Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML13227A127
Person / Time
Site:	Hope Creek
Issue date:	08/12/2013
From:	Todd Fish; Operations Branch I
To:	; Public Service Enterprise Group
	Jackson D
Shared Package
ML13077A118	List: IR 05000354/2013301; ML13108A195; ML13227A102; ML13227A107; ML13227A117; ML13227A127; ML13227A207; ML13267A380; ML13267A389; ML13267A415; ML13267A422; ML14010A064; ML14070A491; ML14070A492;
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JOB PERFORMANCE MEASURE S¥06M{ecirculation ll'~tn Scoop Tube Positioner Lock-up Operation

&AlfiiiSP.BB03E

~TERNATE PATH:D APPLICABILITY:

XSIIA D D D D BB\IE:..OPED BY:

Instructor DllliEiliEWED BY:

Operations Representative DXni!ROVED BY:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-1 REV: 01 SYSTEM: Reactor Recirculation TASK NUMBER: 2020080101 TASK: Perform Scoop Tube Positioner Lock-up Operation ALTERNATE PATH: w KIA NUMBER:

IMPORTANCE FACTOR:

202002 A2.05 3.1 3.1 APPLICABILITY: RO SRO EoD Ro[K] STAD sRo[K]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.RPV-0001, Rev 12 HC.OP-SO.BB-0002, Rev 78 TOOLS, EQUIPMENT AND PROCEDURES: Annotated copy of HC.SO.BB-0002.

ESTIMATED COMPLETION TIME: 25 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 13

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation TASK NUMBER: 2020080101 INITIAL CONDITIONS:

1. The plant was at 80% Reactor Power with power ascension in progress.

2. The SPRI guidance is valid.

3. A control signal failure caused the 'A' Reactor Recirc Pump Motor/Generator Scoop Tube to lock-up.

4. The 'A' Reactor Recirc pump was placed in Scoop Tube Positioner Lockup Operation lAW HC.OP-SO.BB-0002.

5. I&C has repaired the control signal failure.

6. An NCO is stationed at the 'A' Reactor Recirc Pump Motor/Generator Scoop Tube Positioner.

7. Manual adjustment of the 'A' Reactor Recirc Scoop Tube has been terminated.

8. The 'A' Reactor Recirc Scoop Tube Positioner Power Switch is ON.

INITIATING CUE:

Reset the Scoop Tube lockup on the 'A' Reactor Recirc pump.

Page 3 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up_Qperation

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.9.1 ENSURE all prerequisites have been Operator ensures prerequisites are satisfied lAW Section 2.9. satisfied.

5.9.1 Page 4 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.9.4 Using Attachment 3, Operator determines the desired

DETERMINE the desired SIC-R621 A SPEED DEMAND to be SIC-621A(B) SPEED DEMAND 58-62% lAW Attachment 3.

for the actual SPEED indicated on SIC-621A(B). Examiner Note: The target SPEED DEMAND is 60%. Some leeway has been added for meter readability and the potential interpolation of Attachment 3 data.

5.9.5 PRESS SIC-R621A(B) SPD CONT Operator presses the SIC-R621A

INCREASE OR DECREASE LOOP A SPD INCR and/or DECR pb pushbutton as necessary to obtain the until SIC-R621A SPEED DEMND #

desired SIC-621 A( B) SPEED matches the SPEED DEMAND from DEMAND from Step 5.9.4. Step 5.9.4.

Examiner Note: .+/-. 2% of the operator determined desired value is acceptable.

For example, if the operator determined 52% was desired, 50-54% would be acceptable.

5.9.6 PRESS SCOOP TUBE TRIP RESET Operator presses the Pump A TRIPS

ANDENSURESCOOPTUBELOC~ RESET PB.

UP light extinguishes. #

Operator observes that the SCOOP TUBE LOCK-UP light is extinguished.

Operator observes 'A' Recirc Pump speed and Reactor power rising.

HC.OP-AB.RPV-0001 Single Reactor Recirc Pump runaway. . ...

Page 5 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluation) 1 PRESS the SCOOP TUBE TRIP Operator presses the Pump A SCOOP

Pushbutton for the affected Recirc TUBE TRIP pushbutton.

Pump Controller. #

Examiner Note: The Scoop Tube may have already tripped due to control signal failure high. If the Scoop Tube is already tripped, it is not critical to push the SCOOP TUBE TRIP pushbutton.

2 PLACE BOTH Recirc Pump individual Operator observes the SIC-R621 A controllers in MANUAL. MAN AND SIC-R621 B MAN is illuminated and AUTO is extinguished.

Examiner Note: Since SIC-R621A and B are already in Manual, it is not critical to press the MAN pushbuttons.

3 REDUCE the NON-affected Reactor Operator presses the SIC-R621 B * !

Recirc Pump Speed to Reduce Power LOOP B SPD DECR pb until reactor to Pre-Transient value. power is:::; 80%. #

Page 6 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, !

THEN RECORD the STOP time.

(It is not necessary to observe the operator take actions for the resulting I Recirc Pump vibration alarms, take local control of the scoop tube, or evaluate Tech Specs.)

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 7 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-1 TASK: Perform Scoop Tube Positioner Lock-up Operation TASK NUMBER: 2020080101 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 8 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant was at 80% Reactor Power with power ascension in progress.

2. The SPRI guidance is valid.

3. A control signal failure caused the 'A' Reactor Recirc Pump Motor/Generator Scoop Tube to lock-up.

4. The 'A' Reactor Recirc pump was placed in Scoop Tube Positioner Lockup Operation lAW HC.OP-SO.BB-0002.

5. I&C has repaired the control signal failure.

6. An NCO is stationed at the 'A' Reactor Recirc Pump Motor/Generator Scoop Tube Positioner.

7. Manual adjustment of the 'A' Reactor Recirc Scoop Tube has been terminated.

8. The 'A' Reactor Recirc Scoop Tube Positioner Power Switch is ON.

INITIATING CUE:

Reset the Scoop Tube lockup on the 'A' Reactor Recirc pump.

Page 9 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I. C.

I Initial INITIALIZE the simulator to 80% power, MOL.

0 REDUCE Reactor Recirc pump speeds to 60% (It is critical that 'A' Recirc pump speed is 60%).

0 INSERT 98 rods to 00.

PRESS the REACTOR RECIRCULATION PUMP A TRIPS SCOOP TUBE TRIP pushbutton.

ENSURE SIC-R621 A AND SIC-R621 B are in Manual.

REDUCE SIC-R621A Demand Output by 4% AND allow SIC-R621A SPEED DEMAND to saturate low.

ENSURE SIC-R620 MAST CONT OUTPUT A SELECT is selected.

REMOVE Crossflow from service by toggling Remote Function PP04 to Not Applied.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

!Initial Description INITIAL a copy of HC.OP-SO.BB-0002 Section 5.5 for the 'A' Reactor Recirc Pump.

COMPLETE Simulator Ready-for-Training/Examination Checklist.

ENSURE Data Collection is trending the following parameters:

APRM Power Channel A EVENT TRIGGERS:

Initial ET# Description EVENT ACTION: rr:k5(1) >= 1.0 II 'A' Recirc Scoop Tube Trip Reset 1 COMMAND:

PURPOSE: Triggers 'A' Recirc Runaway EVENT ACTION:

2 COMMAND:

PURPOSE:

Page 10 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger lnit Val Final Val RR08A 'A' Recirc Pump Runaway --- --- ET-1 --- ---

REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val 1/0 OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger lnitVal Final Val Page 11 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-1 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-1 REV#: 01 TASK: Perform Scoop Tube Positioner Lock-up Operation

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6 .. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Core Spray TASK: Manually Start the Core Spray System TASK NUMBER: 2090030101 JPM NUMBER: 2013 NRC S-2 REV#: 1 SAP BET: NOH05JPBE05E ALTERNATE PATH: ITJ APPLICABILITY:

EO D RO 00 STA D SRO 00 DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-2 REV: 1 SYSTEM: Core Spray TASK NUMBER: 2090030101 TASK: Manually Start the Core Spray System ALTERNATE PATH: [TI KIA NUMBER: _ _2_09_0_0_1_A_4_.0_1_ _

IMPORTANCE FACTOR: 3.8 3.7 APPLICABILITY: RO SRO EO D RO [KJ STA D SRO [KJ EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.ZZ-0001 Attachment 5 Rev. 25 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 7 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 15

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System TASK NUMBER: 2090030101 INITIAL CONDITIONS:

1. The plant has experienced a loss of all offsite power coincident with a small break LOCA.

2. A and C Emergency Diesel Generators have failed to start.

3. HPCI has just tripped.

4. Reactor pressure is approximately 500 psig and lowering.

5. Reactor level is approximately -70 inches and lowering.

INITIATING CUE:

Restore reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop. The simulator is in FREEZE until you are ready to begin.

Page 3 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains/locates procedure Operator obtains the correct procedure.

HC.OP-AB.ZZ-0001, Attachment 5.

1.0 IF an Initiation Signal is present, Operator determines that an Initiation THEN PERFORM the following: Signal is present based on overhead annunciators B3-A1/A2/A3/A4, CORE SPRAY PUMP AUTO START are in aiarm.

1.0.A. ENSURE B Core Spray Pump is Operator observes the B Core Spray RUNNING. Pump is not running.

Operator depresses the BP206 START

push button.

Page 4 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator observes that B Core Spray Pump is running.

1.0.8. ENSURE D Core Spray Pump is Operator observes the D Core Spray RUNNING. Pump is not running.

Operator depresses the DP206 START

push button.

Operator observes that D Core Spray Pump is running.

1.0.C. ENSURE HV-F015B is CLOSED. Operator observes that HV-F015B is CLOSED.

1.0.D. ENSURE HV-F004B is OPEN. Operator observes that HV-F004B is OPEN.

Page 5 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluation) 1.0.E. WHEN REACTOR PRESSURE is Operator observes Reactor Pressure.

< 461 psig, ENSURE HV-F005B is OPEN.

Operator observes that HV-F005B did not open with Reactor pressure below 461 psig.

1.0.F. PERFORM the following as necessary to control Reactor Level:

1.0.F. PRESS HV-F005B AUTO OPEN Operator depresses the HV-F005B 1 OVRD. AUTO OPEN OVRD pb.

Operator observes that HV-F005B AUTO OPEN OVRD illuminates.

1.0.F. CYCLE HV-F005B as necessary to Operator depresses the HV-F005B

2 control Reactor Level. OPEN pb.

Operator observes the HV-F005B red OPEN light illuminates and the green CLSD light extinguishes.

Page 6 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

{*Denotes a Critical Step) COMMENTS STEP

ELEMENT {#Denotes a Sequential Step) EVAL {Required for UNSAT NO.

STANDARD # S/U evaluation) 1.0.G. WHEN flow is> 775 gpm, ENSURE Operator observes Core Spray System HV-F031 B is CLOSED. B flow on FI-R601 B to be >775 gpm.

Examiner Note: HV-F031 has failed Operator observes HV-F031 B is open.

to auto close.

Operator depresses the HV-F031 B CLOSE pb.

Operator observes the HV-F031 B green CLSD light illuminates and the red OPEN light extinguishes.

Page 7 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator restores reactor level to RPV Level 2 to Level 8 band with 8 Core Spray Loop.

Page 8 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-2 TASK: Manually Start the Core Spray System TASK NUMBER: 2090030101 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced a loss of all offsite power coincident with a small break LOCA.

2. A and C Emergency Diesel Generators have failed to start.

3. HPCI has just tripped.

4. Reactor pressure is approximately 500 psig and lowering.

5. Reactor level is approximately -70 inches and lowering.

INITIATING CUE:

Restore reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop. The simulator is in FREEZE until you are ready to begin.

Page 10 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I. C.

Initial Insert below listed malfunctions.

Take simulator out of freeze.

Place Mode Switch in Shutdown.

Inhibit ADS.

Let vessel water level drop to approximately -70 inches.

Reduce reactor pressure to approximately 500 psig.

Freeze the simulator.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET#

Event code: ZDCS31 CB >=1.0 4

Description:

HV-F031 B Close PB pressed II Deletes stuck open min-flow valve.

Event code:

Description:

Event code:

Description:

Page 11 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL}

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None None Insert malfunction DG02A Diesel generator A failure None None Insert malfunction DG02C Diesel generator C failure None None Insert malfunction HP03 HPCI turbine trip None None Insert malfunction CS03B Core spray HV-F005B fail to auto open None None Insert malfunction CS04B Core spray pumpS fail to auto start None None Insert malfunction CS04D Core spray pump D fail to auto start None None Insert malfunction EG12 on event 1 Loss of all off site power Insert malfunction RR31 A 1 to Recirc loop A small break [V] (10%-60 None None 10.00000 on event 2 gpm, 100%-600 gpm)

Insert malfunction RR31A2 to 0 on Recirc loop A large break [V] (10%-6000 None None event 2 gpm, 100%-60000 gpm)

Insert malfunction MS01 to 9.00000 on None None Steam line break in drywell event 3 REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote RH19B to FAIL_CLOSE RH19 HV-F017B RHR INJ VALVE None None Insert remote RH19D to FAIL_CLOSE RH19 HV-F017D RHR INJ VALVE Page 12 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

OVERRIDE SCHEDULE:

Initial @Time Event Action Description Insert override 8S29_B_LO to Off on None None HV-F031 B CLOSED (LO) event 4 Insert override 8S29_C_LO to On on None None HV-F031 B OPEN (LO) event4 Page 13 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-2 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-2 REV#: 01 TASK: Manually Start the Core Spray System

1. Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is _:::3.0 (LOR) or ,:::2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk(*). Sequence

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc TASK NUMBER: 2060180201 JPM NUMBER: 2013 NRC S-3 REV#: 1 SAP BET: NOH05JPBJ06E ALTERNATE PATH: D APPLICABILITY:

EoD RO [KJ STA D SRO [KJ DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-3 REV: 1 SYSTEM: High Pressure Coolant Injection TASK NUMBER: 2060180201 TASK: Place HPCI In Full Flow Recirc ALTERNATEPATH: c==J ~ANUMBER: ____2_06_0_0_0_A_4_.0_6___

IMPORTANCE FACTOR: 4.3 4.3 APPLICABILITY: RO SRO EoD Ro[XJ STAD sRo[XJ EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.ZZ-0001 Rev 25 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - -N/A ----

Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc TASK NUMBER: 2060180201 INITIAL CONDITIONS:

1. The Reactor has scrammed due to a spurious Group 1 isolation.

2. All control rods are full in.

3. RCIC was manually initiated and is injecting to the RPV.

4. Reactor water level is approximately -15 inches and slowly rising.

5. Reactor pressure is being controlled with Lo-Lo Set.

6. RHR loop B is in suppression pool cooling.

7. Another operator is taking the HC.OP-DL.ZZ-0026, Attachment 3.m, Suppression Chamber Average Water Temp 5 Minute Log.

INITIATING CUE:

Place HPCI into the Full Flow Test Mode and initiate a plant cooldown with a target pressure band of 500 to 700 psig.

Page 3 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 11 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U eval**-4-=--

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.ZZ-0001 Attachment 6.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 1.0.

1.0 IF HPCI is NOT in the Injection mode of operation PERFORM the following: N/A 1.0.A ENSURE OP216 VAC TK VACUUM Operator presses the OP216 START STAR Y N PUMP is RUNNING. pb.

Operator observes the red RUNNING light illuminates.

Page 4 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 11 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK Place HPCI In Full Flow Recirc

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.8 ENSURE HV-F059 is OPEN. Operator presses the HV-F059 OPEN

STARY N pb.

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

1.0.C ENSURE HPCI AND RCIC Suctions are Operator observes the HPCI HV-F004 lined up to the CST. OPEN light is illuminated and green CLSD light is extinguished.

Operator observes the RCIC HV-F01 0 OPEN light is illuminated and green CLSD light is extinguished.

1.0.0 PRESS HV-F008 INCR PB for== 20 Operator presses HV-F008 INCR pb for

STARY N seconds. approximately 20 seconds. #

Operator observes the HV-F008 OPEN light illuminates.

Page 5 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 11 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: High Pressure Coolant Injection TASK: Place HPCIIn Full Flow Recirc

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati 1.0.E ADJUST FIC-R600 HPCI FLOW setpoint Operator presses the LOWER

STAR Y N to 1000 gpm. SETPOINT pb on the FIC-R600 #

controller until the pointer is on 1000 gpm.

1.0.F I SIMULTANEOUSLY PERFORM the following: N/A 1.0.F. START AUXILIARY OIL PUMP Operator presses the AUXILIARY OIL

1 PUMP OP213 START pb. #

Operator observes the red RUNNING light illuminates.

1.0.F. PRESS FD-HV-F001 OPEN Pushbutton Operator presses the HV-F001 OPEN

2 pb. #

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

Page 6 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 11 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: High Pressure Coolant Injection TASK* Place HPCI In Full Flow Recirc STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.G IMMEDIATELY OPEN AP-HV-F011. Operator presses the AP-HV-F011

OPEN pb. #

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

1.0.H WHEN Discharge Pressure turns Operator observes HPCI Pump STAR Y N ADJUST FIC-R600 setpoint to 3000 gpm. Discharge Pressure on PI-R601-E41 (red) indicator rises and lowers.

Operator presses the RAISE

SETPOINT or LOWER SETPOINT pbs as necessary to obtain a flow setpoint of 3000 gpm.

I I ---- -- --- - - -

Page 7 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 11 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: High Pressure Coolant Injection TASK: Place HPCIIn Full Flow Recirc

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio 1.0.1 THROTTLE HV-F008 AND ADJUST FIC- Operator presses the HV-F008 INCR or STAR Y N R600 setpoint, as necessary, up to and DECR pbs and/or RAISE SETPOINT or including full flow rate, to control HPCI LOWER SETPOINT pbs as necessary pump parameters/reactor pressure. to adjust pump parameters.

Operator observes reactor pressure lowering.

CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator places HPCI in Full Flow Test at approximately rated flow.

Page 8 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: BJ006 TASK: Place HPCIIn Full Flow Recirc TASK NUMBER: 2060180201 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Reactor has scrammed due to a spurious Group 1 isolation.

2. All control rods are full in.

3. RCIC was manually initiated and is injecting to the RPV.

4. Reactor water level is approximately -15 inches and slowly rising.

5. Reactor pressure is being controlled with Lo-Lo Set.

6. RHR loop B is in suppression pool cooling.

7. Another operator is taking the HC.OP-DL.ZZ-0026, Attachment 3.m, Suppression Chamber Average Water Temp 5 Minute Log.

INITIATING CUE:

Place HPCI into the Full Flow Test Mode and initiate a plant cooldown with a target pressure band of 500 to 700 psig.

Page 10 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I. C.

INITIALIZE the simulator to 100% power, MOL.

Place Mode Switch to SID.

Stabilize RPV level at approximately 30 inches with RFPs. Do NOT allow water lvl to drop to lvl 2.

_ _ _ Arm and depress channels A and D NSSSS, then disarm. (Simulates spurious Group 1 isolation)

_ _ _ Manually initiate RCIC, runback flow controller setpoint to maintain RPV level at approximately 32 inches.

_ _ _ Place "B" RHR in Suppression Pool Cooling.

Freeze simulator.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

!tnitial I Description ENSURE Mode Switch key is removed.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE:

Initial ET# Description 1

Event code: I

Description:

Page 11 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial Description Delay Ramp Trigger lnit Val Final Val REMOTE SCHEDULE:

Initial Description Delay Ramp Trigger Init Val Final Val 1/0 OVERRIDE SCHEDULE:

Initial Description Delay Ramp Trigger Init Val Final Val Page 12 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-3 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-3 REV#: 1 TASK: Place HPCIIn Full Flow Recirc

1. Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is ~3.0 (LOR) or ~2.5 (IL T) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 JPM NUMBER: 2013 NRC S-4 REV#: 1 SAP BET: NOH05JPBC15E ALTERNATE PATH: 0 APPLICABILITY:

EoD RO 0 STA D SRO 0 DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-4 REV: 1 SYSTEM: Residual Heat Removal TASK NUMBER: 2050120101 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop ALTERNATE PATH:[!] KIA NUMBER: 205000 A4.03 IMPORTANCE FACTOR: 3.6 3.5 APPLICABILITY: RO SRO EoD Ro[]J STAD sRo[]J EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-SO.BC-0002 Rev. 28 TOOLS, EQUIPMENT AND PROCEDURES: None.

ESTIMATED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 16

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 INITIAL CONDITIONS:

1. The plant is in OPCON 4.

2. The reactor has been shutdown for 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .

3. 'B' RHR pump has been in shutdown cooling at 10,000 gpm for several hours.

4. RCS temperature is 100 degF.

5. A SACS and SSW loops are aligned to support the evolution.

6. BC-HV-FOO?A and BC-HV-F027A have been tagged closed to support the evolution.

7. Flush of A RHR Loop is not required.

8. Field operators have been briefed and are standing by on location.

INIIATING CUE:

You are an extra NCO.

Transfer RHR Shutdown Cooling to the A RHR loop.

HC.OP-SO.BC-0002 is complete up to step 5.3.5.

The required shutdown cooling flow for the 'A' RHR pump is between 9500 -10,000 gpm.

Page 3 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluati CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains procedure HC.OP-SO.BC-0002 Operator obtains the correct procedure.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE !E excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are N/A satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.3.5.

Page 4 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop STEP (*Denotes a Critical Step) COMMENTS ELEMENT NO. (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluatio 5.3.5. SECURE the inservice Shutdown N/A Cooling Loop as follows:

5.3.5. I ENSURE 1-BC-V262 (1-BC-V212), I Operator contacts Equipment Operator A ECCS Jockey Pmp D(C) DISCH to and directs opening 1-BC-V262.

RHR Loop B(A) is LOCKED OPEN (local), AND INITIAL Attachment 1.

The valve is in the position CUE 1 I N/A requested.

NOTE I Operator reads NOTE.

Steps 5.3.5.8 through 5.3.5.C should be performed in rapid succession.

5.3.5. CLOSE BC-HV-F015B(A) RHR LOOP Operator presses and holds the BC- I

B B(A) RET TO RECIRC AND INITIAL HV-F0158 RHR LOOP 8 RET TO Attachment 1. RECIRC CLSD pb.

Page 5 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.5. WHEN BC-HV-F015B(A) RHR LOOP Operator observes the BC-HV-F015B c B(A) RET TO RECIRC is fully closed, RHR LOOP B RET TO RECIRC CLSD THEN, IMMEDIATELY STOP light illuminated and OPEN is B(A)P202 RHR PUMP. extinguished.

Operator presses BP202 RHR PUMP

STOP pb.

~--

Page 6 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluation) 5.3.5. CLOSE BC-HV-F006B(A) RHR PMP Operator presses the BC-HV-F006B D B(A) SUCT FROM RECIRC AND RHR PMP B(A) SUCT FROM RECIRC INITIAL Attachment 1. CLSD pb.

