CALVERT C~LIFFS NUCLEAR POWER PLANT 2012 …NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERA TOR...
Transcript of CALVERT C~LIFFS NUCLEAR POWER PLANT 2012 …NUCLEAR POWER PLANT 2012 NRC INITIAL LICENSED OPERA TOR...
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APPLICANT: ___
CALVERT C~LIFFS
NUCLEAR POWER PLANT
2012 NRC
INITIAL LICENSED
OPERA TOR ]~XAM
JPM #: SRO-A~DMIN-1
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Appendix C Job Perfonnance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-I
Task Title: Detennine Status of Safety Functions for the FRP
Task Number: 201.078
KIA Reference: 2.1.20 - Ability to interpret and execute procedure steps (4.6, 4.6).
Method of testing:
Simulated Perfonnance: D Actual Performance: ~ Classroom: D Simulator: ~ Plant: D
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job perfonnance measure will be satisfied.
Initial Conditions:
1. Both Units were operating at 100% power
2. The OC DG is OOS for scheduled maintenance
3. AOP-2A was implemented for a SGTR and a Rapid downpower is commenced
4. When the reactor is tripped, lAW AOP-2A, the following complication(s) occur:
a. Oflsite Power is lost
b. The lA DG experiences a start failure
5. EOP-O has been completed
6. EOP-6 has been implemented
7. The affected S/G has been isolated
8. A fault occurs on 14 4KV Bus causing its loss
9. EOP-8 has just been implemented.
10. You are perfonning in the role ofthe STA
Initiating Cue:
The CRS has directed you to:
1. Determine status of safety functions per EOP-8, Step IV.E.
Determine the priority for implementation of the Safety Function Recovery Actions per EOP-8, Step IV.F.3. Are there any questions? You may begin.
Task Standard:
Candidate refers to the Resource Assessment Table and correctly determines the success path available to satisfy each safety function.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time:.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
EOP-8, Section VI, Resource Assessment Table
Completed EOP-O Safety Function Status Check
Completed EOP-6 Safety Function Status Check
General References:
Procedures and manuals normally available in the Control Room
Time critical task:
No
Validation Time:
15 minutes
Simulator Setup:
See next page
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Simulator Setup:
1. Reset to IC-24.
2. Perform switch check.
3. Place simulator in CONTINUE, advance charts and clear alarm display.
4. Place simulator in FREEZE.
5. Enter Malfunctions:
a. OC DG Start Failure, DG002_01 at time zero
b. lA DG Start Failure, DG002_02 at time zero
c. 11 SG Tube Rupture, ms002_01 at 1.0 with no ramp time at time zero
d. Loss of Off-Site Power, swyd002 on Event 1
e. IB DG Start Failure, dg001_02 on Event 2
6. Enter Panel Overrides
a. None
7. Enter Remote Functions I Administrative
a. Caution tag OC DG output bkr HS in PTL and red dot alarms.
b. Caution tag on OC DG start pushbuttons.
8. Drive simulator to desired condition:
a. Set simulator time to real time, then place simulator in CONTINUE.
b. Perform a rapid downpower and trip the n!actor per AOP-2A, Section VI.
c. Commensurate with the trip, insert Event 1, Loss of Off-Site Power
d. Complete the required actions ofEOP-O
e. Implement EOP-6 and proceed thru isolation of 11 S/G
f. Insert Event 2, lA DG Start Failure
__ g. Initiate AFW flow with 11 AFW Pump
9. Place simulator in FREEZE.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
TIME START:
CUE. Provide operator with a filled out copy of the EOP-O Safety Function Status as an aid in . determining correct priority for addressing Safety Functions.
o Identifies and locates EOP-8, Functional Recovery Same as element
Procedure, Section IV, Step IV.E.
o IV.E. - DETERMINE STATUS OF SAFETY FUNCTIONS (STA).
o IV.E.l - Identify success paths for ALL Safety
Functions PER Section VI., RESOURCE
ASSESSMENT TABLE.
o VI. - RESOURCE ASSESSMENT TABLE
Evaluates Reactivity Control Success Paths and chooses: RC-l, Met
Evaluates Vital Auxiliaries Success Paths and chooses: V A-3, Not Met
Evaluates RCS Pressure and Inventory Control Success Paths and chooses: PIC-4, Not Met
Evaluates Core and RCS Heat Removal Success Paths and chooses: HR-2, Not Met
Evaluates Containment Environment Success Paths and chooses: CE-l, Met
Evaluates Radiation Levels o VI.RLEC - Radiation Levels External to External to Containment Success
Containment Success Path Paths and chooses:
RLEC-2, Met
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Appendix C Job Performance Measure Fonn ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
Acknowledge report of recommended Success Paths
Reports results of Safety Function assessment to the CRS:
0 RC-l, Met
0 V A-3, Not Met
0 PIC-4, Not Met
0 HR-2, Not Met
0 CE-l, Met
0 RLEC-2, Met
o IV.F. - PERFORM RECOVERY ACTIONS
NOTE
Safety Functions are presented in order of importance. Selected success paths should be commenced in accordance with the Safety Function hierarchy.
Reports results of Safety Function priority assessment to the CRS:
o 1st priority - V A-3 o 2nd priority - PIC-4 o 3 rd priority - HR-2 o 4th priority - RLEC-2 o 5th priority - RC-l o 6th priority - CE-l
TERMINATING CUE: This JPM is complete when the selected success paths and their priorities have been continned with the CRS. No further actions are required. The evaluator is expected to end the JPM.
I TIME STOP: ___
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Verification of Completion
Job Performance Measure Number: SRO-ADMIN-l
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _________._______
Time to Complete:
Follow up Question: _________________________
Applicant Response: _________________________
Result: SAT ______ UNSAT
Examiner's Signature and Date: _______________________
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Appendix C Job Performance Measure Form ES-C-l Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
1. Both Units were operating at 100% power
2. The OC DG is OOS for scheduled maintenance
3. The IB DG is removed from service due to SRW Hx fouling (per AOP-7A, Att (1))
4. AOP-2A was implemented for a SGTR and a Rapid downpower is commenced
5. When the reactor is tripped, lAW AOP-2A, the following complication(s) occur:
a. Offsite Power is lost
b. The lA DG experiences a start failure
6. EOP-O has been completed
7. EOP-6 has been implemented
8. The affected S/G has been isolated
9. A fault occurs on 14 4KV Bus causing its loss
10. EOP-8 has just been implemented.
11. You are performing in the role of the ST A
Initiating Cue:
The CRS has directed you to:
1. Determine status of safety functions per EOP-8, Step rv.E. 2. Determine the priority for implementation of the Safety Function Recovery Actions per
EOP-8, Step IV.F.3.
3. Are there any questions? You may begin.
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EOP-O Rev 12/Unit 1 Page 24 of 27
VI. SAFETY FUNCTION STATUS CHECK
A. The STA (or person designated by the CRS) will perform the safety function status checks
on entry into this procedure.
B. Record value/status for all safety function parameters. Circle any value/status that does not
meet acceptance criteria.
C. Notify the Control Room Supervisor if any safety function acceptance criteria is not being
satisfied, promptly upon full completion of the safety function status check.
SAFETY PARAMETERS ACCEPTANCE CRITERIA REACTIVITY
CONTROL ACCEPTANCE
PARAMETERS VALUE/STATUSCRITERIA
a. WRNI lowering 5 X 10-3
b. SUR negative (-)1/3 dpm
Unable to NO more than ONE
determine due to c. CEA status CEA NOT fully
loss ofpowerinserted
effects
OR
RCS Boration in d. Boration status
progress
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EOP-O Rev 12/Unit 1 Page 25 of 27
VI. SAFETY FUNCTION STATUS CHECK
VITAL AUXILIARIES PARAMETERS
a. 4KV Vital buses 11 OR 14
b. 125V DC buses 11, 12, 21 and 22
c. 120V AC buses 11, 12, 13,14
d. lY09 or lYlO
RCS PRESSURE
AND
INVENTORY
PARAMETERS
a. Pressurizer Pressure
b. Pressurizer level
c. RCS subcooling
SAFETY FUNCTION ACCEPTANCE CRITERIA
ACCEPTANCE VALUE/STATUSCRITERIA
At least ONE energized 4KV Bus 11 energized
ALL greater than 105 volts
All I25V DC buses greater than 105V
At least THREE energized
All 120V AC Buses energized
At least ONE energized 1Y09 energized
SAFETY FUNCTION ACCEPTANCE CRITERIA
ACCEPTANCE VALUE/STATUS
CRITERIA
1850 PSIA to 1270 PSIA and 2300 PSIA slowly lowering
80 inches to empty
180 inches
21°F and slowly Greater than 30°F
nsmg
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EOP-O Rev 12/U nit 1 Page 26 of 27
VI. SAFETY FUNCTION STATUS CHECK
COREANDRCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT
REMOVAL ACCEPTANCE VALUE/STATUSPARAMETERS CRITERIA
a. RCS TCOLD 52YF to 535°F 532°F
b. THOT minus less than 10°F TcoLD Loop flT(s) = ~26°F
c. RCPs operating per lOR2 loop 0
d. S/G level (-)170 inches 11 S/G, (-)57 inches 11 OR 12 to (+)30 inches 12 S/G, (-)90 inches
CONTAINMENT _____S_A_F_E_T_Y_F_U_N_C__T_I_O_N_A_C_C_E_PT_A_N_C_E_C_R_I_T_E_R_I_A____
ENVIRONMENT ACCEPTANCEPARAMETERS VALUE/STATUSCRITERIA
a. Containment Pressure
less than 0.7 PSIG 0.1 PSIG & steady
b. Containment Temperature less than 120°F 100°F & steady
c. Containment Radiation Monitors
Alarm clear with NO unexplained rise
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EOP-O Rev 12/Unit 1 Page 27 of 27
VI. SAFETY FUNCTION STATUS CHECK
RADIATION LEVELS
EXTERNAL TO
CONTAINMENT
PARAMETERS
e. Noble Gas Monitor (1-RIC-5415)
f. Condenser Off-Gas RMS (1-RI-1752)
S/G BID RMS (l-RI-4014)
h. Main Vent Gaseous RMS (l-RI-5415)
SAFETY FUNCTION ACCEPTANCE CRITERIA
ACCEPTANCE CRITERIA
alarm clear with NO unexplained rise
alarm clear with NO unexplained rise
alarm clear with NO unexplained rise
alarm clear with NO unexplained rise
VALUE/STATUS
In alarm prior to loss of power
In alarm prior to loss of power
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EOP-6 Rev 17/Unit 1
Page 102 of 108
VI. SAFETY FUNCTION STATUS CHECK
A. The ST A (or person designated by the CRS) will perform the safety function status checks on entry into this procedure.
