JOB PERFORMANCE MEASURE SETUP SHEETSVI-F41-T3008, “Reactor Recirculation System Flow Data...

OT-3701-ADM_029_RO Rev 0

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JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO Safety Function: Conduct of Operations Validated Time: 32 Minutes References: SVI-B33-T1160 Rev 5, PDB-A009 Rev. 19, PDB-A10 Rev. 17, PDB-A12

Rev. 16 Required Material: SVI-B33-T1160, Jet Pump Operability PDB-A009, Expected Jet Pump Normalized dP and Flow Ranges PDB-A10, Recirc Loop Drive Flow vs. FCV Position PDB-A12, Recirc Drive Flow vs. Total Core Flow Pictures of B33 instruments Task: 202-525-01-01 Monitor the Operation of the Reactor Recirc System. Task Standard: Complete manual surveillance to determine if jet pumps are operable. K/A: 2.1.7 Ability to evaluate plant performance and make operational

judgments based on operating characteristics, reactor behavior, and instrument interpretation. Importance: RO 4.4 SRO 4.7

1. Setup: Ensure “Required Material” available at JPM site. 2. Location / Method: Class Room / Administrative performance. 3. Initial Condition: A control rod sequence exchange was completed last shift. Restoration

to 100% power is in progress. Reactor power is currently at 87%. A drive in the SPDS (ICS) computer has failed and ICS is not available.

4. Initiating Cue: As the BOP RO, perform SVI-B33-T1160, Jet Pump Operability for the daily requirement and turn it in to the Unit Supervisor.

Start: Stop: Candidate:


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JPM BODY SHEET

Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc… before performing task. Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SVI-B33-T1160, Jet Pump Operability 4.0 PREREQUISITES 5.1 Surveillance Test

Standard: Candidate reviews the SVI and pictures of B33 instruments to determine that both Recirc Pumps are running and flow is within TS limits.

He/she signs in the surveillance and informs the RO ATC.

Instructor Cue: If informed as RO ATC of starting SVI, repeat back to Candidate.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________


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Step 2 5.1.1 Recirculation Loop Drive Flow vs. FCV Position

1. Determine the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, and indicate the method used.

2. Indicate, for each operating loop, whether the relationship determined in Step 5.1.1.1 is within the appropriate “established pattern.”

Critical Step: Uses Attachment 1 of SVI to determine the relationship between recirculation loop drive flow and the corresponding flow control valve position. Determines relationship is within “established pattern.”

Instructor Cue: None

Notes: Needs to use PDB-A10, pages 8 & 10. SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow

1. Determine the relationship between recirculation loop drive flow and total core flow, and indicate the method used.

2. Indicate whether the relationship determined in Step 5.1.2.1 is within the appropriate “established pattern.”

Critical Step: Uses Attachment 2 of SVI to determine the relationship between recirculation loop drive flow and total core flow. Determines relationship is within “established pattern.”

Instructor Cue: When Candidate asks for IV, inform him/her that IV is complete.

Notes: Needs to use PDB-A12, page 6. SAT ___ UNSAT ___

Comment(s):________________________________________________________________


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Step 4 5.1.3 Jet Pump Differential Pressure and Flow

1. Jet Pump Differential Pressure

a. Determine each normalized jet pump diffuser to lower plenum differential pressure for each operating recirculation loop, and indicate the method used.

b. Indicate whether the relationship determined in Step 5.1.3.1.a is within the appropriate “established pattern.”

2. Jet Pump Differential Flow

a. Determine each normalized jet pump flow for each operating recirculation loop, and indicate the method used.

b. Indicate whether the relationship determined in Step 5.1.3.2.a is within the appropriate “established pattern.”

Critical Step: Uses Attachment 3 or Attachment 4 of SVI to determine the relationship between recirculation loop drive flow and total core flow. Determines relationship is within “established pattern.”

Instructor Cue: When Candidate asks for IV, inform him/her that IV is complete.

Notes: It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section may be marked N/A.

SAT ___ UNSAT ___ Comment(s):________________________________________________________________


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Step 5 5.3 Acceptance Criteria

Critical Step: Complete the Acceptance Criteria and the Data Package Cover Sheet.


Notes: See Answer Key for expected markups.

The checkmark in the NON TECH SPEC/PERIODIC TEST DATA block is not CRITICAL on the Data Package Cover Sheet.


Terminating Cue: SVI-B33-T1160 is complete. Evaluation Results: SAT_____ UNSAT_____ End Time


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JPM CUE SHEET

INITIAL CONDITIONS:

• A control rod sequence exchange was completed last shift.

• Restoration to 100% power is in progress.

• Reactor power is currently at 87%.

• A drive in the SPDS (ICS) computer has failed and ICS is not available.

INITIATING CUE: As the BOP RO, perform SVI-B33-T1160, Jet Pump Operability for the daily requirement and turn it in to the Unit Supervisor.

TEST COVER SHEET Functional Location: PY- SVI-B33-T1160

(PY: DATA PACKAGE COVER SHEET) Maintenance Plan #: 52625

NOP-WM-2003-01 Rev. 02 Page 1 of 2 Order #:

Performance Section: TEST COMPLETION FULL PARTIAL FAILED

TECHNICAL SPECIFICATION DATA ACCEPTABLE UNACCEPTABLE NA

ACCEPTABLE OUTSIDE LAIZ

ACCEPTABLE OUTSIDE AV (Allowable Value)

Condition Report #

NON TECHNICAL SPECIFICATION/ ACCEPTABLE UNACCEPTABLE NA PERIODIC TEST DATA

TEST CREDIT CREDIT NO CREDIT Additional Surveillance Test Crediting: Credit

ST/PT: Plan: Order Number: Y N


Work Start (Prerequisites) Approval: / Print Name Signature Date and Time Test Start Approval: / Print Name Signature Date and Time Test Completed (Test Leader): / Print Name Signature Date and Time Lead Work Group Supervisor Review: / Print Name Signature Date and Time

Comments:

x x

x

x

Name Signature Date / Time

N/A - Initial RO Smith - Notified Date / Time




Signature Validation Section NOTE: Printed name or signature must be legible, this is required by 10 CFR 50 Appendix B, Section XVII; Quality Assurance Records which states in part, “Inspection and test records shall, as a minimum, identify the inspector or data recorder...” and by ANSI N45.2.9 – 1974, Section 3.2 which states in part, “…quality assurance records shall be legible, completely filled out and adequately identifiable to the item involved.” Print Name Signature Initials Date SAP ID

Number

Name Signature Initials Date SAP ID #

PERRY NUCLEAR POWER PLANT Procedure Number:

SVI-B33-T1160 Title:

Jet Pump Operability Use Category:

Step-by-Step Revision:

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JET PUMP OPERABILITY

Surveillance Instruction

Effective Date: 8-5-16 Preparer: Thomas Naylor / 7-13-16 Date Approver: Ben Huck / 7-19-16 Date





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1.0 DESCRIPTION 1.1 Scope

This instruction demonstrates the operability of each jet pump in each operating recirculation loop by confirming the existence of two of the following three conditions for each operating recirculation loop:

• Recirculation loop drive flow versus flow control valve position differs by less

than or equal to 10% from established patterns, • Recirculation loop drive flow versus total core flow differs by less than or

equal to 10% from established patterns, • Each jet pump diffuser to lower plenum differential pressure differs by less

than or equal to 20% from established patterns, or each jet pump flow differs by less than or equal to 10% from established patterns.

This instruction satisfies the requirements of Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1.

NOTES

• Not required to be performed until 4 hours after associated recirculation loop is

in operation. • Not required to be performed until 24 hours after greater than 25% RTP.

1.2 Frequency

24 hours 1.3 Technical Specification Applicable MODES 1 and 2 2.0 PRECAUTIONS AND LIMITATIONS 1. Step numbers marked with a dollar sign ($) immediately to the left are

required by Technical Specifications. Such items, if found to exceed their Acceptance Criteria, may be NRC reportable and shall be brought to the immediate attention of the Unit Supervisor.

2. Those steps of this instruction with an initial line are to be initialed as data

are entered or as each step is completed.





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3. Sections 5.1.1, 5.1.2, and 5.1.3 may be performed in any order. Steps within a section are to be performed in the order specified unless otherwise indicated.

4. Avoid performing this test at less than 10% FCV position, as position

indication is not consistent there. 5. Verification of established patterns is conducted in accordance with

SVI-F41-T3008, “Reactor Recirculation System Flow Data Verification” during the initial weeks of operation under circumstances such as:

a. Following refueling activities (fuel assembly replacement or shuffle, as

well as any modifications to fuel support orifice size or core plate bypass flow) that can affect the relationship between core flow, jet pump flow and recirculation loop flow, or

b. Initial entry into extended single loop recirculation operation Jet pump operability is considered acceptable prior to startup based on the

acceptable results obtained during the previous cycle. During performance of SVI-F41-T3008, the Shift Engineer, Responsible System Engineer, or a Reactor Engineer normally provides an “engineering judgment of the daily surveillance results” to detect significant abnormalities which could indicate a jet pump failure. This engineering judgment may be based upon the nature of the refueling activities and may consider the self-consistency of the daily surveillance results, but jet pump noise is the most positive indication that the jet pump is operating. If established patterns are to be revised the associated Plant Data Book entries and SDS screens will be placed on hold. Copies of the SVI-F41-T3008 data should be retained in the Control Room for reference until the revisions have been processed.

6. In order to permit sufficient opportunity for the baselining of new established

patterns, the period of time covering the “initial weeks of operation following refueling activities” normally extends to include five weeks after reaching rated power and flow.

7. When using the established patterns in the Plant Data Book Curves, confirm

the two loop curves are used during two loop operations and the single loop curves are used during single loop operations; likewise, for slow or fast speed operation.





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8. During single loop operations, only the jet pumps associated with the operating recirculation loop need to be demonstrated operable. However, data may be collected from the idle loop for use in demonstrating the OPERABILITY of the operating loop.

9. The following ICS SDS Displays may be used during the performance of this

surveillance instruction, as appropriate for the configuration of the recirculation system:

a. JPFLOW, TWO LOOP NORMALIZED JET PUMP FLOWS b. JPDP, TWO LOOP NORMALIZED JET PUMP DPS c. RFPERF, TWO LOOP RCIRC – FAST SPEED PERFORMANCE d. RSPERF, TWO LOOP RCIRC – SLOW SPEED PERFORMANCE 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication 1. Control Room operator or other qualified member of the unit technical staff

to record data from instruments that are located on UNIT CONTROL CONSOLE 1H13-P680 and/or JET PUMP MONITORING PANEL 1H13-P619.

2. Shift Engineer, Responsible System Engineer, or Reactor Engineer, if

needed, to provide engineering judgment of daily surveillance results. 3. The Independent Verifier may be any of the above individuals. 3.2 Required Measuring and Test Equipment (M&TE) None 3.3 Additional Tools and Equipment 1. PDB-A0009, Expected Jet Pump Normalized dP and Flow Ranges, if

needed. 2. PDB-A0010, Recirc Loop Drive Flow vs. FCV Position, if needed. 3. PDB-A0012, Recirc Drive Flow vs. Total Core Flow, if needed.





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4. SVI-F41-T3008, Reactor Recirculation System Flow Data Verification, if needed.

5. Plant computer provides data, if used. 4.0 PREREQUISITES Initials 1. MARK the Unit Supervisor’s “Authorization to Start Prerequisites”

signature N/A on the Data Package Cover Sheet (DPCS) and initial. 2. CONFIRM that the plant is operating in MODE 1 with

THERMAL POWER greater than 25% RTP. 3. CONFIRM that the recirculation flow is steady and INDICATE the

configuration of the recirculation loops: a. Loop A (only) in operation, with recirculation flow control

in loop manual. b. Loop B (only) in operation, with recirculation flow control

in loop manual. c. Both recirculation loops in fast speed operation, with

recirculation loop jet pump flow mismatch within the limits of SR 3.4.1.1.

d. Both recirculation loops in slow speed operation, with


4. IF using plant computer points or ICS SDS screens, THEN VERIFY no other maintenance or testing is in progress which

would affect recirculation flow indication, OTHERWISE MARK this step N/A.

RO

RO

RO

N/A

√





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4.0 PREREQUISITES Initials

Note During performance of SVI-F41-T3008, engineering judgment by the Shift Engineer, Reactor Engineering, or Responsible System Engineer may determine existing patterns of PDB-A0009, PDB-A0010, and PDB-A0012 to be adequate for performance of this surveillance. 5. For at least 2 of the following, CONFIRM 1 or more listed source is

available OR SVI-F41-T3008 is in progress.

• RFPERF/RSPERF OR PDB-A0010 • RFPERF/RSPERF OR PDB-A0012 • JPDP OR JPFLOW OR PDB-A0009

(INTENTIONALLY BLANK)

RO





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5.0 SURVEILLANCE INSTRUCTION Initials 5.1 Surveillance Test 1. NOTIFY the Reactor Operator before starting and write

“R.O. (operator’s name) notified” in the “Authorization to Start Test” signature on the DPCS. RECORD the time and date and initial the line.

Note

Steps 5.1.1, 5.1.2, and 5.1.3 may be performed in any order. Steps within a section are to be performed in the order specified unless otherwise noted. 5.1.1 Recirculation Loop Drive Flow vs. FCV Position

1. DETERMINE the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, AND indicate the method used.

SDS Screen Attachment 1

a. IF using ICS SDS,

THEN ATTACH a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop - fast speed, or RSPERF for two loop - slow speed), OTHERWISE COMPLETE Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position.

2. INDICATE, for each operating loop, whether the relationship

determined in Step 5.1.1.1 is within the appropriate “established pattern.” a. IF using ICS SDS,

THEN OBSERVE cursor is within limits for the DRIVE FLOW A VS. FCV A and/or for the DRIVE FLOW B VS. FCV B, OTHERWISE REFER to Step 3 on Attachment 1.

• Loop A: YES NO N/A • Loop B: YES NO N/A

√

√ √

RO

RO

RO

RO





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5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow Initials 1. DETERMINE the relationship between recirculation loop drive flow

and total core flow, AND INDICATE the method used.

SDS Screen Attachment 2 a. IF using ICS SDS,

THEN ATTACH a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop - fast speed, or RSPERF for two loop - slow speed), OTHERWISE COMPLETE Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow.

2. INDICATE whether the relationship determined in Step 5.1.2.1 is

within the appropriate “established pattern.” a. IF using ICS SDS, THEN OBSERVE cursor is within limits for the DRIVE FLOW VS. CORE FLOW, OTHERWISE REFER to Step 3 on Attachment 2.

YES NO

√

√ RO

RO

RO





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5.1.3 Jet Pump Differential Pressure and Flow Initials

Notes

• It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section may be marked N/A.

• For single loop operation, the spaces in this section may be marked N/A for the idle

loop. 1. Jet Pump Differential Pressure a. DETERMINE each normalized jet pump diffuser to lower plenum

differential pressure for each operating recirculation loop, AND INDICATE the method used.

SDS Screen Attachment 3 1) IF using ICS SDS,

THEN ATTACH a copy of the JPDP screen, OTHERWISE COMPLETE Attachment 3, Normalized Jet Pump dP’s Data Sheet.

b. INDICATE whether the relationship determined in Step 5.1.3.1.a

is within the appropriate “established pattern.” 2) IF using ICS SDS, THEN OBSERVE NORMAL indication for the JET PUMP DPS, OTHERWISE REFER to Step 6 on Attachment 3.

YES NO N/A

√

√

RO

RO

RO





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Section 5.1.3 Initials 2. Jet Pump Differential Flow a. DETERMINE each normalized jet pump flow for each operating

recirculation loop, AND INDICATE the method used.

SDS screen Attachment 4 1) IF using ICS SDS,

THEN ATTACH a copy of the JPFLOW screen, OTHERWISE COMPLETE Attachment 4, Normalized Jet Pump Flows Data Sheet.


is within the appropriate “established pattern.” 1) IF using ICS SDS, THEN OBSERVE NORMAL indication for the JET PUMP FLOWS, OTHERWISE, REFER to Step 7 on Attachment 4.

YES NO N/A 5.2 Plant/System Restoration None

N/A





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5.3 Acceptance Criteria Initials

Notes

• Satisfactory completion of this surveillance shall be based only on Technical Specification items (marked with a $ sign).

• While baselining new “established patterns,” copies of SVI-F41-T3008 data

should be retained in the Control Room so that the Shift Engineer, the Responsible System Engineer, or a Reactor Engineer may consider the self-consistency of the data in making the “engineering judgment” on the existence of significant abnormalities which could indicate a jet pump failure. Jet pump noise is the most positive indication that the jet pump is operating.