Operator observes the BC-HV-F0068 I I

RHR PMP B(A) SUCT FROM RECIRC CLSD light illuminated and OPEN is extinguished.

5.3.6. ENSURE SACS is in service to the Operator observes the HV-2512A RHR Heat Exchanger for the RHR OPEN light illuminated and CLSD light loop to be placed in service lAW extinguished.

HC.OP-SO.EG-0001 (Q).

Operator observes RHR A HX SACS Flow approximately 9000 gpm.

Page 7 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step}

COMMENTS STEP.

ELEMENT (#Denotes a Sequential Step} EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation}

CAUTION Operator reads CAUTION.

Manual OR automatic opening of BC-HV-F007A(B) RHR PMP A(B)

MIN FLOW MOV will drain Reactor Vessel to Suppression Pool.

If BC-HV-F015 A(B) RHR LOOP A(B) RET TO RECIRC does NOT open immediately to establish flow, then the RHR pump should be secured.

BC-HV-F027 A( B) RHR LOOP A( B)

SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR pump is in shutdown cooling.

I Page 8 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step) COMMENTS STEP

I ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) I 5.3.7. START RHR PUMP A(B)P202 AND Operator presses the AP202 START

IMMEDIATELY THROTTLE OPEN pb.

BG-HV-F015A(B) RHR LOOP A(B)

RET TO REGIRG LOOP UNTIL Fl-R603A(B) OR FR-R608A(B)- GRIDS A3137(A3139), LOOP A(B) FLOW indicates ::::: 3000 gpm.

Operator observes the AP202 START light illuminated and STOP light extinguishes.

Examiner Note: F015A will fail Operator immediately presses and closed and not establish flow. holds the BG-HV-F015A RHR LOOP A Operator should secure the pump. RET TO REGIRC LOOP OPEN pb.

Operator observes the GLSD light remains illuminated.

Operator observes the FI-R603A OR FR-R608A- GRIDS A3137, LOOP A FLOW indicates 0 gpm.

Page 9 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati Operator determines CAUTION applies.

Operator presses AP202 STOP pb.

CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Operator lines up and starts A RHR pump N/A TASK STANDARD: in Shutdown Cooling. When the F015A fails to open, the operator stops the A RHR pump.

Page 10 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-4 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 11 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is in OPCON 4.

2. The reactor has been shutdown for 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .

3. 'B' RHR pump has been in shutdown cooling at 10,000 gpm for several hours.

4. RCS temperature is 100 degF.

5. A SACS and SSW loops are aligned to support the evolution.

6. BC-HV-FOO?A and BC-HV-F027A have been tagged closed to support the evolution.

7. Flush of A RHR Loop is not required.

8. Field operators have been briefed and are standing by on location.

INITIATING CUE:

You are an extra NCO.

Transfer RHR Shutdown Cooling to the A RHR loop.

HC.OP-SO.BC-0002 is complete up to step 5.3.5.

The required shutdown cooling flow for the 'A' RHR pump is between 9500-10,000 gpm.

Page 12 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I. C.

INITIALIZE the simulator to an OPCON 4 IC with 'B' RHR in Shutdown Cooling at 10,000 gpm and an RCS temp of=100 degF.

OPEN BC-HV-F007B breaker OPEN BC-HV-F027B breaker ENSURE BC-HV-F003A is closed.

ENSURE BC-HV-F004A is closed.

ENSURE BC-HV-F007A is closed.

ENSURE EG-HV-2512A is open.

ENSURE BC-HV-F006A is open.

ENSURE associated Schedule File is loaded.

OPEN BC-HV-F007 A breaker using ET-1.

OPEN BC-HV-F027 A breaker using ET -2.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers) ltnitial I Description PLACE red bezel covers on the BC-HV-F007B AND the BC-HV-F027B.

PLACE red bezel covers on the BC-HV-F007A AND the BC-HV-F027A.

MARK procedure HC.OP-SO.BC-0002 complete up to step 5.3.4.

Page 13 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

REMOTE SCHEDULE:

Initial @Time Event Action Description RH30 HV-F007B RHR Pump A Min Flow None None Insert remote RH30B to TAGGED Valve ET006 GROUP 3B HV-F027B RHR None None Insert remote ET006 to RACK_CLOSE Supp. Pool Spray Insert remote RH30A to TAGGED on RH30 HV-F007A RHR Pump A Min Flow None None event 1 Valve Insert remote ET005 to RACK_CLOSE ET005 GROUP 3B HV-F027A RHR None None on event 2 Supp. Pool Spray RH29 GROUP 3E HV-F015A RHR SOC None None Insert remote RH29A to FAIL_CLOSE Return lsol Page 14 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-4 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-4 REV#: 1 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

1. Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is ~3.0 (LOR) or ~2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6.

Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B TASK NUMBER:

JPM NUMBER: 2013 NRC S-5 REV#: 1 SAP BET:

ALTERNATE PATH: D APPLICABILITY:

EOD RO [KJ STA D SRO [KJ DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06~0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-5 REV: 01 SYSTEM: Primary Containment TASK NUMBER:

TASK:

Suppression Chamber Makeup From Service Water Loop B ALTERNATE PATH: D KIA NUMBER: 223001 A2.11 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EO D RO [K] STA D SRO [K]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0314 Rev. 05 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-EO.ZZ-0314 ESTIMATED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - N/A Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME:: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Primarv ContainmP.nt TASK:

Suppression Chamber Makeup From Service Water Loop B TASK NUMBER:

INITIAL CONDITIONS:

1. Suppression Chamber level is 70 inches and normal means of make-up are unavailable.

2. RHR Pump BP202 is shutdown and is not required to assure adequate core cooling.

INITIATING CUE:

Restore suppression chamber level using Suppression Chamber Make-up from Service Water Loop B.

Page 3 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.ZZ-0314.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are N/A satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.2.1.

Page 4 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

{*Denotes a Critical Step)

COMMENTS STEP ELEMENT {#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U evaluati 5.2.1 START TIME: Operator Verifies Prerequisites.

ENSURE that all prerequisites have been satisfied lAW Section 2.2 of this procedure.

5.2.2. CLOSE BC-HV-F003B //RHR HX The operator depresses the close

SHELL SIDE OUTLET MOV// pushbutton for BC-HV-F003B The operator observes that the CLOSED indicator illuminates and the OPEN indicator extinguishes VERIFY CLOSED BC-HV-F048B //8 Operator verifies closed BC-HV-F048B 5.2.3.

RHR HX SHELL SIDE BYP MOV//

OPEN EA-HV-2238 SERVICE The operator depresses the open 5.2.4

WATER LOOP B EMERG M/U pushbutton for EA-HV-2238.

OUTBD ISLN (10C651).

The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes Page 5 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.5 ENSURE breaker 52-222082 is CLOSED, The operator calls booth to ensure #

(to allow 1 EAHV-F073 to be opened). breaker 52-222082 is closed OPEN EA-HV-F073 SERVICE The operator depresses the open 5.2.6

WATER LOOP B EMERG M/U pushbutton for EA-HV-F073 INBD ISLN (1 OC651 ).

The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes 5.2.7 OPEN BC-HV-F075 //SSWS TO RHR

LOOP B SUP MOV//. The operator depresses the open #

pushbutton for BC-HC-F075 The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes.

WHILE diverting the Service Water 5.2.8 flow to the Suppression Chamber, MONITOR temperatures of Operator monitors temperatures all on-service, SACS and RACS cooling loads.

Page 6 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Primary Containment TASK: Suooression Chamber Makeuo From Service Water Looo B

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio 5.2.9 THROTTLE OPEN BC-HV-F024B *

//RHR LOOP B TEST RET Operator depresses the open pushbutton for BC-HV-F024B. #

MOV// to control suppression chamber fill rate 5.2.10 MONITOR Service Water Pump BP502 and/or DP502 Motor Operator monitors motor amps and Amps and Vibration for indications of vibration.

pump run-out due to increased system flow WHEN suppression chamber level

5.2.11 returns to the desired band, Operator determines that suppression RESTORE the RHR and Service #

chamber level is in the normal band.

Water systems to normal using Attachment 2 CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 7 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluatio N/A TASK STANDARD: Operator Restores Suppression Chamber Level By Using Suppression Chamber Makeup From Service Water Loop B Page 8 of 14

TQ-AA-1 06-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-5 TASK: Suppression Chamber Makeup From Service Water Loop B QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 9 of 14

TQ-AA-1 06-0303 JPM NUMBER: 2013 NRC S-5 REV#: 01 I. INITIAL CONDITIONS:

I. C.

Initial INITIALIZE the simulator to IC (Shutdown)

ESTABLISH Suppression chamber level at 70".

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description TOGGLE Control Room Horns to OFF.

ENSURE the simulator is reset AND in FREEZE.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE:

Initial ET#

Event code:

Description:

Event code:

Description:

Event code:

Description:

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description Page 10 of 14

TQ-AA-1 06-0303 REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 11 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-5 Rev# Date Description Validation Required?

01 12/11/12 New JPM for NRC exam. y Page 12 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-5 REV#: 01 TASK: Suppression Chamber Makeup From Service Water Loop B

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date Page 13 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1 . Suppression Chamber level is 70 inches and normal means of make-up are unavailable.

2. RHR Pump BP202 is shutdown and is not required to assure adequate core cooling.

INITIATING CUE:

Restore suppression chamber level using Suppression Chamber Make-up from Service Water Loop B.

Page 14 of 14

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Electrical TASK: Synchronize and Load Main Generator to the Grid TASK NUMBER:

JPM NUMBER: 2013 NRC S-6 REV#: 1 SAP BET:

ALTERNATE PATH: 0 APPLICABILITY:

EO D RO [ ] ] STA D SRO [ ] ]

DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

2013 NRC S-6 STATION: Hope Creek JPM NUMBER: 2013 NRC S-6 REV: 01 SYSTEM: Electrical TASK NUMBER:

TASK:

Synchronize and Load Main Generator to the Grid ALTERNATE PATH: [KJ KIA NUMBER: 262001 A4.04 IMPORTANCE FACTOR: 3.6 3.7 APPLICABILITY: RO SRO EoD RoCK] STAD sRo[K]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-SO.MA-0001, Rev 56, HC.OP-AB.BOP-0002. Rev 13 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: __N_IA _ _ Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 15

2013 NRC S-6 NAME:

DATE:

SYSTEM: Electrical TASK:

Synchronize and Load Main Generator to the Grid TASK NUMBER:

INITIAL CONDITIONS:

1. A normal plant startup is in progress

3. All steps of HC.OP-SO.MA.0001 up to 5.16 have been completed, including prerequisites, precautions and limitations.

INITIATING CUE:

1. Continue with the performance of HC.OP-SO.MA-0001, MAIN TURBINE, and synchronize and load the Main Generator to the grid starting with step 5.16.

Page 3 of 15

2013 NRC S-6 JPM: 2013 NRC S-6 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Electrical TASK:

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U eva I CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure HC.OP-procedure. SO. MA-000 1, Rev 56 Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE !E excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are N/A satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.16.

Page 4 of 15

2013 NRC S-6 JPM: 2013 NRC S-6 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Electrical TASK:

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio 2.0 ENSURE that all prerequisites have Operator Verifies Prerequisites.

been satisfied lAW Section 2.0 of this procedure.

5.2.16 PERFORM the following to synchronize the Main Generator using #

Manual Load Control:

5.2.16. SELECT Control, Speed-Load The operator selects Control, Speed-A Load.

Note: Ramp Rate will indicate 20%/min until breaker is closed, upon breaker #

closure, Ramp Rate will be 60%/min for 2 seconds (2% load), Ramp Rate will then go to setpoint entered SELECT Load Set, Ramp Rate AND Operator selects Load Set, Ramp Rate

5.2.16.

ENTER 10%/min and enters 10%/min.

B #

Page 5 of 15

2013 NRC S-6 JPM: 2013 NRC S-6 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Electrical TASK: S_y_nchronize and Load Main Generator to the Grid

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.16. SELECT Load Set, Manual Adj.: The operator selects Load set, Manual c Raise OR Lower until pointer on the Adj. and RAISES or LOWERS until the SYNCHROSCOPE is moving slowly pointer on the synchroscope is moving slowly in the fast direction.

in the FAST direction.

IF the SYNCH WINDOW green light The operator notes that the green light 5.2.16.

does NOT turn on, THEN REQUEST turns on.

D #

permission from SM/CRS to bypass the synch check relay AND GO TO Step 5.2.17.

5.2.16. PERFORM the following (with Steps E 5.16.E.1 thru 5.2.16.E.3 being #

performed in rapid succession):

5.2.16. \/\/HEN the SYNCHROSCOPE Pointer The operator closes the breaker when

E.1 is at 2 minutes before 12 o'clock the synchroscope pointer is at- 2 minutes before 12 o'Clock position and #

position, AND the SYNCH WINDOW the synch window green light is green light is illuminated, THEN illuminated.

E BS 6-5 (BS 2-6) Breaker.

Note: Ramp Rate will indicate 20%/min until breaker is closed, upon breaker closure, Ramp Rate will be 60%/min for 2 seconds (2% load), Ramp Rate will then go to setpoint entered IMMEDIATELY SELECT Load Set:

5.2.16. The operator immediately selects Load

Setpoint AND ENTER 30%.

E.2 Set: Setpoint and enters 30%. #

Page 6 of 15

2013 NRC S-6 JPM: 2013 NRC S-6 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Electrical TASK: S **-***-***

h t

. .d Load Main G -* *-*---* *- . he Grid STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluation) 5.2.16. IMMEDIATELY OBSERVE the E.3 following: #

Bypass Valves close as generator loads to 30% Load Set Operator observes listed parameters.

Generator phase current increases

MW load and MVAR increases

Synchroscope pointer steady at 12 o'clock position 5.2.16. ADJUST Generator MVARs to within Operator adjusts generator MVARS to E.4 the limits of Excitation Limit Curve of within the limits of Excitation Limit Curve of Attachment 1. #

Attachment 1. _ _, _______L__

Page 7 of 15

2013 NRC S-6 JPM: 2013 NRC S-6 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Electrical TASK:

{*Denotes a Critical Step)

COMMENTS STEP ELEMENT {#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U evaluation Alternate Path: Operator responds to MAIN TURBINE GENERATOR VIB HI alarm lAW

After operator selects load set HC.OP-AR.ZZ-0014, Rev 34, setpoint to 30%, the booth will insert Attachment C5 AND HC.OP-AB.BOP-Bearing 1-10 Vibration> 11 mils(@

1800rpm) initiating alarm D3 C5 0002, Rev. 13 TURBINE GENERATOR VIB HI Operator trips the Main Turbine when Journal bearing 1-10 vibration is determined to be >11 mils (as read on GRIDS points A2519-A2530) lAW Alarm Response Procedure and Retainment Override CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 8 of 15

2013 NRC S-6 JPM: 2013 NRC S-6 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Electrical TASK:

STEP (*Denotes a Critical Step)

COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # I S/U evaluati N/A TASK STANDARD: Operator synchs and loads the Main generator to the grid and trips the main turbine when high vibrations >

retainment override limit condition is indicated.

Page 9 of 15

OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-6 TASK: Synchronize and Load Main Turbine to the Grid QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 10 of 15

JPM NUMBER: 2013 NRC S-6 REV#: 01 I. INITIAL CONDITIONS:

I. C.

Initial INITIALIZE the simulator to IC (Operating)

ESTABLISH Main Turbine running unloaded ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

Ensure trigger to bearing 1-10 vibration > 11 mils PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description TOGGLE Control Room Horns to OFF.

ENSURE the simulator is reset AND in FREEZE.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE:

Initial ET#

Event code:

Description:

Event code:

Description:

Event code:

Description:

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description Page 11 of 15

REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 12 of 15

JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-6 Rev# Date Description Validation Required?

01 4/2/13 New JPM for NRC exam. y Page 13 of 15

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-6 REV#: 01 TASK: Synchronize and Load Main Turbine to the Grid

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date Page 14 of 15

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1 . A normal plant startup is in progress

3. All steps of HC.OP-SO.MA.0001 up to 5.16 have been completed, including prerequisites, precautions and limitations.

INITIATING CUE:

1. Continue with the performance of HC.OP-SO.MA-0001, MAIN TURBINE, and synchronize and load the Main Generator to the grid starting with step 5.16.

Page 15 of 15

NC.TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASUF~E:

STATION: Hope Creek SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks TASK NUMBER: 2001040501 JPM NUMBER: 305H-JPM. SB-012-04 ALTERNATE PATH: D KIA NUMBER: 295037 EA 1.01

~~~~------

IMPORTANCE FACTOR: 4.6 4.6 APPLICABILITY: RO SRO EO[)) RO [ ] ] STAC] SRO[]J EVALUATION SETTING/METHOD: Simulator/Perform OR Control Room Simulate

REFERENCES:

HC.OP-EO.ZZ-0320, Rev. 2 TOOLS, EQUIPMENT AND PROCEDURES:

EOP-320 Implementation Kjt VALIDATED JPM COMPLETION TIME: - -Minutes ---

TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A APPROVAL:

~~

OPERATI~NNAGER OR DESIGNEE CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the SM or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION: Minutes JPM PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE: - - - - - - -

Nuclear Common Page 1 of 8 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks TASK NUMBER: 2001040501 INITIAL CONDITIONS:

1. The plant has experienced a failure to scram.

2. All scram valves have opened but the Scram Discharge Volume is full.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Draining the SDV and attempting a manual scram is required.

5. HC.OP-EO.ZZ-0302 has NOT been implemented.

6. ARI interlocks have been defeated in accordance with Section 5.1 of HC.OP-EO.ZZ-0320.

INITIATING CUE:

Defeat RPS interlocks lAW HC.OP-EO.ZZ-0320.

Successful Completion Criteria:

1. All critical steps completed.

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.

Nuclear Common Page 2 of 8 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC S-7 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

Operator obtains procedure Operator obtains the correct procedure.

HC.OP-EO.ZZ-0320.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

4.0 EQUIPMENT REQUIRED Operator obtains the following required equipment:

4.1 EOP-320 Implementation Kit (NSS office EOP Drawer) contents: EOP-320 Implementation kit from SM 1 set of fuse pullers Office Clerk Area EOP drawer.

1 flashlight 1 plastic bag for ARI fuses -OR 4 banana plug jumpers OR Key #9 from OSC office or key from 4.2 break glass key holder in OSC for OSC Key #9 for EOP Locker in OSC EOP locker.

(obtain from SNSS office or break red key holder glass in OSC) AND AND EOP-320 Implementation kit from EOP locker in OSC.

EOP-320 Implementation kit (EOP Locker in OSC) contents: Examiner Cue: Supply operator with EOP-320 implementation kit.

1 set of fuse pullers 1 flashlight 1 plastic bag for ARI fuses 4 banana plug jumpers Nuclear Common Page 3 of 8 Rev. 1

NC.TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC S-7 OPERATOR TRAINING PROGRAM NAME:

Rev:01 JOBPERFORMANCEMEASURE DATE:------------------

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP COMMENTS

STEP

{*Denotes a Critical Step) EVAL {Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Ste_Q} S/U evaluation)

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.2.1.

5.2.1 ENSURE that Prerequisites have Operator ensures Prerequisites are been satisfied lAW Section 2.2. satisfied.

Examiner Cue: If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.

START TIME:

5.2.2 On H11-P609, front, Division 1, left Operator installs jumper at H11-P609 test box, INSERT a jumper between between test points C71A-K10A-2A and test point C71A-K1 OA-2A (first C71A-K12E-2B.

column-first row, red jack) and test point C71A-K12E-2B (fourth Examiner Cue: IF the JPM is being column-second row, black jack). simulated in the Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

5.2.3 On H11-P609, front, Division 3, left Operator installs jumper at H11-P609 test box, INSERT a jumper between between test points C71A-K10C-2A test point C71A-K1 OC-2A (third and C71 A-K12G-2B.

column-fourth row, red jack) and test Examiner Cue: IF the JPM is being point C71A-K12G-2B (fourth simulated in the Control Room, column-third row, black jack) ..

THEN inform the Operator that a jumper has been placed between the L_ test jacks you indicated.

Nuclear Common Page 4 of 8 Rev. 1

NC.TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC S-7 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Protection System TASK Defeat RPS Interlocks STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Ste~ S/U evaluation)

5.2.4 On H11-P611, front, Division 2, left Operator installs jumper at H11-P611 test box, INSERT a jumper between between test points C71A-K10B-2A and test point C71A-K10B-2A (fourth C71A-K12F-2B.

column-fourth row, red jack) and test Examiner Cue: IF the JPM is being point C71A-K12F-2B (first column-simulated in the Control Room, second row, black jack) ..

THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

5.2.5 On H11-P611, front, Division 4, left Operator installs jumper at H11-P611 test box, INSERT a jumper between between test points C71A-K10D-2A test point C71A-K10D-2A (third and C71A-K12H-2B.

column-third row, red jack) and test Examiner Cue: IF the JPM is being point C71A-K12H-2B (fourth column-simulated in the Control Room, second row, black jack).

THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

STOP TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common Page 5 of 8 Rev. 1

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE: _ _ _,_ _ _ _ _ _ __

SYSTEM: Reactor Protection System TASK: 2013 NRC S-6 Defeat RPS Interlocks TASK NUMBER: 2001040501 QUESTION:

RESPONSE

RESULT: -SAT -UNSAT QUESTION:

RESPONSE

RESULT: -SAT - UNSAT Nuclear Common Page 6 of 8 Rev. 1

NC. TQ-WB.ZZ-031 O(Z)

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced a failure to scram.

2. All scram valves have opened but the Scram Discharge Volume is full.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Draining the SDV and attempting a manual scram is required.

5. HC.OP-EO.ZZ-0302 has NOT been implemented.

6. ARI interlocks have been defeated in accordance with Section 5.1 of HC.OP-EO.ZZ-0320.

INITIATING CUE:

Defeat RPS interlocks lAW HC.OP-EO.ZZ-0320.

Nuclear Common Page 7 of 8 Rev.1

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 JPM NUMBER: 2013 NRC S-8 REV#: 1 SAP BET: NOH05JPGS05E ALTERNATE PATH: m APPLICABILITY:

EOD RO [KJ STA D SRO [KJ DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-8 REV: 1 SYSTEM: Containment Atmosphere Control TASK NUMBER: 2000950501 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches ALTERNATE PATH: w KIA NUMBER: __2_9_5_02_4_E_A_1_.1_9__

IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO EO D RO [K] STA D SRO [K]

EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0318(0) Rev. 7 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 23 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 20

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180inches TASK NUMBER: 2000950501 INITIAL CONDITIONS:

1. The 'B' RHR pump suction was isolated due to a leak.

2. The Plant experienced a large break LOCA.

3. HC.OP-EO.ZZ-01 02, Primary Containment Control has been implemented.

4. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising.

5. Suppression Pool Level indicates approximately 83 inches.

6. The Emergency Instrument Air Compressor has been restored lAW HC.OP-EO.ZZ-0319.

7. The Control Room Emergency Filtration System is operating in the Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001 (Q).

8. FRVS is in operation in accordance with HC.OP-SO.GU-0001 (Q).

9. The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

10. Salem Operations has been notified that containment venting will be performed.

11. The Aux. Bldg. EO is standing by at panei1Y-F404.

12. The Reactor Building is inaccessible and has been evacuated.

INITIATING CUE:

Vent the Containment via the Hard Torus Vent lAW HC.OP-EO.ZZ-0318. Notify the CRS when venting has commenced.

Page 3 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains/locates procedure Operator obtains the correct procedure.

HC.OP-EO.ZZ-0318.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure step to be 5.1 .1 .

Page 4 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches STEP (*Denotes a Critical Step)

COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.1 VENT the containment via the Hard Operator reviews Prerequisites and Torus Vent as follows: ensures Prerequisites complete. I A. ENSURE that all prerequisites have been satisfied in accordance with Section 2.0 of this procedure.

I CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.

5.1.1 B. NOTIFY the Emergency Duty Operator notifies the CRS to notifiy the Officer that containment venting EDO that containment venting via the via the Hard Torus Vent will be Hard Torus Vent will be performed.

performed.

CUE Acknowledge the communication to the EDO.

5.1.1 C. In the Lower Relay Room, Elev Operator directs the field operator to

102'atpanel 1YF404(see install fuse F22 at panel 1YF404.

Attachment 2), INSTALL F22 (6 #

amp fuse).

Page 5 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - -

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches STEP (*Denotes a Critical Step) COMMENTS NO. ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation)

CUE WHEN directed to instaii1YF404 fuse F22, THEN TRIGGER ET-3 AND REPORT the fuse is installed.

5.1.1 D. DEPRESS ISLN OVRD and Operator depresses the ISLN OVRD

OPEN GS-HV-4964 SUPP pushbutton for the HV-4964.

CHMBR TO CPCS DMP. #

Operator observes the amber OVER-RIDDEN indicator illuminates.

Operator depresses the HV4964 OPEN

PB.

Operator observes the red OPEN indicator illuminates and the green CLSD indicator extinguishes.

5.1.1 E. ANNOUNCE that containment Operator announces containment venting will commence at the venting will commence at the South end South end of the Reactor Building of the Reactor Building via the Hard via the Hard Torus Vent. Torus Vent over the plant paging system.

Page 6 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches STEP (*Denotes a Critical Step) COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation}

5.1.1 F. When HV-4964 SUPP CHMBR TO Operator observes that the HV4964 CPCS DMP is full open, then OPEN indicator is illuminated.

OPEN GS-HV-11541 TORUS Operator observes that the HV4964 VENT ISOLATION VALVE.

CLSD indicator is extinguished.

Operator rotates HV11541 keylock * !

switch to the OPEN position.

Operator observes the red HV11541 OPEN indicator REMAINS EXTINGUISHED and the green CLOSED indicator REMAINS ILLUMINATED.

I Operator informs CRS. I CUE Repeat back report from Operator Examiner Note: Based on the Initial and direct Operator to continue to Conditions, the Reactor Building is NOT implement the procedure until a accessible. Manually opening the vent path is established. HV-11541 is not an option.

Page 7 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.1 G. When drywell pressure can be Operator determines drywell pressure maintained below 60 psig, then is not being maintained below 60 psig, CLOSE GS-HV-11541 TORUS continues on in the procedure.

VENT ISOLATION VALVE.

5.1.1 H. REPEAT steps 5.1.1.E thru Operator determines repeating these 5.1.1.G as necessary to reduce steps will not establish a vent path.

and maintain drywell pressure below 65 psig.

5.1.1 I. If actions taken to reduce Operator determined actions taken thus containment pressure have been far have not been successful, continues unsuccessful, then continue in this in the procedure.

procedure.

5.1.2 VENT the containment via the Operator determines this path is not Suppression Chamber supply and available since it requires access to the ILRT piping as follows: Reactor Building and the reactor Building is not accessible.

Page 8 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE IF the Operator requests the status of the "angled piping downstream of 1-GS-V058",

THEN INFORM the Operator the piping has NOT been rotated to align the vent path and the Reactor Building is NOT accessible.

5.1.3 VENT the containment via the Drywell Operator determines this path is not supply and ILRT piping as follows: available since it requires access to the Reactor Building and the reactor Building is not accessible.

5.1.4 VENT the containment via the Operator determines the Suppression Suppression Chamber 2" exhaust as Chamber 2" exhaust is the next most follows: preferable path.

Examiner Note: 3.1.4 states: The selection of vent paths has been presented in priority order. However, if it can be determined that a particular path is unavailable or undesirable, the section addressing that vent path may be omitted (see Attachment 4).

Page 9 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.4 A. ENSURE that all prerequisites Operator reviews Prerequisites and have been satisfied in accordance ensures Prerequisites complete.

with Section 2.0 of this procedure.

CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.

5.1.4 B. NOTIFY the Emergency Duty Operator notifies the CRS to notifiy the Officer that containment venting of EDO that containment venting of the the Suppression Chamber to the Suppression Chamber to the Reactor Reactor Building will be Building will be performed.

performed.

CUE Acknowledge the communication to the EDO.

5.1.4 C. DEPRESS ISLN OVRD and Operator presses the DRYWELL

OPEN GT-HD-9372A Drwl Purge PURGE SHUT OFF DMPRS ISLN Vent Exh Dmpr. OVRD pushbutton. #

Operator observes the pushbutton backlights.

Page 10 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ __

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - -

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator presses the DRYWELL

PURGE SHUT OFF DMPRS HD9372A OPEN pushbutton. #

Operator observes the red HD9372A OPEN light illuminates and green CLOSED light extinguishes.

5.1.4 D. DEPRESS ISLN OVRD and Operator observes the amber OVER-OPEN GS-HV-4964 SUPP RIDDEN light for the HV-4964 ISLN CHMBR TO CPCS DMP. OVRD is already illuminated.

Operator observes red HV4964 OPEN light is already illuminated and green CLSD light is already extinguished.

Examiner Note: It is only critical the HV-4964 is open. It is not critical whether it was left open from step 5.1.1.C, or closed and then re-opened at this step.

5.1.4 E. ANNOUNCE containment venting Operator announces containment

of the Suppression Chamber to venting of the Suppression Chamber to the Reactor Building. the Reactor Building over the plant #

page.

Page 11 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - -

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.4 F. When GS-HV-4964 SUPP Operator observes red HV4964 OPEN CHMBR TO CPCS DMP is full light is illuminated and green CLSD open, then DEPRESS ISLN light is extinguished.

OVRD and OPEN GS-HV-4963 SUPP CHMBR N2 M/U EXH.

Operator presses ISLN OVRD for the

HV4963.

Operator observes the amber OVER-RIDDEN light illuminates.

Operator presses the HV4963 OPEN

pushbutton.

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

5.1.4 G. When drywell pressure can be Operator informs CRS that drywell maintained below 60 psig, then venting has commenced and monitors CLOSE GS-HV-4963 SUPP drywell pressure.

CHMBR N2 M/U EXH and GS-HV-4964 SUPP CHMBR TO CPCS DMP.

Page 12 of 20

TQ-AA-1 06-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

~---

Rev: 01 JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches STEP (*Denotes a Critical Step)

COMMENTS NO. ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation)

CUE IF the operator cannot see the Examiner Note: The rate of drywell pressure reduction on the 10C650E pressure reduction through this path indicators, alone is slow and will not be readily visible on the 1OC650E indicators due THEN inform the operator Drywell to the absence of a tenth digit. The pressure reduction is observable response IS readily observable on on SPDS.

SPDS. The operator may not be satisfied with the initial response and may elect to open an additional vent I path.

I CUE WHEN operator informs you the task is I complete, OR the JPM has been terminated for I other reasons, THEN RECORD the STOP time.

i REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator vents primary containment through alternate vent path.

Page 13 of 20

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-8 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 14 of 20

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The 'B' RHR pump suction was isolated due to a leak.

2. The Plant experienced a large break LOCA.

3. HC.OP-EO.ZZ-01 02, Primary Containment Control has been implemented.

4. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising.

5. Suppression Pool Level indicates approximately 83 inches.

6. The Emergency Instrument Air Compressor has been restored lAW HC.OP-EO.ZZ-0319.

7. The Control Room Emergency Filtration System is operating in the Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001(0).

8. FRVS is in operation in accordance with HC.OP-SO.GU-0001 (Q).

9. The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

10. Salem Operations has been notified that containment venting will be performed.

11. The Aux. Bldg. EO is standing by at panei1Y-F404.

12. The Reactor Building is inaccessible and has been evacuated.

INITIATING CUE:

Vent the Containment via the Hard Torus Vent lAW HC.OP-EO.ZZ-0318. Notify the CRS when venting has commenced.

Page 15 of 20

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE I. INITIAL CONDITIONS:

I. C.

Initial INITIALIZE the simulator to 100% power, MOL, EPU.

CLOSE the BC-HV-F004B RHR pump suction valve.

ISOLATE drywell cooling by closing the inboard and outboard drywell chilled water isolation valves.

TRIGGER ET-1 and ESTABLISH post large break LOCA conditions with a downcomer break and drywell pressure approximately 60 psig. Malfunctions may be modified as necessary.

CLOSE the MSIVs and drains.

IMPLEMENT EOP-101 AND EOP-102 AFTER drywell pressure is raised to approximately 60 psig.

RESTORE Instrument Air lAW EOP-319.

PLACE Temporary Air Compressor in service.

PLACE 'A' RHR pump in drywell spray with the exception of opening the HV-F021A.

FAIL OPEN an ADS SRV.

USE Insight Item rhv021 (1) (set to -0.00 to 0.04) to crack open the F021 A as necessary to establish drywell pressure at 60 psig and rising slowly.

ENSURE CREF is in service in the ISOLATE/RECIRC Mode lAW SO.GK-0001.

ENSURE FRVS is in Service lAW SO.GU-0001.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE:

Initial ET#

Event code: pcpdw >= 16.2 // Drywell Pressure in psia 2

Description:

Inserts Feedwater line break and LOCA after drywell preheated Event code:

Description:

Event code:

Description:

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE MALFUNCTION SCHEDULE:

Initial @Time Event Action Description Insert malfunction FW32 to Feedwater line break inside None None 100.00000 on event 2 containment Insert malfunction FW04A after 60 Secondary condensate pump None None on event 2 AP137 trip Insert malfunction FW04B after 60 Secondary condensate pump None None on event 2 BP137 trip Insert malfunction FW04C after Secondary condensate pump None None 60 on event 2 CP137 trip Insert malfunction MS01 after 90 None None Steam line break in drywell to 4.00000 on event 2 Insert malfunction PC04 on event None None Downcomer break 4

REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote RH23B to TAGGED RH23 RHR Pump B Insert remote RH20A to RH20 HV-F021A RHR CTMT None None RACK OUT SPRAY Insert remote ET067 to None None ET067 HV-11541 Torus vent INSTALLED on event 3 lA 10 Temporary station air None None Insert remote lA 10 to RUN compressor EP38 EOP-319, Restoring None None Insert remote EP38 to Emergency Instrument Air in an Emergency OVERRIDE SCHEDULE:

Initial @Time Event Action Description None None Insert override 6S151 A Dl to Off HV-11541 OPEN KEY SW (DI)

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-8 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-8 REV#: 01 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

1. Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is _:::3.0 (LOR) or _:::2.5 (IL T) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk(*). Sequence

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection TASK NUMBER: 2000490504 JPM NUMBER: 2013 NRC P-1 REV#: 01 SAP BET: NOHOSJ PBC07E ALTERNATE PATH: D APPLICABILITY:

EO D RO 00 STA D SRO 00 DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC P-1 REV: 01 SYSTEM: Residual Heat Removal TASK NUMBER: 2000490504 TASK: Align Fire Water System For Alternate RPV Injection ALTERNATE PATH: D KIA NUMBER: 295031 A 1.08 IMPORTANCE FACTOR: 3.8 3.9 APPLICABILITY: RO SRO EoD RoCK] STAD sRo[KJ EVALUATION SETTING/METHOD: Plant/Simulate

REFERENCES:

HC.OP-EO.ZZ-031 0 Rev. 7 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-EO.ZZ-0310 EOP-31 0 equipment located in EOP locker on E1.1 02' Diesel Bldg. Key(s) specified in section 4.0 of HC.OP-EO.ZZ-0310.

ESTIMATED COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - - N/A---

Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 17

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection TASK NUMBER: 2000490504 INITIAL CONDITIONS:

1. A Station Blackout has occurred due to severe weather conditions.

2. The reactor is shutdown; all control rods are in.

3. A, C, and D Emergency Diesel Generators have failed to start.

4. B Emergency Diesel Generator has started and loaded onto its respective bus.

5. B RHR pump has tripped on overcurrent and cannot be started.

6. The Diesel Driven Fire pump has started and is operating properly.

7. Due to severe weather conditions, the DG building watertight doors are not accessible.

INITIATING CUE:

Lineup for alternate injection using Fire Water lAW HC.OP-EO.ZZ-031 0.

Use the local fire hose station isolation valve as the supply of Fire Water.

The Reactor Building EO is standing by to assist as necessary.

Page 3 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

{* Denotes a Critical Element COMMENTS STEP {*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluatio CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.ZZ-031 0 Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE I IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator N/A that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.1 .

Page 4 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluation)

EQUIPMENT REQUIRED Key# (G1) for EOP Locker on El.

102' diesel bldg. From either: Operator obtains the following required equipment:

0 SM office or 0 From EOPLocker in OSC (Use Key #(G1) for EOP Locker on El.1 02' Key #9 obtained from SM office or diesel bldg. From either:

by breaking red key holder glass in OSC). 0 SM office or 0 From EOPLocker in OSC (use key AND #9 obtained from SM office or by breaking red key holder glass in Equipment located in EOP locker on OSC)

El.1 02' diesel bldg.

Equipment located in EOP locker on El Contents: 102' diesel bldg.

1- 2.5" hose to flange adapter Examiner Note: After operator has 1- 1.5" hose to flange adapter demonstrated ability to obtain 150' of 2.5" Fire Hose 50' of 1.5" Fire Hose (for Fire Hose required equipment, ensure that the Station) equipment is returned to its 2- 1-1/16" Box Wrenches appropriate storage location.

2- Fire Hose Wrenches 1- Hydrant Wrench 5.1.1 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.1 are satisfied. have been satisfied.

Page 5 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluation CUE IF excessive time is taken reviewing prerequisites, N/A THEN INFORM operator that all are satisfied.

5.1.2 CONNECT hose to the appropriate Operator accesses the EOP locker and flange adaptor AND TIGHTEN. identifies the 1 .5" fire hose and correct adapter.