B. Record value/status for all safety function parameters. Circle any value/status that does not meet acceptance criteria.
C. Notify the Control Room Supervisor if any safety function acceptance criteria is not being satisfied, promptly upon full completion of the safety funchon status check.
SAFETY FUNCTION ACCEPTANCE CRITERIAREACTIVITY
CONTROL INTERMEDIATE FINAL
PARAMETERS CRITERIA CRITERIACHECK CHECK
..J less a. WRNI lowering than 10.4%
..J negativeb. SUR negative
or zero
NO more than NO more than c. CEA status ONECEANOT ONECEA
fully inserted NOT fully inserted
OR
greater than or greater than Boration status equal to 40 GPM 2300 PPM
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EOP-6 Rev 17/Unit 1
Page 103 of 108
VI. SAFETY FUNCTION STATUS CHECK
VITAL AUXILIARIES PARAMETERS
a. 4KV Vital buses 11 or 14
b. 125V DC buses 11, 12, 21 and 22
e. 120V AC buses 11, 12, 13,14
d. 1 Y09 or 1 Y 10
SAFETY FUNCTION ACCEPTANCE CRITERIA
CRITERIA INTERMEDIATE
CHECK CRITERIA
FINAL CHECK
At least ONE energized
At least ONE energized
ALL greater than 105 volts ALL greater
than 105 volts
at least THREE energized
at least THREE energized
At least ONE energized At least ONE
energized
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EOP-6 Rev 17/Unit 1
Page 104 of 108
VI. SAFETY FUNCTION STATUS CHECK
RCS PRESSURE
AND
INVENTORY
PARAMETERS
a. Pressurizer Pressure
b. Pressurizer level
c. RCS subcooling
d. Reactor Vessel Level
SAFETY FUNCTION ACCEPTANCE CRITERIA
INTERMEDIATE FINALCRITERIA CRITERIA
CHECK CHECK
Less than the less than the upper limits of upper limits of Att. (1) Att. (1)
Greater than 30 101 inches to inches 180 inches
OR
At least One Charging Pump operating and SIS injecting PER 101 inches to Atts. (10) and (11) 180 inches
less than 140°F
greater than greater than 25°F
25°F
OR
At least One ICharging Pump • greater than operating and SIS
2YFinjecting PER Atts. (10) and (11)
•
above the top core covered
of the hot leg
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EOP-6 Rev 17/Unit 1
Page 105 of 108
VI. SAFETY FUNCTION STATUS CHECK
CORE AND SAFETY FUNCTION ACCEPTANCE CRITERIA RCSHEAT
INTERMEDIATE FINALREMOVAL CRITERIA CRITERIACHECK CHECKPARAMETERS
a. CET less than less than 600°F Temperatures 600°Fl=
constant or constant or b. RCS TCOLD lowering loweringl= OR
c. Unaffected (-)170 inches to ( -)24 inches to S/G level (+)30 inches (+)30 inches l=
trending to ( -)24 inches to (+ )30 inches N/A N/AC
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EOP-6 Rev 17/Unit 1
Page 106 of 108
VI. SAFETY FUNCTION STATUS CHECK
SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT INTERMEDIATE FINAL
CRITERIA CRITERIAPARAMETERS CHECK CHECK
,j I
a. Containment less than 0.7 less than 0.7
Pressure PSIG PSIGI I I
N/A Ib. Containment constant or
Temperature (1) less than 15WF lowering
j •
NO NOc. Containment unexplained unexplainedRadiation nse riseMonitors (2) I
,jalarm clear
alarm clear I I
NOd. Containment
unexplained unexplainedSump level
rIse rise±CL NO (1) NOT available if 1Yl 0 is de~energized
(2) NOT applicable ifOOS due to loss of power
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EOP-6 Rev 17/Unit 1
Page 107 of 108
VI. SAFETY FUNCTION STATUS CHECK
RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS
EXTERNAL TO INTERMEDIATE FINALCRITERIA CRITERIACONTAINMENT CHECK CHECK
PARAMETERS
a. Noble Gas
Monitor
(l-RIC-5415) N/A N/A alarm clear
b. Condenser Off-
Gas RMS
(l-RI-1752)(l) N/A N/A alarm clear
c. S/G BID
RMS
(l-RI-4014)(1) N/A N/A alarm clear
d. Main Vent
Gaseous RMS
(l-RI-5415)(1) N/A N/A alarm clear
e. Affected S/G Less than 920 Less than 920 pressure PSIA PSIA=+±J=
(1) NOT applicable ifOOS due to loss of power
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APPLICANT: ___
CALVERT C~LIFFS
NUCLEAR POWER PLANT
2012 NRC
INITIAL LICENSED
OPERATOR I~XAM
JPM #: SRO-ADMIN-2
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-2
Task Title: Evaluate the need for plant cooldown.
Task Number: 201.005
KIA Reference: 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9,4.2)
Method of testing:
Simulated Performance: D Actual Performance: [2J
Classroom: [2J Simulator: D Plant:
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating
cues. When you complete the task successfully, the objective for this job performance measure
will be satisfied.
,-------------------------------_........_-------,
Initial Conditions:
1. Unit-l is in Mode 6 preparing to enter Mode 5
2. SMECO is unavailable due to maintenance.
3. 11 CST is empty for maintenance
4. Unit-2 is operating at 100% reactor power.
5. A loss of offsite power occurs at 0845.
6. The 1 A DO fails to start
7. 14 4kv Bus is deenergized due to a ground fault.
8. The OC DO is unavailable
9. The plant has been stabilized per EOP-7 with the following-parameters:
a. Unit-l RCS Temperature is 110" F and slowly rising.
b. Unit-2 RCS temperature is 532" F and steady.
c. 12 CST level is 24.5 feet
d. 21 CST level is 30 feet
10. You are performing the duties of an extra SRO.
Initiating Cue:
At 1045, the Unit-2 CRS requests you perform EOP-7, Step AC, EVALUATE THE NEED FOR PLANT COOLDOWN.
Task Standard:
The candidate will assess condensate inventory using EOP Att. (9) and determine there is
insufficient water to cooldown to < 3000 F, the plant must b(~ maintained in hot standby, and the
plant can be maintained in hot standby for approximately 76 hours. The evaluator is expected to
end the lPM.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
1. EOP-7, Station Blackout (Unit-2)
2. EOP Attachments (Unit-2)
General References:
Procedures and manuals normally available in the Control Room
Time critical task:
No
Validation Time:
25 minutes
Simulator Setup:
None
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
TIME START: ___
D Locates EOP-7, Step AC, Evaluate the Need for Plant Same as element
Cooldown.
D IV.AC.I. - WHEN the RCS parameters have been stabilized, THEN evaluate the need for a plant cooldown based on:
D Plant Status Candidate will determine Att (9) completion is required D Auxiliary systems availability
D Condensate inventory PER ATTACHMENT (9),
MAKEUP WATER REQUIRED FOR RCS
COOLDOWN
Locates UNIT-2 EOP ATTACHMENTS, Attachment (9), Same as element.
Makeup Water Required For RCS Cooldown
D 1. - Determine the amount of makeup water required to perform an ADV cooldown and a TBV cooldown, Same as element. based on the time after shutdown:
Candidate uses table "INVENTORY REQUIRED TO COOL DOWN TO 3000 F" to determine 614,531 gallons are required to cool the Unit down to 3000 F two hours following the shutdown.
Candidate enters uses table "Inventory Required to Cool Down to 3000 F" and determines 88,490 gallons are required to cool the Unit
D *l.b. - TBV cooldown and time after shutdown , down to 300 0 F two hours ,
following the shutdown. Candidate may NIA this step due to condenser unavailability.
D 2. Determine the amount of makeup water available in The candidate determines the tank the CSTs: levels from the initiating cue.