$ 1. The jet pumps, in each operating recirculation loop, have been

demonstrated OPERABLE by one of the following two methods: a. At least two of the following three criteria have been satisfied: 1) Recirculation loop drive flow versus flow control valve

position differs by less than or equal to 10% from established patterns. (YES in Step 5.1.1.2)

2) Recirculation loop drive flow versus total core flow differs

by less than or equal to 10% from established patterns. (YES in Step 5.1.2.2)

3) Each jet pump diffuser to lower plenum differential

pressure differs by less than or equal to 20% from established patterns, OR each jet pump flow differs by less than or equal to 10% from established patterns. (YES in either Step 5.1.3.1.b or Step 5.1.3.2.b)

YES NO, U.S. notified N/A √ RO





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SECTION 5.3 Initials b. While baselining the new “established patterns,” the Shift

Engineer (SE), or the Responsible System Engineer (RSE), or a Reactor Engineer (RE) has reviewed the surveillance results and has determined, based upon engineering judgment, that no significant abnormality exists that could indicate a jet pump failure.

___________________________________ /________ SE, RSE, or RE Signature / Date 2. All other items checked in this surveillance performed satisfactorily. YES NO, applicable Supervisor notified 3. Check the appropriate block on the Data Package Cover Sheet to

indicate acceptable or unacceptable test results. Comments: ________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ Performed By: ______________________________________________/_________/________ ______________________________________________/_________/________ ______________________________________________/_________/________ Name (Print) Initials / Date

√

RO

RO

RO

N/A RO

Reactor Operator Date





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6.0 RECORDS 6.1 Records Handling Records handling shall be performed per NOP-SS-3300. 6.2 Records Capture The following documents are completed/generated by this instruction: Quality Records Data Package Cover Sheet SVI-B33-T1160, pages 5 through 11, and: Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position, if used Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow, if used Attachment 3, Normalized Jet Pump dP’s Data Sheet, if used Attachment 4, Normalized Jet Pump Flows Data Sheet, if used Copy SDS screen JPFLOW, TWO LOOP NORMALIZED JET PUMP FLOWS, if used Copy SDS display JPDP, TWO LOOP NORMALIZED JET PUMP DPS, if used Copy SDS display RFPERF, TWO LOOP RCIRC – FAST SPEED PERFORMANCE, if used Copy SDS display RSPERF, TWO LOOP RCIRC – SLOW SPEED PERFORMANCE, if used Non-Quality Records None





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7.0 REFERENCES 7.1 Discretionary B-208-016, Sht. B02, B03, B04 D-302-603 D-302-604 NUREG/CR-3052, Closeout of 1E Bulletin 80-07: BWR Jet Pump Assembly Failure General Electric, Jet Pump Beam Cracks, SIL 330 with supplements NOP-WM-2003, Surveillance Test Control PAP-0500, Perry Technical Procedure Writer’s Guide PAP-0507, Perry Supplemental Procedure Requirements/Guidance SVI-F41-T3008, Reactor Recirculation System Flow Data Verification Plant Data Book 7.2 Obligations Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1 USAR Section 3.2.3.2.1, Definition of Safety Class 2 USAR Section 3.9.5.1.2, Reactor Internals USAR Figure 3.9-22, Jet Pump USAR Section 3.9.5.3.7, Special Requirements for Jet Pump Holddown Beams USAR Section 4.4.3.3.2, Regions of the Power-Flow Map USAR Section 15F.2.1.1, Core Flow Measurement During Single Loop Operation USAR Section 5.4.1.4, Safety Evaluation USAR Section 6.2.1.1.3.3.1, Recirculation Line Break USAR Section 6.3.3.7.2, Accident Description Commitments addressed in this document: None





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8.0 SCOPE OF REVISION: Rev. 6 1. Revise Precaution and Limitation 2.5 to clarify when data from SVI-

F41-T3008 will be used to complete the surveillance. 2. Add Prerequisite Step 4.5 to confirm which data sources will be used

to complete the surveillance. 3. Remove Commitment L01960 from References. L01960 implemented

License Amendment 61, related changes would now go through the 10CFR50.59 process. The commitment is now closed.

4. Upgrade procedure to comply within current SVI format in accordance with PAP-0500, rev bars omitted.

5. Update Steps 4.1 and 5.1.1 to match the words on the current revision of the DPCS, rev bars omitted.

9.0 ATTACHMENTS Attachment 1 - Manual Recirculation Loop Drive Flow vs. FCV Position Attachment 2 - Manual Recirculation Loop Drive Flow vs. Total Core Flow Attachment 3 - Normalized Jet Pump dP’s Data Sheet Attachment 4 - Normalized Jet Pump Flows Data Sheet





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ATTACHMENT 1: Manual Recirculation Loop Drive Flow vs. FCV Position Page 1 of 1

Initials

Note

For single loop operation, the spaces in this attachment may be marked N/A for the idle loop. 1. RECORD, for each operating loop, the flow control valve position from the

instrument on 1H13-P680: a. RCIRC LOOP A FLOW CONTROL: _________ 1B33-K603A (%) b. RCIRC LOOP B FLOW CONTROL: _________ 1B33-K603B (%) 2. RECORD, for each operating loop, the recirculation loop drive flow from

the plant computer or instruments on 1H13-P680, AND indicate the source of the data and the units:

C51-R614-blue (%) a. Flow A: _________ B33EA028 (kGPM) C51-R614-red (%) b. Flow B: _________ B33EA030 (kGPM)

NOTES

The limits on the established recirculation loop drive flows are determined from the: • PDB-A0010 graphs for the recirculation loop configuration of Step 4.3, • Flow control valve positions of Step 1 of this attachment, • Units indicated in Step 2 of this attachment. 3. CONFIRM, for each operating loop, the recirculation loop drive flow

recorded in Step 2 is between the corresponding limits determined from the appropriate “Flow + 10%” and “Flow - 10%” curves in PDB-A0010.

a. Loop A: YES NO N/A b. Loop B: YES NO N/A

36

34

72.81

73.14 √

√

√ √

RO

RO

RO





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ATTACHMENT 2: Manual Recirculation Loop Drive Flow vs. Total Core Flow Page 1 of 2

Initials 1. DETERMINE the total Recirc Drive Flow by adding the individual Recirc

Drive Flows recorded in Step 2 of Attachment 1, AND indicate the corresponding units.

a. IF in single loop operation,

THEN use zero for the Recirc Drive Flow of the idle loop. (%) Total Recirc Drive Flow: _________ (kGPM) Independent Verifier: 2. IF 1B33-R613 is being used to determine Total Core Flow,

THEN RECORD Total Core Flow from 1B33-R613 below, AND MARK Step 2.a. N/A, OTHERWISE COMPLETE Step 2.a.

a. IF Dual loop operation is indicated in Step 4.3, THEN RECORD the sum of the jet pump loop flows as Total Core

Flow, AND MARK the corrected idle loop flow space N/A, OTHERWISE CORRECT the idle loop jet pump flow by multiplying

by 0.95, AND RECORD the Total Core Flow as the operating loop jet pump flow minus the corrected idle loop jet pump flow.

Jet Pump Loop A Flow: ______ 1B33-R612A (Mlb/hr) Jet Pump Loop B Flow: ______ 1B33-R612B (Mlb/hr) Corrected Idle Loop Flow: ______ (Mlb/hr) Loop: A B 1B33-R612A & B Total Core Flow: ______ 1B33-R613 (Mlb/hr) Independent Verifier:

RO

RO

RO √

(72.81 + 73.14 = 145.95)

39 38 (or 39)

Will be marked N/A if used value from R613

Will be 77 or 78 if R612A/B used or 76 if R613 used. Need correct box checked.

√ N/A

145.95





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Initials

Note

The limits on the established recirculation loop drive flow are determined from the: • PDB-A0012 graph for the recirculation loop configuration of Step 4.3, • Total Core Flow of Step 2 of this attachment, • Units indicated in Step 1 of this attachment. 3. Confirm that the flow recorded in Step 1 of this attachment is within the

limits determined from the appropriate “Drive Flow +10%” and “Drive Flow - 10%” curves in PDB-A0012.

YES NO

RO √





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ATTACHMENT 3: Normalized Jet Pump dP’s Data Sheet Page 1 of 2

Initials 1. Record each Jet Pump diffuser to lower plenum dP (%): 2. Sum all Jet Pump dPs for each loop, and record as Loop Total dP: 3. Divide each Loop Total dP by 10 and record as Loop Average dP: 4. Divide each Jet Pump dP by its Loop Average dP, and record as

Normalized Jet Pump dP: Loop A 1H13-P619 Jet Pump Normalized Jet Pump Instrument dP (%) Jet Pump dP 1. 1B33-R610A ________ _________ 2. 1B33-R610E ________ _________ 3. 1B33-R610J ________ _________ 4. 1B33-R610N ________ _________ 5. 1B33-R610T ________ _________ 6. 1B33-R610C ________ _________ 7. 1B33-R610G ________ _________ 8. 1B33-R610L ________ _________ 9. 1B33-R610R ________ _________ 10. 1B33-R610V ________ _________ “A” Loop Total dP ________ “A” Loop Average dP ________ Loop B 1H13-P619 Jet Pump Normalized Jet Pump Instrument dP (%) Jet Pump dP 11. 1B33-R610B ________ ________ 12. 1B33-R610F ________ ________ 13. 1B33-R610K ________ ________ 14. 1B33-R610P ________ ________ 15. 1B33-R610U ________ ________ 16. 1B33-R610D ________ ________ 17. 1B33-R610H ________ ________ 18. 1B33-R610M ________ ________ 19. 1B33-R610S ________ ________ 20. 1B33-R610W ________ ________ “B” Loop Total dP ________ “B” Loop Average dP ________ 5. All calculations independently verified: Independent Verifier:

RO RO RO

RO

26 25 24 26 25 26 25 25 25 26 253 25.3

1.03 0.99 0.95 1.03 0.99 1.03 0.99 0.99 0.99 1.03

24 24 24 23 28 29 23 22 24 21 242 24.2

0.99 0.99 0.99 0.95 1.16 1.20 0.95 0.91 0.99 0.87

Due to readability of the pictures, some “Jet Pump ∆P” may deviate ±1 from what is listed. However, “Loop Total ∆P” should only deviate ±3 from listed. In all cases, “Normalized jet Pump ∆P” values will be in bounds.





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Initials 6. Confirm that each normalized jet pump diffuser to lower plenum

differential pressure as determined in Step 4 of this Attachment is within the corresponding Normalized dP Range of PDB-A0009 for the Recirculation Loop configuration indicated in Step 4.3.

YES NO N/A RO √





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ATTACHMENT 4: Normalized Jet Pump Flows Data Sheet Page 1 of 2

Initials

1. RECORD each Jet Pump diffuser to lower plenum dP (%): 2. TAKE the square root of each Jet Pump dP, and RECORD as Jet Pump

SQRT(dP): 3. SUM all Jet Pump SQRT(dP)s for each loop, and RECORD as Loop Total

SQRT(dP): 4. DIVIDE each Loop Total SQRT(dP) by 10 and RECORD as Loop Average

SQRT(dP): 5. DIVIDE each Jet Pump SQRT(dP) by its Loop Average SQRT(dP), and

RECORD as Normalized Jet Pump Flow: Loop A 1H13-P619 Jet Pump Jet Pump Normalized Jet Pump Instrument dP (%) SQRT(dP) Jet Pump Flow 1. 1B33-R610A ________ _________ _________ 2. 1B33-R610E ________ _________ _________ 3. 1B33-R610J ________ _________ _________ 4. 1B33-R610N ________ _________ _________ 5. 1B33-R610T ________ _________ _________ 6. 1B33-R610C ________ _________ _________ 7. 1B33-R610G ________ _________ _________ 8. 1B33-R610L ________ _________ _________ 9. 1B33-R610R ________ _________ _________ 10. 1B33-R610V ________ _________ _________ “A” Loop Total SQRT(dP) ________ “A” Loop Average SQRTdP) ________ Loop B 1H13-P619 Jet Pump Jet Pump Normalized Jet Pump Instrument dP (%) SQRT(dP) Jet Pump Flow 11. 1B33-R610B ________ ________ _________ 12. 1B33-R610F ________ ________ _________ 13. 1B33-R610K ________ ________ _________ 14. 1B33-R610P ________ ________ _________ 15. 1B33-R610U ________ ________ _________ 16. 1B33-R610D ________ ________ _________ 17. 1B33-R610H ________ ________ _________ 18. 1B33-R610M ________ ________ _________ 19. 1B33-R610S ________ ________ _________ 20. 1B33-R610W ________ ________ _________ “B” Loop Total SQRT(dP) ________ “B” Loop Average SQRT(dP) ________

N/A





6 Page:

22 of 22


Initials 6. All calculations independently verified: Independent Verifier:

7. Confirm that each normalized jet pump flow as determined in Step 5 of

this attachment is within the corresponding Normalized Flow Range of PDB-A0009 for the Recirculation Loop configuration indicated in Step 4.3.

YES NO N/A

N/A


1

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO Administrative Topic: Conduct of Operations Validated Time: 15 Minutes Setting: Classroom References: OAI-1702 Rev 15, SOI-R45 Rev 17, SOI-R45/E22B Rev 17, & Form

PNPP-7961 Rev 10/5/10 Required Material: OAI-1702, Operations Section Rounds Sheets, Logs, and Records

SOI-R45, Division 1 And 2 Diesel Generator Fuel Oil System SOI-R45/E22B, Division 3 Diesel Generator Fuel Oil System Form PNPP-7961, Diesel Fuel Oil Record

Task: 299-770-03-01 Complete Diesel Fuel Oil Record Task Standard: Complete Weekly Diesel Generator Fuel Oil Record, calculating storage

tank levels. K/A Data: 2.1.18 Ability to make accurate, clear, and concise logs, records, status

boards, and reports. Importance: RO 3.6 SRO 3.8

1. Setup Instructions: None 2. Location / Method: Classroom / Administrative Performance 3. Initial Condition: Today is Sunday – Day Shift. The monthly surveillance run was

completed on Div. 1 Diesel Generator this past Thursday. A maintenance run was completed on 3 Diesel Generator last shift. Division 2 Diesel Generator received fuel oil this past Wednesday. Attached are the diesel counters reported by the NLO and a picture of the fuel oil storage tank meters from P877 and P601.

4. Initiating Cue: Unit Supervisor directs you, the Reactor Operator to complete the Diesel

Fuel Oil Record. Start: Stop: Candidate:


2

JPM BODY SHEET


Step 1 OAI-1702, Operations Section Rounds Sheets, Logs, and Records 4.3.2 The following records are controlled by this procedure:

2. Diesel Fuel Oil Record (PNPP No. 7961) is used to compile data for billing

purposes, monitor leakage from the Diesel Fuel Oil Storage Tanks and to provide required Environmental Protection Agency (EPA) data. This record should be maintained in the Control Room and completed as directed by SOI-R45 and SOI-R45/E22B. The completed Fuel Oil Records should be reviewed once per week by the Unit Supervisor. Upon completion, this record should be forwarded to Operations Services.

SOI-R45, Division 1 And 2 Diesel Generator Fuel Oil System (& SOI-R45/E22B, Division 3 Diesel Generator Fuel Oil System) 7.1 Diesel Fuel Oil Record, PNPP No. 7961

7.1.2 COMPLETE the “FUEL INVENTORY/ USE THIS WEEK” portion of the

Diesel Fuel Oil Record each Sunday on dayshift.

Standard: Candidate reviews OAI-1702, SOI-R45, & SOI-R45/E22B.

Instructor Cue: None Notes: Refer to Answer Key for Calculated numbers.

SAT ___ UNSAT ___ Comment(s):_________________________________________________________________


3

Step 2

7.1.2.a DETERMINE the approximate gallons consumed by each diesel for the week each Sunday on dayshift.

Critical Step: Candidate enters Div. 1 Runtime Counter in PRESENT COUNTER and

determines that Div. 1 DG consumed ~600 gallons of fuel.

Instructor Cue: None Notes: Div. 2 did not consume any fuel oil.


Step 3 SOI-R45/E22B, Division 3 Diesel Generator Fuel Oil System 7.1 Diesel Fuel Oil Record (OAI-1702)

7.2.2.b DETERMINE the approximate gallons consumed by each diesel for the week each Sunday on dayshift.

Critical Step: Candidate enters Div. 3 Runtime Counter in PRESENT COUNTER and

determines that Div. 3 DG consumed ~800 gallons of fuel.


Notes: See Answer Key



4

Step 4 Continue to complete Fuel Inventory/Use This Week for Div. 1 DG

Critical Step: Candidate enters 79% in PRESENT LEVEL and determines that

corresponds to 76025 gallons, which is below the ADMIN LEVEL and will require a dipstick reading.

Candidate directs NLO to perform Manual Determination of Storage Tank Level for Div. 1 FOST.

Instructor Cue: When directed, “Understand perform Manual Determination of Storage Tank Level for Div. 1 fuel oil storage tank.”

Report back, “Div. 1 fuel oil storage tank is at 132 inches.”