o 1.5" hose and adapter for fire hose Examiner Note: Based on the Initiating station Cue, Operator determines the 1.5" hose and adapter is the correct equipment.

o 2.5" hose and adapter for yard fire From this point on, actions will be hydrant or fire truck simulated. The installed white hose on the Fire Hose Station is NOT the correct hose for this task.

CUE Once the operator identifies the correct equipment, INFORM the Operator the remainder of the JPM N/A will be simulated.

Operator connects the correct hose to I

the correct adapter.

Page 6 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluatio 5.1.3 REMOVE fire hose fill connection

Y N STAR Operator removes the four bolts on the blank flange on 1-BC-V426 (local, 1-BC-V426 blank flange. (Bolts Diesel Building, Elev. 102', see removed and re-installed using the 1-Attachment 2) AND INSTALL hose to 1/16" Box wrenches).

flange adapter.

Operator removes the blank flange.

CUE I The flange you indicated is removed.

Operator installs the 1.5" hose to flange

adapter using the same four bolts.

(Bolts removed and re-installed using the 1- 1/16" Box wrenches).

CUE I The hose to flange adapter has been installed in the place you indicated.

Page 7 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

{* Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluatio 5.1.4 CONNECT fire hose to one of the following sources of Fire Water:

Operator removes installed Fire Station o Fire Hose Station hose from standpipe.

o Yard Fire Hydrant o Fire Truck Operator installs free end of 1.5" fire

hose to the Fire Hose Station standpipe.

CUE I The fire hose has been connected to the fire water source stated.

Page 8 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U ELEMENT

I eva I 5.1.5 1 OPEN one of the following as

applicable:

o Fire Hose Station Isolation Operator opens the Fire Hose Station Valve Isolation Valve.

o Fire Hydrant Line Valve (side) and Plug Valve (top) o Fire Truck Valves CUE I The valve you have indicated is open, flow noise can be heard past the valve and the fire hose is swelling.

5.1.6 In the South-east corner of the Rx

Y N 3-Way Operator contacts RB Equipment Communications Bldg, Elev. 102', OPEN breaker 52- Operator and directs the opening at 222082. breaker 52-222082.

CUE I As the RB Equipment Operator, report that breaker 52-222082 has been opened.

Page 9 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

COMMENTS STEP (*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluation 5.1.7 OPEN 1-BC-V426, SSWS Sup to

Y N STAR RHR Fire Hose Fill Conn Sup Vlv (local, diesel truck bay, elevation 102 Operator opens 1-BC-V426.

inside stairway door - see Attachment 2).

Examiner Cue: The valve you indicated is open; flow noise can be heard past the valve.

5.1.8 Operator requests that the Control

Y N 3-Way OPEN BC-HV-F075, SSWS TO RHR Communications LOOP 8 SUP MOV (panel 1OC650). Room operator open BC-HV-F075.

CUE I Acknowledge messages from the operator and report that BC-HV-F075 has been opened.

Page 10 of 17

TQ-AA-1 06-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U eva I CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

nes up ror altern N/A TASK STANDARD:

using Fire Water lAW HC.OP-EO.ZZ-0310 using the local fire hose station isolation valve as the supply of Fire Water.

Page 11 of 17

TQ-AA-1 06-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC P-1 TASK: Align Fire Water System For Alternate RPV Injection TASK NUMBER: 2000490504 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 12 of 17

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 2013 NRC P-1 REV#: 1 I. INITIAL CONDITIONS:

I. C.

Initial PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description EVENT TRIGGERS:

Initial ET# Description EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 13 of 17

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 14 of 17

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC P-1 Rev# Date Description Validation Required?

Page 15 of 17

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC P-1 REV#: 1 TASK: Align Fire Water System For Alternate RPV Injection

1. Task description and number, JPM description and number are identified.

Knowledge and Abilities (KIA) is identified, and is ~3.0 (LOR) or ~2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Sequence

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date Page 16 of 17

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A Station Blackout has occurred due to severe weather conditions.

2. The reactor is shutdown; all control rods are in.

3. A, C, and D Emergency Diesel Generators have failed to start.

4. B Emergency Diesel Generator has started and loaded onto its respective bus.

5. B RHR pump has tripped on overcurrent and cannot be started.

6. The Diesel Driven Fire pump has started and is operating properly.

7. Due to severe weather conditions, the DG building watertight doors are not accessible.

INITIATING CUE:

Lineup for alternate injection using Fire Water lAW HC.OP-EO.ZZ-031 0.

Use the local fire hose station isolation valve as the supply of Fire Water.

The Reactor Building EO is standing by to assist as necessary.

Page 17 of 17

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel TASK NUMBER: 2640170404 JPM NUMBER: 2013 NRC P-2 ALTERNATE PATH: KIA NUMBER: 264000 A2.09 IMPORTANCE FACTOR:

3.7 4.1 APPLICABILITY: RO SRO eo[)) RO [ ] ] STAD SRO[]J EVALUATION SETTING/METHOD: Aux Bldg/Simulate

REFERENCES:

HC.OP-SO.KJ-0001 Rev 43 TOOLS, EQUIPMENT AND PROCEDURES:

Key #51 -KIRK- Diesel Eng Takeover/Local Cont. (Work Control)

VALIDATED JPM COMPLETION TIME: 6 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A APPROVAL:

BARGAINING UNIT OPS TRAINING MANAGER OPERATIONS DIRECTOR REPRESENTATIVE OR DESIGNEE OR DESIGNEE CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the SM or Unit CRS;

2. Direct oversight by a qualified individual {determined by the individual granting permission based on plant conditions}.

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION: N/A JPM PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator Frorn The Remote Panel TASK NUMBER: 2640170404 INITIAL CONDITIONS:

1. An earthquake and Loss of Coolant Accident have occurred.

2. The Aux Bldg Operator has been called to the Control Room to perform Communicator duties.

3. The Reactor is shutdown. All rods are full in.

4. Emergency Diesel Generator AG400 has failed to autom.atically start and will not start from the Control Room.

5. HC.OP-AB.ZZ-0135 is being implemented.

6. Loss Prevention has been notified that a Diesel Generator will be placed in service and implementation of the Safety Department sampling plan may be required.

INITIATING CUE:

You are an extra Operator.

Start the 'A' Emergency Diesel Generator AG400 from the Remote Panei1A-C423 (EI. 130').

Loading the EDG is not required at this time.

Successful Completion Criteria:

1. All critical steps completed.

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.

Nuclear Common Page 2 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Emergency Diesel Generator TASK Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

Operator obtains procedure Operator obtains the correct procedure.

HC.OP-SO.KJ-0001.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Examiner Note: It is not critical to initial the procedure step, nor complete Attachment 1 in this and subsequent steps.

4.0 EQUIPMENT REQUIRED Operator obtains Key #51 -KIRK-Key #51 - KIRK- Diesel Eng Diesel Eng Takeover/Local Cont. (Work Takeover/Local Cont. (Work Control) Control)

After operator has demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.4.1.

5.4.1 ENSURE that all prerequisites have Operator ensures that all prerequisites been satisfied lAW Section 2.4 have been satisfied.

of this procedure. Examiner Cue: If excessive time is taken reviewing prerequisites, inform operator that all are satisfied.

Nuclear Common Page 3 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation) 5.4.2 START TIME: Operator observes the READY FOR AUTO START is on.

OBSERVE that READY FOR AUTO START is ON Examiner Cue: The light identified is (Panei1A(B,C,D)-C423 El. 130'). illuminated.

The operator then initials the appropriate procedure step.

~-- - - - - -

Nuclear Common Page 4 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP STEP COMMENTS

NO. (*Denotes a Critical Step) EVAL (Required for UNSAT STANDARD

(#Denotes a Sequential Step) S/U evaluation) 5.4.3 OBSERVE that Control is transferred Operator requests that the Control to Remote Panels through one of the Room press the REMOTE push button following: for AG400.

PRESS REMOTE PB Examiner Cues:

AND ENSURE (1 OC651 E). IF the operator requests the Control REMOTE light is ON. Room to press REMOTE, THEN OR respond as the Control Room you are NOT able to transfer the AG400 to Remote control. REMOTE push button for AG400 has been depressed and the REMOTE light is NOT on.

IF the operator requests the status of the local indications THEN inform them:

On the 423 panel the Main Control Room has Control light is illuminated and the Remote Engine Panel has Control light is extinguished.

On the 422 panel, the Main Control Room has Control lights are illuminated and the Remote Generator Panel has Control lights are extinguished.

OR

- - ~--

Nuclear Common Page 5 of 13 Rev. 2

NC.TQ-WB.ZZ-0310(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Emergency Diesel Generator TASK Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

OBTAIN key #51- KIRK- Diesel Operator obtains key #51 from WCC,

Emg Takeover/Local Cont., from unlocks the AG400 EMERGENCY Work Control Center TAKE-OVER Switch, and places the AND PLACE EMERGENCY AG400 EMERGENCY TAKE-OVER TAKE-OVER Switch in Switch in EMERG position EMERG position.

The operator then initials the appropriate procedure step.

Examiner Cues:

The switch identified is in the stated position.

IF the operator requests the status of the local indications THEN tell them:

On the 423 panel the Main Control Room has Control light is extinguished and the Remote Emergency Takeover light is illuminated.

On the 422 panel, the Main Control Room has Control AND Emergency Takeover in Normal lights are extinguished. The Remote Emergency Takeover light is illuminated.

Nuclear Common Page 6 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME: __________________

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

5.4.4 PLACE REMOTE ENGINE Operator places the AG400 REMOTE CONTROL in START ENGINE CONTROL in START.

(Panei1A(B,C,D)-C423 El. 130').

EXAMINER NOTE: The following cues are dependent upon correct step performance. Cue appropriately.

EXAMINER CUE: On panel1AC423:

1. The Diesel Engine can be heard starting.

2. Engine Stopped indicator is extinguished The operator then initials the appropriate procedure step.

5.4.5 OBSERVE the following: Operator observes: GENERATOR FREQUENCY indicates about 60 Hz.

GENERATOR FREQUENCY Examiner Cue: The indicator indicates about 60Hz.

identified indicates 60 Hz.

The operator then initials the appropriate procedure step.

GENERATOR VOLTS indicates GENERATOR VOLTS indicates about about 4160 Volts. 4160 Volts.

Examiner Cue: The indicator identified indicates 4160 volts.

The operator then initials the appropriate procedure step.

Nuclear Common Page 7 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

Rev: 01 JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator TASK" Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation) 5.4.6 OBSERVE the status of the following Operator observes:

indicating lights JACKET WATER HEATER OFF light is (Panei1A(B,C,D)-C423 El. 130').

illuminated and JACKET WATER

JACKET WATER HEATER is HEATER ON light is extinguished .

OFF.

Examiner Cue: The JACKET WATER HEATER OFF light is illuminated and JACKET WATER HEATER ON light is extinguished.

The operator then initials the appropriate procedure step.

LUBE OIL KEEPWARM HEATER Operator observes:

is OFF.

LUBE OIL KEEPWARM SYSTEM HEATER OFF light is illuminated and LUBE OIL KEEPWARM SYSTEM HEATER ON light is extinguished.

Examiner Cue: The LUBE OIL KEEPWARM SYSTEM HEATER OFF light is illuminated and LUBE OIL KEEPWARM SYSTEM HEATER ON light is extinguished.

The operator then initials the appropriate procedure step.

- - - - - - - - * ----- ------ ~~*~

Nuclear Common Page 8 of 13 Rev.2

NC.TQ-WB.ZZ-0310(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

JACKET WATER KEEPWARM Operator observes:

PUMP is OFF.

JACKET WATER KEEPWARM PUMP OFF light is illuminated and JACKET WATER KEEPWARM PUMP ON light is extinguished.

Examiner Cue: JACKET WATER KEEPWARM PUMP OFF light is illuminated and JACKET WATER KEEPWARM PUMP ON light is extinguished.

The operator then initials the appropriate procedure step.

GENERATOR SPACE HEATER is Operator observes:

OFF.

GENERATOR SPACE HEATER OFF light is illuminated and GENERATOR SPACE HEATER ON light is extinguished.

Examiner Cue: GENERATOR SPACE HEATER OFF light is illuminated and GENERATOR SPACE HEATER ON light is extinguished.

The operator then initials the

--~-**-*-- ~-

appropriate procedure step. - - - -

Nuclear Common Page 9 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME: - - - - - - - - - - - - - - - - - -

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Emergency Diesel Generator TASK" Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

{*Denotes a Critical Step} EVAL {Required for UNSAT

NO. STANDARD

{#Denotes a Sequential Step) S/U evaluation)

DIESEL RUNNING- NOT DIESEL RUNNING- NOT LOADED is LOADED is ON. on.

Examiner Cue: The light identified is illuminated.

The operator then annotates the appropriate procedure step. I 5.4.7 IF DIESEL RUNNING- LOADED is Examiner Cue: The light identified is ON (Panel 1A(B,C,D)-C423 El. 130'), extinguished.

OBSERVE that EDG BREAKER Operator determines the step does CLOSED is ON. NOT apply.

The operator then initials the appropriate procedure step. I 5.4.8 REFER to Attachment 5, Start/Failure Operator refers to Attachment 5.

Criteria for determining the validity of the start or failure to start, THEN LOG results in Control Room I log(s). I Nuclear Common Page 10 of 13 Rev.2

NC.TQ-WB.ZZ-0310(Z)

JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev:01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Emergency Diesel Generator TASK Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT I

NO. STANDARD

(#Denotes a Sequential Ste_m S/U evaluation)

Att. 5 The Shift Manager (SM) shall Operator requests the SM to determine determine the validity of the start or the Start/Failure Criteria per Attachment failure to start utilizing the following 5.

criteria:

Examiner Cue: Repeat back request from Operator. Inform Operator the Start Attempt was a Failure and has been logged in the Control Room log.

The operator then initials the appropriate procedure step.

5.4.9 IF loading of the EDG is required Operator determines local loading of locally, the EDG is NOT required.

PROCEED to Step 5.6.13.

The operator then initials the STOP TIME: - - -

appropriate procedure step.

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common Page 11 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

SYSTEM: Emergency Diesel Generator TASK: 2013 NRC P-2 Manually Emergency Start A Diesel Generator From The Remote Panel TASK NUMBER: 2640170404 QUESTION:

RESPONSE

RESULT:

'---------'~ SAT ,________._jl UNSAT QUESTION:

RESPONSE

RESULT:

'---------'~ SAT ,_______ __.JI UNSAT Nuclear Common Page 12 of 13 Rev.2

NC. TQ-WB.ZZ-031 O(Z)

INITIAL CONDITIONS:

1. An earthquake and Loss of Coolant Accident have occurred.

2. The Aux Bldg Operator has been called to the Control Room to perform Communicator duties.

3. The Reactor is shutdown. All rods are full in.

4. Emergency Diesel Generator AG400 has failed to automatically start and will not start from the Control Room.

5. HC.OP-AB.ZZ-0135 is being implemented.

6. Loss Prevention has been notified that a Diesel Generator will be placed in service and implementation of the Safety Department sampling plan may be required.

INITIATING CUE:

You are an extra Operator.

Start the 'A' Emergency Diesel Generator AG400 from the Remote Panel 1A-C423 (EI. 130').

Loading the EDG is not required at this time.

Nuclear Common Page 13 of 13 Rev.2

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header TASK NUMBER: 2000430504 JPM NUMBER: 2013 NRC P-3 REV#: 1 SAP BET: NOH05JPBF04E ALTERNATE PATH: D APPLICABILITY:

EO 00 RO 00 STA D SRO 00 DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC P-3 REV: 1 SYSTEM: Control Rod Drive Hydraulics TASK NUMBER: 2000430504 TASK: Manually Vent SCRAM Air Header ALTERNATE PATH: D KIA NUMBER: 295037 A 1 .05 IMPORTANCE FACTOR: 3.9 4.0 APPLICABILITY: RO SRO Eo((] Ro[K] STAD sRo[K]

EVALUATION SETTING/METHOD: Plant/Simulate

REFERENCES:

HC.OP-EO.ZZ-0306 Rev. 5 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-EO.ZZ-0306, Pipe wrench ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 13

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header TASK NUMBER: 2000430504 INITIAL CONDITIONS:

1. The plant has experienced an ATWS

2. The Scram Air Header has failed to vent.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Manual insertion of control rods from the Control Room lAW HC.RE-AB.ZZ-0001, Transient Plant Conditions in response to an A TWS, is in progress.

INITIATING CUE:

Manually vent the Scram Air Header lAW HC.OP-EO.ZZ-0306.

Page 3 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header

{* Denotes a Critical Element COMMENTS STEP {*Denotes a Critical Step)

of a Critical Step) EVAL {Required for UNSAT NO. STANDARD ELEMENT

S/U evaluatio CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.ZZ-0306.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, N/A THEN INFORM operator that all are satisfied.

CUE 1 IF excessive time is taken reviewing prerequisites, N/A THEN INFORM operator that all are satisfied.

Page 4 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header STEP (* Denotes a Critical Element

COMMENTS

(*Denotes a Critical Step) of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluation 4.0 EQUIPMENT REQUIRED Operator obtains the following required Key #9 for EOP Locker in OSC equipment:

4.1 (obtain from OS office or break red Key #9 from SM office or key from key holder glass in OSC) break glass key holder in OSC for OSC AND EOP locker EOP-306 Implementation kit (EOP AND Locker in OSC) EOP-306 Implementation Kit from EOP Contents: 1 14" Pipe Wrench Locker in OSC.

1 Wire Cutter Examiner Note: Obtaining a pipe wrench from an alternate location is 1 Flashlight considered satisfactory completion of this step. After operator has demonstrated ability to obtain the required equipment, ensure that the equipment is returned to its appropriate storage location.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1 CUE If at any time the operator requests permission to use section 5.2, DENY permission due to ongoing Control Room actions to manually N/A insert control rods with RMCS.

Page 5 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header STEP {* Denotes a Critical Element

COMMENTS

(*Denotes a Critical Step)

NO. of a Critical Step) EVAL (Required for UNSAT STANDARD ELEMENT

S/U evaluatio NOTE All operations are performed locally at the CRD Flow Control Area, Rx Bldg I Operator reads NOTE.

Elev. 102'.

5.1.1 I UNLOCK AND CLOSE 1BFV-073 Y N STAR Operator simulates removing the lock

//8/U SCRAM PILOT VLVS AIR SUP from 1BFV-073.

VLV//.

CUE I The locking device has been removed. I N/A ~11111 1

~

Operator Simulates closmg 1BFV-073 ... Y N STAR by turning valve handwheel clockwise until coming to a hard stop.

CUE The valve you indicated is in the N/A position stated.

5.1.2 I UNCAP AND OPEN 1BFV-802 //ARI Operator simulates removing the cap

I Y N STAR VLVS AIR SUP HDR DRN VLV// from 1BFV-802 by using the pipe between the scram air header ARI valves.

wrench and rotating the cap in the I#

counter-clockwise direction until the cap comes off.

CUE The cap device has been removed. N/A Operator opens 1BFV-802 by turning Y N STAR valve handwheel counter-clockwise until coming to a hard stop.

Page 6 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header

(* Denotes a Critical Element COMMENTS STEP (*Denotes a Critical Step)

of a Critical Step) EVAL (Required for UNSAT NO. STANDARD ELEMENT

S/U evaluati CUE The valve you indicated is in the N/A position stated. Air can be heard flowing from the drain opening.

5.1.3 OBSERVE PI-R013 SCRAM AIR HEADER PRESSURE (1 0-C-264 Operator observes pressure reading on panel at the CRD flow control panel)

PI-R013 on panel 1OC264.

to verify the air header fully depressurizes.

CUE I The gauge you have indicated is reading zero.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 7 of 13

TQ-AA-1 06-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC P-3 TASK: Manually Vent SCRAM Air Header TASK NUMBER: 2000430504 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 8 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 2013 NRC P-3 REV#: 1 I. INITIAL CONDITIONS:

I. C.

Initial PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description EVENT TRIGGERS:

Initial ET# Description EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 9 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 2013 NRC P-3 REV#: 1 MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val

--- --- NONE --- ---

REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val

--- --- NONE --- ---

1/0 OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val

--- --- NONE --- ---

Page 10 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC P-3 Rev# Date Description Validation Required?

Page 11 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC P-3 REV#: 1 TASK: Manually Vent SCRAM Air Header

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required:

Name Qual Signature Date Name Qual Signature Date Page 12 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced an ATWS

2. The Scram Air Header has failed to vent.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Manual insertion of control rods from the Control Room lAW HC.RE-AB.ZZ-0001, Transient Plant Conditions in response to an ATWS, is in progress.

INITIATING CUE:

Manually vent the Scram Air Header lAW HC.OP-EO.ZZ-0306.

Page 13 of 13

s NU J

E X

REVIEWED DATE:

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: ROA-1 REV: 01 SYSTEM: Radiation Control TASK NUMBER: 2991660301 TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves ALTERNATE PATH: D KIA NUMBER:

IMPORTANCE FACTOR: 3.8 2.3.11

4.3 APPLICABILITY

RO SRO EoD ROCK] STAD SROCK]

EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

OP-HC-1 03-105 Rev 0 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: - - N/A

- - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 14

TQ-AA-1 06-0303 NAME: ----------------------

DATE: ----------------------

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves TASK NUMBER: 2991660301 INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0836 today Operational Condition 4 was entered.

5. At 1142 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE:

COMPLETE today's Containment Prepurge Cleanup, lnerting, Or Pressure Control Valve Permit and Log in accordance with OP-HC-1 03-105.

Page 3 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

(*Denotes a Critical Step) COMMENTS STEP

NO.

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluatio CUE PROVIDE the operator the initiating cue AND a copy of OP-HC-1 03-105 Operator repeats back initiating cue.