JKecords 21 CST level as 30 feet
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
Records 12 CST level as 24.5 feet
Records 11 CST level as 0 feet
o 2.d. - Determine the status of Unit-l (check one): Same as element. o 2.d.(1) Mode 1,2 or 3 and does NOT
require AFW operation. Determines step is NOT applicable
o 2.d.(2) __ Mode 1, 2 or 3 and does require AFW operation.
Determines step is NOT applicable
Determines step IS applicable based on stated conditions
NOTE: Calculated negative values should be entered as zero.
o 2.e. - Determine the amount ofmakeup water available to Unit 1 using one of the following
Same as element. formulas, based on the status checked in step 2.d above:
o 2.e.( 1) - IF step d.( 1) is checked, THEN correct Determines step is NOT applicableCST levels for usable volume:
o 2.e.(2) - IF step d.(2) is checked, THEN correct Determines step is NOT applicable
CST levels for usable volume:
o 2.e.(3) - IF step d.(3) is checked, THEN correct Determines step IS applicable
CST levels for usable volume:
Records 21 CST usable volume as: 27.25 feet
Records 12 CST usable volume as: 22 feet
Records 11 CST usable volume as: ofeet
Records total usable volume as: 49.25 feet
Performs calculation determining approximately 474,611 gallons of CST inventory are available
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
NOTE
The nominal capacity of a Well Water pump is 300 GPM. The nominal capacity of a
Demineralized Water Transfer pump is 300 GPM. The Fire System can fill the CST via fire
hoses at greater than 500 GPM.
CAUTION
The status of both units should be considered when evaluating a makeup source.
Candidate determines there is NOT 3. IF adequate inventory exists to perform cooldown, adequate inventory to perform a
THEN determine if an adequate makeup source exists cooldown. to maintain hot standby. Water required is 614,531,
inventory available is 474,611
The Shift Manager requests the candidate to determine how long hot standby canCUE:
be maintained with the current inventory. Supply examinee with Cue Sheet #2.
The candidate uses ATT (9), Makeup Water Required to Maintain Hot Standby.
If the chart is NOT interpolated, the value would be 72 hours of hot standby. If chart is interpolated, the value would be 76 ± 1 hours
Acceptable answer is 72 - 77 hours
Returns to EOP-7, Step AC.2.2 Same as element.
o IV.AC.2. - IF a plant cooldown is NOT desired, THEN perform the following: Same as element. Crew focus
would be on restoration of powero IV.AC.2.a. - Maintain stabilized plant conditions. and a makeup source
o IV.AC.2.b. - PROCEED to step AG.
TERMINATING CUE: This lPM is complete when it is determined there is NOT adequate inventory to perform a cooldown and how long hot standby can be maintained. No further actions are required. The evaluator is expected to end the lPM.
[iIME STOP: ___
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Appendix C Job Performance Measure Form Worksheet
Verification of Completion
Job Performance Measure Number: SRO-ADMIN-2
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _________________
Time to Complete:
Follow up Question: _________________________
Applicant Response: ________________________
Result: SAT ______ UNSAT ________
Examiner's Signature and Date: _____________________
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Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
EXAMINEE'S CUE SHEET #2
Initiating Cue:
Given the same initial conditions provided in Cue Sheet # 1, you have completed a detennination of whether or not adequate makeup water inventory exists to perfonn a cooldown.
The Shift Manager now requests you detennine how long hot standby can be maintained with the current makeup water inventory.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
EXAMINEE'S CUE SHEET #1
Initial Conditions:
1. Unit-I is in Mode 6 preparing to enter Mode 5
2. SMECO is unavailable due to maintenance.
3. 11 CST is empty for maintenance
4. Unit-2 is operating at 100% reactor power.
5. A loss of offsite power occurs at 0845.
6. The IA DG fails to start
7. 14 4kv Bus is deenergized due to a ground fault.
8. The OC DG is unavailable
9. The plant has been stabilized per EOP-7 with the following parameters:
a. Unit-l RCS Temperature is 110 0 F and slowly rising.
b. Unit-2 RCS temperature is 532 0 F and steady.
c. 12 CST level is 24.5 feet
d. 21 CST level is 30 feet
10. You are performing the duties of an extra SRO.
Initiating Cue:
At 1045, the Unit-2 CRS requests you to determine if adequate inventory exists to perform a cool down per EOP-7, Step IV.AC.l.
:
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APPLICANT: ___
CALVERT CLIFFS
NUCLEAR POWER PLANT
2012 NRC
INITIAL LICENSED
OPERATOR EXAM
JPM #: SRO-ADMIN-3
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I
Appendix C Job Performance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performanc€~ Measure No.: SRO-ADMIN-3
Task Title: Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Instrumentation
Task Number: 204.129
KIA Reference: 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications (3.9, 4.6)
Method of testing:
Simulated Performance: D Actual Performance: ~ Classroom: C8J Simulator: 0 Plant: D
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating
cues. When you complete the task successfully, the objective for this job performance measure
will be satisfied.
Initial Conditions:
1. Unit-l power was recently reduced to 70% power to facilitate repairs to 11 SGFP.
2. CEAs are currently inserted to 108 inches on Group 5.
3. Channel "A" LRNI Lower Sub-Channel is out of service and Channel "D" LRNI Upper Sub-Channel is out of service. Applicable T.S. LCO 3.3.1 conditions have been entered.
4. The plant computer has "crashed" and is inoperable.
5. DAS has been determined to be operable.
6. Last good value for FrT 1.66.
7. OPS CALC is not available.
8. You are performing the duties of an extra SRO.
9. LRNI Sub-Channel readings are as follows:
Channel Upper Lower
A 70.7 0
B 68.0 69.7
C 69.4 67.5
D 0 68.7
Initiating Cue:
AOP-7H, LOSS OF PLANT COMPUTER, has been implemented and the Shift Manager has
directed you to perform Section IV.E, to monitor Tq.
Task Standard:
. Calculate and determine whether or not Tq is in spec. Evaluates administrative requirements to I determine if any additional action is necessary.
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Appendix C Job Perfonnance MeasuH~ Fonn ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
1. AOP-7H, Loss of Plant Computer in Mode One or Two.
2. NEOP-30I, Operator Surveillance Procedure
3. T.S. 3.2.3 Total Integrated Radial Peaking Factor (FRT)
4. T.S. 3.2.4 Azimuthal Power Tilt (Tq)
1. Unit-I, Cycle 20, Core Operating Limits Report
General References:
1. AOP-7H, Loss of Plant Computer in Mode One or Two.
2. NEOP-30l, Operator Surveillance Procedure
3. Tech Specs
4. Unit-I, Cycle 20, Core Operating Limits Report
Time critical task:
No
Validation Time:
20 minutes
Simulator Setup:
None
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Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
I TIME START:
i CUE: The Shift Manager directs you to determine the Azimuthal Power Tilt (Tq) using the excore NIs per Section IV.E.
(J Locates AOP-7H, Section IV.E. - IF Greater than Same as element.
50% Rated Thennal Power, Monitor Tq.
AOP-7H, Section IV.E. - IF Greater than 50% Rated Thermal Power, Monitor Tq.
(J IV.E.1. - IF ALL four Linear Power Channels are I operable, THEN perfonn EITHER of the following Detennines Step is NIA to calculate upper and lower Tq:
NOTE
For the purposes of Tq monitoring, a total of 3 upper and 3 lower RPS power range detectors are required to be operable. The failed detectors can be on different channels.
(J IV.E.2. - IF ONLY three upper AND three lower
RPS power range detectors are operable, THEN Detennines Step is applicable
perfonn the following:
(J IV.E.2.a. - IF greater than 75% Rated Thennal Power, THEN reduce power to less than or equal Detennines Step is NIA to 75% Rated Thennal Power within 12 hours.
(J IV.E.2.b. - Perfonn either of the following to
calculate upper and lower Tq:
i
(J Calculate Tq using Opscalc function Tq Calculator.
(J Record the readings on ATTACHMENT Detennines Step is NIA(2), Tq CALCULATION USING
EXCORE DETECTORS
OR
(J Calculate Tq using the method in Records Readings on Att (2) ATTACHMENT (2), Tg CALCULATION
Perfonns calculations per Att (2) USING EXCORE DETECTORS. • Calculates Upper Tq .03070*
(J Record the readings on ATTACHMENT • Calculates Lower Tq .02561 * (2), Tq CALCULATION USING EXCORE DETECTORS * with a Tolerance of± .0006
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
0 IV.E.3. - IF less than three upper OR three lower RPS power range detectors are operable, THEN
Determines Step is NIAreduce power to less than or equal to 50% Rated
Thermal Power within four hours, AND exit Step E.
0 IV.E.4. - Ensure that Tq is within limits of LCO Candidate proceeds to NEOP-301,
3.2.4, as directed by NEOP-301, OPERATOR Section 6.6
SURVEILLANCE PROCEDURE.
NEOP·301, Section 6.6 Azimuthal Power Tilt (T q) Monitoring (MODE 1, >50% Power)
0 6.6.1. - IF incore monitoring ofTq is available, Determines step is N/A
THEN:
0 6.6.2. - IF incore monitoring ofTq is not available, Determines step is applicable THEN
0 6.6.2.1. - IF the DAS is unavailable ... Determines step is NIA
0 6.6.2.2. - IF the plant computer is unavailable,
THEN PERFORM the actions of IF GREATER
Determines step is applicable and in THAN 50% RATED THERMAL POWER,
progressMONITOR Tq for LOSS OF PLANT
COMPUTER in AOP-07H.