Notes: Candidate may inform Unit Supervisor about Div.1 FOST level now or upon completion of all three divisions.



Critical Step: Candidate enters ~92% in PRESENT LEVEL and determines that

corresponds to 84866 gallons, which falls within the acceptable channel check range for adding 7500 gallons of fuel.


Notes: None



5


Critical Step: Candidate enters 93% in PRESENT LEVEL and determines that

corresponds to 37435 gallons, which is below the ADMIN LEVEL and will require a dipstick reading.

Candidate directs NLO to perform Manual Determination of Storage Tank Level for Div. 3 FOST.

Instructor Cue: When directed, “Understand perform Manual Determination of Storage Tank Level for Div. 3 fuel oil storage tank.”

Report back, “Div. 3 fuel oil storage tank is at 131.0 inches by manual determination.”

Notes: Candidate may inform Unit Supervisor about Div.3 FOST level now or upon completion of all three divisions.


Step 7 COMPLETE the “FUEL INVENTORY/ USE THIS WEEK” portion of the Diesel Fuel Oil Record each Sunday on dayshift per SOI-R45 and SOI-R45/E22B

Standard: Candidate completes the fuel oil inventory record and reports that Div. 1

and Div. 3 fuel oil storage tanks are below the Admin Limits, but above the Tech Spec Limits.

Instructor Cue: None Notes: Terminate the JPM



6

Terminating Cue: Candidate calculates/determines fuel oil storage tank levels for Divisional

DG’s and completes the Diesel Fuel Oil Record (Sunday Requirements) and determines that Div. 1 and Div. 3 fuel oil storage tanks are below the Admin Limits.

Evaluation Results: SAT_____ UNSAT_____ End Time:


7

DIESEL FUEL OIL RECORD WEEK OF: February 5, 2017 PNPP No. 7961 Rev. 10/5/10 OAI-1702

FUEL OIL RECEIPTS THIS WEEK

DIESEL F.O. DATE TIME LEVEL (% or Inches) GALLONS IN TANK* GALLONS INVOICE END OF MONTH STORAGE TANK PRE-FILL POST-FILL PRE-FILL POST-FILL RECEIVED NUMBER INVENTORY (GAL) ** DIVISION 1 DIV 1

2/8/17 14:50 134.5” 150.5” 77630 85130 7500 0165823 DIV 2 DIVISION 2 DIV 3

DIVISION 3 DATE:

To be completed on Day Shift Sunday FUEL INVENTORY/USE THIS WEEK

PREVIOUS LEVEL (From previous week’s Record)

TOTAL GALLONS

PRESENT LEVEL

GALLONS USED THIS WEEK

DIESEL F.O. STORAGE TANK % or Inches GALLONS *

RECEIVED THIS WEEK (Sum of gallons received above) % or Inches GALLONS * (Previous Gal + Gal received - Present gal)

DIVISION 1 80% 76800

79% 132”

76025 76301

76800 + 0 – 76301 = 499

DIVISION 2 81% 77630 7500 92% 84866 77630 + 7500 - 84866 = 264

DIVISION 3 97% 38242 93% 131.0%”

37435 37435

38242 + 0 – 37435 = 807

RUNTIME TOTAL

HOURS

APPROX

APPROX GAL

FOR EACH DIESEL VERIFY THAT THE GALLONS USED THIS WEEK IS WITHIN 900 GAL (FOR DIV 1 OR DIV 2) OR 400 GALS (FOR DIV 3) OF THE APPROX GALLONS CONSUMED.

DIESEL

PREVIOUS WEEK

PRESENT COUNTER

DIESEL RUN THIS WEEK

GPH USED CONSUMED THIS WEEK

VERIFY EACH F. O. STORAGE TANK LEVEL IS GREATER THAN THE TECH SPEC LIMIT IDENTIFIED IN THE SOI OR APPROPRIATE ACTION HAS BEEN INITIATED.

DIV 1 1895.4 1896.9 1.5 400 GPH 600 gal

DIV 2 2067.7 2067.7 0 400 GPH 0 gal Initials:

DIV 3 1356.0 1360.0 4.0 200 GPH 800 gal

IV Initials:


8

Reported Field Data Diesel runtime counters reported by NLO performing Plant Equipment Rounds Div. 1 DG – 1896.9

Div. 2 DG – 2067.7

Div. 3 DG – 1360.0


9

JPM CUE SHEET

INITIAL CONDITIONS:

• Today is Sunday – Day Shift.

• The monthly surveillance run was completed on Div. 1 Diesel Generator this past Thursday.

• A maintenance run was completed on 3 Diesel Generator last shift.

• Division 2 Diesel Generator received fuel oil this past Wednesday.

• Attached are the diesel counters reported by the NLO and a picture of the fuel oil storage tank meters from P877 and P601.

INITIATING CUE: Unit Supervisor directs you, the Reactor Operator to complete the Diesel Fuel Oil Record.

17518

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DIESEL FUEL OIL RECORD WEEK OF: February 5, 2017 PNPP No. 7961 Rev. 10/5/10 OAI-1702

FUEL OIL RECEIPTS THIS WEEK

DIESEL F.O. DATE TIME LEVEL (% or Inches) GALLONS IN TANK* GALLONS INVOICE END OF MONTH STORAGE TANK PRE-FILL POST-FILL PRE-FILL POST-FILL RECEIVED NUMBER INVENTORY (GAL) ** DIVISION 1 DIV 1 2/8/17 14:50 134.5” 150.5” 77630 85130 7500 0165823 DIV 2 DIVISION 2 DIV 3 DIVISION 3 DATE: To be completed on Day Shift Sunday FUEL INVENTORY/USE THIS WEEK

PREVIOUS LEVEL (From previous week’s Record)

TOTAL GALLONS

PRESENT LEVEL

GALLONS USED THIS WEEK

DIESEL F.O. STORAGE TANK % or Inches GALLONS *

RECEIVED THIS WEEK (Sum of gallons received above) % or Inches GALLONS * (Previous Gal + Gal received - Present gal)

DIVISION 1 80% 76800 DIVISION 2 81% 77630 DIVISION 3 97% 38242

RUNTIME TOTAL

HOURS

APPROX

APPROX GAL

FOR EACH DIESEL VERIFY THAT THE GALLONS USED THIS WEEK IS WITHIN 900 GAL (FOR DIV 1 OR DIV 2) OR 400 GALS (FOR DIV 3) OF THE APPROX GALLONS CONSUMED.

DIESEL

PREVIOUS WEEK

PRESENT COUNTER

DIESEL RUN THIS WEEK

GPH USED CONSUMED THIS WEEK

VERIFY EACH F. O. STORAGE TANK LEVEL IS GREATER THAN THE TECH SPEC LIMIT IDENTIFIED IN THE SOI OR APPROPRIATE ACTION HAS BEEN INITIATED.

DIV 1 1895.4 400 GPH

DIV 2 2067.7 400 GPH Initials:

DIV 3 1356.0 200 GPH

IV Initials: * As determined by the % - inches - gallons cross reference in SOI-R45 or SOI-R45/E22B.

**Record tank volumes (gallons) on the last day of the month.


- 1 -

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Administrative Topic: Equipment Control Setting: Simulator Validated: 20 minutes References: PRI-TSR Rev 38, SVI-E31-T0374 Rev 7 Tasks: 035-506-01-01 Determine Identified/Unidentified leakage rates Task Standard: Calculate Drywell Sump in-leakage rate per SVI-E31-T0374 and

complete Tech Spec Rounds for Drywell Sump in-leakage Required Material: Pictures of DW FDS level of 11.78” with time (T=0130 hrs). Pictures of DW EDS with a leak rate of 1.5 and DW Cnds Flow with 0

gpm. Partially completed PRI-TSR page 34 Calculator. SVI-E31-T0374 with US signature on the Test Cover Sheet and filled

out up to but not including step 5.1.3 K / A Data: 2.2.12 Knowledge of surveillance procedures. 3.7 / 4.1 1. Setup Instructions: If to be done in simulator: Set Overrides ZA1E31R0618-BLU to 6.0

for DW FDS Level, ZA1E31R0619-RED to 1.5 for DW EDS Rate and ZA1E31R0609 to 0.0 for Upper DW Cooler Drain Flow. Reset gross fail on 1E31R609. If to be done in classroom: Use 01:00 pictures.

2. Location / Method: Simulator / Perform 3. Initial Condition: The plant is at 100% power. It has been determined that DW Floor

Drain Sump 1E31-R618 (red indicator) is inoperable. SVI-E31-T0374, “Reactor Cooling System Unidentified Leakage Determination” has been started. The DW Floor Drain Sump has NOT been recently pumped down (within the last hour). It is Tuesday, 0100 hours and you are the BOP operator.

4. Initiating Cue

• Complete SVI-E31-T0374, “Reactor Cooling System Unidentified Leakage Determination” using the Sump Level Recorder Method.

• Perform the Operator Tech Spec Rounds for “Drywell Leak Detect”, Step 42. Start Time: End Time: Candidate:


- 2 -

JPM BODY SHEET


Step 1 Record DW Floor Drain Sump Level.

Standard: Operator records the 1E31-R618 blue sump level reading of 6.0” in the surveillance.


Notes: Provide Candidate with handouts 1, 2, & 3. SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Wait for sump to fill up for second reading.

Standard: Operator waits for sump to fill.

Instructor Cue: After the operator logs the initial 6” sump reading, inform the operator that, using time compression, it is now 01:30 hrs and provide the operator with the 01:30 hour pictures of the sumps/flow (Handouts 4 & 5).


Comment(s):________________________________________________________________


- 3 -

Step 3 Calculate floor sump level increase.

Critical Step: Operator determines sump level has increased by 5.78”


Notes: 5.7” to 5.8” is acceptable. SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Calculate elapsed time.

Critical Step: Operator determines 30 minutes have elapsed.



Comment(s):________________________________________________________________


- 4 -

Step 5 Calculate Unidentified Leakage.

Critical Step: Operator determines 90.3414 gallons of unidentified leakage.


Notes: An answer from 89.0 to 90.7 gallons is acceptable (based upon acceptable answers for step 3)


Step 6 Calculate Unidentified Leakage Rate.

Critical Step: Operator determines an Unidentified Leakage Rate of 3.01138


Notes: An answer of 2.9 to 3.1 is acceptable (based upon acceptable answers for step 5).



- 5 -

Step 7 Independently verify calculations

Standard: Operator asks for independent verification.

Instructor Cue: When asked, inform the operator that the calculations have been verified.


Comment(s):________________________________________________________________

Step 8 Record DW FDS rate in PRI-TSR.

Standard: Operator records 3.01 gpm leakage rate on TS Rounds sheet.


Notes: An answer of 2.9 to 3.1 is acceptable (based upon acceptable answers for step 5).



- 6 -

Step 9 Determine Equipment Drain Sump Rate.

Standard: Operator records 1.5 gpm on TS Rounds Sheet.



Comment(s):________________________________________________________________

Step 10 Determine total leakage rate.

Standard: Operator records a total leakage rate of 4.51 on TS Rounds Sheet.


Notes: An answer of 4.4 to 4.6 is acceptable. (based upon acceptable answers for step 8).



- 7 -

Step 11 Determine 24 hour total leakage average rate

Standard: Operator averages the last 3 readings and obtains an average of 3.20.


Notes: An answer of 3.1 to 3.3 is acceptable. (based upon acceptable answers for step 10).


Step 12 Record DW CNDS FLOW

Standard: Records zero GPM.



Comment(s):________________________________________________________________


- 8 -

Step 13 Verify increase in Unidentified Leakage is < 2 gpm in 24 hours.

Critical Step: Operator notifies US that increase in unidentified leakage is > 2 gpm in a 24 hour period.



Comment(s):________________________________________________________________

Terminating Cue: Operator notifies US that increase in Unidentified Leakage is > 2 gpm in a

24 hour period. Evaluation Results: SAT_____ UNSAT_____ End Time:

PRI-TSR Rev 37 Candidate Handout 1 Sheet 18 of 36 Page 37

- 9 -

MODES 1, 2 & 3 TECHNICAL SPECIFICATION ROUNDS

SHEET 17 WEEK OF :___________________________

TSR-MODES 1,2&3-17 Rev. Error! Reference

source not found.

T I T L E

PANEL OR ORIGIN

PARAMETER/ INSTRUMENT

R E Q M T

U N I T S

MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

LEA

K D

ETEC

TIO

N R

CIC

IS

OLA

TIO

N <

B001

39>

41 P632 RCIC AREA T (1E31-N700A-A6-1)

CC (1 4 3 ) ° F 78 80 82 79

1H13-P642 RCIC AREA T (1E31-N700B-A6-1)

CC (1 4 3 ) ° F 78 81 78 80

1H13-P632 RHR AREA 1 T (1E31-N700A-A6-4)

CC (1 5 7 ) ° F 80 82 78 78

1H13-P642 RHR AREA 1 T (1E31-N700B-A6-4)

CC (1 5 7 ) ° F 82 82 80 81

1H13-P632 RHR AREA 2 T (1E31-N700A-A6-5)

CC (1 5 7 ) ° F 81 80 79 78

1H13-P642 RHR AREA 2 T (1E31-N700B-A6-5)

CC (1 5 7 ) ° F 83 81 81 79

DR

YW

ELL

LEA

K D

ETEC

T

42 Reading for 1E31-R618 (red) is only valid if DW Floor Drains Sump Level 1E31-R618 (blue) is < 12.5”. If 1E31-R618 (red) is not operable, perform SVI-E31-T0374 to determine DW Floor Drains Rate. Obtain TOTAL LEAKAGE RATE by summing DW FDS RATE and DW EDS RATE. Obtain 24 Hr TOTAL LEAKAGE AVERAGE by averaging the last 3 TOTAL LEAKAGE RATES. Verify 24 Hr TOTAL LEAKAGE AVERAGE ≤ 30 gpm.

<F01291> <F01332> <F01490> <L01448>

FDS SUMP LEV 1E31-R618 (blue) < 12.5 INCH 8.00 7.20 6.30 11.78

DW FDS RATE 1E31-R618 (red) ≤ 5 GPM .7 .8 .7 3.01

DW EDS RATE 1E31-R619 (red) GPM 1.8 1.9 1.7 1.5

1H13-P642 TOTAL LEAKAGE RATES

SEE NOTE GPM 2.5 2.7 2.4 4.51

24 Hr TOTAL LEAKAGE AVG

SEE NOTE GPM 2.4 2.6 2.5 3.20

1H13-P692 DW CNDS FLOW 1E31-R609 GPM 0 0 0 0

Required in Mode 1. Verify that the increase in “Unidentified Leakage” within the previous 24 hour period is ≤ 2 gpm.

1H13-P642 DW FDS RATE INCREASE

SEE NOTE INIT AJ BN CC XX

Initials circled in RED ink.

PRI-TSR Rev 37 Candidate Handout 1 Sheet 18 of 36 Page 37

- 10 -

MODES 1, 2 & 3 TECHNICAL SPECIFICATION ROUNDS

SHEET 17 WEEK OF :___________________________

TSR-MODES 1,2&3-17 Rev. Error! Reference

source not found.

T I T L E

PANEL OR ORIGIN

PARAMETER/ INSTRUMENT

R E Q M T

U N I T S

MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

M I D

D A Y

A F T

LEA

K D

ETEC

TIO

N R

CIC

IS

OLA

TIO

N <

B001

39>

41 P632 RCIC AREA T (1E31-N700A-A6-1)

CC (1 4 3 ) ° F 78 80 82 79

1H13-P642 RCIC AREA T (1E31-N700B-A6-1)

CC (1 4 3 ) ° F 78 81 78 80

1H13-P632 RHR AREA 1 T (1E31-N700A-A6-4)

CC (1 5 7 ) ° F 80 82 78 78

1H13-P642 RHR AREA 1 T (1E31-N700B-A6-4)

CC (1 5 7 ) ° F 82 82 80 81

1H13-P632 RHR AREA 2 T (1E31-N700A-A6-5)

CC (1 5 7 ) ° F 81 80 79 78

1H13-P642 RHR AREA 2 T (1E31-N700B-A6-5)

CC (1 5 7 ) ° F 83 81 81 79

DR

YW

ELL

LEA

K D

ETEC

T

42 Reading for 1E31-R618 (red) is only valid if DW Floor Drains Sump Level 1E31-R618 (blue) is < 12.5”. If 1E31-R618 (red) is not operable, perform SVI-E31-T0374 to determine DW Floor Drains Rate. Obtain TOTAL LEAKAGE RATE by summing DW FDS RATE and DW EDS RATE. Obtain 24 Hr TOTAL LEAKAGE AVERAGE by averaging the last 3 TOTAL LEAKAGE RATES. Verify 24 Hr TOTAL LEAKAGE AVERAGE ≤ 30 gpm.

