANDARD: Candidate rotates the control switch for the above breakers

to the CLOSE position located on 1AB3 and observes the white open lights off and the red closed lights on.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

18 58

Place the following switches in AUTO: __ CT5 BUS 1 AUTO/MAN __ CT5 BUS 2 AUTO/MAN


AUTO position for each of the switches listed above. COMMENTS:

___ SAT

___ UNSAT


19 59

Verify Standby Bus #1 energized. STANDARD: Candidate observes that ≈ 4160 volts are indicated for

Standby Bus #1 located on 2AB3. COMMENTS:

___ SAT

___ UNSAT

20 60

Notify CRS in each unit where a blackout exists that Standby Bus #1 is energized. STANDARD: Candidate notifies the CRS that Standby Bus #1 is

energized located on 2AB3.

Cue: If asked, inform the candidate that only Unit 1 is affected.

COMMENTS:

___ SAT

___ UNSAT

21 61

Close the following breakers: __ S11 STBY BUS 1 TO MFB1 __ S21 STBY BUS 2 TO MFB2

STANDARD: Candidate rotates the switches to the CLOSE position for

each of the breakers listed above and observes the white open lights off and the red closed lights on.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


22 62

Verify any of the following energized: __ 1TC __ 1TD __ 1TE STANDARD: Candidate observes ≈ 4160 volts indicated on either MFB

voltmeters or on the OAC. COMMENTS:

END TASK

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

3 Step is required to protect the RCP seals.

17 Step is required to energize the Main Feeder Bus.

21 Step is required to energize the Main Feeder Bus.

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 1 has experienced a lockout on CT-1 followed by a Reactor trip. The Blackout tab of the EOP in progress. The Blackout tab directs the initiation of Enclosure 5.38 (Restoration of Power). INITIATING CUES The Control Room SRO directs you to initiate EOP Enclosure 5.38 (Restoration of Power) to regain power to the Main Feeder Buses.

RO-804 h Page 1 of 10


RO-804

PLACE REACTOR BUILDING PURGE IN OPERATION


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Place Reactor Building Purge in Operation Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 min K/A Rating(s): System: 029 K/A: A2.03 Rating: 2.7/3.1 Task Standard: The Reactor Building Purge is placed in operation correctly in accordance with OP/1/A/1102/014 Enclosure 4.1. References: OP/1/A/1102/014 (RB Purge System) rev. 046 PT/0/A/0230/001 (Radiation Monitor Check) rev. 169 Tools/Equipment/Procedures Needed: OP/1/A/1102/014 Enclosure 4.1 (RB Purge Release) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 218 2. There are NO files to import

3. Ensure T/O Sheet tags are removed from the 1A or 1B RB Aux Fans from the prior JPM



READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS RCS temperature = 120°F RCS pressure = 41 psig No GWD or LWD releases are in progress RB Hatch is CLOSED Continuous release is NOT in progress RB Purge startup is in progress using OP/1/A/1102/014 (RB Purge System), Enclosure 4.1 (RB Purge Release) INITIATING CUE The CRS directs you to place the RB Purge in operation at 1/3 Station Limit using OP/1/A/1102/014 Enclosure 4.1 starting at Step 3.8


START TIME: _______

SEQ STEP


1 3.8

3.8 Perform the following: 3.8.1 Ensure one of the following:

__ 1A RB AUX FAN is Off. __ 1B RB AUX FAN is Off.

3.8.2 Ensure "T/O Sheet" CR Tag on 1A RB AUX FAN. 3.8.3 Ensure "T/O Sheet" CR Tag on 1B RB AUX FAN. 3.8.4 Ensure note on Turnover sheet: "If RB Purge Fan is operating,

1A RB Aux Fan OR 1B RB Aux Fan should be off." STANDARD: *Candidate rotates the control switch for the 1A or 1B RB

Aux Fan to the STOP position and verifies the green off light is on and the red on light is off.

Candidate ensures a T/O Sheet tag is on the 1A and 1B RB AUX Fan switches (not critical).

Candidate states that he/she would place a note on the Turnover sheet as stated above (not critical).

Cue: If asked as the SRO, inform the candidate that the 1A RB Aux Fan should be secured.

Cue: If the candidate tries to put a note on the turnover sheet, inform him/her that another RO will place the note on the turnover sheet.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT

2 3.9

NOTE: Completion of Step 3.9 establishes an appropriate vent path during Fuel Movement Operations with any Transfer Tube open per the Shutdown Protection Plan. This prevents FTC and SFP level variations caused by differential pressures between RB and SFP.

3.9 Perform the following: 3.9.1 Open 1PR-1 (RB PURGE OUTLET (RB)).

STANDARD: Candidate rotates 1PR-1 switch located on 1AB3 to the

open position and verifies the red open light lit and green closed light off.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


3 3.9

3.9 Perform the following: 3.9.2 Open 1PR-2 (RB PURGE OUTLET (PR)).

STANDARD: Candidate rotates 1PR-2 switch located on 1AB3 to the

open position and verifies the red open light lit and green closed light off.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

4 3.9

3.9 Perform the following: 3.9.3 Ensure closed 1PR-3 (RB PURGE FLOW). (Bailey Controller)

STANDARD: Candidate ensures 1PR-3 is closed by rotating the Bailey

Controller knob until the position indication indicates zero demand located on 1AB3.

COMMENTS:

___ SAT

___ UNSAT

5 3.9

3.9 Perform the following:

NOTE: It may take several minutes for the air to bleed off 1PR-3.

3.9.4 Verify 1PR-3 closed using alternate indication. STANDARD: Candidate verifies 1PR-3 is closed on the Component

Status Panel and/or the switch located under the Component Status Panel both located on 1VB-2. Candidate may also verify 1PR-3 is closed by using the OAC graphic display.

COMMENTS:

___ SAT

___ UNSAT


6 3.9

3.9 Perform the following: 3.9.5 WHILE RB Purge operating, monitor unit vent RIAs.

STANDARD: Candidate monitors Unit Vent RIAs (RIA-43, 44, 45, & 46)

using the RIA View Node located on 1VB3 or by using the OAC while the RB Purge is operating.

COMMENTS:

___ SAT

___ UNSAT

7 3.9

3.9 Perform the following: 3.9.6 Perform the following:

NOTE: When 1PR-3 (RB PURGE OUTLET SWITCH) is positioned to open, 1PR-3 will remain in the closed position since 1PR-3 Bailey Controller is closed.

A. Position 1PR-3 (RB PURGE OUTLET SWITCH) to open. B. Throttle 1PR-3 (RB PURGE FLOW) to > 60% demand on

Bailey Controller. STANDARD: Candidate rotates 1PR-3 switch to the open position located

on 1VB2. Candidate rotates the knob on 1PR-3 Bailey Controller in

the increase direction until the controller indicates > 60% demand located on 1AB3.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


8 3.10

3.10 IF required to operate the RB Purge Fan, perform the following: 3.10.1 Perform one of the following:

A. Perform the following: • Open 1PR-4 (RB PURGE INLET) • Open 1PR-5 (RB PURGE INLET (PR)) • Open 1PR-6 (RB PURGE INLET (RB))

B. Ensure the following: (Not Applicable)

NOTE: • Starting/Stopping RB Purge may cause SFP level changes. Entry into AP/1-2/A/1700/35 NOT required if SFP level changes are evaluated and stabilizes.

• There is ≈ 20 second time delay to open the dampers before the Purge starts.

3.10.2 Start RB Purge Fan.

NOTE: • Interlock may trip Purge if 1PR-3 demand is < 35%.

• Operating 1PR-3 slowly allows time for the valve to respond to demand changes.

3.10.3 Ensure 1PR-3 (RB PURGE FLOW) (Bailey Controller)

adjusted to < recommended release rate. STANDARD: *Candidate opens 1PR-4, 1PR-5, and 1PR-6 by rotating the

control switches to the open position located on 1AB3 and verify the red open lights are on and the green closed lights are off.

*Candidate starts the RB Purge Fan by rotating the switch to the start position located on 1AB3 and verify the red on light is on and green off light is off.

Candidate ensures 1PR-3 is adjusted to < the recommended release rate as read on Chessel Misc. System Recorder 1 located on 1VB1 or the OAC.

Cue: Another RO will complete this release.

COMMENTS:

END TASK

*CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1 This step is required to prevent tripping 1XR incoming feeder breaker. 2 This step is required to establish RB Purge flow. 3 This step is required to establish RB Purge flow. 7 This step is required to establish desired RB Purge flow. 8 This step is required to establish RB Purge flow and start the RB Purge fan.