0 6.6.2.3 - IF incore monitoring is unavailable for Determines step is NIA I
any other reason
0 6.6.2.4. - PROCEED to Step 6.6.3. Determines step is applicable
0 6.6.3. - ENSURE that Tq is within limits PER LCO Determines step is applicable
3.2.4
0 6.6.3.1. - IF Azimuthal Power Tilt (Tq) is less
than or equal to 0.03, then the surveillance is Determines step is NIA
complete and satisfactory.
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Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
Detennines T.S. 3.2.4 limits have been exceeded.
• Detennines Tq must be restored to within limits within 4 hours.
OR
[J 6.6.3.2. - IF Azimuthal Power Tilt (Tq) is greater • Verify F/ is within the limit of than 0.03 but less than or equal to 0.10 THEN: LCO 3.2.3, "Total Integrated
Radial Peaking Factor" within 4 hours.
Per COLR Figure 3.2.3, verifies CEAs withdrawn to or above the Long Term Steady State Insertion Limits of Figure 3.1.6 (Not critical)
Acknowledge notification, as Reactor Engineering and the as-Operations, that CUE:
indicated T Q is greater than 0.03 but less than or equal to 0.10.
[J 6.6.3.2.a. - NOTIFY Reactor Engineering
and the as-Operations that indicated T q is
Same as element greater than 0.03 but less than or equal to 0.10.
Shift Manager directs documenting the Total Integrated Radial Peaking Factor (FRT) is CUE: within the limits ofTS 3.2.3, using Att (5) while Reactor Engineering fonnulates a
recovery plan
[J 6.6.3.2.b. - PERFORM EITHER of the
following: Completes Att (5) supplying the [J DETERMINE AND CORRECT (if following data:
possible) TQ within four hours so that Tq • Tq - .03070 (not critical) is less than or equal to 0.03. • FRT limit -1.74 ± .01
OR • FRT measured - 1.66 (not critical) FRT within limits - yes [J DETERMINE AND DOCUMENT on • Max allowable pwr - 98% ± 1%Attachment 5 within four hours AND at •
least once per subsequent eight hours that • Reactor power - 70% (not critical)the Total Integrated Radial Peaking Factor
(FRT) is within the limits ofTS 3.2.3.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
CUE: I Acknowledge request for an independent review of the information on Att. (5)
0 6.6.3.2.c. - INDEPENDENTLY REVIEW Requests independent review of the information on Attachment 5. completed Att (5)
0 6.6.3.2.d. - IF neither condition of 6.6.3.2.b
can be satisfied THEN REDUCE power to
Determines step is NIAless than or equal to 50% within the following
4 hours.
0 6.6.3.3. - IF Azimuthal Power Tilt (Tq) is greater Determines step is N/A
than 0.10 THEN:
AOP-7H, Section IV.E. - IF Greater than 50%. Rated Thermal Power, Monitor Tq.
I
0 IV.E.5. - Once every 12 hours, recalculate the Azimuthal power Tilt using the Excore Detectors Determines step is NIA at this time PER Step E, Page 10.
.
TERMINATING CUE: This JPM is complete when calculated azimuthal power tilt (Tq) is determined to be outside acceptable limits with T.S. components appropriately addressed and the NEOP-30l Attachment (5) completed. No further actions arie required.
ITIME STOP: ___
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Appendix C Job Perfoffi1ance Measure FOffi1 ES-C-l Worksheet
Verification of Completion
Job Perfoffi1ance Measure Number: SRO-ADMIN-3
Applicant:
NRC Examiner:
Date Perfoffi1ed:
Facility Evaluator:
Number of Attempts: __________________
Time to Complete:
Follow up Question: ____
Applicant Response: _________________________
Result: SAT ______ UNSAT _________
Examiner's Signature and Date: ______________________
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Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
1. Unit-1 power was recently reduced to 70% power to facilitate repairs to 11 SGFP.
2. CEAs are currently inserted to 108 inches on Group 5.
3. Channel "A" LRNI Lower Sub-Channel is out of service and Channel "D" LRNI Upper Sub-Channel is out of service. Applicable T.S. LCO 3.3.1 conditions have been entered.
4. The plant computer has "crashed" and is inoperable.
5. DAS has been detennined to be operable.
6. Last good value for F/ = 1.66
7. OPS CALC is not available
8. You are perfonning the duties of an extra SRO.
9. NI Readings are as follows:
Channel Upper Lower I IA 70.7 0 i
B 68.0 69.7
C 69.4 67.5 I
D 0 68.7
Initiating Cue:
AOP-7H, LOSS OF PLANT COMPUTER, has been impleme:nted and the Shift Manager has directed you to perfonn Section IV.E, to monitor Tq.
-
APPLICANT: ___
CALVERT CLIFFS
NUCLEAR POWER PLANT
2012 NRC
INITIAL LICENSED
OPERATOR EXAM
JPM #: SRO-ADMIN-4
-
--...--------------------------------------- Appendix C Job Perfonnance Measure Fonn ES-C-I
Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-4
Task Title: Respond to a contaminated injured person
Task Nnmber: 204.025, 204.098
2.3.14 - Knowledge of radiation or contamination hazards that may arise during KJA Reference:
normal, abnormal, or emergency conditions or activities. (3.4, 3.8)
Method of testing:
Simulated Performance: Actual Performance: I:8J
Classroom: I:8J Simulator: D Plant: D
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When
you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
1. Unit-l is operating at 100% power.
2. The FASW calls the Control Room on 911, and informs you of the following:
• A Chemistry Technician received serious steam bums while performing RCS sampling activities at the RCS Sample Sink.
• The sampling system has been stabilized and no radioactive releases are in progress.
• The Chemistry Technician is located on the 45' of the Unit-l Aux Buildingjust outside the elevator doors
• The Chemistry Technician is radioactively contaminated and requires transport to Calvert Memorial Hospital.
• He can be reached at 495-4586
Initiating Cue:
Determine and write down on the paper provided the following information for the event described in the Initial Conditions:
1. All onsite and offsite notifications required by the Control Room during and after the event. Include
any time limitations associated with the notification(s), if applicable.
2. All announcements that must be made during and after the event, including termination of the event.
Include personnel that must be dispatched by the Control Room to ensure the Chemistry Technician
receives prompt first aid and appropriate medical attention. For announcements that must be made,
include all information required in the announcement.
Task Standard:
identifies all required on site and offsite notifications and associated time limits. I I
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Appendix C Job Performance Measure Fonn ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
None
General References:
ERPIP 3.0, Attachment 15, Personnel Emergency
Time critical task:
No
Validation Time:
15 minutes
Simulator Setup:
None
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
TIME START: ___
EXAMINER NOTE
When the Candidate determines the need for any procedure, provide them with a copy. At your discretion you may have them describe how to obtain the current revision of the
procedure prior to handing them a copy.
I 0 Candidate performs the following:
0 Locates ERPIP 3.0, Attachment 15, Personnel i Same as element
Emergency
o 1. RECORD the following information:
No announcements, onsite o Caller's Name:
notifications or offsite notifications o Location of injured person:
requiredo Nature of injury:
o Phone number to call to reach the scene:
NOTE
If based on the report the injury is minor in nature (small cut with little bleeding, small contusion or minor sprain with person able to easily walk), then sounding the Emergency Alarm is
unwarranted.
o 2. IF initial assessment by the Control Room is that
sounding the Emergency Alarm is unwarranted, Determines step is NIA
THEN: ...
Announcements, onsite notifications or offsite notifications required and associated time limits are:
Announcement
"A personnel emergency exists on the 45' elevation of the Auxiliary Bldg outside the elevator doors." "First Aid Team and Radiation Protection Technician respond." (wording may be slightly different but must convey the same basic message)
Repeat twice (not critical)
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
No announcements, on site 4. CONFIRM and MONITOR response. notifications or offsite notifications
required
5. DETERMINE contamination and hospitalization Same as element
status.
o 5.a. IF the injured person is suspected to be contaminated, THEN HAVE an RPT determine AND report the person's contamination status. Contamination status provided by
o 5 .a.( 1) IF unknown whether the injured person . the F ASW in his initial report is contaminated or not, THEN TREAT as contaminated.
NOTE
First Aid Team Leader can directly communicate with offsite responding units on Radio Channel 1
Announcements, on site notifications or offsite notifications required and associated time limits are:
.Notification - Notify CAS/SAS to call for offsite assistance. Transport of a contaminated individual to CMH is required.
Announcements, onsite notifications or offsite notifications required and associated time limits are:
Notification - Notify CMH that one injured/contaminated person suffering steam burns will be transported to CMH
ETA not a critical task
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Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
o 6. CONTINUE to monitor the event and direct assistance to the scene as requested by the First Aid Team Leader.
o 7. WHEN notified by the First Aid Team Leader that the event may be tenninated, THEN ANNOUNCE a brief update on status of personnel emergency.
STANDARD
Announcements, onsite notifications or offsite notifications required and associated time limits are:
Notification - Notify RP supervision by activating ERONS.
Announcements, on site notifications or offsite notifications required and associated time limits are:
!~otification - An 8-hour ENS Report is required to the NRC for "Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment."