<F01291> <F01332> <F01490> <L01448>

FDS SUMP LEV 1E31-R618 (blue) < 12.5 INCH 8.00 7.20 6.30

DW FDS RATE 1E31-R618 (red) ≤ 5 GPM .7 .8 .7

DW EDS RATE 1E31-R619 (red) GPM 1.8 1.9 1.7

1H13-P642 TOTAL LEAKAGE RATES

SEE NOTE GPM 2.5 2.7 2.4

24 Hr TOTAL LEAKAGE AVG

SEE NOTE GPM 2.4 2.6 2.5

1H13-P692 DW CNDS FLOW 1E31-R609 GPM 0 0 0

Required in Mode 1. Verify that the increase in “Unidentified Leakage” within the previous 24 hour period is ≤ 2 gpm.

1H13-P642 DW FDS RATE INCREASE

SEE NOTE INIT AJ BN CC

Candidate Handout 1


01:00 hrs Upper Drywell Cooler Drain Flow Monitor Candidate Handout 2

- 11 -

Time = 01:00


01:00 hrs DWS & EDS Level/Rate Monitors Candidate Handout 3

- 12 -

Time = 01:00


01:30 hrs DWS & EDS Level/Rate Monitors Candidate Handout 4

- 13 -

Time = 01:30


01:30 hrs Upper Drywell Cooler Drain Flow Monitor Candidate Handout 5

- 14 -

Time = 01:30


- 15 -

JPM CUE SHEET

INITIAL CONDITIONS:

• The plant is at 100% power. • It has been determined that DW Floor Drain Sump 1E31-R618 (red

indicator) is inoperable. • SVI-E31-T0374, “Reactor Cooling System Unidentified Leakage

Determination” has been started. • The DW Floor Drain Sump has NOT been recently pumped down (within

the last hour). • It is Tuesday, 0100 hours and you are the BOP operator.

INITIATING CUE: • Complete SVI-E31-T0374, “Reactor Cooling System Unidentified Leakage Determination” using the Sump Level Recorder Method

• Perform the Operator Tech Spec Rounds for “Drywell Leak Detect”, Step 42.

TEST COVER SHEET Functional Location: PY-SVI-E31-T0374

(PY: DATA PACKAGE COVER SHEET) Maintenance Plan #:






Condition Report #





Work Start (Prerequisites) Approval: Tom Smith / Tom Smith Today / Now Print Name Signature Date and Time Test Start Approval: Jack Jones / Jack Jones Today / Now Print Name Signature Date and Time Test Completed (Test Leader): / Print Name Signature Date and Time Lead Work Group Supervisor Review: / Print Name Signature Date and Time

Comments:

TEST COVER SHEET Functional Location: PY-SVI-E31-T0374

(PY: DATA PACKAGE COVER SHEET) Maintenance Plan #:



Number Tom Smith Tom Smith TS Today 10110 Jack Jones Jack Jones JJ Today 11100 Roy X. Opter Roy X. Opter RXO Today 10100

PERRY NUCLEAR POWER PLANT Procedure Number:SVI-E31-T0374

Title:

Reactor Cooling System Unidentified Leakage Determination

Use Category: Step-by-Step

Revision:7

Page:1 of 11

REACTOR COOLING SYSTEM UNIDENTIFIED LEAKAGE DETERMINATION


Effective Date: 4-22-15

Preparer: Kurt Jones / 4-15-15 Date

Approver: Ed Condo / 4-20-15 Date

Working Copy Verified - Today - RXO


Title:



Revision:7

Page:2 of 11

1.0 DESCRIPTION

1.1 Scope

A Drywell Floor Drain Sump Monitoring System is required by Technical Specifications 3.4.7. This instruction provides two alternate methods of verifying that unidentified leakage is within the limits of Technical Specifications 3.4.5. These alternate methods are required by the Bases for Technical Specifications 3.4.7.

This instruction records the necessary data and calculates the unidentified leakage rate. The calculated leakage rate will then be recorded in the PRI-TSR. The PRI-TSR is still the procedure that satisfies the surveillance requirement of Technical Specifications SR 3.4.5.1.

1.2 Frequency

At least once per 12 hours when the normal method of the PRI-TSRs can not be used.

1.3 Technical Specification Applicable MODES

1, 2, and 3

2.0 PRECAUTIONS AND LIMITATIONS

1. Those steps of this instruction designated with an initial block/line are tobe initialed as data is entered or as each step is completed. Thesesteps may require additional initials or signatures to be entered on othersheets, such as an attachment.

2. This instruction should be read in its entirety before proceeding with theperformance of the instructional steps.

3. All steps are to be performed in sequence and the instruction carriedthrough to completion unless otherwise indicated.

4. The Unit Supervisor must be notified immediately if an instruction stepcannot be completed as stated or if problems develop during theperformance of this instruction.

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Revision:7

Page:3 of 11

3.0 MANPOWER AND EQUIPMENT

3.1 Manpower/Location/Communication

1. One operator is required to perform this instruction.

2. Operation of the drywell floor drain sump pumps will require assistanceof the Radwaste Control Room.

3.2 Required Measuring and Test Equipment (M&TE)

1. A stopwatch (Robotic SC-700 or equivalent) will be required ifdetermining unidentified leakage per 5.1.4, Manual Timing Method.

3.3 Additional Tools and Equipment

None


N/A

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Page:4 of 11


1. OBTAIN US’s “Work Start (Prerequisites) Approval”signature on the Test Cover Sheet/Surveillance Order.

2. IF determining unidentified leakage per 5.1.4, ManualTiming Method,THEN VERIFY the calibration due date is current onall M&TE.

StopwatchFloc ________ Cal Date ________ Due Date ________

3. This surveillance may be performed in any Mode.

5.0 SURVEILLANCE INSTRUCTION

5.1 Surveillance Test

5.1.1 OBTAIN the Reactor Operator’s “Test Start Approval” signature on the Test Cover Sheet/Surveillance Order.

NOTE

If the Sump Level Recorder Method can be used to determine unidentified leakage rate, then the Drywell Floor Drain Sump Monitoring System can be considered operable per T.S. 3.4.7.

5.1.2 PERFORM one of the following alternate methods of determiningunidentified leakage: (N/A section not used.)

1. Sump Level Recorder Method per 5.1.3.

2. Manual Timing Method per 5.1.4

RXO

RXO

RXO

RXO

N/A

RXO

N/A

17518

Oval

17518

Oval

17518

Oval

17518

Oval

17518

Line

17518

Line

17518

Line

17518

Line

17518

Oval

17518

Oval

17518

Line

17518

Oval

17518

Line

17518

Oval

17518

Line

17518

Oval

17518

Line

17518

Oval

17518

Line


Title:



Revision:7

Page:5 of 11

5.1.3 Sump Level Recorder Method Initials

1. IF drywell floor drain sump level is 12.5 inches,as indicated on Panel H13-P642 level recorder1E31-R618,THEN REQUEST Radwaste Control Room to manually pumpdown the sump per RWI-G61(FDSS) until the sump level is< 10 inches.

NOTES

If the sump was recently pumped down to the automatic pump trip, it may take greater than an hour for level to increase sufficiently to accurately perform the following step.

The following readings must cover a period of time when the sump pump has not been in operation and sump level is <12.5 inches.

The more time allowed between the initial and current readings the more accurate the calculation.

2. Using Panel H13-P642 level recorder, 1E31-R618 bluepen, RECORD the following information:

a. in.(Initial Sump Level (Time of Taking From 1E31-R618) Initial Reading)

b. in.(Current Sump Level (Time of Taking From 1E31-R618) Current Reading)

3. CALCULATE the sump level rate of increase by performing thefollowing:

a. in. (Current Level 5.1.3.2.b)

- in. (Initial Level 5.1.3.2.a)

= in. (Sump Level Increase)


Title:



Revision:7

Page:6 of 11

SECTION 5.1.3 Initials

b. min. (Current Time 5.1.3.2.b)

- min. (Initial Time 5.1.3.2.a)

= min. (Elapsed Time)

c. in. (Sump Level Increase 5.1.3.3.a)

* 15.63 gals/in.

= gal. (Unidentified Leakage)

d. gal. (Unidentified Leakage 5.1.3.3.c)

min. (Elapsed Time 5.1.3.3.b)

= gpm (Unidentified Leakage Rate)

4. INDEPENDENTLY VERIFY all calculations.

5. RECORD the calculated unidentified leakage rate in theDrywell Leak Detect section of the PRI-TSR in place of the1E31-R618 red pen reading.

5.1.4 Manual Timing Method

1. VERIFY that the last performance of PTI-G61-P0001 is withinthe previous 24 months.

Date of last performance


Title:



Revision:7

Page:7 of 11


2. ESTABLISH the initial conditions for leakage determination asfollows:

a. REQUEST that the Radwaste Control Room manuallypump down the drywell floor drain sump and note thetime (clock time) that the pump trips on low level.

b. Time pump tripped:

c. REQUEST that the Radwaste Control Room placeboth drywell floor drain sump pumps in OFF.

NOTE

The following steps should not be performed until the sump level has increased sufficiently that a sump pump run time can be accurately determined. The waiting period will be determined by the expected leakage rate into the sump, taking into consideration the required 12 hour frequency of T.S. SR 3.4.5.1.

3. During the following step RECORD the time the pump trips(clock time) and MEASURE the time from pump start until thepump trips on sump low level. (stopwatch time)

4. COORDINATE with the Radwaste Control Room Operator tomanually pumpdown the drywell floor drain sump using onesump pump.

a. Sump pump used (circle one) A or B

b. Sump pump run time in minutes -(stopwatch time)

c. Time sump pump tripped -(clock time)


Title:



Revision:7

Page:8 of 11


NOTE

Capacity of drywell floor drain sump pumps per PTI-G61-P0001 (04-08-2015):

1G61-C008A: 36.0 gpm

1G61-C008B 45.0 gpm

5. To calculate the unidentified leakage rate, PERFORM thefollowing:

a. min. (Time Pump tripped 5.1.4.4.c)

- min. (Time Pump tripped 5.1.4.2.b)

= min. (Fill time)

b. min. (Sump Pump Run time 5.1.4.4.b)

* gpm (Pump Capacity)

= gal. (Gallons Pumped Out)

c. gal. (Gallons Pumped Out 5.1.4.5.b)

min. (Fill time 5.1.4.5.a)

= gpm (Unidentified Leakage Rate)

6. INDEPENDENTLY VERIFY all calculations.

7. RECORD the calculated unidentified leakage rate in theDrywell Leak Detect section of the PRI-TSR in place ofthe 1E31-R618 red pen reading.


Title:



Revision:7

Page:9 of 11

5.2 Plant/System Restoration Initials

1. IF Section 5.1.4 was performed,THEN RESTORE the Drywell Floor Drain Sump Pumpsas required by RW Supervisor:

1H51-P031

1G61-C008A1G61-C008B

5.3 Acceptance Criteria

$ 1. Drywell unidentified leakage rate has been determined andrecorded in the PRI-TSR at least once per 12 hours.

YES NO, U.S. notified

Comments:

Performed By: / /

/ /

/ /

/ /Signature Initials Date

RXORoy X. Opter Today


Title:



Revision:7

Page:10 of 11

6.0 RECORDS

6.1 Records Handling

Records completed/generated by this document shall be handled in accordance with the established records management program.

6.2 Records Capture

The following documents are completed/generated by this instruction:

Quality Records

Test Cover Sheet/Surveillance Order SVI-E31-T0374, pages 4 through 9

Non-Quality Records

None

7.0 REFERENCES

7.1 Discretionary

B-208-99-15

B-208-99-16

D-302-740

D-302-964

7.2 Obligations

Perry Plant Technical Specifications

Commitments addressed in this document:

None


Title:



Revision:7

Page:11 of 11

8.0 SCOPE OF REVISION

Rev. 7 1. Note at 5.1.4 Step 5 - corrected the referenced performance date and data for PTI-G61-P0001.

9.0 ATTACHMENTS

None


- 1 -

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: Radiation Control Setting: Classroom Validated: 15 minutes References: Radiation Worker Training Handout Rev 3

NORM-OP-4000, Radiation Protection Definitions & References Rev 1 Form NOP-OP-4107-4, ALARA Plan Tasks: 299-848-01-01 Comply with the Administrative Requirements for the

Perry Plant Radiation Dose Control Program Task Standard: Determine if a radiological entry to perform an assigned evolution

would be more ALARA with or without a respirator. Required Material: Calculator & Computer with access to FileNet K / A Data: 2.3.14 Knowledge of radiation or contamination hazards that may arise

during normal, abnormal, or emergency conditions or activities. Importance: RO 3.4 SRO 3.8

1. Instructions: None 2. Location / Method: Classroom / Administrative performance. 3. Initial Condition: The Plant is in a Site Area Emergency. You have been assigned to enter

Containment to isolate a primary system leak. The general area dose rates for the travel path and the work location are 25 mrem/hr. In addition Containment is posted an Airborne Area with current airborne particulate levels of 20 DAC. You estimate that it will take 45 minutes without a respirator and 75 minutes with a respirator.

4. Initiating Cue: As the assigned worker in order to keep your exposure ALARA would you perform the job with or without a respirator and how much dose would you save? Start Time End Time Candidate


- 2 -

JPM BODY SHEET


Step 1

Determine dose without respiratory protection.

Critical Step: The Candidate calculates radiation dose:

Area radiation dose 0.75 hr x 25 mr/hr = 18.75 mrem. Airborne dose 20 DAC x 2.5 mrem/DAC-hr x 0.75 hr = 37.50 mrem. Total Dose = 56.25 mrem



Comment(s):________________________________________________________________


- 3 -

Step 2 Determine dose with respiratory protection.

Critical Step: The Candidate calculates radiation dose:

Area radiation dose 1.25 hr x 25 mr/hr = 31.25 mrem. Airborne dose 0 mrem. Total Dose = 31.25 mrem



Comment(s):________________________________________________________________

Step 3 Determine how to maintain Dose ALARA.

Critical Step: The Candidate determines a Respirator should be worn, with a dose savings of 25 mrem.


Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The Candidate calculates dose both with and without a respirator and determines a respirator should be worn to maintain dose ALARA with a dose savings of 25 mrem. Evaluation Results: SAT_____ UNSAT_____ End Time


- 4 -

JPM CUE SHEET

INITIAL CONDITIONS:

• The Plant is in a Site Area Emergency.

• You have been assigned to enter Containment to isolate a primary system leak.

• The general area dose rates for the travel path and the work location are 25 mrem/hr.

• In addition Containment is posted an Airborne Area with current airborne particulate levels of 20 DAC.

• You estimate that it will take 45 minutes without a respirator and 75 minutes with a respirator.

INITIATING CUE: • As the assigned worker in order to keep your exposure ALARA would you perform the job with or without a respirator and

• How much dose would you save?

OT-3701-ADM_029SRO Rev 0

- 1 -

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: SRO Safety Function: Conduct of Operations Validated Time: 17 Minutes References: SVI-B33-T1160 Rev 6, PDB-A009 Rev. 19, PDB-A10 Rev. 17, PDB-A12

Rev. 16 Required Material: SVI-B33-T1160, Jet Pump Operability

PDB-A009, Expected Jet Pump Normalized dP and Flow Ranges PDB-A10, Recirc Loop Drive Flow vs. FCV Position PDB-A12, Recirc Drive Flow vs. Total Core Flow

Task: 202-525-01-01 Monitor the Operation of the Reactor Recirc System. Task Standard: Review manual surveillance to determine if jet pumps are operable. K/A: 2.1.7 Ability to evaluate plant performance and make operational

judgments based on operating characteristics, reactor behavior, and instrument interpretation. Importance: RO 4.4 SRO 4.7

1. Setup: Ensure “Required Material” SVI-B33-T1160, PDB-A009, PDB-A10, PDB-A12

and calculator available at JPM site. 2. Location / Method: Class Room / Administrative performance. 3. Initial Condition: A control rod sequence exchange was completed last shift. Restoration

to 100% power is in progress. Reactor power is currently at 87%. A drive in the SPDS (ICS) computer has failed and ICS is not available. SVI-B33-T1160, Jet Pump Operability was just completed for the daily requirement.

4. Initiating Cue: As the Unit Supervisor, perform SRO review of the attached SVI-B33-T1160, Jet Pump Operability. Document the results of your review on the Data Package Cover Sheet. The data collected was recorded accurately.



- 2 -

JPM BODY SHEET


Step 1 Review surveillance.

SVI-B33-T1160, Jet Pump Operability 4.0 PREREQUISITES

3 Confirm that the recirculation flow is steady; and indicate the configuration of the recirculation loops: c. Both recirculation loops in fast speed operation, with recirculation loop jet

pump flow mismatch within the limits of SR 3.4.1.1.

Critical Step: Candidate reviews the SVI and determine that PREREQUISITE Step 4.3.D was inappropriately checked. Step 4.3.C should be checked.