WITH the attached paperwork.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 4.4.2.

4.4 Calculating Valve Open Time N/A 4.4.1 In Section C of Form 2, ENTER the time the valve(s) listed in Section 2.2 or the line(s) listed in Section 2.4 or 2.5 are opened in Condition 1, 2, or 3 N/A (Filled in by previous Operator) or when Condition 2 OR 3 is entered from Condition 4 with the valve(s)/line(s) open.

4.4.2 In Section C of Form 2, ENTER the

time the valve(s) listed in Section 2.2 Operator enters 0836 in section C of or the line(s) listed in Section 2.4 or Form 2 in the "Time at which valve/line 2.5 are closed in Condition 1, 2, or 3 was closed or Condition 4 or 5 was or when Condition 4 is entered from entered with valve/line opened" space.

Condition 2 or 3 with the valve(s)/line(s) open. [T/5 1.34]

Page 4 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

(*Denotes a Critical Step) *

COMMENTS STEP NO.

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD I # S/U evaluati 4.4.3 COMPUTE the total hours (round up Operator calculates the open cycle as

to the nearest 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or to the 7.0 hours0 days 0 hours 0 weeks 0 months (6.6 rounded up to 7.0) and nearest 1.0 hour0 days 0 hours 0 weeks 0 months ) for each open cycle. enters in Section C "Total number of hours valve/line opened this cycle" space.

4.4.4 When the valve permit is no longer

valid due to either the evolution is complete, Operator totals the hours that the or mode change to Condition 4 has valve(s)/line(s) were open. (7.0 hours0 days 0 hours 0 weeks 0 months ) occurred, and enters in Section C "Total number or the day has ended of hours valves/line open this permit" TOTAL the hours that the space.

valve(s)/line(s) were open (should be less than the time authorized in Section 8 of Form 2). [T/S 1.52]

4.4.5 The NCO performing the section C Operator signs the "NCO performing calculations should sign in the calculations" space and enters appropriate space and enter the time Date/Time in Section C.

and date.

4.4.6 The SM/CRS should verify the calculations, sign in the appropriate Operator hands the paperwork to the space for verification and close out CRS.

and enter the time and date.

CUE SIGN and DATE the appropriate N/A spaces and RETURN to the operator.

Page 5 of 14

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-1 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

(*Denotes a Critical Step) *

COMMENTS STEP NO.

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD I # S/U evaluatio 4.4.7 On Form 1, ENTER the name of the SM/CRS closing out the valve permit On Form 1 , the operator enters the and the number of hours the valves name of the SM/CRS closing out the were open on this permit. The NCO valve permit.

entering this information should initial in the appropriate space.

On Form 1 , the operator enters the

number of hours the valves were open.

(7.0 hrs THIS PERMIT/ 55.5 TOTAL)

On Form 1, the operator initials entry.

CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 6 of 14

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC RO A-1 TASK: Monitor, Log and Control the Drywall and Suppression Chamber Purge System Valves TASK NUMBER: 2991660301 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 7 of 14

OP-HC-1 03-105 IJMDOODOO @OO[SW Revision 0 Page 7 of 8

~~[JiJi)nUilnP~ @lfl)W FORM 1 Page of_ _

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO I PREV. AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL.

YEAR THIS PERMIT PERMIT PREVIOUS I (Note 1) PERMIT YEAR (Note 1) I I

11/15/07 12.0 24 P. Oliver CFO 13.0 25.0 0. North 01{

3/3/08 22.5 24 H. Davidson S(]) 5.5 28.0 A. West S(])

6/25/08 18.5 24 G. Washington 'T<J{W 3.5 22.0 G. Clooney 'T<J{W 8/30/08 22.0 24 O.W. Holmes 1{ 24.00 46.0 V. Price 1{

8/31/08 46.0 24 B. Lee P, V. Bono P, 2.5 48.5 !

Today 35.5 24 A. Jones JS 7.0 42.5 SM/CRS Name IW'T !

Note 1:The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

Hope Creek Page 5 of 9 Rev.5

OP-HC-1 03-105

~@lli1U0QU[f~ ©rPW Revision 0 Page 8 of 8 FORM2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Toda~ NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit#: 020020001 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) H 35.5 DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 {=} 24 3/3/08 5.5 OR 24, whichever is less) 6/25/08 3.5 Hours authorized this date (max 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 24 8/30/08 24.0 8/31/08 2.5 NCO performing calculation Date/Time Jofin Smitfi Toda~/0100 SM/CRS verification and authorization Date/Time

}lndrew Jones Toda~/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 0836 7.0 Total number of hours valves/line open this permit:

NCO performing calculations Operator Signature Date/Time (])ate/lime SM/CRS Closing permit P.J(pminer Signature Date/Time (])ate/lime Note 1: The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-1 04 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

Hope Creek Page 5 of9

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0836 today Operational Condition 4 was entered.

5. At 1142 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE:

COMPLETE today's Containment Prepurge Cleanup, lnerting, Or Pressure Control Valve Permit and Log in accordance with OP-HC-103-105.

Hope Creek Page 5 of9

OP-HC-1 03-105 lr~D~D~ @~~W Revision 0

@~rrcruQuP @[?)W Page 7 of 8 FORM 1 Page _ _of_ _

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO PREV. AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL YEAR THIS PERMIT PERMIT PREVIOUS (Note 1) PERMIT YEAR (Note 1) 11/15/07 12.0 24 P. Oliver CFO 13.0 25.0 0. North O:N 3/3/08 22.5 24 H. Davidson S(]) 5.5 28.0 A. West S(])

6/25/08 18.5 24 G. Washington qtl{,W 3.5 22.0 G. Clooney 'T1{W 8/30/08 22.0 24 O.W. Holmes 1{ 24.00 46.0 V. Price 1{

8/31/08 46.0 24 B. Lee P. 2.5 48.5 V. Bono P.

Today 35.5 24 A. Jones JS Note 1:The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

Hope Creek Page 5 of 9 Rev.S

OP-HC-1 03-1 05

@~@[J@~@lf~ ©~~

Revision 0 Page 8 of 8 FORM2 CONTAINMENT PREPURGE CLEANUP. INERTING. OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit#: 020020001 SECTION 8 HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) H 35.5 DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 (=} 24 3/3/08 5.5 OR 24, whichever is less) 6/25/08 3.5 Hours authorized this date (max 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 24 8/30/08 24.0 8/31/08 2.5 NCO performing calculation Date/Time Jolin Smitli Toda~/01 00 SM/CRS verification and authorization Date/Time

}lnarew Jones Toda~/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 Total number of hours valves/line open this permit:

NCO performing calculations Date/Time SM/CRS Closing permit Date/Time Note 1: The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-1 04 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC RO A-1 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC RO A-1 REV#: 01 TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 JPM NUMBER: 2013 NRC RO A-2 REV#: 01 SAP BET: NOH05JPZZ11 E ALTERNATE PATH:

D APPLICABILITY:

EO D RO [KJ STA D SRO D DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC RO A-2 REV: 01 SYSTEM: Reactor Recirculation TASK NUMBER: 2020160101 TASK: Perform a Reactor Recirculation Pump Quick Restart ALTERNATE PATH: D KIA NUMBER:

2.2.40 IMPORTANCE FACTOR: 3.4 4.7 APPLICABILITY: RO SRO EoD Ro[KJ STAD sRoD EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.RPV-0003 Rev 23 TOOLS, EQUIPMENT AND PROCEDURES:

Steam Tables/Calculator ESTIMATED COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 16

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 INITIAL CONDITIONS:

1. The Reactor was scrammed when both Reactor Recirculation Pumps tripped.

2. Evidence of thermal stratification is present.

3. Actions have been taken in accordance with HC.OP-AB.RPV-0003 through step G.11.

INITIATING CUE:

Complete HC.OP-AB.RPV-0003 step G.12 as necessary for restart of A Reactor Recirc Pump.

Page 3 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

COMMENTS STEP NO.

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC. OP-AB. RPV-0003.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be G.12.

G.12 ENSURE Differential Temperature Operator obtains HC.OP-AB.RPV-0003 requirements are met by completing Attachment 2.

Attachment 2. [TIS 4.4.1.4]

Page 4 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

HC.OP-AB-RPV-0003 Attachment 2 1.0 REACTOR VESSEL TO BOTTOM HEAD DRAIN LINE DIFFERENTIAL TEMPERATURE CRITERIA NA 1.1 Rx Pressure Vessel Steam Space Coolant Saturation Temperature. (Rx Pressure and Steam Tables) (Note 1) Operator reads Note 1.

Operator determines RPV pressure 885 psig. (900 psia)

Operator determines Steam space

Coolant Saturation Temperature to be 900 psia = 532 degF (Steam Tables)

Operator records value in space provided on Attachment 1.

Page 5 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Note 1 Steam Table as part of this attachment may be utilized to I determine temperature rounding the numbers in a conservative fashion.

For a more accurate conversion from NA pressure to temperature a more detailed set of steam tables should be utilized.

1.2 Bottom Head Drain Coolant Temperature. (Note 2) (Computer Point A2942) Operator accesses GRIDS terminal.

Note 2 RWCU Flow required for accurate Bottom Head Drain Coolant Temperature indication. Operator reads Note 2.

Operator determines RWCU is in service and the Bottom Head Drain Coolant Temperature is valid.

Operator obtains value of 467 degF

from GRIDS point A2942.

~~-

Page 6 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart STEP (*Denotes a Critical Step)

COMMENTS NO.

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT I STANDARD # S/U evaluation) 1.3 < 145°F between Rx Pressure Vessel

Steam Space Coolant AND Bottom Operator subtracts value of step 1.2 Head Drain Line Coolant (A- B). [T/S from value of step 1.1. and determines 4.4.1.4] value of 65 degF .+/- 1F.

Operator records value in space provided.

1.4 Time Readings taken: Operator records current time in space

provided.

2.0 REACTOR VESSEL TO RECIRCULATION LOOP DIFFERENTIAL TEMPERATURE NA CRITERIA.

Page 7 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart STEP (*Denotes a Critical Step)

COMMENTS NO. ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation) 2.1 Temperature of the Rx Coolant within the idle loop to be started up.

Operator reads Note 3.

(Note 3)

Note 3 Use TR-650-831 Recirc Pump Suction Loop A(8) (if available) OR if above 400° F- GRIDS points A221 and A222 for A loop (A223 and A224 for 8 loop). IF below 400°F AND TR-650-831 not available, THEN have NA I&C obtain temperatures using RTD ohm values (reference RTD ohm values to calibration data in TOR using HC.OP-GP.ZZ-0008(0))

Page 8 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator determines Idle Recirc Loop Temp for A Loop is above 400 F.

Operator obtains value of 510 degF from GRIDS point A221 or A222.

2.2 Temperature of coolant in the Rx Pressure Vessel. (RX Pressure and Steam Tables) (Note 1) Operator reads Note 1.

Operator determines RPV pressure is

885 psig. (900 psia)

Operator determines Steam space Coolant Saturation Temperature to be:

900 psia = 532 degF (Steam Tables)

Operator records value in space provided on Attachment 1.

Page 9 of 16

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME: - - - - - - - - - - - - - - - - - -

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step) COMMENTS STEP ELEMENT NO. (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # I S/U evaluati 2.3 < 50°F between the Rx Coolant within

Operator determines differential temp is the loop not in operation AND the

<50 F.

Coolant in the Rx Pressure Vessel (A-B). [T/S 4.4.1.4] Examiner Note:

Actual value is 22 degF .+/- 1 F.

2.4 Time Readings taken: _ _ _ _ __ Operator records current time in space

provided.

HC.OP-AB-RPV-0003 ENSURE Differential Temperature

G.12 requirements are met by completing Operator initials step G.12.

Attachment 2. [TIS 4.4.1.4]

CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 10 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC RO A-2 TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 11 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Reactor was scrammed when both Reactor Recirculation Pumps tripped.

2. Evidence of thermal stratification is present.

3. Actions have been taken in accordance with HC.OP-AB.RPV-0003 through step G.11.

INITIATING CUE:

Complete HC.OP-AB.RPV-0003 step G.12 as necessary for restart of A Reactor Recirc Pump.

Page 12 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I. C.

INITIALIZE the simulator to 100% power, MOL.

Trip both Reactor Recirc Pump Drive Motor Breakers.

Take appropriate Scram actions lAW HC.OP-AB.ZZ-0001.

IMPLEMENT EOP-1 01 to stabilize plant at 885 psig RPV pressure on DEHC.

IMPLEMENT HC.OP-AB.RPV-0003 up to and including step G.11.

Acknowledge alarms.

Put Simulator in FREEZE.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

!Initial I Description MARKUP a copy of HC.OP-AB.RPV-0003 up to and including step G.11.

ENSURE Mode Switch key is removed.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE:

Initial ET#

Event code:

Description:

Event code:

Description:

Event code:

Description:

Page 13 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 14 of 16

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC RO A-2 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC RO A-2 REV#: 1 TASK: Perform a Reactor Recirculation Pump Quick Restart

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk(*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

STATION: Hope Creek SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

JPM NUMBER: 2013 NRC RO A-3 ALTERNATE PATH: D KIA NUMBER: 2.2.41 IMPORTANCE FACTOR: 3.5 3.9 APPLICABILITY: ----=-R-=-0---

SRO EoD Ro[K] STAD sRoD EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

M-52-1 Sh. 1 Core Spray P&ID TOOLS, EQUIPMENT AND PROCEDURES:

M-52-1 Sh. 1 Core Spray P& ID Electrical Core Spray P&ID for F001A AND CSS 'A' Pump Motor VALIDATED JPM COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE OR DESIGNEE OR DESIGNEE CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the SM or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION: Minutes JPM PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-'B' RHR Pump is CIT for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

Successful Completion Criteria:

1. All critical steps completed.

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.

Nuclear Common Page 2 of 6 Rev.1

NC.TQ-WB.ZZ-0310(Z)

JPM: 2013 NRC RO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

Operator obtains M-52..:1 Sh. 1 Core Operator obtains the correct drawings Spray P&ID and Electrical Core Spray P&ID for F001A AND CSS 'A' Pump Motor START TIME:

1. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical isolation valves:

required to ISOLATE the leak on the suction of the AP206 Core

HV-F001A SHUT Spray pump.

V-009 SHUT

V-027 SHUT

V-037 OPEN (check valve bypass)

V-045 SHUT

V-049 SHUT

V-107 SHUT

PSV F-032A GAGGED OPEN

V-9974 SHUT

V-9975 SHUT

V-9996 SHUT

V-9997 SHUT

V-9998 SHUT

V-9999 SHUT Nuclear Common Page 3 of 6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC RO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

STEP

{*Denotes a Critical Step) EVAL {Required for UNSAT

NO. STANDARD

{#Denotes a Sequential Step) S/U evaluationl

2. Applicant reviews P&IDs and Applicant identifies the following identifies electrical components electrical components required for required to ISOLATE the leak on isolation:

the suction of the AP206 Core Spray pump.

MCC 108212, breaker 012 (HV-F001A)

1OA401, breaker 05 ('A' CSS Pump Motor)

3. Applicant reviews P&ID and Applicant identifies the following identifies mechanical components mechanical VENT valves in the OPEN required to VENT the isolated position:

section of the Core Spray train.

(Valves OPEN)

V-041 OPEN

4. Applicant reviews P&ID and Applicant identifies the following identifies mechanical components mechanical DRAIN valves in the OPEN required to DRAIN the isolated position:

section of the Core Spray train.

(Valves OPEN)

V-108

5. STOP TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common Page 4 of 6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE~=-----------------

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

QUESTION:

RESPONSE

RESULT: -SAT - UNSAT QUESTION:

RESPONSE

RESULT: -SAT - UNSAT Nuclear Common Page 5 of 6 Rev. 1

NC. TQ-WB.ZZ-031 O(Z)

INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-'8' RHR Pump is CIT for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001 A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

Nuclear Common Page 6 of6 Rev.1

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 JPM NUMBER: 2013 NRC RO A-4 REV#: 01 SAP BET: NOH05JPZZ19E ALTERNATE PATH: D APPLICABILITY:

EOD RO [KJ STA D SRO D DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC RO A-4 REV: 01 SYSTEM: Administrative TASK NUMBER: 4000270401 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates ALTERNATE PATH:

D KIA NUMBER:

IMPORTANCE FACTOR:

295938 EA 1.01 3.9 4.2 APPLICABILITY: RO SRO EoD Ro[KJ STAD SROD EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0004 Rev. 5 HC.OP-DL.ZZ-0026 Rev. 128 TOOLS, EQUIPMENT AND PROCEDURES: Calculator ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

-- - - Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 13

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 INITIAL CONDITIONS:

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590.

2. SPDS is unavailable.

3. Abnormal HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity.

4. NPV Exh Flow instrumentation channel 9AX300 is inoperable. Flow is being estimated in accordance with HC.OP-DL.ZZ-0026(0), Attachment 3u (Provided).

INITIATING CUE:

Determine the Release Rate of NOBLE GAS from the NPV in accordance with HC.OP-AB.CONT-0004, Action A.4.

Page 3 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-4 OPERATOR TRAINING PROGRAM NAME: - - - - - - - - - - - - - - - - - -

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates

(*Denotes a Critical Step) *

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.CONT-0004.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be A.4 A.4 DETERMINE the Total Release Rates Operator determines that to calculate of Noble Gas and Iodine as follows: the Noble Gas release from the NPV USE the SPDS Noble Gas Total. the formulas in Table "A" must be used.

OR USE one of the Formulas in Table "A".

Page 4 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates

{*Denotes a Critical Step)

COMMENTS STEP ELEMENT {#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U evaluation) lEthe effluent (IJCi/sec) channel on the RM-11 is NOT operating for a specific plant vent, THEN CALCULATE the Noble Gas release rate for that vent using the following:

472 =

Plant Vent Exh iJCi/sec (n.g.)

iJCi/cc (n.g.)

Flow in cfm Where:

iJCi/sec (n.g.) - the calculated release rate from the specified plant vent (Noble Gas) iJCi/cc (n.g.) - The concentration of Noble Gas obtained from the RM-11 (the operable channel will be highlighted in GREEN) OR from an actual sample of the plant vent 472 - The conversion factor in units of cc/sec/cfm Operator manipulates the RM-11

terminal to obtain the value of NPV Noble Gas release from the 9RX602 Low Range detector and enters the value into the formula.

3.65E-7 uCi/cc.

Operator transfers the Plant Vent Exh

Flow value from Attachment 3u of :

HC.OP-DL.ZZ-0026 (provided).

49613.9 CFM !

- - - ~-

Page 5 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC RO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates

{*Denotes a Critical Step) *

COMMENTS STEP ELEMENT {#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U evaluatio Operator calculates the NPV Noble Gas

release rate.

Calculated Value=

3.65E-7 JJCi/cc

49613.9 CFM

472

=8.547 uCi/sec (+/- 0.5)

CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 6 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC RO A-4 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 7 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590.

2. SPDS is unavailable.

3. Abnormal HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity.

4. NPV Exh Flow instrumentation channel 9AX300 is inoperable. Flow is being estimated in accordance with HC.OP-DL.ZZ-0026(0), Attachment 3u (Provided).

INITIATING CUE:

Determine the Release Rate of NOBLE GAS from the NPV in accordance with HC.OP-AB.CONT-0004, Action A.4.

Page 8 of 13

HC.OP-DL.ZZ-0026(Q)

JOB PERFORMANCE MEASURE ATTACHMENT 3u Page 1 of 1 Radioactive Gaseous Effluent Monitoring (North Plant Vent)

T/S 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 1f the North Plant Vent Flow Rate Monitor is Inoperable, then Effluent Releases via this pathway may continue for up to 30 days provided flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Readings are taken every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to ensure that the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Tech Spec Action limit is not exceeded per administrative requirements and after a change in the ventilation line-up.

If flow indication(s) become unavailable, then the "NORM" flow value may be logged for the specific fan alignment.

HCGS DATE: Today's Date Location Auxffurb/Radwaste ENTER TIME OF EACH READING BELOW PARAMETER NORM NOW

- -= I I COMMENTS SOLID RADWASTE EXH FAN A318 17,000 17358 SOLID RADWASTE EXH FAN 8318 17,000 17163 CHEMLA8EXH A307 7,500 7528 CHEMLA8EXH 8307 7,500 7519 '

OFFGAS DISCHARGE HA-XR- --- l 10022 OR HA- 45.9 I FI5665 TOTAL FLOW 49613.9 ESTIMATED TOTAL FLOW REPORTED TO RAD PRO- (YES) Yes

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I. C.

INITIALIZE the simulator to 100% power, MOL.

INSERT Malfunctions:

RM9590@ O.OE+OO

RM9591 @ O.OE+OO

RM9602 @ 3.65E-7

RM9603 @ O.OE+OO

CC03 SPDS CRT Failure Acknowledge alarms.

Put Simulator in FREEZE.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

I Initial l Description ENSURE SPDS and CRIDS Displays are off.

ENSURE MARKUP copy of HC.OP-DL.ZZ-0026 Attachment 3u available.

COMPLETE "Simulator Ready-for-Training/Examination Checklist".

EVENT FILE:

Initial ET#

Event code:

Description:

Event code:

Description:

Event code:

Description:

Page 10 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description 9RX590, NPV EFF - North Plant Vent None None Insert malfunction RM9590 to 0.00000 Noble Gas Effluent 9RX591, NPV HIGH- North Plant None None Insert malfunction RM9591 to 0.00000 Vent High Range Noble Gas 9RX602, NPV LOW - North Plant None None Insert malfunction RM9602 to 3.65E-7 Vent Range Noble Gas 9RX603, NPV MID- North Plant Vent None None Insert malfunction RM9603 to 0.00000 Mid Range Noble Gas None None Insert malfunction CC03 SPDS CRT failure REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 11 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC RO A-4 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC RO A-4 REV#: 1 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity- Calculate Noble Gas Release Release Rates

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 JPM NUMBER: 2013 NRC SRO A-1 REV#: 01 SAP BET: NOH05JPZZ03E ALTERNATE PATH: D APPLICABILITY:

EoD ROD STA D SRO [ ] ]

DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC SRO A-1 REV: 01 SYSTEM: Radiation Control TASK NUMBER: 2990420302 TASK: Verify Compliance with Gaseous Release Permit ALTERNATE PATH: D KIA NUMBER: 2.3.6 IMPORTANCE FACTOR: 2.0 3.8 APPLICABILITY: RO SRO EoD RoD STAD sRo[KJ EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

OP-HC-103-105 Rev 1 TOOLS, EQUIPMENT AND PROCEDURES:

Prepared OP-HC-1 03-105 Form 2, Calculator ESTIMATED COMPLETION TIME: 9 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: ___N_IA ___ Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 13

TQ-AA-1 06-0303 NAME: ----------------------

DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0436, the Purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation, due to a damper problem.

5. At 0800, Purging of Primary Containment re-commenced.

6. At 1252 today Operational Condition 4 was entered.

7. At 1548 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE:

Review AND Close Out today's Containment Prepurge Cleanup, lnerting, Or Pressure Control Valve Permit in accordance with OP-HC-1 03-105.

Page 3 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio CUE PROVIDE the operator the initiating cue AND:

D Prepared OP-HC-103-105 log Operator repeats back initiating cue.

Forms 1 & 2 (Attached)

D Copy of OP-HC-103-105 CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 4.4.6.

Page 4 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit STEP (*Denotes a Critical Step) COMMENTS ELEMENT NO. (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U evaluation 4.4.6 The SM/CRS should verify the calculations, sign in the appropriate Operator reviews Form 2.

space for verification and close out and enter the time and date.

Operator recognizes NCO incorrectly

rounded down from 2.6 to 2.5 instead of rounding up to 3.0 lAW 4.4.3 during calculation of first purge period.

Operator recognizes NCO incorrectly

used securing of purge lineup for end time of second purge period instead of using entry into OPCON 4 time lAW step 4.4.2.

CUE !E the operator requests the NCO to make changes, THEN DIRECT the operator to make N/A any required changes.

Page 5 of 13

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

{*Denotes a Critical Step) COMMENTS STEP

ELEMENT {#Denotes a Sequential Step) EVAL {Required for UNSAT NO. #

STANDARD S/U evaluation 4.4.6 The SM/CRS should verify the Operator makes corrections to Form 2

calculations, sign in the appropriate Stop times and Total Hours.

space for verification and close out Examiner Note: Refer to Examiners and enter the time and date.

Copy for appropriate corrections.

CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 6 of 13

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC SRO A-1 TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UN SAT

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE FORM2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit#: 020020001 Calculate Total Hours Open During Previous Year (Note 1) 452 hrs NUMBER OF HOURS

(-) 35.5

(=) 24 4/3/11 6/25/11 24 8/30/11 8/31/11 Dateffime Jolin Smitli Today/0100 SM/CRS verification and authorization Dateffime

}lnarew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 0436 u 3.0 0800 4e4S 1252 8-:G 5.0 Total number of hours valves/line open this permit: _ _ _. . :. 1.=. 0:. : .5---=-8*:. : 0_ __

NCO performing calculations ------=)f_ruf.___.,ry'-q"'-r._ll_na_t_e_{[i_z_ _ __ Dateffime __'Ii_od"a----Lryi~'%._ow 1)4fe/7U~te SM/CRS Closing permit ---~-~ 111

_ _ _S_UJ4_"__f<<<r,e _ _ __ Dateffime Note 1: The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-104 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0436, the Purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation, due to a damper problem.

5. At 0800, Purging of Primary Containment re-commenced.

6. At 1252 today Operational Condition 4 was entered.

7. At 1548 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE:

Review AND Close Out today's Containment Prepurge Cleanup, lnerting, Or Pressure Control Valve Permit in accordance with OP-HC-1 03-105.

OP-HC-1 03-1 05 IJ~D~D~ @~[SW Revision 0

@[p[§~IJ@~ @@[p)f Page 7 of 8 FORM 1 Page of_ _

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO I PREV. AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL I YEAR THIS PERMIT PERMIT PREVIOUS (Note 1) PERMIT YEAR (Note 1)

I 4/3/11 22.5 24 H. David S(]) 5.5 28.0 S. West S(])

6/25/11 18.5 24 G. Williams ifi}{W 3.5 22.0 G. Cloon ifi}{W 8/30/11 22.0 24 W. Holmes I]{ 24.00 46.0 P. Price I]{

8/31/11 46.0 24 B. Lee P, 2.5 48.5 V. Bonovan P, Today 35.5 24 A. Jones JS Note 1:The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

LFm&D[mO[m @[m!1W OP-HC-1 03-105 Revision 0

©l?C§m&LF©~ ©©l?W Page 8 of 8 FORM2 CONTAINMENT PREPURGE CLEANUP. INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit#: 020020001 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) H 35.5 DATE NUMBER OF HOURS Hours available this date (line 1 minus line 2 {=} 24 4/3/11 5.5 OR 24, whichever is less) 6/25/11 3.5 Hours authorized this date (max 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 24 8/30/11 24.0 8/31/11 2.5 NCO performing calculation Date/Time Jofin Smitfi Today/0100 SM/CRS verification and authorization Date/Time

}lnarew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 0436 2.5 0800 1548 8.0 Total number of hours valves/line open this permit: 10.5 NCO performing calculations )lndj qranatelli Date/Time rr'otfay/Now SM/CRS Closing permit Date/Time Note 1: The previous year includes the period from 2400 on today's date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-1 04 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

OP-HC-1 03-105 Revision 0 Page 8 of 8 REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-1 Rev# Date Description Validation Required?

OP-HC-1 03-105 Revision 0 Page 8 of 8 VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-1 REV#: 01 TASK: Verify Compliance with Gaseous Release Permit

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: SRO Name Qual Signature Date Name Qual Signature Date

STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 JPM NUMBER: 2013 NRC SRO A-2 ALTERNATE PATH: D KIA NUMBER: 2.1.29 IMPORTANCE FACTOR: 3.4 3.3 APPLICABILITY: RO SRO EoD RoD STAD SRO[KJ EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

HC.OP-IO.ZZ-0003 Rev 71 TOOLS, EQUIPMENT AND PROCEDURES:

NSSSS Elementary Print 821-1090-0062, P&ID M-041, Computer with access to SAP VALIDATED JPM COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A APPROVAL:

N/A BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE OR DESIGNEE OR DESIGNEE CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the SM or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION: Minutes JPM PERFORMED BY:

GRADE: D SAT D UNSAT REASON. IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 INITIAL CONDITIONS:

1. A start-up is in progress lAW HC.OP-IO.ZZ-0003.

2. Preparations are being made to enter Operational Condition 1 lAW Attachment 4 of the lOP.

3. The Current Mode has been changed to Mode 1 lAW step IV.1.2.1 of Attachment 4.

4. A Components in OFF-Normal Position Report has been generated lAW step IV.1.2.3 of HC.OP-IO.ZZ-0003 Attachment IV.

INITIATING CUE:

Review the Components in OFF-Normal Position Report and determine if any components require re-positioning lAW step IV.2.4 of HC.OP-IO.ZZ-0003 Attachment 4.

You will be allowed access to SAP and DCRMS to research component data.

The provided Off Normal Report does NOT reflect the current status of the actual plant.

Do NOT perform ANY changes to actual plant data.

Successful Completion Criteria:

1. All critical steps completed.

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.

Nuclear Common Page 2 of6 Rev.1

NC.TQ-WB.ZZ-0310(Z)

JPM: 2013 NRC SRO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev:01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Conduct of Operations TASK Initiate and Review System Lineup Sheets STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation) I HC.OP-IO.ZZ-0003 Attachment 4 IV.1.2.3 GENERATE a Components In Examiner Cue: PROVIDE the N/A N/A Off-Normal Position Report Operator the attached Components USING WCM Reports/Off Normal In Off-Normal Position Report for Report function. review.

IV.1.2.4 START TIME: Operator reviews Components In Off-Normal Position Report.

POSITION all components as required. Operator recognizes that handswitches for E-521 Separator Heater (HS-8722A

& HS-87228) are in AU.

Operator recognizes handswitches for E-521 Separator Heater (HS-8722A &

HS-87228) should be in SO in OPCON 1.

Examiner Note: AU=Automatic SO=Stop/Off STOP TIME: I Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common Page 3 of 6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE~: _________________

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2013 NRC SRO A-3 QUESTION:

RESPONSE

RESULT: -SAT - UNSAT QUESTION:

RESPONSE

RESULT: -SAT - UNSAT Nuclear Common Page 4 of 6 Rev. 1

NC. TQ-WB.ZZ-031 O(Z)

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A start-up is in progress lAW HC.OP-IO.ZZ-0003.

2. Preparations are being made to enter Operational Condition 1 lAW Attachment 4 of the lOP.

3. The Current Mode has been changed to Mode 1 lAW step IV.1.2.1 of Attachment 4.

4. A Components in OFF-Normal Position Report has been generated lAW step IV.1.2.3 of HC.OP-IO.ZZ-0003 Attachment IV.

INITIATING CUE:

Review the Components in OFF-Normal Position Report and determine if any components require re-positioning lAW step IV.2.4 of HC.OP-IO.ZZ-0003 Attachment 4.

You will be allowed access to SAP and DCRMS to research component data.

The provided Off Normal Report does NOT reflect the current status of the actual plant.

Do NOT perform ANY changes to actual plant data.

Nuclear Common Page 5 of 6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

JOB PERFORMANCE MEASURE User: NUJ8B Off Normal Report Date: 10/26/2005 Plant: NNUC Mode 01 Time: 09:10:58 echnical Object escription oc. Description em ark OKD -O-KD-V455 UX BLDG TRUCK WASH DRAIN C YARD-EAST OF POWER BLOCK EF NOTIF# 20248261 OKD -O-KD-V456 UX BLD TRK W/DWN EXTER HYDRT C YARD-HHB/AUX STM TRENCH AREA EF NOTIF# 20248261 OKD -O-KD-V458 B S TRK W/DN EXTR HYDRT ISO V C YARD-SOUTH OF POWER BLOCK EF NOTIF# 20248261 OLE -HS-8722A NDSWCH,OA-E-521 SEPARATOR HTR C YARD-OIL & WASTEWTR TRT AREA S PER CHEMISTRY OLE -HS-8722B NDSWCH,OB-E-521 SEPARATOR HTR IHC YARD-OIL & WASTEWTR TRT AREA S PER CHEMISTRY OLE -HS-8776 S,OOP589 OIL RECYCLE PMP SW OOC574 PN C YARD-OIL & WASTEWTRTRT AREA S PER CHEMISTRY OLE -HS-8777 /S,OOE523 SLUDGE TK HTR OOC574 PNL C YARD-OIL & WASTEWTRTRT AREA S PER CHEMISTRY OZZ -OOB508-01 PARE C DEEPWELL PUMPHOUSE LOS ED TO SUPPORT TEMPORARY LIGHTING ozz -OOB508-03 PARE C DEEPWELL PUMPHOUSE ANGED TO BKRS 1 & 5 OZZ -OOB508-05 PARE C DEEPWELL PUMPHOUSE ANGED TO BREAKERS 1 & 3 OZZ -OOL327-08 PARE C UNRESTRICTED MACHINE SHOP B PER ORDER# 60054720 OZZ -OOL327-09 PARE C UNRESTRICTED MACHINE SHOP B PER ORDER# 60053935 OZZ -OOL327-10 PARE C UNRESTRICTED MACHINE SHOP B PER ORDER# 60054720 OZZ -OOL327-12 PARE C UNRESTRICTED MACHINE SHOP B ER ORDER # 60055303 OZZ -OOL327-23 PARE C UNRESTRICTED MACHINE SHOP B PER ORDER# 60053935 OZZ -OBJ595-22 PARE C HC/SALEM COMMON GDHSE EL.104' UPPLYING UNKNOWN LOAD NOT# 20247903 OZZ -OBJ595-23 PARE C HC/SALEM COMMON GDHSE EL.104' UPPLYING UNKNOWN LOAD NOT# 20247903 ozz 595071 PARE C AUX BLR SUBSTA ROOM-S.E.QUAD KR DCP'D-PWR SUPPLY TO BRE 1KC KC-V282 TRAINER B/D VLV C FUTURE CONTROLLED STOR AREA D 0240203 NO THREADS TO PUT CAP ON 1QA -10L221-08 TG,TORUS PLATF EL 77 C MCCAREAC ORUS PROPER CLOSEOUT-RP PROCEDURE 1QA -10L221-09 ECEPT,TORUS PLATF EL 77 C MCCAREAC ORUS PROPER CLOSEOUT-RP PROCEDURE 1QA -10L221-10 TG,TORUS PLATF EL 77 C MCCAREAC ORUS PROPER CLOSEOUT-RP PROCEDURE 1AB-1ABV501 NST PDT-N086C&DISO VLV PEN J25 C TORUS AREA A, AZIMUTH 0-45 LOSED FOR I&C 1AB -1ABV504 NST PDT-N086C&DISO VLV PEN J25 C TORUS AREA A, AZIMUTH 0-45 LOSED FOR I&C 1ZZ -10L221-11 ECEPT,TORUS PLATF EL 77 C MCCAREAC ORUS PROPER CLOSEOUT-RP PROCEDURE 1ZZ -1CD318-08 PARE C AUXILIARY PANEL ROOM EE NOTIFICATION 20223509 1ZZ -1CD318-23 PARE C AUXILIARY PANEL ROOM EE NOTIFICATION 20223509 1zz 272024 PARE C MCCAREAB reaker removed 1ZZ 313035 PARE C H&V EQUIPMENT AREA B PARE 1ZZ 313053 PARE C H&V EQUIPMENT AREA B PARE 1ZZ 313054 PARE C H&V EQUIPMENT AREA B PARE Nuclear Common Page 6 of 6 Rev.1

STATION: Hope Creek SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

JPM NUMBER: 2013 NRC SRO A-3 ALTERNATE PATH: D KIA NUMBER: 2.2.41 IMPORTANCE FACTOR: 3.5 3.9 APPLICABILITY: RO SRO EoCJ RoO STAO SRO[TI EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

M-52-1 Sh. 1 Core Spray P&ID TOOLS, EQUIPMENT AND PROCEDURES:

M-52-1 Sh. 1 Core Spray P& ID Electrical Core Spray P&ID for F001A AND CSS 'A' Pump Motor Technical Specifications VALIDATED JPM COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE OR DESIGNEE OR DESIGNEE CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the SM or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION: Minutes JPM PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-'B' RHR Pump is CIT for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

Identify the most limiting Tech Spec condition (if any) AFTER the leak has been isolated.

Successful Completion Criteria:

1. All critical steps completed.

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.

Nuclear Common Page 2 of6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC SRO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Equipment Control TASK" Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a SeQuential Step) S/U evaluation)

Operator obtains M-52-1 Sh. 1 Core Operator obtains the correct drawings Spray P&ID and Electrical Core Spray P&ID for F001A AND CSS 'A' Pump Motor START TIME:

I I

1. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical isolation valves:

required to ISOLATE the leak on the suction of the AP206 Core

HV-F001 A SHUT Spray pump.

V-009 SHUT

V-027 SHUT

V-037 OPEN (check valve bypass)

V-045 SHUT

V-049 SHUT

V-107 SHUT??

PSV F-032A SHUT ??

V-9974 SHUT

V-9975 SHUT

V-9996 SHUT

V-9997 SHUT

V-9998 SHUT

V-9999 SHUT Nuclear Common Page 3 of 6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

JPM: 2013 NRC SRO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 1 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD

(#Denotes a Sequential Step) S/U evaluationl

2. Applicant reviews P&IDs and Applicant identifies the following identifies electrical components electrical components required for I required to ISOLATE the leak on isolation:

the suction of the AP206 Core Spray pump.

MCC 108212, breaker 012 (HV- I F001A)

1OA401, breaker 05 ('A' CSS Pump Motor)

3. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical VENT valves in the OPEN required to VENT the isolated position:

section of the Core Spray train.

(Valves OPEN)

V-041 OPEN

4. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical DRAIN valves in the OPEN required to DRAIN the isolated position:

section of the Core Spray train.

(Valves OPEN)

V-108

5. Applicant reviews Tech Specs and Applicant identified the following as the identifies the most limiting Tech most limiting Tech Spec Action Spec action statement AFTER Statement:

leak isolation.

3.5.1.a.1 Restore within 7 days of be in Hot S/D within 12hrs and Cold S/D within 24hrs

6. STOP TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common Page 4 of 6 Rev.1

NC. TQ-WB.ZZ-031 O(Z)

OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE.~=-----------------

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

QUESTION:

RESPONSE

RESULT: -SAT - UNSAT QUESTION:

RESPONSE

RESULT: -SAT - UNSAT Nuclear Common Page 5 of 6 Rev. 1

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-'8' RHR Pump is CIT for routine maintenance

-A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001 A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

Identify the most limiting Tech Spec condition (if any) AFTER the leak has been isolated.

Nuclear Common Page 6 of6 Rev.1

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow)

TASK NUMBER: 2990010101 JPM NUMBER: 2013 NRC SRO A-4 REV#: 01 SAP BET: NOH05JPZZ36E ALTERNATE PATH: D APPLICABILITY:

EO D RO [KJ STA D SRO [KJ DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC SRO A-4 REV: 01 SYSTEM: Equipment Control TASK NUMBER: 2990010101 TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow)

ALTERNATE PATH: D KIA NUMBER: 2.2.23 IMPORTANCE FACTOR: 3.1 4.6 APPLICABILITY: RO SRO EoD Ro[KJ STAD SROCK]

EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0026 Rev 128 TOOLS, EQUIPMENT AND PROCEDURES:

Blank HC.OP-DL.ZZ-0026 ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of 15

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow)

TASK NUMBER: 2990010101 INITIAL CONDITIONS:

1. The plant is at 100% power.

2. B Circ Water Pump is tagged for motor replacement.

3. A, C, and D Circ Water Pumps are in service.

4. Cooling Tower Slowdown Weir Flow Rate Monitor OSP-RI4861 is reading blank and is INOPERABLE. TSAS # 2012-001 entered.

5. RM-11 point 9AX327 historical data is NOT available.

6. SSW Loop Flow GRIDS Point values as follows:

A2440 SERVICE WATER FLOW RATE DIVA= 13,560 gpm

A2441 SERVICE WATER FLOW RATE DIV B = 21,345 gpm INITIATING CUE:

You are the Reactor Operator.

The CRS has directed you to complete HC.OP-DL.ZZ-0026 Attachment 1a ITEM 47 Day Shift reading for the inoperable RMS Cooling Tower Slowdown Weir Flow Rate Monitor.

Page 3 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio CUE PROVIDE the operator the initiating cue AND:

Operator repeats back initiating cue.

A blank copy of HC.OP-DL.ZZ-0026.

CUE I ENTER START TIME AFTER Operator repeats back the Initiating Cue: I N/A START TIME:

HC.OP-DL.ZZ-0026 Attachment 1a I N/A ITEM CHANNEL CHECK: COOLING Operator reads ITEM 47.

47 TOWER SLOWDOWN WEIR FLOW RATE MONITOR OPER COND Operator determines the ITEM is AT ALL TIMES applicable is the current Op Condition ACCEPTABLE LIMITS MIN NORM MAX Operator reads the limits.

ITEM 002 < 40K ?OK INSTRUMENT (PANEL)

OSP-RI4861 (1 OC604) Operator reads NOTE 45 and ITEM 029 determines that data is not available RM-11 (9AX327) (NOTE 45) from the Initial Conditions.

Page 4 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME: ------------------

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluati NOTE Operator reads NOTE 33 and 33 determines that data is not available from the Initial Conditions.

NOTE Operator reads NOTE 35 and 35 determines that data is not available from the Initial Conditions.

NOTE IF INSTRUMENT IS INOP, USE 46 ATTACHMENT 3YTO ESTIMATE Operator reads NOTE 46 and

WEIR FLOW. THIS IS REQUIRED determines that Attachment 3Y is REGARDLESS OF WHETHER A applicable.

RADIOACTIVE LIQUID RELEASE IS IN PROGRESS.

Operator locates Attachment 3Y.

Examiner Note: Refer to steps below and Examiner Copy of Attachment 3Y for Standards associated with this step.

Page 5 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluatio HC.OP-DL.ZZ-0026 Attachment 3Y DATE Operator enters current date on Attachment 3Y.

METHOD 1 Operator determines data for Method 1 completion is not available and continues to METHOD 2.

TIME Operator enters current time on

Attachment 3Y under Method 2 SSW LOOP A FLOW# Operator reads # Footnote Page 6 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

READ FROM FIT-2218A/B OR FR-2218-1/2 OR CRIDS A2440/A2441.

(B SSW LOOP FLOW (FIT-2218B) IS OBTAINED LOCALLY AT PANAMETRICS MONITOR. FLOW Operator determines A SSW Loop Flow VALUE IS THE AVERAGE is 13,560 gpm from GRIDS point A2440 VOLUMETRIC FLOW RATE WHICH in the Initial Conditions. !

IS DISPLAYED AS "AVG I

VOLUMETRIC GAL/MIN" ON THE MONITOR DISPLAY.

I Operator enters the value 13,560 under

SSW LOOP A FLOW # on ATT 3Y.

SSW LOOP B FLOW# Operator reads # Footnote

READ FROM FIT-2218A/B OR FR-2218-1/2 OR CRIDS A2440/A2441.

I (B SSW LOOP FLOW (FIT -2218B) IS OBTAINED LOCALLY AT PANAMETRICS MONITOR. FLOW Operator determines B SSW Loop Flow VALUE IS THE AVERAGE is 21,345 gpm from GRIDS point A2441 VOLUMETRIC FLOW RATE WHICH in the Initial Conditions.

IS DISPLAYEO AS "AVG VOLUMETRIC GAL/MIN" ON THE MONITOR DISPLAY.

- - ~-

Page 7 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator enters the value 21 ,345 under

SSW LOOP B FLOW# on ATT 3Y.

TOTAL SSW FLOW Operator calculates Total SSW Flow at 34,905 gpm by summing Loop A and Loop B flows.

Operator enters the value 34,905 under

TOTAL SSW LOOP FLOW on ATT 3Y.

EVAPORATIVE LOSSES*. Operator reads

Footnote

REFERENCE PRINT 10855-M15-181-1 FOR EVAPORATIVE LOSS ESTIMATES. USE 16,700 GPM FOR DEFAULT VALUE(MIN. DILUTION FLOW), FOR EVAPORATIVE LOSS ESTIMATES IF 4 CIRCULATING Operator determines Evaporative WATER PUMPS ARE IN SERVICE, Losses from

Footnote at bottom of OR 12,500 GPM IF ONLY 3 page for 3 Circ Water Pump operation CIRCULATING WATER PUMPS as 12,500 gpm.

ARE IN SERVICE. THIS BLOCK IS N/A IF THE COOLING TOWER IS OUT OF SERVICE.

Page 8 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME: - - - - - - - - - - - - - - - - - -

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

(*Denotes a Critical Step) COMMENTS STEP

ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U eva I Operator enters the value 12,500 under

EVAPORATIVE LOSSES* on ATT 3Y.

TOTAL WEIR FLOW Operator determines TOTAL WEIR FLOW is 22,405 gpm by subtracting Evaporative Losses from Total SSW Loop Flow.

Operator enters the value 22,405 under

TOTAL WEIR FLOW on ATT 3Y.

HC.OP-DL.ZZ-0026 Attachment 1a I N/A Examiner Note: Refer to steps below and Examiner Copy of Attachment 1a for Standards associated with this step.

ITEM CHANNEL CHECK: COOLING Operator reads ITEM 47.

47 TOWER SLOWDOWN WEIR FLOW RATE MONITOR Page 9 of 15

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Slowdown Weir Flow)

STEP (*Denotes a Critical Step)

COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

DAY Operator logs DAY reading of F/1 or I INOP on ATTACHMENT 1a for ITEM

47. J Examiner Note: Operator will annotate with F/1 (Failed instrument), I INOP, or other similar description. I The entry should be circled. The TS Action Statement # and that Attachment 3Y should be entered in the comments area of attachment 1a line item 47.

INST TRIPPED Operator logs F/1 or INOP on ATTACHMENT 1a for ITEM 47 INST TRIPPED.

Page 10 of 15

TQ-AA-1 06-0303 CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from I N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 11 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC SRO A-4 TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

TASK NUMBER: 2990010101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UN SAT Page 12 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE HC.OP-Dl.ZZ..0026{Q~

ATTACHMENT 1a Pae~e 10 of 17 Surveillance Log -Control Room Operational Condition Date

-EM s*,)R\fEI LLA."JC: OPER AC2EP-ABLE Lit,' IT~ 1%-~UM:NT IPAN:L: JAY EVE 1/IC COM'r1ENTS co~m M'l NORM 'MIX 47 CHA~>'lEL CH:CK: COOLING AT ALL IT:M OSP-R4S51 ;1::::e.~~! TSAS 2012-oo1 TOWER BLOWDOWN '*'iEIR TiMES !)Jl <.:or=: 7CK ITEM 02[>

See Attachment 3Y FLOW ~ATE MOr>ITO~ RM-11 i9AX3~TI

- NO -- NST T~IPPc:O (NOTE 33 .* 35., 46 .. 47.}

45 CHAN"JEL OH:CJ<: CO<JL NG AT.t..LL - -- ITEM SP-RIS517 N/A (NOTE30 .. 41.)

TOW!:R SLOWDOWN TII.'ES 009 RADATI O*N MONTOR S.t..\~PL:O FLSVI' 1.0 - 14.0 SP-RI8517 :~ 1):5D4*,

ITEM 02<'

SAMPLE LO'N FLO','*' ALARl,l 1.0 - 1:J SP-RI8S17 ;~c~:o~)

ITEf,l OJ2

- GOOQ ---

ANY OF ITEM 45 49 CHAt,t*IEL CHECK: N:A (NOTE30.1

~o CH.I\MIEL CH:OCK: [NOTE30.}

R.I\CS RACIA- ON MOl 51 CHAt,NEL OHECI<: SA (1EC2e7; (NOTE30.!