CANDIDATE CUE SHEET


INITIAL CONDITIONS RCS temperature = 120°F RCS pressure = 41 psig No GWD or LWD releases are in progress RB Hatch is CLOSED Continuous release is NOT in progress RB Purge startup is in progress using OP/1/A/1102/014 (RB Purge System), Enclosure 4.1 (RB Purge Release) INITIATING CUE The CRS directs you to place the RB Purge in operation at 1/3 Station Limit using OP/1/A/1102/014 Enclosure 4.1 starting at Step 3.8

RO-P404 e Page 1 of 10


RO-P404

ALIGN ECCS SUCTION TO EMERGENCY SUMP


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Align ECCS Suction to Emergency Sump Task Number : N/A Alternate Path: No Time Critical: No Validation Time: 15 min K/A Rating(s): System: BW/E08 K/A: EA1.1 Rating: 4.0/3.7 Task Standard: ECCS suction is properly aligned to the Reactor Building Emergency Sump in accordance with EOP Enclosure 5.12 (ECCS Suction Swap to RBES) References: EP/1/A/1800/001 (Unit 1 Emergency Operating Procedure) Tools/Equipment/Procedures Needed: EOP Enclosure 5.12 (ECCS Suction Swap to RBES) rev. 0 ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 217 2. IMPORT simulator files for RO-P404


4. Ensure SHOWDIG O1P1600 (BWST Level) OAC screen is available

5. Timer 1 will lower BWST level to 9.3’ if needed at step 5

6. Timer 2 will lower BWST level to 6.3’ if needed at step 7


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS A Large Break LOCA has occurred. The LOCA Cooldown Tab is in progress. INITIATING CUES The CRS directs you to align ECCS suction to the Emergency Sump per EOP Enclosure 5.12 (ECCS Suction Swap to RBES).


START TIME: _______

SEQ STEP


1 1

Start: __ 1A LPI PUMP __ 1B LPI PUMP

STANDARD: Candidate locates the control switches for 1A and 1B LPI

pumps and verifies the red on lights are lit and pump amps are indicated on 1UB2.

COMMENTS:

___ SAT

___ UNSAT

2 2

Verify either:

__ LPI FLOW TRAIN A plus LPI FLOW TRAIN B ≥ 3400 gpm

__ Only one LPI header is operating, AND flow in that header is ≥ 2900 gpm STANDARD: Candidate determines that LPI flow train A plus LPI flow

train B is > 3400 gpm by observing the LPI flow gauges located on 1UB2.

COMMENTS:

___ SAT

___ UNSAT

3 3


___ SAT

___ UNSAT


4 52

WHEN BWST level is ≤ 15', THEN stop all HPI pumps. STANDARD: Candidate determines BWST level is < 15’ by using any of

the following: • BWST level from the OAC • BWST level gauge on 1UB2 • BWST level from the ICCM monitors located on 1UB1

Candidate then places the control switch for the 1A HPI pump in the OFF position and rotates the 1C HPI pump control switch to the TRIP position and verifies all HPI pumps are not operating by observing the red on lights off and no indicated HPI flow on 1UB1.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

5 53

NOTE RB level of ≥ 2' is expected when BWST level reaches 9'.

WHEN BWST level ≤ 9', AND RB level is rising, THEN continue procedure. STANDARD: Candidate determines BWST level is < 9’ by using any of


Candidate continues to Step 54.

Cue: If needed, inform the candidate that using time compression BWST level has been lowered and RB level has increased.

Booth cue: Fire TIMER 1 to lower BWST level to < 9’.

COMMENTS:

___ SAT

___ UNSAT


6 54

Simultaneously open: __ 1LP-19 __ 1LP-20

STANDARD: Candidate locates the control switches for 1LP-19 and

1LP-20 on 1UB2 and simultaneously rotates both control switches in the OPEN direction and then verifies the red open light is on and the green closed light is off for both valves.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

7 55

IAAT BWST level is ≤ 6', THEN perform Steps 56 - 59. STANDARD: Candidate determines BWST level is < 6’ by using any of


Candidate continues to Step 56.

Cue: If needed, inform the candidate that using time compression BWST level has been lowered and RB level has increased.

Booth cue: Fire TIMER 2 to lower BWST level to < 6’.

COMMENTS:

___ SAT

___ UNSAT

8 56

Verify 1LP-19 open. STANDARD: Candidate locates the control switch for 1LP-19 on 1UB2

and verifies the red open light on and green closed light off. COMMENTS:

___ SAT

___ UNSAT


9 57

Verify 1LP-20 open. STANDARD: Candidate locates the control switch for 1LP-20 on 1UB2

and verifies the red open light on and green closed light off. COMMENTS:

___ SAT

___ UNSAT

10 58

Simultaneously close: __ 1LP-21 __ 1LP-22

STANDARD: Candidate locates the control switches for 1LP-21 and

1LP-22 on 1UB2 and simultaneously rotates both control switches in the CLOSE direction and then verifies the red open light is off and the green closed light is on for both valves.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

11 59

Dispatch an operator to close 1LP-28 (BWST Outlet) (East of Unit 1 BWST). STANDARD: Candidate dispatches and AO to locally close 1LP-28. COMMENTS:

END TASK

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

4 This step is required to protect the HPI pumps since the suction source from the BWST

will be isolated. 6 This step is required to align LPI pump suction to the Reactor Building Emergency

Sump.

10 This step is required to secure LPI pump suction from the BWST.

CANDIDATE CUE SHEET


INITIAL CONDITIONS A Large Break LOCA has occurred. The LOCA Cooldown Tab is in progress. INITIATING CUES The CRS directs you to align ECCS suction to the Emergency Sump per EOP Enclosure 5.12 (ECCS Suction Swap to RBES).

RO-S403a c Page 1 of 12


RO-S403a

ALIGN PSW TO HPI PUMP MOTOR COOLERS

Alternate Path: Yes Alt Path Failure: Time Critical: No Time Critical Criteria:

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Align PSW to HPI Pump Motor Coolers Task Number : N/A Alternate Path: Yes Time Critical: No Validation Time: 10 min K/A Rating(s): System: 076 K/A: A2.01 Rating: 3.5*/3.7* Task Standard: Align PSW to supply the HPI Motor Coolers in accordance with AP/2/A/1700/024 (Loss of LPSW) Enclosure 5.4 (PSW to HPI Pump Motor Coolers) References: AP/2/A/1700/024 (Loss of LPSW) rev. 028 AP/3/A/1700/024 (Loss of LPSW) Tools/Equipment/Procedures Needed: AP/2/A/1700/024 (Loss of LPSW) Enclosure 5.4 (PSW to HPI Pump Motor Coolers) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. RECALL SNAP 214 2. IMPORT RO-S403a simulator files



READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS Unit 3 has experienced a total loss of LPSW. Operators have been dispatched to cross connect Unit 1&2 LPSW system with Unit 3 LPSW system. The PSW Booster Pump is available for operation. AP/3/A/1700/024 (Loss of LPSW) directs an RO to perform AP/2/A/1700/024 Enclosure 5.4 (PSW to HPI Pump Motor Coolers). INITIATING CUE The Control Room Supervisor directs you to perform AP/2/A/1700/024 Enclosure 5.4 to align PSW to supply HPI pump motor cooling.


START TIME: _______

SEQ STEP


1 1

NOTE Other procedures may direct the performance of this Enclosure in order to supply the HPI Pump motor coolers with water supplied from the PSW Booster Pump. If directed by another procedure to perform Encl 5.4 (PSW to HPI Pump Motor Coolers), it is permissible to run this Enclosure, by itself, without meeting the Entry Conditions of Unit 2 AP/24 (Loss of LPSW).

Verify PSW Booster Pump available for operation. STANDARD: Candidate determines from the Initial Conditions that the

PSW Booster Pump is available for operation. COMMENTS:

___ SAT

___ UNSAT

2 2

Verify all: __ PSW 13KV FANT POWER AVAILABLE light lit __ FANT BKR B closed __ FANT BKR D closed

STANDARD: Candidate determines that the PSW 13KV Fant Power

Available light on EF7 is NOT lit and continues to Step 2 RNO.

COMMENTS:

___ SAT

___ UNSAT


3 2

RNO

1. IF GENERATOR OPERATION COMPLETE light NOT lit on any Keowee unit, THEN Emergency start Keowee units: __ KEOWEE EMER START CHANNEL A __ KEOWEE EMER START CHANNEL B

STANDARD: Candidate determines that the GENERATION OPERATION

COMPLETE light is NOT lit for either Keowee on 2AB3 and then locates KEOWEE EMER START CHANNEL A and CHANNEL B switches and rotates both switches to the START position located on 1UB1.