Instructor Cue: If asked, direct candidate to continue review.

Notes: Candidate should be able to ascertain that Recirc Pumps cannot be in SLOW speed with the Rx at 87% power.



- 3 -


Critical Step: Candidate determines jet pumps 1 and 15 are not within “established pattern”.


Notes: Step 5.1.3.1.b should be marked NO vs. YES and Attachment 3 Step 6 should be marked NO vs. YES.



Standard: Candidate determines “All other items checked in this surveillance” did not perform satisfactorily.


Notes: Step 5.3.2 should be marked NO vs. YES.

On Data Package Cover Sheet, NON TECHNICAL SPECIFICATION TEST DATA is marked UNACCEPTABLE.



- 4 -


Standard: Reviews Acceptance Criteria 5.3.1.a and determines 2 of the 3 have been satisfied.


Notes: Need only 2 of the 3 criteria for surveillance to be considered SAT. SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 Review surveillance Data Package Cover Sheet.

Critical Step: Reviews Data Package Cover Sheet and determines that “TECHNICAL SPECIFICATION DATA” block should be checked ACCEPTABLE.


Notes: Jet pumps 1 and 15 “NORMALIZED JET PUMP dP” was not within the established pattern. Therefore Acceptance Criteria 5.3.2 was not met.

Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Review of SVI-B33-T1160 is complete and problems have been

documented on the Data Package Cover Sheet. Evaluation Results: SAT_____ UNSAT_____ End Time


- 5 -

JPM CUE SHEET

INITIAL CONDITIONS:

• A control rod sequence exchange was completed last shift. Restoration to 100% power is in progress.

• Reactor power is currently at 87%. • A drive in the SPDS (ICS) computer has failed and ICS is not available.

• SVI-B33-T1160, Jet Pump Operability was just completed for the daily requirement.

INITIATING CUE: As the Unit Supervisor, perform SRO review of the attached SVI-B33-T1160, Jet Pump Operability. Document the results of your review on the Data Package Cover Sheet.

The data collected was recorded accurately.








Condition Report #





Work Start (Prerequisites) Approval: / Print Name Signature Date and Time

Test Start Approval: / Print Name Signature Date and Time

Test Completed (Test Leader): / Print Name Signature Date and Time

Lead Work Group Supervisor Review: / Print Name Signature Date and Time

Comments:

N/A – RXO

Today / 30 min.. ago - RXO “RO Smith Notified”

Rector X Operator Rector X Operator Today / 10 min.. ago

Performed manual SVI due to ICS being out of service.

X

X

X





Number Today 10010 Today 10110

I V R RXO Rector X Operator Rector X Operator

Indy V. Rever Indy V. Rever

PERRY NUCLEAR POWER PLANT Procedure Number: SVI-B33-T1160

Title:

Jet Pump OperabilityUse Category:


6 Page:

1 of 22

JET PUMP OPERABILITY


Effective Date: 8-5-16

Preparer: Thomas Naylor / 7-13-16 Date

Approver: Ben Huck / 7-19-16 Date

Working Copy Verified - Today - RXO





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1.0 DESCRIPTION 1.1 Scope

This instruction demonstrates the operability of each jet pump in each operating recirculation loop by confirming the existence of two of the following three conditions for each operating recirculation loop:

• Recirculation loop drive flow versus flow control valve position differs by less

than or equal to 10% from established patterns, • Recirculation loop drive flow versus total core flow differs by less than or

equal to 10% from established patterns, • Each jet pump diffuser to lower plenum differential pressure differs by less

than or equal to 20% from established patterns, or each jet pump flow differs by less than or equal to 10% from established patterns.

This instruction satisfies the requirements of Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1.

NOTES

• Not required to be performed until 4 hours after associated recirculation loop is

in operation. • Not required to be performed until 24 hours after greater than 25% RTP.

1.2 Frequency

24 hours 1.3 Technical Specification Applicable MODES 1 and 2 2.0 PRECAUTIONS AND LIMITATIONS 1. Step numbers marked with a dollar sign ($) immediately to the left are

required by Technical Specifications. Such items, if found to exceed their Acceptance Criteria, may be NRC reportable and shall be brought to the immediate attention of the Unit Supervisor.

2. Those steps of this instruction with an initial line are to be initialed as data

are entered or as each step is completed.





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3. Sections 5.1.1, 5.1.2, and 5.1.3 may be performed in any order. Steps within a section are to be performed in the order specified unless otherwise indicated.

4. Avoid performing this test at less than 10% FCV position, as position

indication is not consistent there. 5. Verification of established patterns is conducted in accordance with

SVI-F41-T3008, “Reactor Recirculation System Flow Data Verification” during the initial weeks of operation under circumstances such as:

a. Following refueling activities (fuel assembly replacement or shuffle, as

well as any modifications to fuel support orifice size or core plate bypass flow) that can affect the relationship between core flow, jet pump flow and recirculation loop flow, or

b. Initial entry into extended single loop recirculation operation Jet pump operability is considered acceptable prior to startup based on the

acceptable results obtained during the previous cycle. During performance of SVI-F41-T3008, the Shift Engineer, Responsible System Engineer, or a Reactor Engineer normally provides an “engineering judgment of the daily surveillance results” to detect significant abnormalities which could indicate a jet pump failure. This engineering judgment may be based upon the nature of the refueling activities and may consider the self-consistency of the daily surveillance results, but jet pump noise is the most positive indication that the jet pump is operating. If established patterns are to be revised the associated Plant Data Book entries and SDS screens will be placed on hold. Copies of the SVI-F41-T3008 data should be retained in the Control Room for reference until the revisions have been processed.

6. In order to permit sufficient opportunity for the baselining of new established

patterns, the period of time covering the “initial weeks of operation following refueling activities” normally extends to include five weeks after reaching rated power and flow.

7. When using the established patterns in the Plant Data Book Curves, confirm

the two loop curves are used during two loop operations and the single loop curves are used during single loop operations; likewise, for slow or fast speed operation.





6 Page:

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8. During single loop operations, only the jet pumps associated with the operating recirculation loop need to be demonstrated operable. However, data may be collected from the idle loop for use in demonstrating the OPERABILITY of the operating loop.

9. The following ICS SDS Displays may be used during the performance of this

surveillance instruction, as appropriate for the configuration of the recirculation system:

a. JPFLOW, TWO LOOP NORMALIZED JET PUMP FLOWS b. JPDP, TWO LOOP NORMALIZED JET PUMP DPS c. RFPERF, TWO LOOP RCIRC – FAST SPEED PERFORMANCE d. RSPERF, TWO LOOP RCIRC – SLOW SPEED PERFORMANCE 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication 1. Control Room operator or other qualified member of the unit technical staff

to record data from instruments that are located on UNIT CONTROL CONSOLE 1H13-P680 and/or JET PUMP MONITORING PANEL 1H13-P619.

2. Shift Engineer, Responsible System Engineer, or Reactor Engineer, if

needed, to provide engineering judgment of daily surveillance results. 3. The Independent Verifier may be any of the above individuals. 3.2 Required Measuring and Test Equipment (M&TE) None 3.3 Additional Tools and Equipment 1. PDB-A0009, Expected Jet Pump Normalized dP and Flow Ranges, if

needed. 2. PDB-A0010, Recirc Loop Drive Flow vs. FCV Position, if needed. 3. PDB-A0012, Recirc Drive Flow vs. Total Core Flow, if needed.





6 Page:

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4. SVI-F41-T3008, Reactor Recirculation System Flow Data Verification, if needed.

5. Plant computer provides data, if used. 4.0 PREREQUISITES Initials 1. MARK the Unit Supervisor’s “Authorization to Start Prerequisites”

signature N/A on the Data Package Cover Sheet (DPCS) and initial. 2. CONFIRM that the plant is operating in MODE 1 with

THERMAL POWER greater than 25% RTP. 3. CONFIRM that the recirculation flow is steady and INDICATE the

configuration of the recirculation loops: a. Loop A (only) in operation, with recirculation flow control

in loop manual. b. Loop B (only) in operation, with recirculation flow control

in loop manual. c. Both recirculation loops in fast speed operation, with


d. Both recirculation loops in slow speed operation, with


4. IF using plant computer points or ICS SDS screens, THEN VERIFY no other maintenance or testing is in progress which

would affect recirculation flow indication, OTHERWISE MARK this step N/A.

RXO

RXO

RXO

N/A

√





6 Page:

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Note During performance of SVI-F41-T3008, engineering judgment by the Shift Engineer, Reactor Engineering, or Responsible System Engineer may determine existing patterns of PDB-A0009, PDB-A0010, and PDB-A0012 to be adequate for performance of this surveillance. 5. For at least 2 of the following, CONFIRM 1 or more listed source is

available OR SVI-F41-T3008 is in progress.

• RFPERF/RSPERF OR PDB-A0010 • RFPERF/RSPERF OR PDB-A0012 • JPDP OR JPFLOW OR PDB-A0009


RXO





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5.0 SURVEILLANCE INSTRUCTION Initials 5.1 Surveillance Test 1. NOTIFY the Reactor Operator before starting and write

“R.O. (operator’s name) notified” in the “Authorization to Start Test” signature on the DPCS. RECORD the time and date and initial the line.

Note

Steps 5.1.1, 5.1.2, and 5.1.3 may be performed in any order. Steps within a section are to be performed in the order specified unless otherwise noted. 5.1.1 Recirculation Loop Drive Flow vs. FCV Position

1. DETERMINE the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, AND indicate the method used.

SDS Screen Attachment 1

a. IF using ICS SDS,

THEN ATTACH a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop - fast speed, or RSPERF for two loop - slow speed), OTHERWISE COMPLETE Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position.

2. INDICATE, for each operating loop, whether the relationship

determined in Step 5.1.1.1 is within the appropriate “established pattern.” a. IF using ICS SDS,

THEN OBSERVE cursor is within limits for the DRIVE FLOW A VS. FCV A and/or for the DRIVE FLOW B VS. FCV B, OTHERWISE REFER to Step 3 on Attachment 1.

• Loop A: YES NO N/A • Loop B: YES NO N/A

√

√ √

RXO

RXO

RXO

RXO





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5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow Initials 1. DETERMINE the relationship between recirculation loop drive flow

and total core flow, AND INDICATE the method used.

SDS Screen Attachment 2 a. IF using ICS SDS,

THEN ATTACH a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop - fast speed, or RSPERF for two loop - slow speed), OTHERWISE COMPLETE Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow.

2. INDICATE whether the relationship determined in Step 5.1.2.1 is

within the appropriate “established pattern.” a. IF using ICS SDS, THEN OBSERVE cursor is within limits for the DRIVE FLOW VS. CORE FLOW, OTHERWISE REFER to Step 3 on Attachment 2.

YES NO

√

√ RXO

RXO

RXO





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5.1.3 Jet Pump Differential Pressure and Flow Initials

Notes

• It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section may be marked N/A.

• For single loop operation, the spaces in this section may be marked N/A for the idle

loop. 1. Jet Pump Differential Pressure a. DETERMINE each normalized jet pump diffuser to lower plenum

differential pressure for each operating recirculation loop, AND INDICATE the method used.

SDS Screen Attachment 3 1) IF using ICS SDS,

THEN ATTACH a copy of the JPDP screen, OTHERWISE COMPLETE Attachment 3, Normalized Jet Pump dP’s Data Sheet.


is within the appropriate “established pattern.” 2) IF using ICS SDS, THEN OBSERVE NORMAL indication for the JET PUMP DPS, OTHERWISE REFER to Step 6 on Attachment 3.

YES NO N/A

√

√

RXO

RXO

RXO





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Section 5.1.3 Initials 2. Jet Pump Differential Flow a. DETERMINE each normalized jet pump flow for each operating

recirculation loop, AND INDICATE the method used.

SDS screen Attachment 4 1) IF using ICS SDS,

THEN ATTACH a copy of the JPFLOW screen, OTHERWISE COMPLETE Attachment 4, Normalized Jet Pump Flows Data Sheet.


is within the appropriate “established pattern.” 1) IF using ICS SDS, THEN OBSERVE NORMAL indication for the JET PUMP FLOWS, OTHERWISE, REFER to Step 7 on Attachment 4.

YES NO N/A 5.2 Plant/System Restoration None

N/A





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5.3 Acceptance Criteria Initials

Notes

• Satisfactory completion of this surveillance shall be based only on Technical Specification items (marked with a $ sign).

• While baselining new “established patterns,” copies of SVI-F41-T3008 data

should be retained in the Control Room so that the Shift Engineer, the Responsible System Engineer, or a Reactor Engineer may consider the self-consistency of the data in making the “engineering judgment” on the existence of significant abnormalities which could indicate a jet pump failure. Jet pump noise is the most positive indication that the jet pump is operating.

$ 1. The jet pumps, in each operating recirculation loop, have been

demonstrated OPERABLE by one of the following two methods: a. At least two of the following three criteria have been satisfied: 1) Recirculation loop drive flow versus flow control valve

position differs by less than or equal to 10% from established patterns. (YES in Step 5.1.1.2)

2) Recirculation loop drive flow versus total core flow differs

by less than or equal to 10% from established patterns. (YES in Step 5.1.2.2)

3) Each jet pump diffuser to lower plenum differential

pressure differs by less than or equal to 20% from established patterns, OR each jet pump flow differs by less than or equal to 10% from established patterns. (YES in either Step 5.1.3.1.b or Step 5.1.3.2.b)

YES NO, U.S. notified N/A √ RXO





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SECTION 5.3 Initials b. While baselining the new “established patterns,” the Shift

Engineer (SE), or the Responsible System Engineer (RSE), or a Reactor Engineer (RE) has reviewed the surveillance results and has determined, based upon engineering judgment, that no significant abnormality exists that could indicate a jet pump failure.

___________________________________ /________ SE, RSE, or RE Signature / Date 2. All other items checked in this surveillance performed satisfactorily. YES NO, applicable Supervisor notified 3. Check the appropriate block on the Data Package Cover Sheet to

indicate acceptable or unacceptable test results. Comments: ________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ _____________________________________________________________________ Performed By: ______________________________________________/_________/________ ______________________________________________/_________/________ ______________________________________________/_________/________ Name (Print) Initials / Date

√

RXO

RXO RXO

N/A RXO

Reactor X. Operator

Performed manual SVI due to ICS being out of service.

Indy V. Rever I V R Today

Today





6 Page:

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6.0 RECORDS 6.1 Records Handling Records handling shall be performed per NOP-SS-3300. 6.2 Records Capture The following documents are completed/generated by this instruction: Quality Records Data Package Cover Sheet SVI-B33-T1160, pages 5 through 11, and: Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position, if used Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow, if used Attachment 3, Normalized Jet Pump dP’s Data Sheet, if used Attachment 4, Normalized Jet Pump Flows Data Sheet, if used Copy SDS screen JPFLOW, TWO LOOP NORMALIZED JET PUMP FLOWS, if used Copy SDS display JPDP, TWO LOOP NORMALIZED JET PUMP DPS, if used Copy SDS display RFPERF, TWO LOOP RCIRC – FAST SPEED PERFORMANCE, if used Copy SDS display RSPERF, TWO LOOP RCIRC – SLOW SPEED PERFORMANCE, if used Non-Quality Records None





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7.0 REFERENCES 7.1 Discretionary B-208-016, Sht. B02, B03, B04 D-302-603 D-302-604 NUREG/CR-3052, Closeout of 1E Bulletin 80-07: BWR Jet Pump Assembly Failure General Electric, Jet Pump Beam Cracks, SIL 330 with supplements NOP-WM-2003, Surveillance Test Control PAP-0500, Perry Technical Procedure Writer’s Guide PAP-0507, Perry Supplemental Procedure Requirements/Guidance SVI-F41-T3008, Reactor Recirculation System Flow Data Verification Plant Data Book 7.2 Obligations Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1 USAR Section 3.2.3.2.1, Definition of Safety Class 2 USAR Section 3.9.5.1.2, Reactor Internals USAR Figure 3.9-22, Jet Pump USAR Section 3.9.5.3.7, Special Requirements for Jet Pump Holddown Beams USAR Section 4.4.3.3.2, Regions of the Power-Flow Map USAR Section 15F.2.1.1, Core Flow Measurement During Single Loop Operation USAR Section 5.4.1.4, Safety Evaluation USAR Section 6.2.1.1.3.3.1, Recirculation Line Break USAR Section 6.3.3.7.2, Accident Description Commitments addressed in this document: None





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8.0 SCOPE OF REVISION: Rev. 6 1. Revise Precaution and Limitation 2.5 to clarify when data from SVI-

F41-T3008 will be used to complete the surveillance. 2. Add Prerequisite Step 4.5 to confirm which data sources will be used

to complete the surveillance. 3. Remove Commitment L01960 from References. L01960 implemented

License Amendment 61, related changes would now go through the 10CFR50.59 process. The commitment is now closed.