LOCI" A R..:..DIATION MC CRlJS (=1:9~:,~):

RM-11 ('ilP..X~t:Cn E*2 CHA~,NEL CH:OCK: SACS - e=*~ SP-R145f*9E1CR i_1HC2e7~ (NOTE30.1 B RADIATION MONITOR C~IJS (F~£'5:!2).

Rl,l-11 (QR:>",::;:.

NOTE<:: 30. IF NORJAAL !.JST~UMENT IS INOP At,D CRICS IS USEC iFCLLO'.'.'ING EQU 'lA:...:ONCv R:OVIEV~I. T-Et-1 O~.JLY OBT..:..IN CRIDS VALUE FROM PAGE CIS-PLt.:1**. CRIDS* ?OI'H SIJW,'A~~' CC:O!: NOT PRCVIC:O AN ADEQUATE VALUE.' [7003732:i]

33. TC OB-A N V..!..U.JES ace OR Ct:2. ::"'lESS MCN ::g ~<;:yIN 006 OG: IJO~. THEN ITEM "3.

35. TO 08-A N VA"'LIES 023. 029. OR 073, PRESS MON PB, r:::Y IN 022 0::!9, OR 073, --':ON IE\-1 "B

40. TG OB-A N VA:..UE :44. P.=iESS I*'CN "8 KEY IN J44, -HEN IEM "'8. IF VALU!: IS 'JOT A- :J8:(* H..!.'*/:0 lg,C.Rti.D ~?.0 INV:OSTIGATE OPERABUTY

41. I::: OB"A N Vl(.. ,..JE *XIt. =>G:E!:S LIC: PB. f':EY I"J COG. TH!:N ITEM PE.

45. CHANNEL CHECK SHALL CONS IS- OF ".*':O?.IFiiNG INCICATION OF ROW CURING PERIGDS o= =iE'-.:OASE C'"'.t.,NN:O:... C-EO<: SHALL i:E MADE AT LEAS- ONC:O PER 24 HOURS ON CAYS O'H*\'H C:-' CG\ITINJOUS, PERIOD C OR BA"CH RELEASES A =IE r,*.A.JE WHa, THR::O SS'/\'.S PUI*'=.s AR:O IN-SERVICE. :..ND, -H:: R'.l-11 ~- AVAI~..A3l:O GECOR:*

THE LO'.... ES.T 0~ TH:O Lt..S.T 12iHO~RLYi AV!:G.A.GES FO=i Gftv"X3~7 :c-B FlO'N:- AS FOLL:JWS: FROM THE -o::. LEV:O~ t.t::NU -_,_::._r SAN BE A:;,RIVEJ AT BY DEPR:O:S3 'IJG TH:O "ESC" KEY. CLICK TH:O 'LC3SiRE"ORTS' Eh./10~-J. THEN --E "DAILY LOG S!:TUP" 3JTTON. (F1! OR -ypE '"Z..~CHI'*/:0' IN TH:O V:OLLO'.',' =uNOT ON Fl:O~D: CHANG;: DATE M,[l Tlt,*E U~~D!:R *a,TER S"AR- TI1,1E' TO AT L:OAST 12 -<ou:;s AGO (m1LYTHE BAGKSl= ..:..::::E K:OY ~IJ~4CTIO~,S T::J ER.:..s: EXISTING -=.xn: I*HHE F.E:.D UNDER 'OR E"JT::=:

PIJS ;COMMA. D:LIM*-ED):' ENTER TRtG42et-4' --'IS IS THE 5D MINUTE AVERAGE TREND FOR THE DESIRE;:! =*o t*lT; SELECT.=::, C:R C:.IO~ --E "F3=VI:*,v "'IJ" B._ITTON :..-

THE SCRE:O~,; BOTTOM -o JISPLAY THE. CAT.t... [70026506]

46. IF INSTR'..:M!:NT IS INOP.liS: ATTt..C-MENT 3"' -o ESTIM.I\-:0 1;\'Eiq FLOW -HIS IS REOUI~EC REGAG.DLESS c= '*VHETHER A R.t..DICACI'./E L QUID ~ELEt-.SE 1:; 1\1 PRC~3:~ES~..

47. REFER -o HC.OP-S.O.SP-0001ia'i, RACIAT ON MONITO=~ING SYS-EM OPERATION, FOR NOTES ON OPERABI:..IT".

Hope Creek Page 28 of 101 Rev. 128 Page 13 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE HC .OP -DL.ZZ-0026{0}

ATTACHMENT 3y Page 1 of 1 Radioactive Liquid Effluent Monitoring Instrumentation TIS 6.8.4.g ODCM Table 3.3.7.10-11tem 3b, ACTION 112 Wi:h the number of channe s OPERABLE less than requ red by the minimum channels OPERABLE requirement. then etfi*Jent releases

~*ia this pathwaj.' may continue provided the flow rate s estmated at !east once per 4 hourf:i durin*;~ actual releases Pump pertormance curves \VTD 322548) should be used ;fusing Method 3. [70042554]

Readings are taken regardless of whether a Liquid F'..elease is in progress.

DATE TODAY Readings are taken every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to ensure that the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Tech Spec Action Imit is NOT exceeded per administrative requirements.

Any one of the following Methods may be used to satisfy the requirements of Action 112.

ENTER liME OF E.Q.CH READING IN THET-= II, T + 3 HRS, T + 6 HRL ... , BLOCKS ITt METHOD 1 DIRECT READING OF WEIR FlOW (USE ANY ONE Of THE FOLLOWING)

A)- CRIDS POINT A!I:S27 (CTB SLOWDOWN DISCH FLOW]

1Tl~~ T=IJ T+3 HRS T + BHRS T+ 9HRS 12 HRS T'~- 15HRS ~+18HRS l+ 21 HRS l+ 24 HRS B)- Rlll-11, 9RX5<9S (PROCESS FLOWN)

C) -10C604 PANEL, LIQUID Rt\'i 0SP-RI4BB1 ~C.TB FLOW P.B.)

METHOO 2 CALCUlATED WEIR FLOW TIME SSW LOOP A fLOW#

1~~Rn

+

SSW LOOP B fLOW#

21345

=

TOTAL SSW FLOW

~on~

EVAPORATIVE LOSSES

12500

=

TOTAL WEIR FLOW 77.40~

+ = - =

~ ~~

+ =

+

=

METHOD 3 ESmATED WEIR FLOW (Vlll 322;., SHOULD BE USED F~ ~ ~

DATEJTIME A & C SSW PUMP FLOW O\'

+

f-B & 0 SW

~ t,

~

I

~ ~ D' -

IN -

=

TOTAL WEIR FLOW

\ ~ + ~ - =

'S~~\\

\ ~ v-

=

\ _......,--4" = =

RE=EREN;JE F;;;l~,- KS::-M15-1E.1-l F;Jq EVA=OR."'.TIVE LOS:;. ESTII,IATES. *usE 16,700 G=M FOR DE=AULT 'v'ALUE>:M'N. Ji~.-- 01*1 FLOW; =oR EV..!..=c=.A-1'/E LOSS E:STIMt..TES IF t. C RCiJLATING WATER =UMPS ARE IN SER'*l CE. OR 12,500 G=lA IF ot~l Y 3 CIRCULATING WATER PJI.'FS ll.RE IN SER*/ CE -HIS !LOG!<. s. N:A IF--iE G88:..1NG -o'.'.'ER IS OUT CF SER*.** CE -

READ FRO!.' FI--2212A,'S OR FR-22' 5-'*'2 0=.: CRIDS A2t..!.Q.'A2441. IE SSW LOOP FLOW ;FIT-221SB;i S OBT.:.. t-1:::0 UJC.o1.-LY II.T =.A."lll.METRIC:S ',10t-l -oR. FLC'o'." VALIJE IS T-E AVERAGE '*i;JLJt.1ETRG FLOW' RATE 'NHI::::H IS D SPLA.'>'ED AS "AVG VOLUMETRIC GAUMIW ON ""-E MONITOR DISF3.V Hope Creek Page 96 of 101 Rev. 128 Page 14 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1 . The plant is at 100% power.

2. B Circ Water Pump is tagged for motor replacement.

3. A, C, and D Circ Water Pumps are in service.

4. Cooling Tower Slowdown Weir Flow Rate Monitor OSP-RI4861 is reading blank and is INOPERABLE. TSAS # 2012-001 entered.

5. RM-11 point 9AX327 historical data is NOT available.

6. SSW Loop Flow GRIDS Point values as follows:

A2440 SERVICE WATER FLOW RATE DIVA= 13,560 gpm

A2441 SERVICE WATER FLOW RATE DIV B = 21,345 gpm INITIATING CUE:

You are the Reactor Operator.

The CRS has directed you to complete HC.OP-DL.ZZ-0026 Attachment 1a ITEM 47 Day Shift reading for the inoperable RMS Cooling Tower Slowdown Weir Flow Rate Monitor.

Page 15 of 15

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-4 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-4 REV#: 01 Perform the Watchstanding Duties of the Nuclear Control Room TASK: Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Slowdown Weir Flow)

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified (in-plant, control room, or simulator).

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the specified criteria and are identified with an asterisk (*).

8. Verify the JPM steps match the most current revision of the procedure.

9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict

b. ensure performance time is accurate VALIDATED BY:

Qualification Level Required: RO Name Qual Signature Date Name Qual Signature Date

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505 JPM NUMBER: 2013 NRC SRO A-5 REV#: 01 SAP BET: NOHOSJPCLOSE ALTERNATE PATH: D APPLICABILITY:

EO D ROD STA [ [ ] SRO [ [ ]

DEVELOPED BY: DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-1 06-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC SRP A-5 SYSTEM: Administrative Duties/Reporting Requirements TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition ALTERNATE PATH: D KIA NUMBER: 2.4.38 IMPORTANCE FACTOR: 2.2 4.0 APPLICABILITY: RO SRO EoD RoD STACK] SRoCK]

EVALUATION SETTING/METHOD: Simulator/Perform or In Plant/Simulate

REFERENCES:

Hope Creek Event Classification Guide, TOC Rev 0 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15/13 Minutes JPM PERFORMED BY: GRADE: D SAT D UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: I Minutes REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 2 of21

TQ-AA-1 06-0303 NAME:

DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportabilitv Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505 INITIAL CONDITIONS:

1. The plant was at 100% power with the AD483 inverter isolated to it's backup AC supply.

2. Then, a Loss of Offsite Power occurred.

3. All Emergency Diesel Generators have failed to start and all vital buses are de-energized.

4. Due to a loss of rod position indication, the Control Room was unable to verify the reactor shutdown, and EOP-101A is being implemented.

5. The following conditions exist:

A, C, and E APRMs are de-energized

B, D, and F APRMS are reading 0% power.

RCIC is injecting.

RPV Level is -80", rising after reaching a minimum value of -90".

RPV pressure is 900# being controlled with SRVs.

6. Efforts to energize the Vital buses have been unsuccessful; maintenance has reported that they should be able to restore the 'B' EDG to service in one hour.

7. The current 33ft. elevation wind direction is from 332° at 21 mph.

INITIATING CUE:

Based on this information, classify this event and make the initial notifications.

This is a Time Critical Task, and has two Time Critical elements.

Time zero for this event is now.

Page 3 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Administrative Duties/Reporting Requirements STEP NO.

ELEMENT I

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD II I TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition EVAL S/U COMMENTS (Required for UNSAT evaluati CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the correct Operator obtains Hope Creek Event procedure. Classification Guide.

ECG The primary tools for determining the Section emergency classification level are the 8.4 EAL flowcharts or EAL wallcharts. The user of the EAL flowcharts or wallcharts may (but is not required to) consult the EAL Technical Basis in order to obtain additional information concerning the EALs under classification consideration.

To use the EAL flowcharts or wallcharts, follow this sequence:

ECG ASSESS the event and/or plant Operator assesses the initial conditions, conditions and DETERMINE which and determines that S1, Loss Of AC Section ECG-EAL Group/Section is most Power, and S3, ATWS/Criticality are 8.4.1 appropriate. appropriate ECG sections.

Page 4 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME: - - - - - - - - - - - - - - - - - -

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT I

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD II I Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition EVAL S/U COMMENTS (Required for UNSAT evaluation ECG REVIEW EAL categories and Operator refers to Flowchart Diagrams Section subcategories on the appropriate and/or Wallcharts and identifies that the 8.4.2 flowcharts/wallcharts. Initial Conditions for EALs SS1.1, SG1.1, and SA3.1 are related to the event that has occurred.

ECG If using the ECG - EAL flowcharts, for each applicable subcategory, Section 8.4.3 REVIEW EALs in the subcategory beginning with the lowest emergency classification level to the highest classification level (left to right).

ENSURE all pages of a particular subcategory being considered are reviewed.

ECG If using the ECG - EAL Wallcharts, for each applicable subcategory, Section 8.4.4 REVIEW EALs in the subcategory beginning with the highest emergency classification level to the lowest classification level (left to right).

Page 5 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev:01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP NO.

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT STANDARD # S/U eval ,

ECG If in OPCON 1, 2 or 3, also REVIEW Section the Fission Product Barrier (FPB)

Table: N/A 8.4.5 ECG EXAMINE the FPB categories in the Operator refers to FPB Table and left column of the table. identifies that the Initial Conditions do Section not meet any FPB Table thresholds.

8.4.5.a ECG SELECT the category that most likely coincides with event conditions.

N/A Section 8.4.5.b ECG REVIEW all thresholds in this Section category for each fission product N/A 8.4.5.c barrier.

Page 6 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:-----------------

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG For each threshold that is exceeded, Section IDENTIFY its point value and 8.4.5.d DETERMINE the classification level in accordance with the instructions on the Fission Product Barrier Table (or in EAL Technical Bases, Attachment 1).

N/A If sum Emergency Action Levels Refer to Classify as:

is: (EALs) ECGATI#

UNUSUAL ANY loss or ANY potential loss 1

2,3 EVENT of Containment (NOTE 11 ANY loss or ANY potential loss 1\W 2 4,5 of either Fuel Clad or RCS Loss or potenballoss of ANY 3

6-11 two barriers

!MRE'C(

Loss of ANY two barriers

<lNH\_ 4 12,13 ANDLoss or potential loss of the

!MRE'C(

~-

~-- , thirdbamer Page 7 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

FPB The Primary Containment Barrier Operator reads NOTE.

Table should not be declared lost or NOTE potentially lost based on exceeding 1

Technical Specification action statement criteria, unless there is an event in progress requiring mitigation by the Primary Containment barrier.

When no event is in progress (Loss or Potential Loss of either Fuel Clad and/or RCS barrier) the Primary Containment Barrier status is addressed by Technical Specifications.

Page 8 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition STEP (*Denotes a Critical Step)

COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG REVIEW the associated EALs as Section compared to the event and SELECT 8.4.6 the highest appropriate emergency. If identification of an EAL is questionable refer to paragraph 8.1 above.

If there is any doubt with regard to assessment of a particular EAL, the ECG EAL Technical Bases Document should be reviewed. Words contained Operator reviews the EALs in section S, in an EAL that appear in uppercase and determines that EAL # 551.1 is the highest emergency action level met or and bold print (e.g., VALID) are exceeded (SITE AREA EMERGENCY).

defined at the end of the bases for the particular EAL or in ECG - EAL Technical Basis Document, !

Attachment 3, EP-HC-111-232, EAL Definitions. Words or numbers I contained in an EAL that are in bold print but not uppercase are EAL I threshold values (e.g.,;::::: 15 minutes).

I

~-

Page 9 of21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition STEP (*Denotes a Critical Step)

COMMENTS ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluatio ECG If an EAL has been exceeded, equal Section level EALs or lower level EALs are 8.4.7 not required to be seperately reported as long as the applicable information Examiner Note: Filling out the NRC is communicated to the NRC using Data Sheet is beyond the scope of this ECG Attachment 5, EP-HC-111-F5, JPM.

NRC Data Sheet & Completion Reference.

ECG When the Shift Manager (SM) is the Emergency Coordinator, the Shift Section 8.4.8 Technical Advisor (STA) is responsible to perform an independent verification of the EAL IF time permits, classification. The STA verification THEN Operator requests STA/IA does not alleviate the requirement of verification of classification.

the SM to make a timely Examiner Note: Due to time spent classification. Should the SM fill the assessing and/or nature of JPM STA role, independent verification of administration, Operator may not the EAL classification will be request a verification.

delegated to another on-shift SRO, thelndependentAssesso~

Page 10 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO.

STANDARD # S/U evaluati CUE IF the Operator requests the STAliA to independently verify the EAL Classification, THEN INFORM the Operator the N/A STAliA is not available.

ECG IDENTIFY and IMPLEMENT the Section referenced ECG form based on the 8.4.9 Emergency Classification Level.

Unusual Event Implement EP-HC-111-F1

Alert Implement EP-HC-111-F2 Operator identifies and implements EP-HC-111-F3 Attachment 3 Site Area

Site Area Emergency Implement EP-HC-111-F3 Emergency.

General Emergency Implement EP-HC-111-F4

Unusual Event (Common Site) Implement EP-HC-111-F24 ECG I. EMERGENCY COORDINATOR Att.3 (EC) LOG SHEET ECG CLASSIFICATION Att. 3.

A ECG CALL communicators to the Control Operator calls communicators to the Att.3 Room. Control Room.

1.

Page 11 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition STEP (*Denotes a Critical Step)

COMMENTS NO ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT

~ . STANDARD # S/U evaluationJ CUE After 2 minutes, report as the N/A communicators and give your name as CM1 and CM2.

ECG If a security event is in progress, Att. 3 THEN, IMPLEMENT the prompt Operator determines this step is not 2.

actions of NC.EP-EP.ZZ-0102, EC applicable.

Response, Attachment 10, prior to classification.

ECG As time allows, OBTAIN Classification Att. 3 lE time permits, Independent Verification (ensure THEN Operator requests STA/IA 3.

verifier understands the EAL verification of classification.

assessment clock is running); Examiner Note: Due to time spent

STA or designee performs assessing and/or nature of JPM Independent Verification for administration, Operator may not SM request a verification.

SM or designee performs Independent Verification for EDO

EDO or designee performs Independent Verification for ERM Page 12 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - - - -

SYSTEM: Administrative Duties/Reporting Requirements STEP NO. ELEMENT I

(*Denotes a Critical Step}

(#Denotes a Sequential Step)

II TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition EVAL COMMENTS (Required for UNSAT STANDARD # S/U evaluation}

CUE IF the Operator requests the STAIIA to independently verify the EAL Classification, THEN INFORM the Operator the N/A STAliA is not available.

ECG While classification verification is in Operator commences filling out ICMF.

Att. 3 progress and if time allows, 4.

COMMENCE filling out the INITIAL CONTACT MESSAGE FORM (ICMF)

(last page of this attachment).

ECG After classification verification and Operator declares a Site Area

Att. 3 before 15 minute EAL assessment Emergency, places the EAL # SS 1.1,

5. time and date in the appropriate spots clock expires, DECLARE a SITE AREA EMERGENCY at Hope Creek. in Attachment 3, and initials the step as the EC.

EAL#(s) , , _ __

Examiners Note: ENTER the DECLARED AT hrs on _____ declaration time that the operator time date entered on Att. 3. The difference between the START TIME and the "DECLARED AT" TIME is the first critical time_(15 min.) Initialing the step is not critical.

Page 13 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

COMMENTS STEP NO.

ELEMENT I (#Denotes a Sequential Step) EVAL (Required for UNSAT ECG Att. 3 NOTIFICATIONS STANDARD # S/U evaluation)

B.

ECG ACTIVATE "ERO Emergency Callout" Operator activates the ERO per posted Att.3 per posted instructions titled: instructions titled Training Use B.1. Emergency Callout Activation.

"Emergency Callout Activation" (EP96-003) Examiner Note: ENSURE the operator is using the Simulator Training Activation instructions.

ECG COMPLETE the INITIAL CONTACT Operator Completes the ICMF.

Att. 3

MESSAGE FORM (ICMF) (last page Examiners Note: See the attached B.2.

of this attachment). ICMF for an example of what the form should look like when filled out properly.

Note that the exact words do not have to be in the "DESCRIPTION OF EVENT", but the description must convey the sense of the Initiating Condition for EAL SS1.1. The operator may place the Examiner's name as the Communicator or tell the Examiner to place his/her name as the Communicator.

Page 14 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 J08PERFORMANCEMEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT

(*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD II I Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition EVAL S/U COMMENTS (Required for UNSAT evaluatio ECG IF time allows, OBTAIN an accuracy Att. 3 Operator requests a Peer Check of the peer check of the completed ICMF.

8.3. completed ICMF.

CUE !E the Operator requests a Peer Check, THEN INFORM the Operator a Peer Check has been performed as N/A requested.

ECG PROVIDE the ICMF to the Primary Att. 3 Communicator (CM1) and DIRECT Operator provides the ICMF to CM1 8.4. the Communicator to implement ECG and directs implementation of Att.6.

Attachment 6.

CUE I LOG the time the ICMF is provided to CM1.

Examiners Note: The difference LOG TIME: _ _ _ _ __ between the "DECLARED AT" TIME Role-play as CM1 and repeat back and this LOG TIME is the second the direction as given. critical time (13 min.)

Page 15 of 21

TQ-AA-1 06-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK:

STEP NO.

ELEMENT I

(*Denotes a Critical Step}

(#Denotes a Sequential Step)

STANDARD II I Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition EVAL S/U COMMENTS (Required for UNSAT evaluatio EGG DIRECT the Secondary Operator directs CM2 to implement Att.

Att. 3

Communicator (CM2) to implement 8 for a SITE AREA EMERGENCY.

B.6.

ECG Attachment 8 for a SITE AREA EMERGENCY.

CUE I ROLE-PLAY as CM2 and REPEAT BACK the direction as given. N/A CUE I WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

TASK STANDARD: Operator declares a Site Area N/A Emergency lAW EGG SS1.1, and makes notifications within identified Critical Times.

Page 16 of 21

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC SRO A-5 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505 QUESTION:

RESPONSE

RESULT: SAT UN SAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 17 of 21

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE ECG ATT3 Pg. 2 of2 I::\"ITL\L CO~TACT ::\IESSAGE FOR.\1 I. THIS IS Not Required . CO).f)..ll_"NICATOR IN THE [21 CONTROL ROOl\1

~-------

(NA..I\1E) 0 TSC OEOF AT THE HOPE CREEK NCCLEAR GENERA.TIKG STATIOK II. THIS IS KOTIFICATION OF A SITE AREA E::\IERGE::\"CY \\'RICH \VAS DECLARED AT Todays Time OK Todays Date (TI:\1E - ~-I HOCR CLOCK) (DATE)

EAL #( ~) -------=5=5=-1~*:_:_1_ ___

DESCRIPTION OF EVENT: Loss of Power to All Vital Buses III.

\'OTE; Radiological Release is defined as: Plant Ef11uem Tech Spec Limit of 1.20E..L04 f..lCi*sec Noble Ga~ or 1.70E+Ol ~tCisec I-131.

lXI 1\0 F..ADIOLOGICAL RELL\SE IS IN PROGRESS. see NOTE tor release 0 THERE IS A R.ADIOLOGIC\L RELEASE IN PROGRESS. definition IV. 121 33 FT. LEVEL \\1ND DIRECTION (From): 332 WIND SPEED: 21 (From :~viET Computer :sPDS) (DEGREES) (lvlPH)

V. ::\"0 PROTECTIVE ACTIO::\"S ARE RECO:\DIE::\"DED AT THIS TI:\IE Initials EC Initials (Approval to Transmit IC\IF)

HCGS Rev. 08

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant was at 100% power with the AD483 inverter isolated to it's backup AC supply.

2. Then, a Loss of Offsite Power occurred.

3. All Emergency Diesel Generators have failed to start and all vital buses are de-energized.

4. Due to a loss of rod position indication, the Control Room was unable to verify the reactor shutdown, and EOP-1 01A is being implemented.

5. The following conditions exist:

A, C, and E APRMs are de-energized

8, D, and F APRMS are reading 0% power.

RCIC is injecting.

RPV Level is -80", rising after reaching a minimum value of -90"

RPV pressure is 900# being controlled with SRVs.

6. Efforts to energize the Vital buses have been unsuccessful; maintenance has reported that they should be able to restore the '8' EDG to service in one hour.

7. The current 33ft. elevation wind direction is from 332° at 21 mph.

INITIATING CUE:

Based on this information, classify this event and make the initial notifications.

This is a Time Critical Task, and has two Time Critical elements.

Time zero for this event is now.

Page 19 of 21

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-5 Rev# Date Description Validation Required?

TQ-AA-1 06-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-5 REV#: 01 Utilize The ECG To Determine The Emergency Classification And/Or TASK:

Reportability Of An Event And/Or Plant Condition

1. Task description and number, JPM description and number are identified.

Knowledge and Abilities (K/A) is identified, and is :::3.0 (LOR) or :::2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

Critical steps meet the criteria for critical steps and are identified with an asterisk(*). Sequence

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: SRO Name Qual Signature Date Name Qual Signature Date

SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Loss ofRBVS, Loss of 10A120, Recirc Vibes, FW Break SCENARIO NUMBER: NRC 2013 Scenario #1 (ESG 029)