Note: Only one of the Keowee EMER Start switches must be placed in the START position to satisfy the Critical Step.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

4 2

RNO

NOTE • KPF-9 and KPF-10 have a 6 sec closing delay. • Acceptable Keowee operating limits are: Output voltage

13.5 - 14.5 KV Frequency 57 - 63 Hz

2. IF both the following: __ ACB-3 is closed __ Keowee U2 within limits THEN close KPF-10.

STANDARD: Candidate determines that ACB-3 is open by observing the

white open light on and the red closed light off located on 2AB3 and continues to Step 2 RNO Step 3

COMMENTS:

___ SAT

___ UNSAT


5 2

RNO

3. IF both the following: __ ACB-4 is closed __ Keowee U1 within limits THEN close KPF-9.

Note: Per the note in the previous step, KPF-9 has a 6 second closing delay.

STANDARD: Candidate determines that ACB-4 is closed by observing

the white open light off and the red closed light on located on 2AB3 and determines that Keowee U1 is operating within limits by observing Keowee output voltage 13.5-14.5 KV and Keowee frequency 57-63 Hz located on 2AB3.

Candidate closes KPF-9 by rotating the control switch to the close position and verifying the red closed light on and the white open light off located on 2AB3.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

6 2

RNO

4. IF neither KPF-9 nor KPF-10 closed, THEN close the breaker on any Keowee unit that is within limits: __ KPF-9 (supplied from Keowee U1) __ KPF-10 (supplied from Keowee U2)

STANDARD: Candidate determines that KPF-9 is closed by observing the

red closed light on and the white open light off located on 2AB3.

COMMENTS:

___ SAT

___ UNSAT

7 2

RNO

5. Open FANT PSW BREAKERS B & D. STANDARD: Candidate opens PSW BREAKERS B & D by rotating the

switch to the TRIP position and observing the green open lights lit and red closed lights OFF located on 2EF7.

COMMENTS:

___ SAT

___ UNSAT


8 2

RNO

6. Close KEOWEE PSW BREAKERS A & C. STANDARD: Candidate closes Keowee PSW Breakers A & C by rotating

the control switches to the close position and observing the red closed light on and white open light off located on 2EF7.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

9 2

RNO

7. IF the PSW 4KV POWER AVAILABLE light is NOT lit, THEN: A. Inform the CRS on all units that PSW power is NOT available. B. EXIT this enclosure.

STANDARD: Candidate determines that the PSW 4KV POWER

AVAILABLE light is lit located on 2EF7. COMMENTS:

___ SAT

___ UNSAT

10 2

RNO

8. GO TO Step 3. STANDARD: Candidate continues to Step 3. COMMENTS:

___ SAT

___ UNSAT

11 3

IAAT PSW power is lost, THEN GO TO Step 2. STANDARD: Candidate acknowledges the IAAT step and continues to

Step 4. COMMENTS:

___ SAT

___ UNSAT


12 4

Ensure PSW-14 in AUTO. STANDARD: Candidate places PSW-14 is in AUTO by rotating the switch

to the Auto position on 2EF6. COMMENTS:

___ SAT

___ UNSAT

13 5

Verify PSW-14 is beginning to throttle open or is open. STANDARD: Candidate determines that PSW-14 is closed and not

throttling open by observing the green closed light ON and red open light OFF. Candidate may also observe that there is no flow indicated on the PSW Booster Pump flow gauge (both located on 2EF6).

COMMENTS:

___ SAT

___ UNSAT

14 5

RNO

[ALTERNATE PATH] 1. Place PSW-14 in Manual.

2. Open PSW-14. STANDARD: Candidate places PSW-14 controller in Manual by rotating

the control switch to the Manual position and then throttles PSW-14 open until the red open light is lit and green closed light is OFF located on 2EF6.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

15 6

Start the PSW BOOSTER PUMP. STANDARD: Candidate places the control switch for the PSW Booster

Pump in the start position and verifies the red on light lit and white light off located on 2EF7.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


16

Notify all that PSW Booster Pump is feeding HPI Pump motor coolers: __ U1 CRS __ U2 CRS __ U3 CRS

STANDARD: Candidate notifies Unit 3 control room that the PSW Booster

Pump is feeding HPI Pump motor coolers.

COMMENTS:

END TASK

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

3 This step is required to supply power to the PSW Booster Pump. 5 This step is required to supply power to the PSW Booster Pump. 8 This step is required to supply power to the PSW Booster Pump.

14 This step is required to supply cooling water to the HPI Pump motor coolers

15 This step is required to supply cooling water to the HPI Pump motor coolers

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 3 has experienced a total loss of LPSW. Operators have been dispatched to cross connect Unit 1&2 LPSW system with Unit 3 LPSW system The PSW Booster Pump is available for operation AP/3/A/1700/024 (Loss of LPSW) directs an RO to perform AP/2/A/1700/024 Enclosure 5.4 (PSW to HPI Pump Motor Coolers) INITIATING CUE The Control Room Supervisor directs you to perform AP/2/A/1700/024 Enclosure 5.4 to align PSW to supply HPI pump motor cooling.

Admin-S203 Page 1 of 8


Admin S203

COMPLETE PLANT CONFIGURATION SHEET (TIME TO CORE BOIL) AND DETERMINE ANY

REQUIRED ACTIONS

Alternate Path: (No) Alt Path Failure: ____________________________________________________________ Time Critical: (No) Time Critical Criteria: ________________________________________________________

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Complete Plant Configuration Sheet (Time to Core Boil) and Determine Any Required Actions

Task Number : Alternate Path: (No) Time Critical: (No) Validation Time: 25 Minutes K/A Rating(s): System: GEN K/A: 2.2.18 Rating: 2.6/3.9 Task Standard: Tables in OP/0/A/1108/001 A are used to determine Total Loss Of DHR Time to Boil is less than 16 minutes and that the RB Equipment hatch must be closed

References: OP/0/A/1108/001 A (Reactor Core and SFP Loss Of Cooling Heatup Tables) Enclosure 4.1 (Total Loss of DHR Time to Boil) Rev. 05

Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A

Tools/Equipment/Procedures Needed: OP/0/A/1108/001 A (Reactor Core and SFP Loss Of Cooling Heatup Tables) Enclosure 4.1 (Total Loss of DHR Time to Boil) Rev. 05

Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A

===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. N/A


READ TO OPERATOR


INITIAL CONDITIONS • Unit 1 was shutdown on 12/01 at 0400

• Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A is being prepared for this shift

• LPI aligned for Normal Decay Heat Removal

INITIATING CUES

Current Date/Time: 12/03 at 0615

The CRS instructs you to determine the “Time To Core Boil” utilizing OP/0/A/1108/001 A, (Reactor Core and SFP Loss of Cooling Heatup Tables), and perform any required actions based on the results, in accordance with Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A.


START TIME: _______

SEQ STEP


1

Refer to Enclosure 4.1 of OP/0/A/1108/001 A. Chose the correct Table

STANDARD: Refer to enclosure 4.1 of OP/0/A/1108/001 A, Table 9 (Initial Temp = 120ºF) (24-120 Hours); Time to Boiling, Min. table.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

2

Determine the number of hours the reactor has been shutdown.

STANDARD: Candidate determines the reactor has been shut down for 50 Hours:

• shutdown 12/01 at 0400 • current date/time is 12/03 at 0615 • 50 hours and 15 minutes (rounded down to

most recent whole hour) EXAMINER NOTE: For tables that have time since Rx was shut

down measured in hours, select the most recent whole hour (per Encl. 4.1, step 1.5)

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


3

Determine time to boil.

STANDARD: Candidate determines time to boil is 15.7 minutes by

using 50 hours and 70 inches on LT-5.

• LT-5 level is 76 inches per Attachment 9.2.A • Next lower level is 70 inches

EXAMINER NOTE: If RCS level is at some point between the columns provided, use the column for the next lower level (per Encl. 4.1, step 1.4)

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

4

Ensure equipment hatch is closed. STANDARD: Candidate determines the equipment hatch must be

closed since the Configuration Sheet indicates that the Equipment Hatch is Open and time to Core Boil is less than 16 minutes.

COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1 Required to determine the time for core boil. 2 Required to determine the time for core boil. 3 Required to determine the time for core boil. 4 Required to determine actions required as a result of the time to core boil

CANDIDATE CUE SHEET


INITIAL CONDITIONS • Unit 1 was shutdown on 12/01 at 0400

• Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A is being prepared for this shift

• LPI aligned for Normal Decay Heat Removal

INITIATING CUES

Current Date/Time: 12/03 at 0615

The CRS instructs you to determine the “Time To Core Boil” utilizing OP/0/A/1108/001 A, (Reactor Core and SFP Loss of Cooling Heatup Tables), and perform any required actions based on the results, in accordance with Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A.

Admin-108 1.1B Page 1 of 8


Admin-108

Determine Time for SFP to Reach 200ºF


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Determine Time for SFP to Reach 200ºF Task Number : Alternate Path: No Time Critical: No Validation Time: 15 minutes K/A Rating(s): System: GEN K/A: 2.1.25 Rating: 3.9/4.2 Task Standard: Tables in AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) are used to determine total time required for SFP temperature to reach 200ºF References: AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) Rev 17 Tools/Equipment/Procedures Needed: AP/1-2/A/1700/035 Encl. 5.4 (Unit 1-2 SFP Time to Reach 180ºF, 200 ºF) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. N/A


READ TO OPERATOR


INITIAL CONDITIONS

• Unit 1 is at 100% stable

• Unit 1 EFPD = 278


• Unit 2 was operating at 100% when it experienced a Unit blackout

• SSF has been activated for Unit 2

• Unit 2 RCMUP is aligned and operating

• 2HP-426 is being cycled to maintain Pressurizer Level as directed by AP/25

• AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) has been initiated

• Unit 1 & 2 SFP level = 0.0 ft stable

• Unit 1 & 2 SFP temperature = 102ºF INITIATING CUES

CRS has directed you to utilize AP/35 Enclosure 5.4 and determine the time for Unit 1&2 SFP to reach 200 ºF.


START TIME: _______

SEQ STEP


1

1. Refer to tables A, B, and C below. 2. ONLY one row from one table below applies 3. Check the row in Table A, B, or C that applies to current conditions, and

then use Tables listed on subsequent pages of Encl 5.4, as directed, to calculate SFP heat up times.

STANDARD: Candidate selects Table B and then chooses to use Table

11 based on:

• SSF Event in progress for U1 or U2 with Unit letdown going to SFP

AND

• U1 and U2 each have 177 Fuel Assemblies in RB

Candidate proceeds to Table 11 (page 41 of 63)

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

2

Determine the Time (in days) row based on direction from page 5 of 63

STANDARD: Candidate selects the lower EFPD unit (Unit 2 = 47 days) and adds 20, which results in 67 days.

Determines that 67 days is between 60 and 70 days on far left column of Table 11.

Based on guidance in Step 7 on Page 7 of 63, candidate elects to use 60 days (the shorter time).

NOTE: Steps 2 and 3 can be performed in any order

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


3

Determine initial Spent Fuel Pool Temperature column based on directions from page 7 of 63 Step 6.

STANDARD: Candidate utilizes the 105 column based on:

• Actual SFP temperature = 102ºF • Temperature columns available are 100 and 105 • Directions in Step 6, page 7 of 63, direct the use of

the higher temperature column.

NOTE: Steps 2 and 3 can be performed in any order

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

4

Find the Time in hours based on the intersection of the 60 day row and the 105 degree column. STANDARD: Based on the intersection of the 60 day row and the 105

degree column, determine that 20.0 hours is the time to reach 200ºF

COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1 Required to determine the time to reach 200 ºF

2

Required to determine the time to reach 200 ºF

3 Required to determine the time to reach 200 ºF

4

Required to determine the time to reach 200 ºF

CANDIDATE CUE SHEET


INITIAL CONDITIONS

• Unit 1 is at 100% stable



• Unit 2 was operating at 100% when it experienced a Unit blackout

• SSF has been activated for Unit 2

• Unit 2 RCMUP is aligned and operating

• 2HP-426 is being cycled to maintain Pressurizer Level as directed by AP/25

• AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) has been initiated

• Unit 1 & 2 SFP level = 0.0 ft stable

• Unit 1 & 2 SFP temperature = 102ºF INITIATING CUES

CRS has directed you to utilize AP/35 Enclosure 5.4 and determine the time for Unit 1&2 SFP to reach 200 ºF.

Admin-109 1.2R Page 1 of 12


Admin-109

Unit 3 SFP Boron and Volume Change Calculation

Alternate Path: No Alt Path Failure: ____________________________________________________________ Time Critical: No Time Critical Criteria: ________________________________________________________

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Calculate the minimum makeup volumes from CBAST and 3B BHUT to raise Final SFP Boron Concentration and level and determine operability of CBAST if makeup is performed Task Number : Alternate Path: No Time Critical: No Validation Time: 20 min K/A Rating(s): System: Gen K/A: 2.1.23 Rating: (4.3/4.4) Task Standard: Calculate makeup volumes and recognize that CBAST will be within the procedural limits of operability if used as the boric acid makeup source References: OP/3/A/1104/006 C (SFP Makeup), Enclosure 4.8 (Unit 3 SFP Makeup From CBAST) rev. 18 OP/3/A/1104/006 C (SFP Makeup), Enclosure 4.1 (Unit 3 SFP Boron and Volume Change Calculation) OP/0/A/1108/001 Enclosure 4.2 (CBAST Volume Vs. Level Curve – All Units) rev. 111 OP/0/A/1108/001 Enclosure 4.15 (CBAST Concentration Vs. Level Curve – All Units) Tools/Equipment/Procedures Needed: OP/3/A/1104/006 C (SFP Makeup), Enclosure 4.8 (Unit 3 SFP Makeup From CBAST) OP/3/A/1104/006 C (SFP Makeup), Enclosure 4.1 (Unit 3 SFP Boron and Volume Change Calculation) OP/0/A/1108/001 Enclosure 4.2 (CBAST Volume Vs. Level Curve – All Units) OP/0/A/1108/001 Enclosure 4.15 (CBAST Concentration Vs. Level Curve – All Units) ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. N/A


READ TO OPERATOR


INITIAL CONDITIONS

• Unit 3 Reactor power = 75% stable

• Unit 3 Spent Fuel Pool (SFP) level = 0.0 ft

• 3A SF Cooling pump is operating

• Unit 3 SFP Boron = 2525 ppm

• Unit 3 CBAST Boron = 13,200 ppm

• Unit 3 CBAST level = 75 inches

• 3B BHUT Boron = 0 ppm

• Unit 3 SFP level will be increased to +0.5 ft and the Unit 3 SFP concentration will be raised to 2575 ppm using Unit 3 CBAST and 3B BHUT.

INITIATING CUE You are directed to perform the procedure to makeup to the Unit 3 SFP as follows:

• Raise Final Unit 3 SFP Boron Concentration to 2575 ppm and level to +0.5 feet. Using the in-progress procedure provided and any other required procedure(s), perform OP/3/A/1104/006 C (SFP Makeup), Encl. 4.8 (Unit 3 SFP Makeup) through Step 2.4. Assume you have SRO agreement/concurrence whenever it is required.


START TIME: _______

SEQ STEP


1 2.2

Determine required U3 SFP makeup volume from CBAST and DW.

IF, desired utilize Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation).

STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change

Calculation) and determine that there is 1041gal / 0.1 foot in the SFP and then calculate total gallons required to raise level to +0.5ft.

0.5 ft x 1041 gal/0.1 ft = 5205 gallons OR Calculate the total gallons required to raise level to +

0.5 ft using OP/1108/001 (Curves and General Information) Encl. 4.26 (Miscellaneous Data).

0.5 ft x 1041 gal/0.1 ft = 5205 gallons COMMENTS:

___ SAT

___ UNSAT


2 2.2

con't.

Determine the required concentration of the makeup volume

STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation)step 2.1.

Note: SFP final vol = 376,000 gal + (1041 gal/0.1ft X 0.5 ft) = 381,205 gal

C1V1 + C2V2 = CfVf C1= 2525 ppm= Present Unit 3 SFP Boron concentration V1 = 376,000 gal = Present Unit 3 SFP volume gal C2 = unknown V2 = 5205gal Cf= 2575 ppm = Desired SFP Boron Concentration Vf = 381,205 gal = Final SFP Volume Required makeup concentration = 6186.9 ppm (Accept: 6186 – 6187 ppm)

Note: This calculation may be performed in different sequences using various derivations of the same equation below.

(C1V1 + C2V2 + C3V3 = CfVf) COMMENTS:

___ SAT

___ UNSAT


3 2.2

con't.