4. Upgrade procedure to comply within current SVI format in accordance with PAP-0500, rev bars omitted.

5. Update Steps 4.1 and 5.1.1 to match the words on the current revision of the DPCS, rev bars omitted.

9.0 ATTACHMENTS Attachment 1 - Manual Recirculation Loop Drive Flow vs. FCV Position Attachment 2 - Manual Recirculation Loop Drive Flow vs. Total Core Flow Attachment 3 - Normalized Jet Pump dP’s Data Sheet Attachment 4 - Normalized Jet Pump Flows Data Sheet





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ATTACHMENT 1: Manual Recirculation Loop Drive Flow vs. FCV Position Page 1 of 1

Initials

Note

For single loop operation, the spaces in this attachment may be marked N/A for the idle loop. 1. RECORD, for each operating loop, the flow control valve position from the

instrument on 1H13-P680: a. RCIRC LOOP A FLOW CONTROL: _________ 1B33-K603A (%) b. RCIRC LOOP B FLOW CONTROL: _________ 1B33-K603B (%) 2. RECORD, for each operating loop, the recirculation loop drive flow from

the plant computer or instruments on 1H13-P680, AND indicate the source of the data and the units:

C51-R614-blue (%) a. Flow A: _________ B33EA028 (kGPM) C51-R614-red (%) b. Flow B: _________ B33EA030 (kGPM)

NOTES

The limits on the established recirculation loop drive flows are determined from the: • PDB-A0010 graphs for the recirculation loop configuration of Step 4.3, • Flow control valve positions of Step 1 of this attachment, • Units indicated in Step 2 of this attachment. 3. CONFIRM, for each operating loop, the recirculation loop drive flow

recorded in Step 2 is between the corresponding limits determined from the appropriate “Flow + 10%” and “Flow - 10%” curves in PDB-A0010.

a. Loop A: YES NO N/A b. Loop B: YES NO N/A

35

34

70.43

69.11 √

√

√ √

RXO

RXO

RXO





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Initials 1. DETERMINE the total Recirc Drive Flow by adding the individual Recirc

Drive Flows recorded in Step 2 of Attachment 1, AND indicate the corresponding units.

a. IF in single loop operation,

THEN use zero for the Recirc Drive Flow of the idle loop. (%) Total Recirc Drive Flow: _________ (kGPM) Independent Verifier: 2. IF 1B33-R613 is being used to determine Total Core Flow,

THEN RECORD Total Core Flow from 1B33-R613 below, AND MARK Step 2.a. N/A, OTHERWISE COMPLETE Step 2.a.

a. IF Dual loop operation is indicated in Step 4.3, THEN RECORD the sum of the jet pump loop flows as Total Core

Flow, AND MARK the corrected idle loop flow space N/A, OTHERWISE CORRECT the idle loop jet pump flow by multiplying

by 0.95, AND RECORD the Total Core Flow as the operating loop jet pump flow minus the corrected idle loop jet pump flow.

Jet Pump Loop A Flow: ______ 1B33-R612A (Mlb/hr) Jet Pump Loop B Flow: ______ 1B33-R612B (Mlb/hr) Corrected Idle Loop Flow: ______ (Mlb/hr) Loop: A B 1B33-R612A & B Total Core Flow: ______ 1B33-R613 (Mlb/hr) Independent Verifier:

RXO

RXO √

139.54

√

N/A

I V R

N/A N/A

76

I V R

N/A





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Initials

Note

The limits on the established recirculation loop drive flow are determined from the: • PDB-A0012 graph for the recirculation loop configuration of Step 4.3, • Total Core Flow of Step 2 of this attachment, • Units indicated in Step 1 of this attachment. 3. Confirm that the flow recorded in Step 1 of this attachment is within the

limits determined from the appropriate “Drive Flow +10%” and “Drive Flow - 10%” curves in PDB-A0012.

YES NO

RXO √





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Initials 1. Record each Jet Pump diffuser to lower plenum dP (%): 2. Sum all Jet Pump dPs for each loop, and record as Loop Total dP: 3. Divide each Loop Total dP by 10 and record as Loop Average dP: 4. Divide each Jet Pump dP by its Loop Average dP, and record as

Normalized Jet Pump dP: Loop A 1H13-P619 Jet Pump Normalized Jet Pump Instrument dP (%) Jet Pump dP 1. 1B33-R610A ________ _________ 2. 1B33-R610E ________ _________ 3. 1B33-R610J ________ _________ 4. 1B33-R610N ________ _________ 5. 1B33-R610T ________ _________ 6. 1B33-R610C ________ _________ 7. 1B33-R610G ________ _________ 8. 1B33-R610L ________ _________ 9. 1B33-R610R ________ _________ 10. 1B33-R610V ________ _________ “A” Loop Total dP ________ “A” Loop Average dP ________ Loop B 1H13-P619 Jet Pump Normalized Jet Pump Instrument dP (%) Jet Pump dP 11. 1B33-R610B ________ ________ 12. 1B33-R610F ________ ________ 13. 1B33-R610K ________ ________ 14. 1B33-R610P ________ ________ 15. 1B33-R610U ________ ________ 16. 1B33-R610D ________ ________ 17. 1B33-R610H ________ ________ 18. 1B33-R610M ________ ________ 19. 1B33-R610S ________ ________ 20. 1B33-R610W ________ ________ “B” Loop Total dP ________ “B” Loop Average dP ________ 5. All calculations independently verified: Independent Verifier:

RXO RXO RXO

RXO

25 29 32 33 31 31 32 31 32 31

307 30.7

0.81 0.94 1.04 1.07 1.01 1.01 1.04 1.01 1.04 1.01

20 18 19 17 18 20 20 21 22 27

202 20.2

0.99 0.89 0.94 0.84 0.89 0.99 0.99 1.04 1.09 1.34

I V R





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Initials 6. Confirm that each normalized jet pump diffuser to lower plenum

differential pressure as determined in Step 4 of this Attachment is within the corresponding Normalized dP Range of PDB-A0009 for the Recirculation Loop configuration indicated in Step 4.3.

YES NO N/A RXO √





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Initials

1. RECORD each Jet Pump diffuser to lower plenum dP (%): 2. TAKE the square root of each Jet Pump dP, and RECORD as Jet Pump

SQRT(dP): 3. SUM all Jet Pump SQRT(dP)s for each loop, and RECORD as Loop Total

SQRT(dP): 4. DIVIDE each Loop Total SQRT(dP) by 10 and RECORD as Loop Average

SQRT(dP): 5. DIVIDE each Jet Pump SQRT(dP) by its Loop Average SQRT(dP), and

RECORD as Normalized Jet Pump Flow: Loop A 1H13-P619 Jet Pump Jet Pump Normalized Jet Pump Instrument dP (%) SQRT(dP) Jet Pump Flow 1. 1B33-R610A ________ _________ _________ 2. 1B33-R610E ________ _________ _________ 3. 1B33-R610J ________ _________ _________ 4. 1B33-R610N ________ _________ _________ 5. 1B33-R610T ________ _________ _________ 6. 1B33-R610C ________ _________ _________ 7. 1B33-R610G ________ _________ _________ 8. 1B33-R610L ________ _________ _________ 9. 1B33-R610R ________ _________ _________ 10. 1B33-R610V ________ _________ _________ “A” Loop Total SQRT(dP) ________ “A” Loop Average SQRTdP) ________ Loop B 1H13-P619 Jet Pump Jet Pump Normalized Jet Pump Instrument dP (%) SQRT(dP) Jet Pump Flow 11. 1B33-R610B ________ ________ _________ 12. 1B33-R610F ________ ________ _________ 13. 1B33-R610K ________ ________ _________ 14. 1B33-R610P ________ ________ _________ 15. 1B33-R610U ________ ________ _________ 16. 1B33-R610D ________ ________ _________ 17. 1B33-R610H ________ ________ _________ 18. 1B33-R610M ________ ________ _________ 19. 1B33-R610S ________ ________ _________ 20. 1B33-R610W ________ ________ _________ “B” Loop Total SQRT(dP) ________ “B” Loop Average SQRT(dP) ________

N/A





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Initials 6. All calculations independently verified: Independent Verifier:

7. Confirm that each normalized jet pump flow as determined in Step 5 of

this attachment is within the corresponding Normalized Flow Range of PDB-A0009 for the Recirculation Loop configuration indicated in Step 4.3.

YES NO N/A

N/A


- 1 -

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: SRO Safety Function: Administrative Setting: Classroom / Simulator Validated: 28 minutes References: NOP-OP-1015 Rev 03, NOBP-OP-1015 Rev 05, NOBP-LP-4017 Rev 01,

10CFR20 Rev 2012 Required Material: NOP-OP-1015 Event Notifications, NOBP-OP-1015 Event Notifications,

NOBP-LP-4017 Preparation and Submittal of Licensee Event Reports, and 10CFR20, Standards For Protection Against Radiation, Subpart M, 20.2201

Reports of theft or loss of licensed material. & Appendix A, Quantities of Licensed Material Requiring Labeling

Tasks: 341-513-03-02 Make Required Notifications to the NRC Operations Center via the ENS Within the Specified Time Frame

341-641-03-02 Prepare an Event Notification Form Task Standard: Determine reportability requirements (Immediate Notification to NRC) for

lost/ missing licensed material by reviewing NOBP-OP-1015 and 10CFR20. K/A Data: 2.1.18 Ability to make accurate, clear, and concise logs, records, status

boards, and reports. Importance: RO 3.6 SRO 3.8 1. Setup Instructions: None 2. Location / Method: Classroom / Administrative 3. Initial Condition: The plant is at 100% rated thermal power.

• A Radiation Protection Supervisor just delivered a condition report to the Control Room reporting a source is missing.

• A search for the missing source was not successful. • The missing source has a concentration of 240,000 µCi of Cs-136 (Cesium).

4. Initiating Cue: As the Shift Manager: 1) Determine if any external reporting requirements to outside regulatory agencies

apply and 2) If so, document your findings below. (Include to whom any report(s) due and

imposed time limits.). Start Time: End Time: Candidate:


- 2 -

JPM BODY SHEET


Step 1 Review procedures to determine Federal reportability requirements. NOBP-OP-1015 Event Notifications Attachment 37: Notification R1.4: Lost, Stolen, or Missing Licensed Material Requirement: 10 CFR 20.2201(a)(1)(i) RIS 2005-21 §20.2201(a)(1) Each licensee shall report by telephone as follows: (i) Immediately after its occurrence becomes known to the licensee, any lost, stolen, or missing licensed material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in appendix C to part 20 under such circumstances that it appears to the licensee that an exposure could result to persons in unrestricted areas; or (ii) Within 30 days after the occurrence of any lost, stolen, or missing licensed material becomes known to the licensee, all licensed material in a quantity greater than 10 times the quantity specified in appendix C to part 20 that is still missing at this time. Time Limit Required Notification(s) IMMEDIATE Notify the NRC Operations Center via ENS immediately upon discovering any lost, stolen, or missing licensed material in a aggregate quantity equal or greater than 1,000 times the quantity specified in 10 CFR 20 Appendix C under such circumstances that it appears to the licensee that an exposure could result to persons in unrestricted areas. [10 CFR 20.2201(a)(1)(i)] JPM Step 1 continued on next page.


- 3 -

JPM Step 1 continued: 30 DAYS Notify the NRC Operations Center via ENS within 30 days after the occurrence of any lost, stolen, or missing licensed material in a quantity greater than 10 times the quantity specified in 10 CFR 20 Appendix C that is still missing at this time. [10 CFR 20.2201(a)(1)(ii)] Discussion: • For this report the term Immediately means within 4 hours of discovery [RIS 2005-21]

Critical Step:

Candidate reviews 10CFR20 to determine if the quantity missing is equal or greater than 1,000 times the quantity specified in 10 CFR 20 Appendix C.


Notes: FEDERAL: If requested, provide Candidate with a copy of 10CFR20. Candidate will need to ascertain the value in App. C of Part 20 for Cs-136 to determine if notification is required.



- 4 -

Step 2 Review procedures to determine State reportability requirements. NOBP-OP-1015 Event Notifications Attachment 46: Notification RP.2: Lost, Stolen, or Missing Radioactive Material – PY

Requirement: Ohio Administrative Code Section 3701:1-38-21

§3701:1-38-21

Immediately after the licensee determines that licensed radioactive material is stolen, lost, or missing in an aggregate quantity equal to or greater than one hundred times the quantity specified in appendix A to rule 3701:1-38-18 of the Administrative Code under such circumstances that it appears to the licensee that an exposure could result to individuals in unrestricted areas;

Time Limit Required Notification(s) IMMEDIATE

Report to the Director, Ohio Department of Health immediately upon discovery that a registered radioactive source is stolen, lost, or missing in an aggregate quantity equal to or greater than one hundred times the quantity specified in Appendix A of 3701:1-38-18 of the Ohio Administrative Code under such circumstances that it appears to the licensee that an exposure could result to individuals in unrestricted areas.

Standard: • Candidate reviews State of Ohio Appendix A to determine if the quantity missing is equal or greater than 100 times the quantity specified in Ohio Administrative Code Appendix A.

• If notification to state of Ohio is made, then a 4-hour NRC notification is also required under 10CFR50.72(b)(2)(XI) / 10CFR72.75(b)(2) and Candidate should identify it as such.


Notes: STATE: If requested, provide Candidate with a copy of “Appendix A to rule 3701:1-38-18 of the Administrative Code”. Candidate will need to ascertain the value in Appendix A for Cs-136 to determine if notification is required.



- 5 -

Step 3 Determine Immediate Notification reportability is required.

Critical Step: Candidate determines that IMMEDIATE NOTIFICATION shall be made to the NRC Operations Center.



Comment(s):________________________________________________________________

Step 4 Determine Immediate Notification reportability is required.

Standard: Candidate determines that IMMEDIATE NOTIFICATION shall be made to the Director, Ohio Department of Health.


Notes: Notifications to the Director, Ohio Department of Health is not a Critical Step for this JPM (NOBP-OP-1015 Attachment 46).


Terminating Cue: Candidate determined that missing quantity of material meets notification

threshold and immediate notification to the NRC Operations Center is required.



- 6 -

JPM CUE SHEET

INITIAL CONDITIONS:

The plant is at 100% rated thermal power.

• A Radiation Protection Supervisor called the Control Room reporting a source is missing.

• A search for the missing source was not successful.

• The missing source has a concentration of 240,000 µCi of Cs-136 (Cesium).

INITIATING CUE: As the Shift Manager:

1) Determine if any external reporting requirements to outside regulatory agencies apply and

2) If so, document your findings below. (Include to whom any report(s) due and imposed time limits.).


- 1 -

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: SRO Safety Function: Equipment Control Validated Time: 10 Minutes References: PAP-1910 Rev 37 Required Material: PAP-1910 Fire Protection Program

Tech Spec 3.8.2 Task: 343-684-03-02 Determine Required Actions for an Unplanned Fire

Impairment / Barrier Removal When the P54 RSE is not Available. Task Standard: Using PAP-1910, specify compensatory actions to be taken for fire

protection systems/equipment (fire hydrant) identified as not functional. K/A: 2.1.14 Knowledge of the process for controlling equipment configuration

or status Importance Rating: SRO 4.3 1. Setup: Ensure “Required Material” available at JPM site. 2. Location / Method: Class Room / Administrative performance. 3. Initial Condition: Plant is in Mode 5. Fuel movement is in progress. Division 2 and 3

ECCS and diesel generators are out of service. Division 1 ECCS & Division 1 Diesel Generator are protected for Shutdown Safety. A notification was received from the Outage Control Center that while moving a dumpster, a back loader ran into Fire Hydrant #24 and substantial damage was incurred to the hydrant. Isolation actions have been initiated by the OCC. A repair Notification has been written.

4. Initiating Cue: As the Unit Supervisor, determine if any additional required action(s) is/are required to be taken for the Fire Protection System.



- 2 -

JPM BODY SHEET


Step 1 PAP-1910, Fire Protection Program: 4.4.2 Fire Protection System Operation

Fire protection systems and components are aligned, maintained, and operated to ensure system functionality and availability in accordance with the following:

2 Completion of the surveillance requirements (e.g., by performing inspections, verifications and tests), at frequencies based on Attachment 3, Fire Protection Functional Specifications ensures proper system/component operation.

3. Impairment actions as specified within the functional specifications for those systems/components declared not functional. These actions will maintain their operational status until corrective action is taken.

Standard: Candidate identifies that Impairment actions are contained in PAP-1910, Fire Protection Program, Attachment 3, and Fire Protection Functional Specifications.


Notes: When requested by candidate, provide a copy of PAP-1910 and/or Tech Specs.



- 3 -

Step 2

ATTACHMENT 3: Fire Protection Functional Specifications. TABLE OF CONTENTS Page 6.A Yard Fire Hydrants and Hydrants Hose Houses 75

Standard: Candidate reviews Table of Contents and identifies Functional Specification 6.A Yard Fire Hydrants applies.