No announcements, onsite notifications or offsite notifications
required
Announcements, on site notifications or offsite notifications required and associated time limits are:
l\.nnouncement - Now secure from ]:>ersonnel Emergency, injured person is being transported to hospital (wording may be slightly different but must convey the same basic message)
Repeat twice (not critical)
TERMINATING CUE: The task is complete when the applicant has determined content for announcement notifying the Site that we are securing from the personnel emergency.
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Appendix C Job Performance Measure Form ES-C-I Worksheet
Verification of Completion
Job Performance Measure Number: SRO-ADMIN-4
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: ______________.
Time to Complete:
Follow up Question: ___________________________
Applicant Response: __________________________
Result: SAT ______ UNSAT _______
Examiner's Signature and Date: ___________.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
3. Unit-I is operating at 100% power.
4. The FASW calls the Control Room on 911, and informs you of the following:
• A Chemistry Technician received serious steam bums while performing RCS sampling activities at the RCS Sample Sink.
• The sampling system has been stabilized and no radioactive releases are in progress.
• The Chemistry Technician is located on the 45' of the Unit-l Aux Building just outside the elevator doors
• The Chemistry Technician is radioactively contaminated and requires transport to Calvert Memorial HospitaL
• He can be reached at 495-4586
Initiating Cue:
Determine and write down on the paper provided the following information for the event described in the Initial Conditions:
1. All onsite and offsite notifications required by the Control Room during and after the event. Include any time limitations associated with the notification(s), if applicable.
2. All announcements that must be made during and after the event, including termination of the event. Include personnel that must be dispatched by the Control Room to ensure the Chemistry Technician receives prompt first aid and appropriate medical attention. For announcements that must be made, include all information required in the I
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Appendix C Job Performance Measure Form ES-C-l Worksheet
CANDIDATE NAME:
List all onsite and offsite notifications required by the Control Room during and after the event. Include any time limitations associated with the notification( s), if applicable.
Describe all announcements that must be made and personnel that must be dispatched by the Control Room to ensure the Chemistry Technician receives prompt first aid and appropriate medical attention. For announcements that must be made, include all information required in the announcement.
-
APPLICANT: ___
CALVERT CJLIFFS
NUCLEAR POWER PLANT
2012 NRC
INITIAL LICENSED
OPERATOR EXAM
JPM #: SRO-A])MIN-5
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performanc,e Measure No.: SRO-ADMIN-5
Task Title: Determine Appropriate Emergency Response Actions
Task Number: 204.097
KIA Reference: 2.4.41 (2.9,4.6)
Method of testing:
Simulated Performance: D Actual Performance: ~
Classroom: ~ Simulator: D Plant: D
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
1. Unit-2 was at 100% power when an event occurred, causing a Reactor trip.
2. SIAS failed to automatically actuate and required manual actuation.
3. RCS subcooling is O°F.
4. Containment pressure was 30 PSIG and rising when it suddenly lowered to 1 PSIG.
5. Containment High Range Radiation Monitors are currently reading 4000 RlHr.
6. The Meteorological Data Screen (DRDT) indicates the following:
a. DIRlO 3090
b. DIR60 = 300°
7. You are performing the duties of the Shift Manager.
8. This JPM is TIME CRITICAL.
Initiating Cue:
You have been requested to determine appropriate Emergency Response Actions, per the ERPIP, based on the current plant conditions provided.
Task Standard:
Determines EAL classification, Protective Action Recommendations and completes the initial notification form within prescribed time limits.
i
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
1. ERPIP 3.0, "Immediate Actions"
2. ERPIP 3.0 Attachment 1, "EMERGENCY ACTION LEVEL (EAL) CRITERIA"
3. ERPIP 3.0 Attachment 2, "EMERGENCY CLASSIFICATION"
4. A blank copy ofERPIP 3.0, Attachment 3, "INITIAL NOTIFICATION FORM"
5. ERPIP 3.0 Attachment 4, "GENERAL EMERGENCY ACTIONS"
6. ERPIP 3.0 Attachment 5, "GENERAL EMERGENCY PROTECTIVE ACTION
RECOMMENDATIONS"
General References:
Procedures and manuals normally available in the Control Room
Time critical task:
Yes
Validation Time:
12 minutes
Simulator Setup:
None
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Appendix C Job Performance Measure Form ES-C-1 Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
EVALUATOR NOTE:
The "EAL CLOCK" starts after candidate reads "Initial Conditions" CUE sheet.
TIME START:
EAL CLOCK TIME START:
0 Identify and locate ERPIP 3.0 Same as element
0 Refers to Immediate Actions, identifies the category Determines A TT ACHMENT 2 is
from the listing and goes to the appropriate applicable.
Attachment.
ATTACHMENT 2, EMERGENCY CLASSIFICATION
0 A. - CLASSIFY the Event
A.I. - WHEN an event is in progress potentially requiring emergency response, THEN Determines step is applicable. CONDUCT the following actions in parallel:
· CUE: I The Unit-2 CRS will perform step A.I.a
0 A.l.a. - DETERMINE if existing conditions
warrant implementation of one of emergency
response attachments:
• Personnel Emergency, Att 15 • Fire,Att 16,17,18 • Radiological Event, Att 19 • Severe Weather, Att 20,21 The Unit-2 CRS will evaluate • Hazardous Material Release, Att 22 existing conditions to determine if • Containment Evacuation, Att 23 implementation of any of the listed
attachments is necessary• Security, Att 24 • Large Area Loss, Att 25
Large Steam Leak, Att 26 • • Extensive Damage Mitigation Guidelines,
Att27
• S/G Level Monitoring During Extensive
Damage Mitigation, Att 28 i
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Appendix C Job Performance Measure Form ES-C-I Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
o A.I.b. - EVALUATE the existing conditions against Attachment 1, Emergency Action Level (EAL) Criteria, to determine if an EAL threshold has been met.
STANDARD
Evaluates Attachment 1 and determines a GENERAL EMERGENCY classification is warranted, under EAL H.G.5.1.4, in the Fission Product Barrier Category, based on the loss of all 3
• fission product barriers.
Fuel Clad Barrier-Containment Radiation reading> 3500 remlhr
RCS Barrier- RCS subcooling <
25°F due to RCS leakage.
Containment Barrier-Rapid unexplained CNTMT pressure decrease following initial increase.
Inform candidate the Unit-2 CRS will implement emergency response attachments as CUE:
necessary
o B. - IMPLEMENT Emergency Response Actions o B.1. - IF existing conditions warrant
implementation of an emergency response attachment, in parallel, THEN GO TO that attachment AND begin response actions.
o B.2. - IF an EAL condition is met, THEN OBTAIN an Attachment 3, Initial Notification Form, AND GO TO the appropriate EAL Declaration attachment:
o General Emergency Actions, Att 4 o Site Area Emergency Actions, Att 9 o Alert Actions, Att 11 o Unusual Event Actions, Att 13
ERPIP 3.0, ATTACHMENT 4, General Emergency Actions
o A.I - COMPLETE Attachment 3, Initial Notification Form.
The Unit-2 CRS will implement emergency response attachments as necessary
Determines from previous evaluation that an EAL is satisfied and obtains an Initial Notification form. Identifies General Emergency as the appropriate declaration. Goes to Attachment 4, General Emergency Actions.
Refers to Attachment Initial iC:ltlon
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Appendix C Job Performance Measure Fonn ES-C-I Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
ERPIP 3.0, ATTACHMENT 3, Initial Notification Form
NOTE TO EVALUATOR
Page 2 ofA TT ACHMENT 3 contains instructions for completing the form and should be referred to as the applicant comple:tes page 1.
Checks "is" a drill
Checks "Unit-2"
Checks "General Emergency"
Enters "H.G.S.l.4"
Checks "Yes"
o Complete Item A.S.a Checks "No"
o Complete Item ASb Checks "Airborne"
NOTE TO EVALUATOR
Attachment 5, GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS, should be used to determine the correct Protective Action Recommendations
Checks box for "A.6.e", "Evacuate PAZ 1 & 3 unless conditions make evacuation dangerous, notify the public in PAZ 1 & 3 to take KI,
;C~:§~~lij'!'i'Y;;"1 shelter remainder of the 1 0 mile EPZ."
When a Peer Check of the EAL call is requested, acknowledge the request.
o Requests a Peer Check upon completion of items A.I. Same as element
thru A.6.
NOTE TO EVALUATOR
EAL Clock should be stopped when candidate completes item A.7 (date and time of EAL Declaration)
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Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
Completes A.7 only after items 1 6 are completed, and a Peer check has been obtained.
::s 15 minutes
Selects blocks for:
o Drill o General Emergency
o B. - Complete Section B, Personnel Notification o StaffNornlal Emergency Determination. Response Facilities (May staff
alternate ERF s based on radiological hazard)
o Prints name and signs (only after Section A is completed)
ERPIP 3.0, ATTACHMENT 4, General Emergency Actions
Acknowledge request(s) to recall the Emergency Response Organization according to CUE: Step B.l of this attachment and to transmit the Initial Notification Form to the offsite
agencies according to Step C.I of this attachment.
Same as element
(within 15 minutes ofEAL Clock
Time Stop)
Same as element
(within 15 minutes ofEAL Clock
Time Stop)
TERMINATING CUE: This JPM is complete when an EAL classification is determined based on given plant conditions, the initial notification form is completed and the CR Communicator has been requested to recall the ERO and to notify offsite agencies. No further actions are required. The evaluator is expected to end the JPM.