Determine the required CBAST makeup volume

STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation) step 2.1.

C1V1 + C2V2 = CfVf C1= 0 ppm = 3B BHUT concentration V1 = unknown C2 = 13,200 ppm = CBAST concentration V2 = unknown Cf= 6187ppm = Required Boron Concentration of makeup Vf = 5205 gal = Final SFP Makeup Volume V2 = Cf Vf /C2 =2439.6 gal CBAST volume = 2439 gal (Accept: 2439 – 2440 gal)

Note: This calculation may be performed in different sequences using various derivations of the same equation. Steps 2, 3, and 4 demonstrate one method. Step 5 demonstrates an alternate method. If the candidate performs the calculation as one formula (shown below), skip steps 2, 3, and 4 and go to step 5

(C1V1 + C2V2 + C3V3 = CfVf)

*NOTE: Step only critical if step 5 NOT performed.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT


4 2.2

con't.

Determine 3B BHUT makeup volume required.

STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change

Calculation) step 2.1. 3B BHUT volume = Total required makeup volume - CBAST volume

3B BHUT volume = 5205 gal – 2439 gal = 2766 gal

= 5205 gal – 2440 gal = 2765 gal

3B BHUT volume = 2766 gal

(Accept: 2765 – 2766 gal)

Note: This calculation may be performed in different sequences using various derivations of the same equation. Steps 2, 3, and 4 demonstrate one method. Step 5 demonstrates an alternate method. If the candidate performs the calculation as one formula (shown below), skip steps 2, 3, and 4 and go to step 5

(C1V1 + C2V2 + C3V3 = CfVf)

*NOTE: Step only critical if step 5 NOT performed.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT


5 2.2

con't.

Determine required U3 SFP makeup volume from CBAST and DW.

STANDARD: Refer to Enclosure 4.1 (U3 SFP Boron and Volume Change Calculation) step 2.1.

C1V1 + C2V2 + C3V3 = CfVf

C1= 0 ppm = 3B BHUT concentration V1 = unknown C2 = 13,200 ppm = CBAST concentration V2 = unknown C3 = 2525 ppm = initial SFP concentration V3 = 376,000 gal = initial SFP volume Cf = 2575 ppm = final SFP concentration Vf = 381,205 gal = final SFP volume (376,000+5205) CBAST volume = 2439 gal (Accept: 2433 – 2440 gal) 3B BHUT volume = 5205 gal – 2439 gal = 2766 gal

= 5205 gal – 2440 gal = 2765 gal

(Accept: 2764 – 2767 gal)

*NOTE: Step only critical if steps 3 and 4 NOT performed.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT

6 2.3

Obtain SRO approval of required Unit 3 SFP makeup volume from CBAST and DW.

STANDARD: SRO approval of the CBAST and DW makeup volumes is obtained.

NOTE: SRO approval is granted per cue sheet.

COMMENTS:

___ SAT

___ UNSAT


7 2.4

IF Unit 3 in MODE 1 OR 2, verify that sufficient level will be available to satisfy "CBAST Concentration vs. Level" curve in OP/0/A/1108/001 (Curves and General Information).

STANDARD: Refer to OP/0/A/1108/001 Enclosure 4.2 (CBAST Volume

Vs. Level Curve – All Units) and determine that a CBAST level of 75 inches equates to 11,700 (11,600 – 11,800 is acceptable) gallons in CBAST

COMMENTS:

___ SAT

___ UNSAT

8 2.4

con't.


STANDARD: Refer to OP/0/A/1108/001 Enclosure 4.15 (CBAST

Concentration vs. Level Curve - All Units) and determine that the minimum level required in CBAST at 13,200 ppm to meet Operability is approximately 58+/- 1 inches

COMMENTS:

___ SAT

___ UNSAT

9 2.4

con't.


STANDARD: Refer to OP/0/A/1108/001 Enclosure 4.2 (CBAST Volume

Vs. Level Curve – All Units) and calculate the remaining level in CBAST if 2439 gallons is transferred from CBAST to the Unit 3 SFP.

75 inches = 11,600 – 11,800 gallons

High: 11,800 gal – 2439 gal = 9361 gal (~ 62 inches)

Low: 11,600 gal – 2440 gal = 9160 gal (~ 61 inches)

Level is more than the required level of 58-59 inches COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________

11,600 – 11,800

57 – 59 inches



SEQ STEP #

Explanation

3 This step is required to determine U3 CBAST volume if step 5 NOT performed. 4 This step is required to determine 3B BHUT volume if step 5 NOT performed. 5 This step is required to determine U3 CBAST and 3B BHUT volumes if steps 3 and 4

NOT performed. 9 This step is required to determine if final U3 CBAST level is sufficient to meet Operability

requirements.

CANDIDATE CUE SHEET


INITIAL CONDITIONS


• Unit 3 Spent Fuel Pool (SFP) level = 0.0 ft

• 3A SF Cooling pump is operating

• Unit 3 SFP Boron = 2525 ppm

• Unit 3 CBAST Boron = 13,200 ppm

• Unit 3 CBAST level = 75 inches

• 3B BHUT Boron = 0 ppm

• Unit 3 SFP level will be increased to +0.5 ft and the Unit 3 SFP concentration will be raised to 2575 ppm using Unit 3 CBAST and 3B BHUT.

INITIATING CUE You are directed to perform the procedure to makeup to the Unit 3 SFP as follows:

• Raise Final Unit 3 SFP Boron Concentration to 2575 ppm and level to +0.5 feet. Using the in-progress procedure provided and any other required procedure(s), perform OP/3/A/1104/006 C (SFP Makeup), Encl. 4.8 (Unit 3 SFP Makeup) through Step 2.4. Assume you have SRO agreement/concurrence whenever it is required.

Admin-204 2R Page 1 of 9


Admin 204 Perform SG Downcomer Temperature Surveillance


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Perform SG Downcomer Temperature Surveillance

Task Number : Alternate Path: No Time Critical: No Validation Time: 18 Min K/A Rating(s): System: Gen K/A: 2.2.12 Rating: 3.7/4.1 Task Standard: Perform SG Downcomer Temperature Surveillance by procedure for the 1A (ONLY) SG and determine that the surveillance requirement is NOT met for either of the specified computer points References: OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl 4.1 (Mode 1 & 2) rev. 42 OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.19 (Channel Check Of OTSG Downcomer Temperatures) Tools/Equipment/Procedures Needed: OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) OAC Screen capture image for SG information ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. N/A


READ TO OPERATOR


INITIAL CONDITIONS Unit 1 Reactor power = 75% OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) in progress. INITIATING CUE CRS directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) on page 6 of 16 component check for the 1A SG Downcomer Temperature.


START TIME: _______

SEQ STEP


1 Encl 4.1

Verify All SG Downcomer Temperature computer points agree within 3°F of each other. IF All SG Downcomer Temperatures DO NOT agree within 3°F of each other, then perform Enclosure 4.19, (Channel Check Of OTSG Downcomer Temperatures).

STANDARD: Candidate observes OAC computer points on the

handout provided. O1E2008 – 528.87°F O1E2009 – 538.97°F O1E2012 – 532.77°F O1E2013 – 533.63°F

Determines that the above OAC points do NOT agree within 3°F of each other, and continues to Enclosure 4.19, (Channel Check of OTSG Downcomer Temperatures).

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

2 Encl 4.19 3.1.1

Determine saturation temperature for 1A OTSG based on power level and 1A OTSG outlet pressure as follows:

Step 3.1.1 Determine 1A OTSG outlet pressure using any one of the following computer points:

• O1E2281 – 888.5 psig • O1E2283 – 888.5 psig • O1E2031 – 888.5 psig • O1E2032 – 888.5 psig

STANDARD: Using the OAC handout, determines that 1A OTSG pressure is 888.5 psig.

COMMENTS:

___ SAT

___ UNSAT


3 3.1.2

Using table in Section 4, determine the 1A OTSG saturation temperature based on power level and 1A OTSG Outlet Pressure obtained in step 3.1.1. ____________ 1A OTSG saturation temperature STANDARD: Candidate determines that 1A OTSG saturation

temperature is ≈ 533.9°F (533.8 - 534.0°F) by using the table in section 4.

Examiner Note: Candidate must interpolate the values in Table

4. One way to do this is to determine the values at 75% power for 880 (532.8) and 890 (534.1).

534.1 - 532.8 = 1.3 1.3 divided by 10 = .13 .13 x 8.5 = 1.105 (1A SG Outlet press = 888.5) 1.105 + 532.8 = 533.9°F (Add to value for 880) COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

4 3.1.3

Compare O1E2008 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2: STANDARD: Candidate compares OAC point O1E2008 (528.87°F)

to value calculated in step 3.1.2 (533.9°F).