Comment(s):________________________________________________________________


- 4 -

Step 3 6. FIRE SUPPRESSION EQUIPMENT

A. SYSTEMS: Yard Fire Hydrants and Hydrants Hose Houses

B. FUNCTIONALITY REQUIREMENTS:

Yard Fire Hydrants shall be deemed functional if they are accessible and capable of delivering adequate water flow. Hose Houses shall be deemed functional if they contain the proper equipment.

The following hydrants and hose houses protect Fire-Safe Shutdown Components:

Hydrant 24 – Diesel Generator Building

Hydrant 23 – Diesel Generator Fuel Oil Storage Tanks

Hydrant 1 – Unit 2 Startup Transformer


C. APPLICABILITY:

Fire hydrants and hose houses shall be functional whenever equipment in the area protected is required to be Operable.

Critical Step: Candidate determines that Hydrant 24, Diesel Generator Building is required to be functional whenever equipment in the area protected is required to be Operable.


Notes: Tech Spec 3.8.2, AC Sources- Shutdown, requires one diesel generator capable of suppling one division of onsite Class 1E AC electrical power distribution subsystem. Division 1 DG is required to be operable.



- 5 -

Step 4

D. ACTIONS FOR NOT FUNCTIONAL:

IF:

1) Any of the following hydrants are not functional:

Hydrant 24 – Diesel Generator Building

Hydrant 23 – Diesel Generator Fuel Oil Storage Tanks



THEN:

24 HRS a. Route sufficient additional lengths of 2 ½” or 3” fire hose from the nearest functional Hydrant to provide protection to the unprotected area.

Critical Step: Candidate determines that the Impairment Action is to, “route sufficient additional length of 2 ½” or 3” fire hose from the nearest functional Hydrant to the unprotected area.” And is required within 24 hours.

Instructor Cue: If asked, no other hydrants are NOT FUNCTIONAL.

If asked, routing of the fire hose does not present a safety hazard.

Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Review of PSP-1910 is complete and Fire Impairment actions have been

identified for hydrant 24 being Not Functional. Evaluation Results: SAT_____ UNSAT_____ End Time


- 6 -

JPM CUE SHEET

INITIAL CONDITIONS:

• Plant is in Mode 5.

• Fuel movement is in progress.

• Division 2 and 3 ECCS and diesel generators are out of service.

• Division 1 ECCS & Division 1 Diesel Generator are protected for Shutdown Safety.

• A notification was received from the Outage Control Center that while moving a dumpster, a back loader ran into Fire Hydrant #24 and substantial damage was incurred to the hydrant.

• Isolation actions have been initiated by the OCC.

• A repair Notification has been written.

INITIATING CUE: As the Unit Supervisor, determine if any additional required action(s) is/are required to be taken for the Fire Protection System.


- 1 -

JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: SRO only Safety Function: Radiation Control Validated Time: 15 Minutes References: HPI-B0003 Rev 27 Form 10136 Rev 7/26/01 Required Material: HPI-B0003, Processing of Personnel Dosimetry Form PNPP 10136, Emergency Dose Authorization NOP-OP-4201, Routine External Exposure Monitoring Task: 344-511-05-03 Request and Authorize increased exposure limits for

emergency responders during emergency events. 451-656-05-50 Discuss TSC or CR EC responsibilities for authorization plans personnel to receive dose in excess of 10CFR20 limits under emergency situations.

Task Standard: Determine if an Operator can perform an emergency evolution due to radiation levels and complete an Emergency Dose Authorization if evolution can be performed.

K/A: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. Importance: SRO 3.7


- 2 -

JOB PERFORMANCE MEASURE SETUP SHEET Cont 1. Setup: Ensure “Required Material” available at JPM site. 2. Location / Method: Class Room / Administrative performance. 3. Initial Condition: The plant is in an Unusual Event due to lowering Spent Fuel Pool level.

No facilities are currently activated and Emergency Coordinator duties remain in the Control Room. While investigating a leak in the FPCC Heat Exchanger Room, an NLO (Roberts) became pinned against the east wall near the “A” HX when a scaffold supporting lead blankets collapsed. Due to the weight of the blankets he is unable to move, but is shielded. He has suffered potentially life threatening injuries. You must assign two operators to rescue NLO Roberts. RP Supervision informs you that travel path dose rates are 3 REM/hr to NLO Roberts and 60 REM/hr where NLO Roberts is located. It is estimated that total travel time to and from NLO Roberts is 5 minutes (2&½ minutes each way) and it will take 30 minutes to move the blankets and rescue NLO Roberts.

The following on-shift personnel are available for job assignments: Bob Smith, Bill Johnson, Ray Jones, and Tom Bell.

Bob Smith is 52 years old and has a life time dose of 7.2 Rem. Bob has a year to date dose of 20 mrem.

Bill Johnson is 34 years old and has a life time dose of 16.5 Rem. Bill has a year to date dose of 200 mrem.

Ray Jones is 28 years old and has a life time dose of 700 mrem. Ray has a year to date dose of 100 mrem.

Tom Bell is 21 years old and has a lifetime dose of 128 mrem. Tom has a year to date dose of 23 mrem.

4. Initiating Cue #1: As the Shift Manager, determine which if any of these operators can be assigned to rescue NLO Roberts.

Initiating Cue #2: Complete the Perry Emergency Dose Authorization form. Start: Stop: Candidate:


- 3 -

JPM BODY SHEET


Step 1 Determine the radiation dose that will be received.

Critical Step: Determine dose to be received by the rescue operators.


Notes: 3 REM/60 min*5 min=0.25 REM. 60 REM/60 min* 30 min =30 REM Total dose = 30.25 REM per rescuer



- 4 -

Step 2 Determine that the rescuers may receive greater than 25 REM for lifesaving if he is a volunteer.

Critical Step: Determines that Bill Johnson and Ray Jones will rescue the NLO Roberts.

Instructor Cue: When Candidate asks for volunteers, reply Johnson and Jones have volunteered.

If procedure error is identified on page 5 of HPI-B03, inform Candidate that the error was previously identified and procedure change submitted.

If asked what Federal Limits are, ask candidate where they can find the information.

Notes: Do not give Dose Authorization Form to Candidate until he demonstrates where he can obtain it.

Federal Limits found in NOP-OP-4201.

If above steps completed sat, provide 2nd Initiating Cue to Candidate SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Complete Emergency Dose Authorization (Form # - PNPP 10136)

Critical Step: Fill in NAME, CURRENT YEAR DOSE, LIFETIME DOSE, & LEVEL APPROVED on form PNPP 10136.

Approve the Emergency Dose Authorization

Instructor Cue: If asked, Jones’ SSN is 555-55-5551 and Johnson’s SSN is 555-55-5552

If asked, acting as Jones & Johnson, sign for Jones & Johnson.

Notes: Level approved needs to be ≥ 30.25 Rem.

No signatures are required in the REQUEST block, but if requested, inform Candidate that RP supervisor is not available.



- 5 -

Step 4 Approve Emergency Dose Authorization (Form # - PNPP 10136) as Shift Manager acting as Emergency Coordinator.

Critical Step: Approve the Emergency Dose Authorization form PNPP 10136 in the APPROVAL Section



Comment(s):________________________________________________________________

Terminating Cue: Assigns Ray Jones & Bill Johnson to rescue the NLO ROBERTS and

approve the Emergency Dose Authorization. Evaluation Results: SAT_____ UNSAT_____ End Time

OT-3701-ADM_019SRO Answer Key Rev 0

- 6 -

EMERGENCY DOSE AUTHORIZATION PNPP No. 10136 Rev. 7/26/01 HPI B-0003 RE Q U E S T

INCREASE IS REQUIRED TO SUPPORT THE FOLLOWING EMERGENCY OPERATIONS:

Rescue NLO Roberts from FPCC HX Room

Name SSN Current

Year – All Facilities

Lifetime required to exceed 5 rem

Signature Required to exceed 5 rem

Level Approved

Ray Jones 555-55-5551 100 mRem

700 mRem

(≥) 30.25 Rem

Bill Johnson 555-55-5552 200 mRem

16.5 Rem

(≥) 30.25 Rem

OSC Support Supervisor/Operations Shift Manager: May fill in as Requester Print / Signature Date Health Physics Support Supervisor/Shift Health Physics Supervisor: N/A Print / Signature Date LIMITS TEDE:

10CFR20 – 5 rem Services – 5 rem Valuable Property – 10 rem Large Pop. or Lifesaving – 25 rem*

* If persons have volunteered to perform lifesaving activities or protect large populations and are fully aware of the risks involved the above dose limits may be exceeded. Doses should be limited to the lowest practicable.

Operations Shift Manager and Shift Health Physics Supervisor should submit Emergency Dose Authorizations prior to OSC activation.

A P P R O V A L

TSC Operations Manager/Operations Shift Manager: Print / Signature Date Radiation Protection Coordinator/Supervision, RP: Print / Signature Date Operations Shift Manager and Supervision, RP should approve Emergency Dose Authorizations prior to TSC activation.


- 7 -

EMERGENCY DOSE AUTHORIZATION PNPP No. 10136 Rev. 7/26/01 HPI B-0003 RE Q U E S T

INCREASE IS REQUIRED TO SUPPORT THE FOLLOWING EMERGENCY OPERATIONS:

Name SSN Current

Year – All Facilities

Lifetime required to exceed 5 rem

Signature Required to exceed 5 rem

Level Approved

OSC Support Supervisor/Operations Shift Manager: Print / Signature Date Health Physics Support Supervisor/Shift Health Physics Supervisor: Print / Signature Date LIMITS TEDE:

10CFR20 – 5 rem Services – 5 rem Valuable Property – 10 rem Large Pop. or Lifesaving – 25 rem*

* If persons have volunteered to perform lifesaving activities or protect large populations and are fully aware of the risks involved the above dose limits may be exceeded. Doses should be limited to the lowest practicable.

Operations Shift Manager and Shift Health Physics Supervisor should submit Emergency Dose Authorizations prior to OSC activation.

A P P R O V A L

TSC Operations Manager/Operations Shift Manager: Print / Signature Date Radiation Protection Coordinator/Supervision, RP: Print / Signature Date Operations Shift Manager and Supervision, RP should approve Emergency Dose Authorizations prior to TSC activation.

NOTE: Normally, planned doses during an emergency should be controlled to within <10CFR20> limits. However, under emergency circumstances these limits may be waived by TSC Operations Manager along with the Radiation Protection Coordinator, or the Operations Shift Manager, acting as Emergency Coordinator, if the TSC is not activated, to allow personnel to perform valuable emergency actions. Due to the urgent nature of emergency dose requirements, completion of the Emergency Dose Authorization can be accomplished subsequent to receiving dose if situations warrant. The doses received should be voluntary and commensurate with the significance of the objective and held to the lowest practicable level that the emergency permits.


- 8 -

JPM CUE SHEET

INITIAL CONDITIONS:

• The plant is in an Unusual Event due to lowering Spent Fuel Pool level. No facilities are currently activated and Emergency Coordinator duties remain in the Control Room.

• While investigating a leak in the FPCC Heat Exchanger Room, an NLO (Roberts) became pinned against the east wall near the “A” HX when a scaffold supporting lead blankets collapsed. Due to the weight of the blankets he is unable to move, but is shielded. He has suffered potentially life threatening injuries.

• You must assign two operators to rescue NLO Roberts.

• RP Supervision informs you that travel path dose rates are 3 REM/hr to NLO Roberts and 60 REM/hr where NLO Roberts is located. It is estimated that total travel time to and from NLO Roberts is 5 minutes (2&½ minutes each way) and it will take 30 minutes to move the blankets and rescue NLO Roberts.

• The following on-shift personnel are available for job assignments: Bob Smith, Bill Johnson, Ray Jones, and Tom Bell

• Bob Smith is 52 years old and has a life time dose of 7.2 Rem. Bob has a year to date dose of 20 mrem.

• Bill Johnson is 34 years old and has a life time dose of 16.5 Rem. Bill has a year to date dose of 200 mrem.

• Ray Jones is 28 years old and has a life time dose of 700 mrem. Ray has a year to date dose of 100 mrem.

• Tom Bell is 21 years old and has a lifetime dose of 128 mrem. Tom has a year to date dose of 23 mrem.

INITIATING CUE: As the Shift Manager, determine which if any of these operators can be assigned to rescue NLO Roberts.


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JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: Yes Applicability: SRO Safety Function: Emergency Procedures / Plan Setting: Classroom / Simulator Validated: 15 minutes References: EPI-A1 Rev. 26, EPI-A2 Rev. 15, EPI-B1 Rev. 21, & EPI-B8 Rev. 18 Required Material EPI-A1 - Emergency Action Levels EPI-A2 - Emergency Actions Based On Event Classification EPI-B1 - Emergency Notification System EPI-B8, Protective Actions And Guides Tasks: 344-532-05-02 Prepare Emergency Plan Initial Notification Form 344-502-05-03 Determine Protective Action Recommendations (PARs) and

Ensure that the State and Counties are Notified 451-162-05-52 Determine the appropriate PAR using the PAR Decision

Flowchart. Task Standard: Classify the emergency, complete Initial Notifications and issue Protective

Action Recommendations IAW appropriate E-plan procedures. K/A Data: 295017 AK3.03 Implementation of site emergency plan. IR: RO 3.3 SRO 4.5 295038 EK3.01 Implementation of site emergency plan. IR: RO 3.6 SRO 4.5 2.4.30 Knowledge of events related to system operation/status that must be

reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. IR: RO 2.7 SRO 4.1 2.4.44 Knowledge of emergency plan protective action recommendations. IR: RO 2.4 SRO 4.4

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JPM was replaced by OT-3701-ADM_313_SRO; It was determined following administration of this JPM that the specified INITIAL CONDITIONS did not support the desired outcome.

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1. Setup Instructions: None 2. Location / Method: Simulator / Classroom 3. Initial Condition: The Plant scrammed. All rods are in. Reviewed EPI-A1 Emergency

Action Levels, and declared AS3 Site Area Emergency, Challenge to either the Fuel Clad barrier OR Reactor Coolant System barrier, AND the loss of any additional barrier due to RPV water level < 0 inches. Initial notifications were completed 5 minutes ago. Chemistry has performed a MIDAS run due to uncontrolled release and the results are attached.

4. Initiating Cue: With the information provided, declare the emergency action level, complete initial notifications and other required actions. Task is Time Critical

Start Time: End Time: Candidate:

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JPM BODY SHEET


Step 1 Review EPI-A1 and classify the event/ EPI-A1, Emergency Action Levels 5.1 Event Assessment and Event Classification

5.1 Classify the emergency as follows:

1. Using Initiating Condition Index (PNPP No. 8852, Attachment 1), identify the emergency by event category and determine the most appropriate Initiating Condition

2. Refer to Attachment 2 for the applicable Initiating Condition(s) to determine whether the criteria are met for the operating mode(s) listed.

3. Declare an emergency class when all the conditions listed in at least one EAL column have been met, and implement <EPI-A2>.

a. When several Initiating Conditions are met, declare the most severe emergency class.

JPM Step 1 continued next page

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JPM Step 1 continued

Initiating Conditions Entry Criteria

HG1 Site Boundary dose

resulting from an actual or imminent release of gaseous radioactivity

that exceeds 1000 mRem TEDE dose

OR 5000 mRem CDE ChildThyroid dose for theactual or projected duration of the release

Applicable Modes:

A valid indication greater than the reading listed for one or more of the following plant gaseous effluent monitors: • PLANT VENT GAS 1D19-K300 3.8E0 μCi/cc • OG VENT GAS 1D19-K400 2.2E1 μCi/cc • TB/HB VENT GAS 1D17-K856 1.6E5 cpm • PLANT VENT GAS 2D19-K300 6.0E-0μCi/cc

Emergency dose calculations, using actual meteorology indicate that one or more of the following are met at the Site Boundary: • Greater than

1000 mRem TEDE

• Greater than 5000 mRem CDE Child Thyroid

Field survey results indicate that one or more of the following have been met at the Site Boundary: • Greater than

1000 mRem/hr Whole Body

• Greater than 5000 mRem CDE Child Thyroid

Emergency dose calculations CANNOT confirm, within 15 minutes of exceeding above limit, that levels at the Site Boundary are less than 1000 mRem TEDE and 5000 mRem CDE Child Thyroid dose using actual meteorology.

Dose rates are expected to continue for greater than or equal to 1 hour.

1 2 3 4 5 D

Critical Step: Candidate classifies event as HG1 within 15 minutes.


Notes: Dose is GREATER than 1 REM TEDE and 5 REM child thyroid at site boundary per MIDAS printout.