TIME STOP: ___
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Verification of Completilon
Job Performance Measure Number: SRO-ADMIN-5
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result: D SAT D UNSAT
Examiner's Signature and Date:
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Appendix C Job Performance Measure Form ES-C-l Worksheet
APPLICANT'S CUE SHEET
Initial Conditions:
1. Unit-2 was at 100% power when an event occurred, causing a Reactor trip.
2. SIAS failed to automatically actuate and required manual actuation.
3. RCS subcooling is O°F.
4. Containment pressure was 30 PSIG and rising when it suddenly lowered to 1 PSIG.
5. Containment High Range Radiation Monitors are: currently reading 4000 RlHr.
6. The Meteorological Data Screen (DRDT) indicates the following:
a. DIRIO = 309°
b. DIR60 = 300°
7. You are performing the duties of the Shift Manager.
8. This JPM is TIME CRITICAL.
Initiating Cue:
You have been requested to determine appropriate Emergency Response Actions per the ERPIP based on the current plant conditions provided.
-
..
APPLICANT: ___
CALVERT CJLIFFS
NUCLEAR POWI~R PLANT
2012 NRC
INITIAL LICENSED
OPERATOR I~XAM
JPM #: RO-ADMIN-1
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-1
Task Title: Respond to a complete loss of SDC (Estimate Time to Boiling & Core Uncovery)
Task Number: 202.023
KIA Reference: 2.1.20 (4.6, 4.6)
Method of testing:
Simulated Performance: 0 Actual Performance: ~ Classroom: ~ Simulator: 0 Plant: 0
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective: for this job performance measure will be satisfied.
Initial Conditions:
1. Unit-l RCS is drained to 38.6 feet in preparation for Vacuum Fill of the RCS.
2. RCS temperature is 100° F.
3. The reactor was shut down 25 days ago after an extended period of full power operation.
4. Refueling operations have been completed. 88 fresh fuel assemblies were loaded in the core.
5. A loss of shutdown cooling has occurred.
6. You are performing the duties of an extra CRO.
Initiating Cue:
The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, Step IV.B.S.
Task Standard:
Determines Time to Boil and Time to Core Uncovery.
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Appendix C Job Performance Measure Form ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
AOP-3B, Abnormal Shutdown Cooling Conditions
General References:
AOP-3B, Abnormal Shutdown Cooling Conditions
Time critical task:
No
Validation Time:
20 minutes
Simulator Setup:
None
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Appendix C Job Performance Measure Form ES-C-1 Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
Locates AOP-3B, Step IV.B.5 Same as element
o IV.B.S. - IF the RCS in NOT capable of being pressurized, THEN estimate the time to boiling AND core uncovery using A TTACHMENT(ll), Same as element CALCULATION OF TIME TO BOIL OR CORE UNCOVERY.
o Locates AOP-3B, Attachment (11) Same as element
Note to evaluator:
Completion of this JPM requires interpreting graphs lthat have the potential to induce minor variations in calculated results. For that reason, calculated results are given an
"acceptable" band.
o 1. - Calculate Time To Boil
Determines Attachment (8), Time o l.a. - Determine the Time To Boil at 24 hours after to Start Boiling (TTB) After
shutdown from the appropriate figure, based on LOSDC 24 Hours After Shutdown, RCS level and RCS temperature: is the correct Attachment for stated
• conditions
U sing Attachment (8), determines TTB @ 24 hrs is approximately 13.5 minutes
Using A TT (10), determines multiplier of3.39
Determines post refueling multiplier is applicable. Uses ATT (10), to determine the Post Refueling multiplier is 1.36
PerfOlIDs TTB calculation
13.5 X 3.39 X 1.36 62.2 mins
(Answers in the range of 58 to 63.5 minutes are acceptable)
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Appendix C Job Performance Measure Form ES-C-I Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
CUE: Acknowledge request for independent verification of the TTB calculation
o I.d. - Independently verify the calculation. . Requests independent verification
o 2. - Calculate Time To Core Uncovery:
Determines Attachment(12), Time to Core Uncovery After LOSDC 24 o 2.a. - Determine the Time To Core Uncovery at 24 Hours After Shutdown No Nozzle
hours after shutdown from the appropriate figure, Dams, No Injection, No Cold Leg
based on RCS level and RCS temperature: Hole, is the correct Attaclunent for stated conditions
Using Att (12), determines Time To Core Uncovery @ 24 hrs is approximately 129 minutes (127 133 mins)
Using ATTACHMENT (10), determines multiplier of 3.39
Determines post refueling multiplier is applicable. Uses Att (10), to determine the Post Refueling multiplier is 1.36
Performs Time To Core Uncovery calculation
129 X 3.39 X 1.36 = 595 mins or
9 Hours 55 Minutes
(Answers in the range of 585 Mins
to 613 Mins are acceptable)
Acknowledge request for independent veritication of the TTB calculation
o 2.d. - Independently verify the calculation. Requests independent verification
ITERMINATING CUE: This JPM is complete when the ~OP-3B, Att (11), Calculation of Time i iLto Boil or Core Uncovery, worksheet has been completed. No further actions are required. ..____________________________________________________________________~
STOP:
-
---------
-------------------------
Appendix C Job Performance Measure Form ES-C-l Worksheet
Verification of Completion
Job Performance Measure Number: RO-ADMIN-l
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: ______________
Time to Complete:
Follow up Question: _______________.
Applicant Response: _________________________
Result: SAT ______ UNSAT
Examiner's Signature and Date:
-
Appendix C Job Performance Measure Form ES-C-I Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
1. Unit-l RCS is drained to 38.6 feet in preparation for Vacuum Fill of the RCS.
2. RCS temperature is 100° F.
3. The reactor was shut down 2S days ago after an extended period of full power operation.
4. Refueling operations have been completed. 88 fresh fuel assemblies were loaded in the core.
5. A loss of shutdown cooling has occurred.
6. You are performing the duties ofan extra CRO.
Initiating Cue:
The Shift Manager directs you to estimate the time to boiling AND core uncovery per AOP-3B, I Step IV.B.S.
-
APPLICANT: ___
CALVERT C~LIFFS
NUCLEAR POWI~R PLANT
2012 NRIC
INITIAL LICE~NSED
OPERA TOR I~XAM
JPM #: RO-AI)MIN-2
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-2
Task Title: Calculate BAST volume required to raise RWT to refueling boron concentration
Task Number: 041.011 - Borate the RWT
KIA Reference: 2.1.25 (3.9,4.2)
Method of testing:
Simulated Performance: D Actual Performance: [ZJ Classroom: [ZJ Simulator: D Plant:
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
1. Unit-2 RWT parameters are:
a. Boron Concentration = 2550 PPM
b. Temperature = 80· F
c. Level = 460 inches
2. 21 & 22 BAST Boron Concentrations are 7.25 %
3. CEAs will NOT be credited
4. You are performing the duties of the Unit-2 RO
Initiating Cue:
In preparation for the upcoming Unit-2 Refueling Outage, the CRS directs you to calculate BAST volume required to raise the RWT boron concentration to 25 PPM above the Refueling Boron Concentration per OI-2B, Step 6.7
-
Appendix C Job Performance Measure Form ES-C-1 Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
1. OI-2B, CVCS Boration, Dilution and Makeup Operations
2. NEOP-23, Technical Data Book (Unit 2)
3. U-2 Technical Specifications Core Operating Limits Report
4. Calculator
General References:
Procedures and manuals normally available in the control room
Time critical task:
No
Validation Time:
15 minutes
Simulator Setup:
None
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
TIME START: ___
o Locates NEOP-23, Figure 2-11-A-6 or Unit-2 Core Operating Limits Report for Cycle 19 (3.9.1)
6.7.B.2. - DETERNIINE the volume (gallons) of boric acid needed to achieve the desired Refueling Water Tank boron concentration by using one of the following:
CUE: The Ops Calc Program is ,not available
OOps Cales Program - R WT Boration under the BORIC ACID MENU
o The following formula: (842.15) (LlB) (L+ 18)
STANDARD
Same as element
Determines required Refueling Boron Concentration is ~ 2634
PPM for the
Same as element
Same as element.
Calculation ([2634 + 25] - 2550)
should yield a LlB of 109 PPM
Determines manual calculation must be performed
Determines following values for input to manual calculation:
• LlB = 109 PPM • L = 460 inches
• CB 12676 PPM
• I 2550 PPM • VRWT = 0.01607
(from Table 1)
• V I40 0.01629 ft3/lb
Determines volume of Boric Acid required is: 4456 ± 1 (4455 to 4457
-
I
Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
CUE: I Acknowledge request for independent verification of the calculation
o 6.7 .B.3. - INDEPENDENTLY VERIFY the proper Requests an independent volume of boric acid for the desired R WT boron verification of the calculation be concentration. [80270] performed
TERMINATING CUE: This JPM is complete when the proper volume of boric acid to raise the RWT boron concentration to the desired value has been determined. No further actions are required.
ISTUl": ___
-
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
Verification of Completion
Job Perfonnance Measure Number: RO-ADMIN-2
Applicant:
NRC Examiner:
Date Perfonned:
Facility Evaluator:
Number of Attempts: _____________.