COMMENTS:

___ SAT ___ UNSAT


5 3.1.4

IF O1E2008 SG Lower Downcomer Temperature Loop A is NOT within + 4.9°F of the 1A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable. STANDARD: Candidate determines that O1E2008 SG Lower

Downcomer Temperature Loop A (528.87°F) is NOT within ± 4.9°F of the 1A OTSG saturation temperature (533.9°F), and entry Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable is required.

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT

6 3.1.5

Compare O1E2009 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2 STANDARD: Candidate compares OAC point O1E2009 (538.97°F)

to value calculated in step 3.1.2 (533.9°F).

COMMENTS:

___ SAT ___ UNSAT

7 3.1.6

IF O1E2009 SG Lower Downcomer Temperature Loop A is NOT within ± 4.9°F of the 1A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable. STANDARD: Candidate determines that O1E2009 SG Lower

Downcomer Temperature Loop A (538.97) is NOT within ± 4.9°F of the 1A OTSG saturation temperature (533.9°F), and entry Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable is required.

COMMENTS:

END TASK

CRITICAL STEP

___ SAT ___ UNSAT

TIME STOP: ________



STEP #

Explanation

1 Step is required to complete the surveillance. 3 Step is required to complete the surveillance.

5 Determining that the computer points in Step 3.1.4 is out of the allowable band is

critical to ensure that SLC 16.7.5 Condition A is not exited prior to BOTH computer points being repaired.

7 Determining that the computer points in Step 3.1.6 is out of the allowable band is critical to ensure that SLC 16.7.5 Condition A is not exited prior to BOTH computer points being repaired.

CANDIDATE CUE SHEET


INITIAL CONDITIONS Unit 1 Reactor power = 75% OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) in progress. INITIATING CUE CRS directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) on page 6 of 16 component check for the 1A SG Downcomer Temperature.

Admin-304 3B Page 1 of 8


Admin-304

Determine the Maximum Permissible Stay Time Within Emergency Dose Limits (EDL)

Alternate Path: (No) Alt Path Failure: _______________________________________________________ Time Critical: (No) Time Critical Criteria: ___________________________________________________

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Determine the Maximum Permissible Stay Time Within the Emergency Dose Limits. Task Number : Alternate Path: (No) Time Critical: (No) Validation Time: 20 Min K/A Rating(s): System: Gen K/A: 2.3.4 Rating: 3.2/3.7 Task Standard: Determine the Maximum Permissible Stay Time Within the Emergency Dose Limits. References: PD-RP-ALL-0001 Radiation Worker Responsibilities OMP 1-18 (Implementation Standard During Abnormal And Emergency Events) Tools/Equipment/Procedures Needed: Calculator Note tablet =============================================================================== Candidate: __________________________________ Time Start: _______________

NAME Time Finish: ______________ Performance Rating: SAT ______ UNSAT ______ Performance Time: _________ Examiner: ______________________________ ________________________________/_________ NAME SIGNATURE DATE ===============================================================================

Comments



1. N/A


READ TO OPERATOR


INITIAL CONDITIONS Steam Generator Tube Rupture has occurred on Unit 3 Emergency Dose Limits are in effect Before assuming today’s shift, AO “A” has received 1.26 Rem TEDE this year, and AO “A” has not received any dose for this event except as specified below. The following tasks are required to be performed: # TASK TIME REQUIRED DOSE RATE 1 Close 3C-573 9 min 9.35 R/hr

2 Open 3FDW-313 4 min 21.25 R/hr

3 Open all Unit 3’s ADVs 7.55 R/hr Note: Assume no dose is received while traveling between tasks. Tasks 1, 2, 3 are not for lifesaving or protecting valuable property.

INITIATING CUE Refer to the above information. AO “A” has completed tasks 1 and 2 in the time required. Determine how long (in minutes) that AO “A” has to complete task 3 without exceeding Emergency Dose Limits. ROUND ALL CALCULATIONS TO TWO (2) DECIMAL PLACES


START TIME: _______

SEQ STEP


1

Examiner Note: • Candidate may perform these steps in a different order;

however, the calculated stay time must be correct. • EDL is 5 Rem per event (LOCA or SGTR). • Current exposure for the year is not counted toward the

Emergency Dose Limits (EDL).

2

Determine dose received while performing task 1.

STANDARD: Determine dose received while performing task 1. 9.35 R/hr X 1hr/60 min X 9 min = 1.4025 R (1.40 to 1.41 R)

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

3

Determine dose received while performing task 2.

STANDARD: Determine dose received while performing task 2.

21.25 R/hr X 1hr/60 min X 4 min = 1.4166 R

(1.41 to 1.42 R) COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


4

Determine dose remaining from EDLs.

STANDARD: Determine dose remaining from EDLs.

5R – 1.40R – 1.42R = 2.18R

(2.17 to 2.19 R)

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

5

Determine time available for the AO to complete task 3 without exceeding EDL.

STANDARD: Stay time is calculated to be:

Available Dose = 2.18R = .29 hr X 60 min = 17.4 min Dose Rate 7.55 R/hr 1hr

(17 to 18 Minutes)

COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



STEP # Explanation

1

Required to calculate stay time.

2 Required to calculate stay time.



CANDIDATE CUE SHEET


INITIAL CONDITIONS Steam Generator Tube Rupture has occurred on Unit 3 Emergency Dose Limits are in effect Before assuming today’s shift, AO “A” has received 1.26 Rem TEDE this year, and AO “A” has not received any dose for this event except as specified below. The following tasks are required to be performed: # TASK TIME REQUIRED DOSE RATE 1 Close 3C-573 9 min 9.35 R/hr

2 Open 3FDW-313 4 min 21.25 R/hr

3 Open all Unit 3’s ADVs 7.55 R/hr Note: Assume no dose is received while traveling between tasks. Tasks 1, 2, 3 are not for lifesaving or protecting valuable property.

INITIATING CUE Refer to the above information. AO “A” has completed tasks 1 and 2 in the time required. Determine how long (in minutes) that AO “A” has to complete task 3 without exceeding Emergency Dose Limits. ROUND ALL CALCULATIONS TO TWO (2) DECIMAL PLACES

Admin-S107 1.2S Page 1 of 11


Admin-S107 CALCULATION OF PRIMARY TO SECONDARY LEAK RATE

AND DETERMINATION OF SHUTDOWN REQUIREMENTS


Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Calculation of Primary to Secondary Leak Rate and determination of shutdown requirements

Task Number : Alternate Path: (No) Time Critical: (No) Validation Time: 15 Minutes K/A Rating(s): System: Gen K/A: 2.1.7 Rating: 4.4/4.7 Task Standard: Utilize AP/1/A/1700/031 (Primary to Secondary Leakage) Subsequent Actions to determine correct procedure path, calculation enclosure to use to quantify the leak rate, and enclosure to determine unit shutdown requirements. Utilize AP/1/A/1700/031 (Primary to Secondary Leakage) Enclosure 5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40) and RCS Samples to correctly calculate SG Tube Leak flow rate. Utilize AP/1/A/1700/031 (Primary to Secondary Leakage), Enclosure 5.1 (Unit Shutdown Requirements) to determine shutdown requirements based on quantified leak rate from Enclosure 5.5. References: AP/1/A/1700/031, Primary to Secondary Leakage Rev 21 Tools/Equipment/Procedures Needed: AP/1/A/1700/031 complete up thru Step 4.18 Calculator ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. N/A


READ TO OPERATOR

DIRECTIONS TO STUDENT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS


• AP/1/A/1700/031 (Primary to Secondary Leakage) entered due to suspected leakage > 5 gpd but < 25 gpm

• 1RIA-40 (from View Node information) = 552 cpm Spiked as high as 805 cpm approximately 2 hours ago

• Off Gas Blower is in operation

• OAC primary to secondary leak rate calculation became unavailable at shift turnover

• RP and Primary Chemistry sample results are as follows: Total Xe 133 equivalent activity (from RP CSAE off-gas sample) = 2.1 E-5 µCi/ml Total Xe 133 activity (from RP CSAE off-gas sample) = 2.23 E-5 µCi/ml RCS Xe 133 equivalent corrected (from Primary Chemistry RCS sample) = 0.278

µCi/ml RCS Xe 133 activity (from Primary Chemistry RCS sample) = 0.301 µCi/ml CSAE off-gas flow = 12.5 scfm

INITIATING CUES AP/1/A/1700/031 is complete up thru Step 4.18. You are to continue in the AP and determine the primary to secondary leak rate and make a recommendation for continued operation and/or required time to shutdown based on the calculated leak rate. Document the primary to secondary leak rate and your operational recommendation below. Another operator will make all required log entries. LEAK RATE _______________ DATE/TIME LEAK QUANTIFIED _______________ DATE/TIME REQUIRED TO BE IN MODE 3 _______________


START TIME: _______

SEQ STEP


1 4.19

Verify OAC primary to secondary leak rate calculation available (including 1RIA-40 operable with CSAE OFFGAS BLOWER operating).