Start Time ________ Classification Time __________ SAT ___ UNSAT ___

Comment(s):________________________________________________________________

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Step 2

4. Complete the EVENT CLASSIFICATION CHECKLIST (PNPP No. 7983A), contained in <EPI-A2>.

Standard: Operator uses Event Classification Checklist to assist with required actions.

Instructor Cue: Give Operator E-Plan Packet, when he identifies where to obtain. I&C has been contacted and is en route.

Notes: Checklist to be completed through line A.6. SAT ___ UNSAT ___

Comment(s):________________________________________________________________

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Step 3 EPI-B8, Protective Actions And Guides 5.1 Protective Action Logic 5.1.3 Emergency Coordinator:

3. APPROVE PARs for the general public developed utilizing Attachment 1 and ensure that the State of Ohio, local counties, and the NRC are notified per <EPI-B1>.

JPM Step 3 continued next page

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JPM Step 3 continued

Critical Step: Protective action recommendation, evacuate 1, 3, and Lake. Block 5.a and 6.a are checked.

Instructor Cue: If asked, “No impediment to evacuation, No controlled release.”

Notes: Wind Direction on MIDAS is 53 degrees = 12° to 101° EVACUATE 1, 3, & Lake*. Table A is used due to Child thyroid > 5 Rem at Site Boundary and < 5 REM at 5 miles.


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Step 4 EPI-A2, Emergency Actions Based On Event Classification Attachment 1 - Event Classification Checklist 4. Complete an Initial Notification form (PNPP No. 7794) and forward to communicators

within 10 minutes of decision to classify event

Critical Step: Initial Notification form completed within 13 minutes of Classification. The following items are Critical:

• Block 2 is checked “A Drill” • Block 3.a is checked for General Emergency HG1. • Block 4 is completed similar to Answer Key • Block 5.a is checked • 6.a “Evacuation” and Subareas 1, 3, & Lake are also checked.


Notes: Time Given to Communicator ________ The goal is to give to communicator within 10 minutes, but MUST be completed within 13 minutes.


Standard: Candidate provides I&C Communicator with Emergency Notification Cover Sheet when handing him the Initial Notification Form.



Comment(s):________________________________________________________________

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Step 5 EPI-A2, Emergency Actions Based On Event Classification

Attachment 1 - Event Classification Checklist

6. Complete the Pager Messages form (PNPP No. 9100), approve, and forward to the SAS within 10 minutes of decision to classify event or revise PARs.

Standard: Pager Message completed, Scenario ID No. 4



Comment(s):________________________________________________________________

Terminating Cue: Event Classified (HG1) within 15 minutes and Initial Notification given to communicator within 13 minutes of Classification.


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EVENT CLASSIFICATION CHECKLIST PNPP No. 7983A Rev. 6/20/13 Page 1 of 2 EPI-A2

Event classified as a/an: General Emergency Site Area Emergency Alert Unusual Event

At Within 15 minutes of CUE on / / . Time Date

Checklist completed by: (Shift Manager/TSC Operations Manager/ EOF Emergency Coordinator)

A. IMMEDIATE ACTIONS INITIAL TIME 1. Announce event classification and reason for declaring emergency over the Plant PA

System. √

2. Sound Plant Emergency Alarm. (Request Control Room to initiate Alarm) √

3. [CONTROL ROOM ONLY] Call the shift I&C technician to the Control Room as a communicator. √

NOTE: For a GENERAL EMERGENCY, ensure that PAR is included using EPI-B8, Attachment 1, PAR Decision Flowchart.

4. Complete an Initial Notification form (PNPP No. 7794), approve, and forward to communicators within 10 minutes of decision to classify event or revise Protective Action Recommendations (PARs).

√

5a. Determine facilities to be activated using table below: (R-required; O-optional) √ Classification/Facility OSC TSC PIRT EOF JIC Unusual Event O O O O O Alert R R R O O Site Area Emergency R R R R R General Emergency R R R R R 5b. Announce facilities to be activated over the Plant PA System. √ NOTE: (1) Completion of form is delegated to the Security Coordinator once TSC is

operational. (2) Activation of ERO pagers is NOT needed if required facilities have already been/are being mobilized.

6. Complete the Pager Messages form (PNPP No. 9100), approve, and forward to the SAS within 10 minutes of decision to classify event or revise PARs.

√

7. Complete a Reactor Plant Event Notification Worksheet form (NOP-OP-1015-01), approve, and forward to communicators immediately following notification of the State of Ohio and local counties, but within 50 minutes of event classification.

NOTE: It may be prudent to delay implementation of accountability in situations where personnel safety could be jeopardized, such as a security event or severe weather.

8. [SITE AREA EMERGENCY or above] Initiate personnel accountability per EPI-B5, if not yet implemented: Not Required

8a. Direct Shift Manager, or designee, to initiate appropriate “Emergency” message over the Exclusion Area Paging System, and use PA feature to provide further guidance on offsite assembly if required.

8b. The Shift Manager, or designee, is to manually repeat the accountability message approximately every 5 minutes until accountability is completed, if the automated message is not working

9. Verify that notifications and/or requests for offsite support were completed by the SAS:

a. Fire Department (911) Not Required b. Ambulance (911) Not Required c. Hospital: Primary - TriPoint; Backup - Lake West Not Required 10. If the NRC requests that the ENS circuit remains open then verify that an individual

knowledgeable in system operations is assigned to the NRC ENS Circuit to answer questions and inquiries.

REFER TO page 2 of 2 FOR LISTING OF FOLLOW-UP ACTIONS

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Candidate

FENOC NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM Perry PNPP No. 7794 Rev. 6/8/11 EPI-B1

USE FOR: INITIAL CLASSIFICATIONS, CHANGES IN CLASSIFICATIONS, CHANGES IN PROTECTIVE ACTION

RECOMMENDATIONS. EVENT TERMINATION

STATE / COUNTY USE ONLY DATE: _______ TIME: ______

MESSAGE NO: ______________

1. This is the:

Perry Nuclear Power Plant 2. This is: An Actual Emergency A Drill

3. a. A(n) GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT

was declared at: 15 min from on Today

based on EAL: HG-1 (TIME) (DATE) b. The Emergency situation has been terminated at: _

on ___

(TIME) (DATE)

c. The Protective Action Recommendation is being changed at: _____

on _

(TIME) (DATE)

4. Brief non-technical description of event: Site Boundary dose resulting from an actual or imminent release of

gaseous radioactivity that exceeds 1000 mRem TEDE dose OR 5000 mRem CDE Child Thyroid dose for the actual or projected duration of the release 5. The radiological conditions are:

a. A non-routine release of radioactive material, as a result of this event, is in progress.

b. The release of radioactive material associated with this event has been terminated.

c. NO Radiological Release in progress as a result of this event.

6. Utility Protective Action Recommendations (PAR’s): a. Evacuation:

(check applicable subareas)

1 2 3 4 5 6 7 LAKE

AND that potassium iodide (KI) be administered to the general public in accordance with State procedures. The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

b. Sheltering: (check applicable subareas)

1 2 3

AND Evacuate the Lake AND that potassium iodide (KI) be administered to the general public in accordance with State procedures. The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

c. None

For Utility Use Only

Approved: _________________________________

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Candidate

PAGER MESSAGES

PNPP No. 9100 Rev. 9/8/14 Page 1 of 1 EPI-B1 CONTROL ROOM/TSC SECURITY COORDINATOR INSTRUCTIONS: 1. Select appropriate Scenario ID number. 2. Initiate the notification by forwarding to SAS or by forwarding the information contained within the form to an ERS

representative. TSC SECURITY COORDINATOR/SAS OPERATOR INSTRUCTIONS: Using the information on this form, initiate the notification of the Emergency Response Organization per SPI-0032.

(√)

Scenario ID No. Event Code Message Narrative

1 1111 Unusual Event – No facility activation. 2 2222 Alert - OSC, TSC, and PIRT to be activated.

3 3333 Site Area Emergency - OSC, TSC, EOF, PIRT, and JIC to be activated.

√ 4 4444 General Emergency - OSC, TSC, EOF, and JIC to be activated. 51 5555 Event Termination 52 5555 OSC to be staffed. 53 5555 TSC to be staffed. 54 5555 PIRT to be staffed. 55 5555 OSC, TSC and PIRT to be staffed. 56 5555 EOF to be staffed. 57 5555 JIC to be staffed.

61 6666 ERO Teams respond to your offsite facility. 62 6666 Site Inaccessible, ERO Teams respond to your offsite facility. 81 8888 Drive-In Drill – OSC, TSC & EOF to be activated. 91 9999 Weekly Pager Test (Shift Manager approval not required) 92 9999 Unannounced Pager Test (Shift Manager approval not required) 93 9999 Security Pager Test (Shift Manager approval not required)

Approved by: / / Date Time Emergency Coordinator Delivered to: / / Date Time Name Activated by: / / Date Time Name

Date Time

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JPM CUE SHEET

INITIAL CONDITIONS:

• The Plant scrammed. • All rods are in. • Reviewed EPI-A1 Emergency Action Levels, and declared AS3 Site Area

Emergency, Challenge to either the Fuel Clad barrier OR Reactor Coolant System barrier, AND the loss of any additional barrier due to RPV water level < 0 inches.

• Initial notifications were completed 5 minutes ago. • Chemistry has performed a MIDAS run due to uncontrolled release and

the results are attached.

INITIATING CUE: With the information provided:

• Declare the emergency action level

• Complete initial notifications and other required actions. Task is Time Critical

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FENOC NUCLEAR POWER PLANT State/ County USE ONLY FOLLOW-UP NOTIFICATION FORM Part B Page 1 of 1 DATE: _____________ TIME: _____________ MESSAGE NO: _________________________

Dose Assessment Data Form SITE: PERRY ACTUAL MENU: A Summary For Calculation: Today – 5 minutes ago DATE PRINTED: Today - Now Current Input Data Adjusted Measured Precipitation Meteorological Data: Level Wind Direction from Wind Speed Wind Speed inch/15 min Stability Class 10 meters 53 degrees 6.0 mph 6.0 mph No Rain E Effective Release Monitor Conversion Concentration Flow Release Rate Monitor ID Point Reading Status* Units to uCi/cc (uCi/cc) Reading Status* Units (uCi/sec) TB VNT L 1 1.8E+05 0 cpm 3.5E-08 6.3E-03 3.1E+05 0 CFM 9.2E+05 * Status: 0=Good, 1=Questionable, 2=Bad, 7=Manual Override of Raw Data Release Characterization: Accident Type: Mix ID # 0: CONTAINMENT GAP RELEASE Type Noble Gases Iodines Particulates Total Units 3.3E-02 8.9E-01 0.0E+00 9.2E-01 Ci/sec Start of Release: A while ago - Today End of Release: 4 hours after start - Today Time of Trip: A while ago - Today Start of Projection: A while ago - Today Dose Projection Parameters: Projection Period: 4.00 Hours Estimated Remaining Release Duration: 4.00 Hours Dose Results Dispersion: (s/m3) Projected Dose: (mrem) Current Dose Rate: (mrem/hr) Child Child TEDE/EDE at Distance X/Q TEDE Thyroid CDE TEDE Thyroid CDE EDE TEDE Rate EAB / Site Boundary 5.9E-05 2.6E+02 8.5E+03 1.2E+02 5.5E+03 2.6E+01 4.78

2 miles 1.4E-05 1.4E+02 3.9E+03 1.0E+01 4.2E+03 1.4E+00 5 miles 4.5E-06 6.4E+01 1.4E+02 0.0E+00 0.0E+00 0.0E+00

10 miles 1.9E-06 2.0E+01 4.5E+01 0.0E+00 0.0E+00 0.0E+00 PAG Limit is Exceeded 10% of PAG Limit Exceeded

Prepared by:_________________________ /____________ Reviewed by:_________________________ /____________ (Date) (Date)

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JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: Yes Applicability: SRO Safety Function: Emergency Procedures / Plan Setting: Classroom Simulator Validated: 15 minutes References: EPI-A1 Rev. 22, EPI-A2 Rev. 15, & EPI-B1 Rev. 21 Required Material EPI-A1 - Emergency Action Levels EPI-A2 - Emergency Actions Based On Event Classification EPI-B1 - Emergency Notification System Tasks: 344-532-05-02 Prepare Emergency Plan Initial Notification Form Task Standard: Classify the emergency and complete Initial Notifications IAW appropriate

E-plan procedures. K/A Data: 295017 AK3.03 Implementation of site emergency plan. Importance RO 3.3

SRO 4.5 295038 EK3.01 Implementation of site emergency plan. Importance RO 3.6

SRO 4.5 1. Setup Instructions: None 2. Location / Method: Administrative / Perform 3. Initial Condition: The unit was at 100%. RHR Pump “A” is INOPERABLE and tagged

out. A Reactor scram occurred and all rods are full in. An SRV is stuck open and Suppression Pool temperature is rising. While placing RHR “B” into Suppression Pool Cooling, RHR B HX’S BYPASS VALVE, 1E12-F048B, is full open and cannot be closed remotely or locally. Reactor pressure is 715 psig, Suppression Pool level is 19.3 feet. Suppression Pool temperature continues to rise and is currently 135oF. Wind speed is 10 mph and wind is out of the south at 180 degrees.

4. Initiating Cue: With the information provided, declare the emergency action level, complete initial notifications and other required actions. Task is Time Critical

Start Time: End Time: Candidate:


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JPM BODY SHEET


Step 1 EPI-A1, Emergency Action Levels 5.1 Event Assessment and Event Classification 5.1 Classify the emergency as follows:

1. Using Initiating Condition Index (PNPP No. 8852, Attachment 1), identify the emergency by event category and determine the most appropriate Initiating Condition

2. Refer to Attachment 2 for the applicable Initiating Condition(s) to determine whether the criteria are met for the operating mode(s) listed.

3. Declare an emergency class when all the conditions listed in at least one EAL column have been met, and implement <EPI-A2>.

a. When several Initiating Conditions are met, declare the most severe emergency class.

Initiating Conditions Entry Criteria

BS1

Complete loss of functions needed to

achieve COLD SHUTDOWN

Applicable Modes:

RHR Loops A and B are NOT capable of lowering RPV temperature.

The plant is operating in the UNSAFE Region on the HCL figure.

1 2 3


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Classify Event as BS1.

Critical Step: Operator classifies event as BS1, 15 minutes to classify.

Instructor Cue: Notify the operator that time critical action starts after the first read of initial conditions and he is given initiating cue.

Notes: Based on conditions in Initiating Cue, BS-1 conditions are met.

Start Time ________ Classification Time __________ SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2

4. Complete the EVENT CLASSIFICATION CHECKLIST (PNPP No. 7983A), contained in <EPI-A2>.

Standard: Operator uses Event Classification Checklist to assist with required actions.

Instructor Cue: Give Operator E-Plan Packet, when he identifies where to obtain. I&C has been contacted and is en route.

Notes: Event Classification Checklist completed through line A.6. SAT ___ UNSAT ___

Comment(s):________________________________________________________________


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Step 3 EPI-A2, Emergency Actions Based On Event Classification Attachment 1 - Event Classification Checklist 4. Complete an Initial Notification form (PNPP No. 7794) and forward to communicators

within 10 minutes of decision to classify event

Critical Step: Initial Notification Completed within 15 minutes of classification. The following items are Critical

• Block 2 is checked “A Drill” • Block 3.a is checked for Site Area Emergency BS1. • Block 4 is completed with words similar to,” Complete loss of

function needed to achieve cold shutdown.” • Block 5.c checked. • Block 6.c checked.


Notes: Time Given to Communicator ________ The goal is to forward to communicators within 13 minutes.



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Step 4 6. Complete the Pager Messages form (PNPP No. 9100), approve, and forward to the SAS

within 10 minutes of decision to classify event or revise PARs.

Standard: Pager Message completed, Scenario ID No. 3



Comment(s):________________________________________________________________

Terminating Cue: Event Classified within 13 minutes and Initial Notification given to

communicator 5 minutes prior to notification due time. Evaluation Results: SAT_____ UNSAT_____ End Time:


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JPM CUE SHEET

INITIAL CONDITIONS:

• The unit was at 100%. • RHR Pump “A” is INOPERABLE and tagged out. • A Reactor scram occurred and all rods are full in. • An SRV is stuck open and Suppression Pool temperature is rising. • While placing RHR “B” into Suppression Pool Cooling, RHR B HX’S

BYPASS VALVE, 1E12 F048B, is full open and cannot be closed remotely or locally.

• Reactor pressure is 715 psig. • Suppression Pool level is 19.3 feet. • Suppression Pool temperature continues to rise and is currently 135oF. • Wind speed is 10 mph and wind is out of the south at 180 degrees.

INITIATING CUE: With the information provided, declare the emergency action level, complete initial notifications and other required actions. Task is Time Critical

JOB PERFORMANCE MEASURE SETUP SHEETSVI-F41-T3008, “Reactor Recirculation System Flow Data...

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