Time to Complete:
Follow up Question: _-'--___________.
Applicant Response: _____________
Result: SAT ______ UNSAT _______
Examiner's Signature and Date: __________.__________
-
,
Appendix C Job Performance Measure Form ES-C-l Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
5. Unit-2 RWT parameters are:
a. Boron Concentration 2550 PPM
b. Temperature = 80° F
c. Level 460 inches
6. 21 & 22 BAST Boron Concentrations are 7.25 %
7. CEAs will NOT be credited
8. You are performing the duties of the Unit-2 RO
Initiating Cue:
In preparation for the upcoming Unit-2 Refueling Outage, the CRS directs you to calculate BAST volume required to raise the R WT boron concentration to 25 PPM above the Refueling
i Boron Concentration per OI-2B, Step 6.7
-
APPLICANT: ___
CALVERT CLIFFS
NUCLEAR POWE~R PLANT
2012 NRC
INITIAL LICENSED
OPERATOR EXAM
JPM #: RO-ADMIN-3
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-3
Determine protective clothing requirements and dose limits associated with Task Title:
performance of a task in the RCA
Task Number: 204.138
KIA Reference: 2.3.7 - Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5, 3.6)
Method of testing:
Simulated Performance: Actual Performance: IZl
Classroom: [gJ Simulator: D Plant:
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
1. Both Units are at 100% power.
2. Spent Fuel Pool Cooling is being aligned to provide cooling using 12 SFP Clg Pp - 12 SFP Cooler - Suction from 21 SFP and discharging to 11 SFP.
Initiating Cue:
You have been directed to throttle 12 SFP PP Disch, O-SFP-l 07, two turns open and then stand by to slowly open 12 SFP PP Disch, 0-SFP-107.
State the radiological requirements for entering this area. Include in your discussion:
1. Expected radiological protective clothing for valve operation
2. Highest radiation level in the work area
3. Expected dose for this assignment (assuming a ten minute job duration)
4. Dose rate alarm
5. Low dose waiting area
Task Standard:
Determine radiological conditions for personnel exposure:
-
Appendix C Job Perfonnance Measure Fonn ES-C-1 Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
1. Survey Map for the affected area 2. RWP-2, "Operations Activities, including Fuel Shuffle, in Non-High Radiation Areas
(Low Risk)"
General References:
RP-1-100, Radiation Protection
Time critical task:
No
Validation Time:
10 minutes
Simulator Setup:
None
-
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
TIME START: ___
Once candidate detennines the need for a survey map and an SWP, provide them with CUE:
the Survey Map and a copy of R WP 2
o Candidate perfonns the following:
Detennines RWP 2, Task 2 o Locates and reviews Survey Map and RWP. requirements are applicable
Candidate states partial anti-Cs (gloves and booties) or full anti-Cs.
Detennines that highest radiation level in the area is 60 mRlhr at the north end of 12 SFP Clg Pp
Detennines that expected dose in 10 minutes is 116 * 25mRlhr = 4.2 ± 0.1 mR
Detennines from R WP that dose rate alarm will be set at 80 mRlhr.
Identifies from R WP room low dose waiting area is by the room door, or identifies lowest general area is by the door (.4 mRlhr), or states would wait outside of the room in the hallway.
TERMINATING CUE: The task is complete when the applicant has provided requested radiological infonnation.
-
------- ------
Appendix C Job Performance Measure Form ES-C-l Worksheet
Verification of Completion
Job Performance Measure Number: RO-ADMIN-3
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: ____________
Time to Complete:
Follow up Question: _______________________"__
Applicant Response: _____________
Result: SAT UNSAT
Examiner's Signature and Date: _________.
-
i
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
1. Both Units are at 100% power.
2. Spent Fuel Pool Cooling is being aligned to provide cooling using 12 SFP Clg Pp 12 SFP Cooler- Suction from 21 SFP and discharging to 11 SFP.
Initiating Cue:
You have been directed to throttle 12 SFP PP Disch, 0-SFP-107, two turns open and then stand
by to slowly open 12 SFP PP Disch, 0-SFP-I07.
State the radiological requirements for entering this area. Include in your discussion:
1. Expected radiological protective clothing for valve operation
2. Highest radiation level in the work area
3. Expected dose for this assignment (assuming a ten minute job duration)
4. Dose rate alarm
5. Low dose waiting area .
-
APPLICANT: ___
CALVERT CLIFFS
NUCLEAR POWER PLANT
2012 NR~C
INITIAL LICENSED
OPERATOR EXAM
JPM #: RO-ADMIN-4
-
Appendix C Job Performance Measure Form ES-C-I Worksheet
Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: RO-ADMIN-4
Perform an Independent Assessment of an Event Using the EOP-O DiagnosticTask Title:
Flowchart and Recommend the Correct Recovery Procedure
Task Number: 204.l24
KIA Reference: 2.4.21 (4.0,4.6)
Method of testing:
Simulated Perfoffilance: D Actual Performance: IS] Classroom: D Simulator: IS] Plant:
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objectiv(;~ for this job performance measure will be satisfied.
Initial Conditions:
1. A Reactor Trip and Safety Injection has occurred on Unit-I.
2. EOP-O is in progress.
3. You are the extra CRO performing the duties of the interim STA.
Initiating Cue:
The Shift Manager directs you to perform the Safety Function Status Check(s) and determine the proper course of action using EOP-O, Post Trip Immediate Actions, Sections V and VI.
Task Standard:
Use plant parameters & the EOP-O Diagnostic Flowchart to Select the Appropriate Recovery Procedure.
L _____________________________________________________________________~
-
Appendix C Job Perfonnance Measure Form ES-C-l Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted tllme..
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
EOP-O, Post Trip Immediate Actions
General References:
EOP-O, Post Trip Immediate Actions
Time critical task:
No
Validation Time:
10 minutes
Simulator Setup:
1. Reset to IC-24, Both Units at 100% power.
Insert Malfunctions, Remotes, Overrides:
a. ms003_0l, MS-MS-4043 (11 MSIV) at 90% open at time zero.
__ b. msOll_Ol, 11 SG Steam Line Rupture outside CNTMT with a value of75% at time zero.
__ 3. Place Simulator in RUN and complete the following:
a. When reactor trips, perfonn immediate and alternate actions ofEOP-O (as required) for HR and PIC safety functions.
4. Place Simulator in FREEZE.
__ 5. Acknowledge all panel and plant computer alanns.
6. Select "Hom ON" for annunciators and "Clock" for time.
-
Appendix C Job Perfonnance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
TIME START: ___
• 0 Locate EOP-O Diagnostic Flowchart.
VI. SAFETY FUNCTION STATUS CHECK
o Reactivity Control Safety Function.
o Vital Auxiliaries Safety Function.
o Containment Environment Safety Function.
o Radiation Levels External to Containment Safety Function.
STANDARD
Same as element
Completes SFSC for RC. Determines RC Safety Function met.
Completes SFSC for V A. Detennines VA Safety Function met.
Completes SFSC for PIC. Detennines PIC Safety Function not met due to low Pressurizer pressure and Pressurizer level.
Completes SFSC for HR. Detennines HR Safety Function not met due to low T COLD.
Completes SFSC for CEo Detennines CE Safety Function is met.
Completes SFSC for RLEC. Detennines RLEC Safety Function met.
CUE: Acknowledges report out on status of Safety Functions
o results of SFSC to CRS
Reports RCS Pressure and Inventory Control Safety Function is not met due to low Pressurizer pressure and level, and Heat Removal Safety Function is not met due to low
-
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
CUE: I Post-trip immediate actions have been completed
V. DIAGNOSTIC FLOWCHART
0 REACTIVITY SAFETY FUNCTION MET?
i
I
0
0
VITAL AUXILIARIES SAFETY FUNCTION MET?
RCS PRESS/INV SAFETY FUNCTION MET?
I 0 EITHER S/G PRESSURE LESS THAN 800 PSIA?
0 RCS SUB COOLING LESS THAN 30° F?
I
I
0 CORE/RCS HEAT REMOVAL SAFETY FUNCTION MET?
o AT LEAST ONE S/G HAS FEED FLOW?
I
I
0 ANY RCPs TRIPPED DUE TO TRIP STRATEGY?
0 S/G B/D OR COND OFF-GAS RMS ALARMS OR RISE?
STANDARD
Selects "YES" flowpath. Proceeds
to "VITAL AUXILIARIES
SAFETY FUNCTION MET?"
Selects "YES" flowpath. Proceeds
to "RCS PRESSIINV SAFETY
FUNCTION MET?"
Selects "NO" flowpath. Proceeds to
"EITHER S/G PRESSURE LESS
THAN 800 PSIA?"
Selects "YES" flowpath. Proceeds
to "RCS SUBCOOLING LESS
THAN 30° F?"
Selects "NO" flowpath. Consider
EOP-4 (ESDE). Proceeds to
"CORE/RCS HEAT REMOV AL
SAFETY FUNCTION MET?"
Selects "NO" flowpath. Proceeds
to "AT LEAST ONE S/G HAS
FEED FLOW?"
Selects "YES". Proceeds to "ANY
RCPs TRIPPED DUE TO TRIP
STRATEGY?"
Selects "YES". Proceeds to "S/G
B/D OR COND OFF-GAS RMS
ALARMS OR RISE?"