STANDARD: Candidate determines from initial conditions that OAC program is NOT available. Utilizes the RNO: GO TO Step 4.22.

COMMENTS:

___ SAT

___ UNSAT

2 4.22

Verify all of the following: __ Rx power > 40 % __ 1RIA-59 operable __ 1RIA-60 operable

STANDARD: Candidate determines from initial conditions that

power is < 40%. Proceeds to the RNO: GO TO Step 4.25.

COMMENTS:

___ SAT

___ UNSAT

3 4.25

Verify 1RIA-40 operable with CSAE OFF-GAS BLOWER operating. STANDARD: Candidate determines from initial conditions that

1RIA-40 is operable and the CSAE Off Gas Blower is operating.

COMMENTS:

___ SAT

___ UNSAT


4 4.26

PERFORM Encl.5.5 (Calculation of Primary to Secondary Leak Rate using 1RIA-40). STANDARD: Candidate proceeds to Enclosure 5.5

COMMENTS:

___ SAT

___ UNSAT

5 Encl 5.5 1

Obtain RCS Xe 133 equivalent corrected from latest available Primary Chemistry RCS sample. __________________(mCi/ml) STANDARD: Candidate must pick the RCS Xe 133 equivalent

corrected from the Initial conditions (0.278 µCi/ml).

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

6 2

NOTE The maximum indicated 1RIA-40 count rate (the peak of any spikes) should be used to calculate leak rate. {15}

Obtain 1RIA-40 counts from the Control Room RIA View Node. (1VB2) _________________ cpm STANDARD: Candidate obtains the 1RIA-40 spike counts (from

initial conditions) per the NOTE preceding Step 2 (805 cpm).

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT


7 3

NOTE Total CSAE off-gas flow has been conservatively assumed, as required by PIP O-07-5869 CA 1, to be 100 ft3/min . This may cause indicated SG tube leak rate to be greater than actual SG tube leak rate.

Determine primary to secondary leak rate from the following formulas: Leak rate = 100 ft3/min X 1RIA-40 (cpm) X 3.67E-4 (gal)(min)(µCi/ml) RCS Xe 133 eq corr (µCi/ml) (ft3)(day)(cpm) Leak rate =100 ft3 X cpm X 3.67E-4 (gal)(min)(µCi/ml) = _________ gpd min µCi/ml (ft3)(day)(cpm) STANDARD: Candidate calculates the SGTL size as follows per

Encl. 5.5. formula, determines leak rate is 106.27 gpd (106 to 107 gpd). Candidate exits enclosure 5.5. Returns to step 4.27.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

8 4.27

GO TO the appropriate step based on Primary to Secondary Leak Rate: STANDARD: Candidate determines that the GO TO step is 4.93

based on leak rate calculation 100 gpd to < 25 gpm, and proceeds to that step.

COMMENTS:

___ SAT

___ UNSAT


9 4.93

Initiate log readings from the following every 15 minutes in the Auto Log:

• 1RIA-16 • 1RIA-17 • 1RIA-40 • 1RIA-59 (when Rx power > 40 %) • 1RIA-60 (when Rx power > 40 %)

STANDARD: Per the cue sheet, another operator will make all log

entries.

COMMENTS:

___ SAT

___ UNSAT

10 4.94

Initiate a unit shutdown to meet requirements of Encl 5.1 (Unit Shutdown Requirements) using the following, as applicable:

• AP/29 (Rapid Unit Shutdown) • OP/1/A/1102/004 (Operation at Power) • OP/1/A/1102/010 (Controlling Procedure for Unit Shutdown)

STANDARD: Candidate proceeds to Enclosure 5.1

COMMENTS:

___ SAT

___ UNSAT


11 Encl 5.1

NOTE • The time limits for all conditions begin when the associated

leak rate is first quantified, typically by OAC point O1P1599 or 1RIA-59/60 reading. Although grab samples may be collected to validate leak size, the time limits begin from the first quantified leak rate.

• For items 1&2, shutdown must commence immediately. • For items 3-5, commencement of shutdown may be

delayed until leak rate is confirmed by grab samples, however the time limit begins when the leak rate was first quantified.

• Continuous Primary to Secondary Leakage Monitoring is provided by the following methods: 1-OAC Point O1P1599 (EST TOTAL PRI TO SEC LEAKRATE) including 1RIA-40 operable with CSAE OFF-GAS BLOWER operating 2-1RIA-59 and 1RIA-60 operable with power > 40%

• If shutdown begins based on crediting 1RIA-59 and 1RIA-60 (1RIA-40 inoperable), the time limit does NOT change when Rx power is decreased below 40%.

STANDARD: Candidate utilizes the Table and Notes in AP/31 Encl.

5.1, Unit Shutdown Requirements, and determines the time to be in Mode 3 based on a leak rate of 106 gpd to be 3 hours from the time of quantification. Unit 1 must be shut down and in Mode 3 by 0700 (or 3 hours).

Leak Rate = 106 gpd

Date/Time Leak Quantified = current time

Date/Time Required to be in Mode 3 = 3 hours from time leak quantified

COMMENTS:

END TASK

CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

5 Required to calculate the leak rate correctly



11 Required to determine time of shutdown to Mode 3

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS


• AP/1/A/1700/031 (Primary to Secondary Leakage) entered due to suspected leakage

> 5 gpd but < 25 gpm

• 1RIA-40 (from View Node information) = 552 cpm Spiked as high as 805 cpm approximately 2 hours ago

• Off Gas Blower is in operation

• OAC primary to secondary leak rate calculation became unavailable at shift turnover

• RP and Primary Chemistry sample results are as follows: Total Xe 133 equivalent activity (from RP CSAE off-gas sample) = 2.1 E-5

µCi/ml Total Xe 133 activity (from RP CSAE off-gas sample) = 2.23 E-5 µCi/ml RCS Xe 133 equivalent corrected (from Primary Chemistry RCS sample) =

0.278 µCi/ml RCS Xe 133 activity (from Primary Chemistry RCS sample) = 0.301 µCi/ml CSAE off-gas flow = 12.5 scfm

INITIATING CUES AP/1/A/1700/031 is complete up thru Step 4.18. You are to continue in the AP and determine the primary to secondary leak rate and make a recommendation for continued operation and/or required time to shutdown based on the calculated leak rate. Document the primary to secondary leak rate and your operational recommendation below. Another operator will make all required log entries. LEAK RATE _______________ DATE/TIME LEAK QUANTIFIED _______________ DATE/TIME REQUIRED TO BE IN MODE 3 _______________

Admin-S404 4S Page 1 of 11


Admin-S404

Determine Emergency Classification and Protective Action Recommendations (Complete Emergency

Notification Form)

Alternate Path: No Alt Path Failure: ____________________________________________________________ Time Critical: Yes Time Critical Criteria: Classify within 15 minutes. Complete ENF within 15 minutes of Declaration

Prepared By:

Date:

EP Review By: Date:

Reviewed By: Date:

Approved By: Date:


REGION II


Task Title : Determine Emergency Classification and Protective Action Recommendations (Complete Emergency Notification Form) Task Number : N/A Alternate Path: No Time Critical: Yes Validation Time: 30 minutes K/A Rating(s): System: Gen K/A: 2.4.38 Rating: 2.4/4.4 Task Standard: Appropriate classification is determined within 15 minutes and the associated Emergency Notification Form is completed within 15 minutes of the declaration.

References: RP/0/A/1000/001 (Rev. 4) RP/0/A/1000/002 (Rev. 10) Basis Document (Volume A, Section D of the Emergency Plan Tools/Equipment/Procedures Needed: RP/0/A/1000/001 RP/0/A/1000/002 ===================================================================================== Candidate: __________________________________ Time Start: _______________


Comments



1. N/A


READ TO OPERATOR


INITIAL CONDITIONS

TIME: 5 Minutes ago

• Unit 2 & 3 at 100% power

• Unit 1 tripped due to a turbine control system malfunction

• 1A SG MSRV 1MS-6 failed to fully reseat resulted in 1A SG pressure stabilizing at ≈ 850 psig

CURRENT CONDITIONS

• Chemistry reports Unit 1 RCS activity is 305 μCi/ml DEI

• 1A SG tube leakage calculated at 105 gpm

• 1RIA-58 (High Range Containment Monitor) reading 1.3 R/hr and slowly increasing INITIATING CUE You are to perform the required actions of the Emergency Coordinator by referring to RP/0/A/1000/01, Emergency Classification:

1. Determine Emergency Classification at present time.

2. Complete appropriate Emergency Notification Form for the current conditions per RP/0/A/1000/002, Control Room Emergency Coordinator Procedure..

Inform the examiner upon declaration of Emergency Classification. Inform the examiner upon completion of ENF. THIS IS A TIME CRITICAL JPM NOTE: • Do not use Emergency Coordinator’s judgment while classifying the event. • When required, an operator will maintain the Emergency Coordinator’s Log,

notify the ERO, and assume the duties of the Control Room Offsite Communicator.


START TIME: _______

SEQ STEP


1

Classify the Event

STANDARD: Refer to RP/0/A/1000/01 (Emergency Classification)

Enclosure 4.1 (Fission Product Barrier Matrix). Classify the event as a “General Emergency” (4.1.G.2)

within 15 minutes due to the following:

Loss of RCS barrier (5 points) (1RIA-58 > 1.0 R/hr)

Loss of Fuel Clad Barriers (5 points) (Coolant activity ≥ 300 μCi/ml DEI)

Loss of Containment Barrier (3 points) (Failure of secondary side of SG results in a direct opening to the environment with SG Tube Leak ≥ 10 gpm in the SAME SG)

Time for Classification __________ COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

2 1.1

Commence the Off-Site Notification Form.

STANDARD: Go to RP/0/A/1000/002 (Control Room Emergency Coordinator Procedure) and initiate procedure by determining symptoms for entry exist and check Step 1.1

COMMENTS:

___ SAT

___ UNSAT


3 2.1

IF an EAL exists, Declare the appropriate Emergency Classification level. Classification ___________ (UE, Alert, SAE, GE) Time Declared: __________ STANDARD: Applicant documents a GE due to 4.1.G.2, Loss of all

three barriers, and records the time that the classification was made.

COMMENTS:

___ SAT

___ UNSAT

4 2.2

IF A Security event is in progress, THEN GO TO Step 2.4. STANDARD: Applicant determines that a security event is NOT in

progress and proceeds to step 2.3.

COMMENTS:

___ SAT

___ UNSAT


5 2.3

IF ERO has NOT yet been activated AND ERO activation is needed, perform the following: 2.3.1: Circle the applicable initial notification code below.

EAL classification

Notification Codes (see Enclosure 4.11 for descriptions)

DRILL EMERGENCY TSC, OSC, &

EOF TSC & OSC TSC, OSC, & EOF

None F1a (TSC & OSC only)

NOUE D1a D1b E1a

Alert D2a D2b E2a

SAE D3a D3b E3a

GE D4a D4b E4a

Augmentation D6b D6a 2.3.2 IF a qualified individual is available to notify the ERO, provide the circled notification code above to a qualified individual and direct them to begin Enclosure 4.10 (Activation of the Emergency Response Organization). STANDARD: Applicant determines that the notification code is either

D4a, D4b, or E4a.

COMMENTS:

___ SAT

___ UNSAT

6 2.4

Direct Control Room Offsite Communicator(s) to perform the following: • Record Name ________________________________________ • REFER TO RP/0/A/1000/015A (Offsite Communications From The Control Room), Immediate Actions steps 2.1 and 2.2 AND Enclosure 4.7 (Guidelines for Manually Transmitting a Message) in preparation for notifying offsite agencies. STANDARD: There is no offsite communicator for this JPM.

COMMENTS:

___ SAT

___ UNSAT


7 2.5

IAAT Changing plant conditions require an emergency classification upgrade, THEN Notify Offsite Communicator to complete in-progress notifications per RP/0/A/1000/15A (Offsite Communications From The Control Room), AND Start a new clean copy of this procedure for the upgraded classification AND stop working on this copy, noting the time in your log that each new copy started.

STANDARD: No upgrade will be required for this JPM.

COMMENTS:

___ SAT

___ UNSAT


8 2.6

Obtain the applicable Offsite Notification form in the control room and complete as follows: ___ *2.6.1 Ensure EAL # as determined by RP/0/A/1000/001 matches

Line 4 (4.1.G.2) ___ 2.6.2 Line 1 - Mark appropriate box "Drill" or "Actual Event" ___*2.6.3 Line 1 - Enter Message # ___*2.6.4 Line 2 - Mark Initial ___ 2.6.5 Line 6 –

A. Mark "Is Occurring" if any of the following are true: • RIAs 40, 45, or 46 are increasing or in alarm • If containment is breached • Containment pressure > 1 psig

B. Mark "None" if none of the above is applicable. ___ 2.6.6 Line 7 - If Line 6 Box B or C is marked, mark Box D.

Otherwise mark Box A. ___ 2.6.7 Line 8 - Mark "Stable" unless an upgrade or additional PARs

are anticipated within an hour. • Refer to Enclosure 4.8 (Event Prognosis Definitions)

___*2.6.8 Line 10 - Military time and date of declaration (Refer to date/time in Step 2.1)

___ 2.6.9 Line 11 - Evaluate the following for classification for all units. • Security event • Seismic event • Tornado on site • Hurricane force winds on site • SSF event • Fire affecting shared safety related equipment Mark or select ALL if event affects the emergency classification on more than one unit. If event only affects one (1) unit OR one (1) unit has a higher emergency class, select or mark the appropriate unit.

___*2.6.10 Line 12 - Mark unit(s) affected (reference Line 11) AND enter percent power for each unit affected. {14} • If affected unit is shutdown, then enter shutdown time

and date. ___ 2.6.11 Line 13 - If the SM has no remarks, write "None" ___ 2.6.12 If Condition "A" exists ensure following PARs are included

on Line 5. A. Evacuate: Move residents living downstream of the

Keowee Hydro Project dams to higher ground. B. Other: Prohibit traffic flow across bridges identified on

your inundation maps until the danger has passed. ___*2.6.13 Line 17 - SM signature, CURRENT Time/Date STANDARD: Correctly fills out Emergency Notification Form 4.1.G.2

in accordance with Key within 15 minutes of the emergency declaration.

COMMENTS:

*CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________



SEQ STEP #

Explanation

1 This is a time critical step. The candidate needs to declare the GE within 15 minutes of

beginning the JPM. (The start of the JPM is the beginning of the assessment period) 8 The emergency notification form is accurately filled-out; identified steps from the KEY are critical

items within 15 minutes from the time the EAL was declared. (Declaration time is the time recorded in JPM step 3)

CANDIDATE CUE SHEET


INITIAL CONDITIONS

TIME: 5 Minutes ago

• Unit 2 & 3 at 100% power

• Unit 1 tripped due to a turbine control system malfunction

• 1A SG MSRV 1MS-6 failed to fully reseat resulted in 1A SG pressure stabilizing at ≈ 850 psig

CURRENT CONDITIONS

• Chemistry reports Unit 1 RCS activity is 305 μCi/ml DEI

• 1A SG tube leakage calculated at 105 gpm

• 1RIA-58 (High Range Containment Monitor) reading 1.3 R/hr and slowly increasing

INITIATING CUE You are to perform the required actions of the Emergency Coordinator by referring to RP/0/A/1000/01, Emergency Classification:

1. Determine Emergency Classification at present time.

2. Complete appropriate Emergency Notification Form for the current conditions per RP/0/A/1000/002, Control Room Emergency Coordinator Procedure..

Inform the examiner upon declaration of Emergency Classification. Inform the examiner upon completion of ENF. THIS IS A TIME CRITICAL JPM NOTE: • Do not use Emergency Coordinator’s judgment while classifying the event. • When required, an operator will maintain the Emergency Coordinator’s Log,

notify the ERO, and assume the duties of the Control Room Offsite Communicator.

Facility: Oconee Scenario No.: Op-Test No.: 1 SRO OATC BOP · OP/1/A/1106/001 Encl 4.8 Crew...

Documents

Transcript of Facility: Oconee Scenario No.: Op-Test No.: 1 SRO OATC BOP · OP/1/A/1106/001 Encl 4.8 Crew...