Selects "NO" flowpath. Proceeds
to "RCS SUB COOLING LESS
THAN 30° F"?
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
ORCS SUB COOLING LESS THAN
30° F?
o CONTAINMENT ENVIRONMENT SAFETY FUNCTION MET?
o RADIATION LEVELS EXTERNAL TO CONTAINMENT SAFETY FUNCTION MET?
o ALL SAFETY FUNCTIONS MET?
o SINGLE EVENT DIAGNOSIS POSSIBLE?
STANDARD
Selects "NO" tlowpath. Consider
EOP-4 (ESDE). Proceeds to
"CONTAINMENT
ENVIRONMENT SAFETY
FUNCTION MET?"
Selects "YES" tlowpath. Proceeds
to "RADIATION LEVELS
EXTERNAL TO CONTAINMENT
SAFETY FUNCTION MET?"
Selects "YES" flowpath. Proceeds
to "ALL SAFETY FUNCTIONS
MET?"
Selects "NO" tlowpath. Proceeds to
"SINGLE EVENT DIAGNOSIS
POSSIBLE?"
Selects "YES" tlowpath". Proceeds
to "IMPLEMENT THE
APPROPRIATE EOP".
Recommends implementation of
EOP-4, EXCESS STEAM
DEMAND EVENT.
TERMINATING CUE: This JPM is complete when EOP-4, Excess Steam Demand Event, is recommended. No further actions are required.
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
Verification of Completion
Job Performance Measure Number: RO-ADMIN-4
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _________________
Time to Complete:
Follow up Question: ____________
Applicant Response: ____________
Result: SAT ______ UNSAT _______
Examiner's Signature and Date: ----------~------------
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Appendix C Job Performance Measure Form ES-C-l Worksheet
EXAMINEE'S CUE SHEET
Initial Conditions:
1. A Reactor Trip and Safety Injection have occurred on Unit-I.
2. EOP-O is in progress.
3. You are the extra CRO performing the duties of the interim STA.
Initiating Cue:
The Shift Manager directs you to perform the Safety Function Status Check(s) and determine the proper course of action using EOP-O, Post Trip Immediate Actions, Sections V and VI.
-
APPLICANT: ___
CALVERT CLIFFS
NUCLEAR POWER PLANT
2012 NRC
INITIAL LICE,NSED
OPERATOR EXAM
JPM #: SIM-1
-
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet
Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-l
Task Title: Respond to a loss of Shutdown Cooling V\ith the RCS open (Alt Path)
Task Number: 202.024
KIA Reference: 025AA207 (3.4, 3.7)
Method of testing:
Simulated Performance: D Actual Perforrnance: [gJ Classroom: D Simulator: [gJ Plant: D
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating
cues. When you complete the task successfully, the objective for this job perfonnance measure
will be satisfied.
Initial Conditions:
1. Unit-l is in Mode 5 for maintenance with the PZR manway removed.
2. The RCS is being maintained at approximately 42.7 feet.
3. SDC is aligned for service and RCS temperature is 1000 F.
4. The Reactor has been shut down for 10 days.
5. Time-To-Boil is approximately 38 minutes
6. The "12 LPSI PP SUCT PRESS LO" annunciator is in alann.
7. You are perfonning the duties of the Unit 1 CRO.
Initiating Cue:
The CRS has directed you to respond to these conditions using the appropriate procedure(s).
Task Standard:
I Restore Shutdown Cooling in accordance with AOP-3B, Abnormal Shutdown Cooling
-
- - --------.. Appendix C Job Performance Measure Form ES-C-l
Worksheet
Evaluation Criteria:
1. All critical steps completed (denoted by shading).
2. All sequential steps completed in order.
3. All time-critical steps completed within allotted time.
4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
1. AOP-3B, Abnormal Shutdown Cooling Conditions
2. lC09-ALM, ESFAS 12 Alarm Manual
General References:
1. Procedures and manuals normally available in the Control Room
Time critical task:
No
Validation Time:
25 minutes
Simulator Setup:
1. Reset the simulator IC-3 (Shutdown, RX Vessel level- 42.7 feet)
__ 2. Refueling cart available, connected for service, and SDC flow alarm setpoints set at 2900 (low flow) and 3100 GPM (high flow).
3. Ensure 12 LPSI pump is running and 11 LPSI is in PTL
4. Place the following keys in their respective keyswitches:
__ a. SDC Return Header MOV keys, 29 & 30
__ b. LPSI Pp RAS Override keys, 38 & 39
__ c. MPT Protection keys 47 & 48
5. Set up conditions for LPSI cavitation indications
a. Place the simulator in "Run"
b. Use the keyswitch for 1-SI-651-MOV to position it to 20% open
c. Run Simulator until "LPSI PUMP SUCTION PRESS LO" alarm is received.
6. Place the Simulator in FREEZE
__ 7. Bring candidate into the simulator, brief the initial conditions.
8. Place the Simulator in RUN when the candidate is ready.
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
Applicant should observe fluctuations in motor amps, discharge pressure and pump CUE: discharge flow. When applicant notes off-normal indications, inform applicant, as the
ABO, that excessive noise is corning from the area of 12 LPSI pump.
a Locates 1 C09-ALM. Same as element
a Investigates cause of alarm using guidance provided by lC09-ALM for Window H-28 "12 LPSI SUCT PRESS LO". Recommends
Same as element
implementing AOP-3B.
CUE: Once the RO has recommended AOP-3B be implemented, direct him, as the SRO, to implement section IV.A.4 of AOP-3B
EXAMINER's NOTE
Once applicant has located the correct section of the AOP, then give them a working copy of the
procedure section.
o Locates AOP-3B, Section IV.A.4 Same as element
a IV.A:4:2!:IF'a LPSI~PPis determined to be cavitating/gas bOmld by considering the following:
a FluctUations in!motor amps ;dFluc~uations i~ di~charge pressure Determines step is applicable.
Monitors 12 LPSI pump indications D-FIK~~tions in pump discharge flow
Determines that indications are a Excessfve 'PiurlP noise consistent with cavitation [j '~LPSFPUMP SUCTION PRESS LO" alarm
aCtuation :f THEN complete the following actions:
a IV.A.4.a. - IF the RCS is in reduced inventory, Determines step is Not Applicable
THEN perform the following actions:
CUE: Report RCS level is 42.7' and steady
o IV.A.4.a.(1) -IF ReS level is less than 37.6 feet, OR 1L£4138 is being used, THEN verify flow is less than or equal to 1800 gpm.
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP)
0 IV.A.4.a.(2) - IF RCS level is greater than 37.6 feet, THEN verify t10w is less than or equal to 3000 gpm.
0 IV.A.4.a.(3) - IF the appropriate SDC Flow is Restored AND LPSI PP cavitation/gas binding stops, THEN IMPLEMENT the appropriate Operating Procedure.
~" :.'i~~~' O· IV.A{'t.b. - Stop the operating LPSI PP(s)
0 IV.A.4.c. - Place BOTH LPSI PP handswitches in PULL TO LOCK
CAUTION
STANDARD
elem
Determines step is Not Applicable
element I
Same as element I
Isolation of the LPSI PP suction flow path can cause pump damage if the LPSI PPs are allowed to operate.
0 IV.A.S. - Check that the SDC HDR RETURN ISOL valves are open
0 1-S1-651-MOV
0 1-S1-652-MOV
0 IV.A.S.I. - IF ANY of the SDC HDRRETURN ISOL valves are open: valves are NOT fully open, THEN complete the following:
0 IV.A.S.I.a. - Stop the operating LPSI PP(s).
0 IV.A.S.1.b. - Place BOTH LPSI PP handswitches in PULL TO LOCK.
0 IV.A.S.l.c. - Initiate Aux Spray as necessary PER Step C.S.b.1, to maintain RCS
pressure less than 260 PSIA.
Determines that 1-S1-651-MOV is
NOT fully open
Same as element
Determines step is Not Applicable
Determines step is Not Applicable
Determines step is Not Applicable
I
-
Appendix C Job Performance Measure Form ES-C-l Worksheet
ELEMENT (shaded + * = CRITICAL STEP) STANDARD
When the candidate attempts to open I-SI-651 from the control room, it opens.
CUE:
When requested, ABO reports that I-SI -651-MOV is opening.
i 0 I . O5.I.d. -Attempt to open the affected
·S HOR RETURN ISOL valve(s) from the
/(;ontr01 Room:
Same as element r::J Fsl=651-Mbv
'.' r::J -652-MOV
r::J IV.AS.l.e. - IF BOTH SDC HDR RETURN
ISOL valves are open, THEN attempt to
Observes that both valves are open restore SDC PER ATTACHMENT (3),
and refers to attachment 3 RETURNING SHUTDOWN COOLING TO
SERVICE.
r::J Locates AOP-3B, Attachment (3) Same as element ~~_ ....---____ __________L_____
EXAMINER's NOTE:
When the applicant has located Atl. (3), then give him a working copy ofAtt. (3)
~.. --------------------.-.-----------------~
r::J 1. - Ensure RCS pressure is less than 260 PSIA Same as element
r::J 2. - Ensure RCS temperature is less than 300°F. Same as element
! r::J 3. - Ensure the SDC HDR RETURN ISOL valves are open:
Same as element r::J I-SI-651-MOV
r::J 1-SI-652-MOV
CUE: When asked: I-SI-444 and I-SI