EFFECTIVE DATE:

EXPECTED DURATION: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months REVISION NUMBER: 1 PROGRAM: L------'1 L.O. REQUAL X I INITIAL LICENSE L------'1 OTHER REVISION

SUMMARY

1.

PREPARED BY:

Senior Simulator Instructor DATE APPROVED BY:

Nuclear Operations Training Supervisor- DATE Hope Creek APPROVED BY:

Operations Director or Designee DATE

I. OBJECTIVE(S):

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an"*.")

II. MAJOR EVENTS:

A. Alternate RACS pumps (Optional)

B. Loss of RBVS C. Loss of 10A120 D. Recirc Pump high Vibrations E. Feedwater Line Break Inside Containment III. SCENARIO

SUMMARY

The scenario begins with the plant at approximately 100% power with RCIC CIT for a leak on the steam line drain pot. At the Lead Examiners discretion, RACS pumps may be swapped to support an oil change on the 'B' RACS pump. RBVS Exhaust isolation damper GU-HD-94148 fails shut, causing a loss of RBVS and requiring FRVS to be placed in service. After FRVS is in service, the 1OA 120 bus is lost resulting in Single Loop operations in Region 1 of the Power to Flow Map. Shortly after the 1OA 120 bus loss, the remaining Reactor Recirc pump develops high vibrations, which require removing the pump from service. This necessitates a reactor scram (Critical Task #1 ). If the Crew does not remove the pump from service, it will develop a partial seal failure and ultimately seize. During the scram, the alpha feedwater line breaks inside containment upstream of the inboard check valve. This results in a High Drywell Pressure, a slow lowering of RPV level due to leakage past the check valve and an increase in Suppression Pool pressure. The line break also prevents stabilizing level with feedwater or HPCI. The first RHR pump placed in Suppression Chamber or Drywell Spray will trip. The remaining pump can be successfully aligned but the corresponding spray valve fails to open. Emergency Depressurization will be required due to a violation of the PSP curve due to a failure of the RHR Pump and Drywell spray valve (Critical Task #2). When Emergency Depressurization is initiated, one ADS SRV will not open due to faulted solenoids. An additional SRV will need to be opened by the Crew (Critical Task #3).

NRC 2013 Scenario #1 Page 2 of27 Rev.: 1

IV. INITIAL CONDITIONS:

I. C.

INITIALIZE the simulator to 100% power.

CIT RCIC as follows.

1. CLOSE the HV -4282

2. CLOSE the HV -F007

3. CLOSE the HV-F008

4. ALLOW RCIC supply pressure to decay to 0 psig

5. CLOSE the HV-F025

6. CLOSE the HV-F026 ENSURE 'B' and 'C' RACS pumps are in service.

PREP FOR TRAINING (i.e., RMll set points, procedures, bezel covers)

I Initial I Description PLACE red bezel covers on the following RCIC controls:

HV-F007

HV-F008

HV-F076

HV-F045

HV-F025

HV-F026 INITIAL 10 6 for po\Hlf at>cemion. 10-X for power reduction.

UPDATE LCO Status book for RCIC outage: T/S 3.7.4 14 days COMPLETE Attachment 2 "Simulator Ready-for-Training/Examination Checklist" ofNC.TQ-DG.ZZ-0002(2).

NRC 2013 Scenario #1 Page 3 of27 Rev.: 1

EVENT TRIGGERS:

Initial ET# Description EVENT ACTION: rrvib(1) >= 11 II 'A' Recirc Pump Radial Vibration 7 COMMAND:

PURPOSE: Triggers INBD Seal Failure when vibrations reach Alert Level EVENT ACTION: rrvib(1) >= 16 II 'A' Recirc Pump Radial Vibration 8 COMMAND:

PURPOSE: Triggers pump seizure when vibrations reach Danger Level EVENT ACTION: zcrprun <= 0.0 II Mode Switch NOT in RUN 9 COMMAND:

PURPOSE: Triggers Feedwater Line Break and LOCA on scram.

EVENT ACTION: ad:k40b(2) >= 1.0 II SRV F013B 'B' Channel solenoid energized 10 COMMAND:

PURPOSE: Triggers blowing of fuses when valve opened to ED.

EVENT ACTION: ad:k40d(2) >= 1.0 II SRV F013B 'D' Channel solenoid energized 11 COMMAND:

PURPOSE: Triggers blowing of fuses when valve opened to ED.

EVENT ACTION: rr:52(1) <= 0.0 && rr:52(2) <= 0.0 II No Recirc Pumps running 12 COMMAND:

PURPOSE: Inserts Power Oscillations when both recirc pumps are tripped.

EVENT ACTION: rrprv <= 815 II Reactor Pressure <800#

13 COMMAND:

PURPOSE: Fails bypass valves shut to prevent anticipating ED and depressurizing to condenser.

EVENT ACTION: rhf27(1) >= 100 & rh_bkr(2) II 'A' RHR in Chamber Spray with 'B' RHR run 14 COMMAND: Trips AP202 RHR pump when placed in Chamber Spray if BP202 is still running PURPOSE:

EVENT ACTION: rhf27(2) >= 100 & rh_bkr(1) // 'B' RHR in Chamber Spray with 'A' RHR run 15 COMMAND: Trips BP202 RHR pump when placed in Chamber Spray if AP202 is still running PURPOSE:

EVENT ACTION: rhf21(1) >= 500 & rh_bkr(2) // 'A' RHR in Drywell Spray with 'B' RHR run 16 COMMAND: Trips AP202 RHR pump when placed in Drywell Spray if BP202 is still running PURPOSE:

EVENT ACTION: rhf21(2) >= 500 & rh_bkr(1) >= 1.0 // 'B' RHR in Drywell Spray with 'A' RHR run 17 COMMAND: Trips BP202 RHR pump when placed in Drywell Spray if AP202 is still running PURPOSE:

NRC 2013 Scenario # 1 Page 4 of27 Rev.: 1

MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger !nit Val Final Val RC02 RCIC Auto Start Failure --- **-- NONE --- ---

ADOl ADS Failure to Auto-Initiate --- --- NONE --- ---

ED04 Loss of 10A120 Bus --- --- ET-3 --- ---

RR26A2 'A' Recirc Pump High Vibration --- 12:00 ET-4 3 15 RROSA 'A' Recirc Pump INBD Seal Failure --- 2:00 ET-7 0% 100%

RRllA 'A' Recirc Pump Trip --- --- ET-8 --- ---

CR02B Power Oscillations APRMs --- 1:00 ET-12 0% 30%

FW32 Feedwater Line Break Inside Containment --- --- ET-9 --- 100%

RR31A2 'A' Recirc Loop Large Break LOCA --- 30:00 ET-9 0% 2%

RR31B2 'B' Recirc Loop Large Break LOCA --- 15:00 ET-9 0% 2%

FW26A 'A' RFPT Trip 5 sec --- ET-9 --- ---

FW26B 'B' RFPT Trip 5 sec --- ET-9 --- ---

FW26C 'C' RFPT Trip 5 sec --- ET-9 --- ---

TCOl-10 All Bypass Valves Failed Shut --- --- ET-13 --- ---

CD09A 'A' CRD FCV Failure 90 sec *--- ET-6 --- 75%

CD09B 'B' CRD FCV Failure --- --- ET-6 --- 0%

REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val RC03 RCIC HV-F007 INBD Steam Supply --- --- NONE --- RACK CLOSE RC04 RCIC HV-F076 Warming Line --- --- NONE --- RACK CLOSE RCOS RCIC HV-F008 OUTBD Steam Supply --- --- NONE --- RACK CLOSE HV06 CVH300 RBVS Fan --- --- ET-2 --- STOP HVOS BVH300 RBVS Fan --- *--- ET-2 --- STOP HV04 AVH300 RBVS Fan --- --- ET-2 --- STOP HV03 CV301 RBVE Fan --- --- ET-2 --- STOP HV02 BV301 RBVE Fan --- *--- ET-2 --- STOP HVOl AV30 1 RBVE Fan --- *--- ET-2 --- STOP AN24 1OC382 Acknowledge 5 sec ET-2 --- NORM CD04 Second CRD Suction filter --- *--- ET-5 --- OPEN CD06 PCV Bypass valve --- 60 sec ET-6 0% 100%

CDlO 'B' FCV 120 sec *--- ET-6 --- ON Insert malfunction QQ20 to SHORT Insert malfunction QQ20 to SHORT Insert malfunction QQ21 to SHORT NRC 2013 Scenario # 1 Page 5 of27 Rev.: 1

Insert malfunction QQ21 to SHORT ADOlB-B PSV-F013B 'B' Channel Fuse --- --- ET-10 --- REMOVE ADOlB-D PSV-F013B 'D' Channel Fuse --- --- ET-11 --- REMOVE 1/0 OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger !nit Val Final Val 9S9 A LO RCIC HV-F045 OVLD/PWR FAIL --- --- NONE --- ON 9S10 A DI RCIC HV-F045 OPEN Pb --- --- NONE --- OFF 9S10 B LO RCIC HV-F045 CLOSED light --- --- NONE --- OFF 9S8 A DI RCIC HV-F025 OPEN Pb --- --- NONE --- OFF 9DS26 B LO RCIC HV -F025 CLOSED light --- --- NONE --- OFF 9S16 A DI RCIC HV-F026 OPEN Pb --- --- NONE --- OFF 9DS27 B LO RCIC HV-F026 CLOSED light --- --- NONE --- OFF 9S45 A Dl RCIC Manual Initiation Pb --- --- NONE --- OFF 4Al F DI HV-F032A CLOSE Pb --- --- NONE --- OFF 1A175 E D1 HD-9414B OPEN PB --- --- ET-1 --- OFF 1A175 F D1 HD-9414B CLOSE Pb --- --- ET-1 --- ON Insert override 10DS40_A_LO to On Insert override 1ODS40_A_LO to On Insert override 1ODS93_A_LO to On Insert override 1ODS93_A_LO to On NRC 2013 Scenario # 1 Page 6 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments Swapping RACS pumps:

CRS directs PO to place AP209 Crew places AP209 RACS RAGS pump in service and pump in service and secures secure BP209 RACS pump.

BP209 RAGS pump after assuming the watch.

!E dispatched to AP209,

PO dispatches RBEO to perform THEN REPORT the AP209 pre-start checks and locally RAGS pump is ready for a observe start of AP209 RAGS start. pump lAW HC.OP-AP.ZZ-0109 (motherhood procedure).

AFTER AP209 is in service,

PO starts AP209 and secures HPI USED:

THEN REPORT AP209 is BP209 lAW SO.ED-0001 Section STARD running SAT. 5.3. PEER CHECK D Monitor Items: FLAGGING D

Normalized AP209 speed OP BARRIERS D cwnra209 Loss of RBVS:

Crew recognizes Loss of RBVS After the Crew swaps RAGS by:

pumps, ~ OHA E1-F5 "COMPUTER PT OR at the discretion of the IN ALARM" Lead Examiner, ~ GRIDS 87164 "REACTOR TRIGGER ET-1 (RBVS BLDG DIFF PRESS" Exhaust Damper HD-9414A ~ OHA E6-C5 "RBVS & WING Fails shut). AREA HVAC PNL 10C382" (delayed)

~ GRIDS D3960 "RBVS EXH RMT PNL C382 TRBL"

~ GRIDS D3961 "RBVS SUPPLY RMT PNL C382 TRBL"

~ RB DIP indication on 10C650E

~ SPDS RB PARAMETERS D/P indication.

CRS implements AB.CONT-003:

~ Condition A IF dispatched to 1OC382,

Crew dispatches RBEO to THEN REPORT Low Flow Trip 1OC382 to investigate.

alarms on all Reactor Bldg Supply and exhaust fans.

NRC 2013 Scenario #1 Page 7 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

RO/PO recognize HD-9414A failed shut by 1OC651 E indication and inform CRS.

!E directed to secure RBVS,

RO/PO place FRVS in service HPI USED:

THEN TRIGGER ET-2. lAW SO.GU-0001 -or- hardcard. STARD PEER CHECK D FLAGGING D OP BARRIERS D IF dispatched to HD-94148,

Crew dispatches NEO and GU-HD-94148 is THEN REPORT there is no Maintenance to investigate located in Room 4624.

obvious reason for the closure. closure of HD-94148.

CRS recognize the following Tech Specs apply:

=> Secondary Containment Integrity 3.6.5.1

=> Secondary Containment Automatic Isolation Dampers 3.6.5.2 action a or b or c Loss of 10A120 Bus:

Crew recognizes:

15 minutes after the Loss of => Reactor power lowering RBVS, => Reactor level swell OR.

at the discretion of the Lead

Examiner, TRIGGER ET-3.

Crew monitors Reactor power, pressure, and level until plant conditions are stable.

PO ensures feedwater restores and maintains RPV level between LVL 4 and LVL 7.

NRC 2013 Scenario #1 Page 8 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

Crew recognizes Loss of 'B' Reactor Recirc pump by:

~ C1-D5 "REACTOR RECIRC B TROUBLE"

~ GRIDS D2918 "RECIRC MG DRIVE MOTOR B BRKR"

~ Flashing TRIP light for 'B' Recirc MG Drive Motor bkr

~ 'B' Reactor Recirc pump flow and d/p indications on 10C651C

RO ensures at least one recirc pump still running.

Crew recognizes trip of 'B' PCP The trips of 'B' PCP and and 'B' SCP by: 'B' SCP are silent and

~ OVLD/PWR FAIL lights may not be immediately

~ STOP lights lit recognized by the

~ Motor amps zero Crew.

Crew validates automatic actions:

~ Feedwater PCP Speed Limiter on

~ Recirc pump lnt and Full Run backs

Crew recognizes entry into the Rx Power ==55%

OPRM Enable Region by: Core Flow ==39 mlbm/hr

~ C3-F1 "OPRM TRIP ENABLE"

Crew recognizes loss of BK111 The trip of BK111 is TB chiller by: silent and may not be

~ OVLD/PWR FAIL light immediately recognized

~ STOP light lit by the Crew.

~ Motor amps zero NRC 2013 Scenario #1 Page 9 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

Crew recognizes loss of 1OA 120 bus from:

~ OHA E3-E1 7.2 KV SYS INCOMING BRKR MALF

~ Solid OVLO/PWR FAIL lights on loads lost

~ Flashing TRIP light for infeed bkr 52-12008

~ CRIOS 03682 "SWGR BUS A120 OIFF LOCKOUT"

~ CRIOS 03684 "SWGR BUS A 120 UNOERVOLTAGE"

Crew announces loss of 1OA 120 on the plant page.

CRS implements AB.RPV-0003: The pace of the

~ Condition A scenario will not allow

~ Condition B the Crew to fully address single loop requirements.

!E the Crew manually scrams,

IF in Region 1 of the Pwr/Fiow HPI USED:

THEN the Feedwater Line map, STARO Break and LOCA will be THEN RO inserts rods lAW ESG PEER CHECK 0 automatically inserted. guidance as necessary to exit Region 1.

RO/PO close HV-F031 B Recirc HPI USED:

pump discharge valve for 5 STARO minutes, then re-open. PEER CHECK 0 FLAGGING 0 OP BARRIERS 0

RO/PO implement OL.ZZ-0026 Att. 3v.

CRS implements AB.RPV-0001:

~ Condition B

CRS implements AB.RPV-0004:

~ Condition 0

~ Condition G

PO closes HV-1680B PCP HPI USED:

discharge valve. STARO PEER CHECK 0 FLAGGING 0 OP BARRIERS 0 NRC 2013 Scenario #1 Page 10 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

PO closes HV-1651B SCP HPJ USED:

discharge valve. STARD PEER CHECK D FLAGGING D OP BARRIERS D

PO bypasses Feedwater HPJ USED:

Run backs. STARD PEER CHECK D WHEN dispatched,

Crew dispatches TBEO and THEN REPORT the 10A120 Maintenance to investigate loss Bus Differential Overcurrent of 10A120 bus.

Relays are tripped. There is no visible indication of damage to the bus.

As RE, REPORT the Enhanced

Crew contacts RE for guidance Stability guidance should be and to check thermal limits.

used to exit Region 1. The first three groups will also satisfy the 80% rod line sequence for single loop lAW AB.RPV-0003.

Crew references Power Maneuvering Tech Specs in AP.ZZ-108.

CRS recognize the following actions apply:

=> Recirculation Loops 3.4.1.1 action a

=> Reactor Coolant System Specific Activity TIS Table 4.4.5-1 Item 4(b)

=> ODCM Table 4.11.2.1.2-1 Items (c) & (f)

CRS notifies Shift Rad Pro and Shift Chern Tech to take samples lAW:

=> TIS Table 4.4.5-1 Item 4(b)

=> ODCM Table 4.11.2.1.2-1 Items (c) & (f)

NRC 2013 Scenario #1 Page 11 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

CRS recognize the following Tech Specs apply:

=:> Recirculation Loops 3.4.1 .1 action a 4.4.1.1.1

Crew contacts ESOC and Trading Floor, gives estimate of MWe output limitations and duration of limitation.

CRS contacts Operations Management.

'A' Recirc Pump High

Crew recognizes rising vibrations Vibration will jump 3 Vibration: on 'A' Reactor Recirc pump by: mils then rise at a rate 15 minutes after the Loss of =:> GRIDS A2601 "RECIRC PMP of one mil per minute.

10A120, A RADIAL VIB MON" C1-E4 and C1-F5 will OR, =:> OHA C1-F5 "COMPUTER PT alarm at 11 mils.

at the discretion of the Lead IN ALARM" Examiner, TRIGGER ET-4. =:> OHA C1-E4 "REACTOR RECIRC PUMP VIB HI"

=:> GRIDS D2920 "RECIRC PUMP MOTOR A VIBRATION"

=:> GRIDS D5351 "RECIRC PUMP AP201 VIBRATION"

CRS implements AB.RPV-0003:

=:> Condition F

=:> WHEN it is determined that

'A' Recirc Pump Vibration points cannot be maintained below the DANGER limits THEN the CRS orders manual scram to support removing 'A' Reactor Recirc pump from service.

RO locks the Mode Switch in HPI USED:

SHUTDOWN and performs STARD scram actions lAW AB.ZZ-0001 HARD CARD D Att. 1. PEER CHECK D NRC 2013 Scenario # 1 Page 12 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

Crew manually scrams the Reactor !E the 'A' Recirc pump within 60 seconds following the loss tripped BEFORE the of both Reactor Recirc pumps. Reactor was scrammed, Scramming before the 'A' THEN RECORD the Reactor Recirc pump trips time between the trip of satisfies this Critical Task. the 'A' Recirc pump and the reactor scram.

Time:

Crew recognizes RPV Level Below 12.5" EOP entry condition by:

=? OHA C5-A4 "RPVWATER LEVEL LO"

=? OHA A 7-D5 "RPV LEVEL 3"

=? Various water level indicators Feedwater Line Break:

Crew recognizes High Drywell RECORD Drywell The feedwater line break inside Pressure EOP entry condition: Pressure reached containment with leakage past =? OHA A7-D4 "DRYWELL 1.68psig for 15 min the check valve will be PRESSURE HI/HI" ECG Classification.

automatically inserted when the =? OHA C5-B5 "DRYWELL Time:

Mode Switch is taken out of PRESSURE HI" RUN. =? Various system initiations and isolations

CRS implements:

=? EOP-101

=? EOP-102

PO attempts to maintain level as HPI USED:

directed by CRS. STARD HARD CARD D PEER CHECK D The feedwater line break will prevent restoring level with HPCI or feedwater.

CRS determines an Alert RECORD time Alert Classification is required lAW declared.

ECG Section 3.2.2.b (Valid High Time Declared:

Drywell Pressure Condition).

NRC 2013 Scenario #1 Page 13 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

!E directed to open the breaker

Crew recognizes 'A' feedwater for the HPCI HV-8278 in an line break by:

attempt to fail the valve shut, => High Flow I Low Discharge THEN REPORT the breaker Pressure on condensate handle on the cubicle door => High Flow I Low Discharge does not appear to be Pressure on HPCI engaging the breaker paddle => Ability to vary HPCI flow with inside the cubicle. You cannot Setpoint get the cubicle door open and => Absence of OHA B 1-E5 have called the 12 Hour "HPCI PUMP DISCHARGE Maintenance Supervisor and FLOW LO" asked for an Electrician to help. => Rapidly rising torus level Do NOT fail the valve shut. => Lowering hotwell level

=> RPV Pressure trend not consistent with a LOCA greater than the capacity of HPCI/Condensate

=> HV-F074A open and HV-F07 48 shut

!E directed to close the F032A,

Crew may attempt to isolate the HPI USED:

THEN REPORT the actuator 'A' Feedwater line if they STARD appears to be broken. The successfully diagnose a FW line PEER CHECK D valve will not stroke from the break. FLAGGING D bucket or locally with the OP BARRIERS D manual handwheel. The HV-F032A will not close from the Control Room.

Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

=> OHA C8-F1 "SUPPR POOL TEMP HIGH"

=> Flashing 95 degree status light on 1OC650C

=> RM11 9AX833/834 alarm

=> Various Suppression Pool temperature indicators

CRS re-enters EOP-1 02.

NRC 2013 Scenario #1 Page 14 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

!E feedwater and condensate remained aligned to feed the reactor vessel, THEN Crew recognizes low main condenser hotwell levels by:

=> OHA A6-F1 "CONDENSATE TRAIN A TROUBLE"

=> OHA A6-F2 "CONDENSATE TRAIN B TROUBLE"

=> OHA A6-F3 "CONDENSATE TRAIN C TROUBLE"

=> GRIDS D2943 "CONDENSER AE 108 LEVEL"

=> GRIDS D2945 "CONDENSER BE1 08 LEVEL"

=> GRIDS D2947 "CONDENSER CE108 LEVEL"

=> 1OC651 A Hotwell Level indication

CRS directs injection with:

=> SLC

=> Two CRD pumps (If RPV level continues to lower)

RO/PO initiate SLC. HPI USED:

STARD PEER CHECK D NRC 2013 Scenario #1 Page 15 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

!E directed to align for two CRD

RO/PO align CRD for Emergency HPI USED:

pump injection, Two CRD Pump Injection lAW STARD THEN PERFORM the SO.BF-0001 Section 5.4. HARD CARD D following: PEER CHECK D REFER to SO.BF-0001 Sect 5.4.

TRIGGER ET-5 (Suction filter).

SET Remote Function for Stby CRD pump discharge valve to 0% (CD01/CD02).

REPORT Stby CRD pump ready for start.

WHEN Stby CRD is running, THEN RAMP discharge valve to 100% open.

AFTER HV-F003 is open, THEN TRIGGER ET-6.

WHEN two minutes have

elapsed, THEN MODIFY Malfunctions CD09AIB to control injection.

RHR Pump Trip & HV0-168

Crew recognizes 'A" RHR pump fails to open: trip by:

The 'A' RHR pump starts on ~ OHA RHR LOGIC OUT OF Local Level 1 signal and SERVICE immediately trips. ~ OUT OF SERVICE status

-AND- light

~ PUMP MOTOR HV0-168 Drywell Spray Valve OVERCURRENT status light fails to open ~ Pump STOP, amp and flow indications

!E dispatched to investigate the

Crew dispatches operator and trip of the 'A' RHR pump, Maintenance to the tripped RHR THEN REPORT: pump and breaker.

The breaker has target flags dropped on the 51 A and 51 B Time Overcurrent relays (401/402 bkr 06)

The pump motor is hot to the touch and bearing oil levels are normal NRC 2013 Scenario #1 Page 16 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

!E the CRS determines 'B' RHR *IF the Crew Sprays the pump is NOT required to assure Drywell, adequate core cooling by WITH Suppression Pool operating in LPCI mode, level above 124",

THEN CRS directs placing: THEN consider this a

'B' RHR pump in Suppression Critical Task Failure.

Chamber Cooling/Spray or Drywell spray (if >9.5psig in the suppression chamber).

RO/PO places 'B' RHR pump in HPI USED:

Suppression Chamber STARD Cooling/Spray or Drywell Spray HARD CARD D lAW AB.ZZ-0001 Att. 2 or 3.

Crew recognizes the failure of HV0-168 to open (Drywell Spray Valve)

Crew recognizes containment not performing properly by:

=> Suppression Chamber pressure approaching Action Required area of PSP curve

=> Suppression Chamber airspace temperature significantly above water temperature

=> Drywell Pressure response

!E necessary,

WHEN the Crew determines THEN REDUCE the ramp on Suppression Chamber pressure malfunction rr31 a2 to raise cannot be maintained below the Supp Pool pressure. Action Required region of the PSP curve, THEN the CRS implements EOP-202 to Emergency Depressurize.

NRC 2013 Scenario # 1 Page 17 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

Crew prevents injection from Core Spray and LPCI pumps not For non-ATWS emergency required for adequate core depressurizations, the Control Room Supervisor should establish and cooling.

maintain an RPV level band between

-38" to +54" on Wide Range indication. This transient level band will prevent adverse hydraulic effects caused by high outside shroud reactor level while maintaining adequate core submergence based on Fuel Zone indication. Following the emergency depressurization, level will be restored and maintained to the preferred EOP reactor level band by using a suggested Wide Range compensated level band of

+12.5" to +54" if possible using Condensate and Startup Level Control or the Control Room Supervisor can maintain an RPV level band of -38" to +54" if still batch feeding with low pressure ECCS to maintain RPV level.

RO/PO open ADS valves lAW HPI USED:

AB.ZZ-0001 Attachment 13. STARD HARD CARD D INPO Fundamentals:

CONTROL D

Crew actuates five SRVs before Suppression Chamber pressure has been in the Action Required region of the PSP curve for over three minutes.

NOTE:

Preventing entry into the Action Required Region of the PSP curve satisfies this critical task.

NRC 2013 Scenario #1 Page 18 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments

Crew recognizes failure of PSV-F013B to remain open by:

~ Acoustic Monitor position indication on 1OC650C

~ Tailpipe temperature on TR-R614

RO/PO opens additional SRV HPI USED:

lAW AB.ZZ-0001 Att. 13, informs STARD CRS of PSV-F013B failure. HARD CARD D PEER CHECK D

CRS directs restoring RPV level to -38" to 54" with Low Pressure ECCS.

RO/PO restore RPV level as HPI USED:

directed by CRS lAW STARD AB.ZZ-0001: HARD CARD D

~ Att. 4 for RHR PEER CHECK D

~ Att. 5 for Core Spray FLAGGING D

!E RPV water level drops below -311 ",

THEN the CRS may implement EOP-206.

WHEN adequate core cooling is

IF the Crew Sprays assured, the Drywell, THEN CRS directs placing: WITH Suppression

~ One loop of RHR in Supp Pool level above 124",

Pool Cooling and Spray THEN consider this a

~ One loop of RHR in Drywell Critical Task Failure.

Spray (If Supp Pool Level is less than 124")

RO/PO align RHR lAW HPI USED:

AB.ZZ-0001: STARD

~ Att 2 Drywell Spray HARD CARD D

~ Att 3 Supp Pool Clg PEER CHECK D FLAGGING D OP BARRIERS D NRC 2013 Scenario #1 Page 19 of27 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event I Instructor Activity Expected Plant/Student Response Comments Termination Requirement: If the scenario does not The scenario may be run for a full 15 minutes terminated at the discretion of after -161" is reached, the Lead Examiner when the SAE Classification either: may not be declared.

RPV level has been restored above 129" and containment parameters are improving OR

EOP-202 is being implemented and RPV pressure is being maintained 50 psig above Suppression Chamber pressure with five SRVs open.

NRC 2013 Scenario #1 Page 20 of27 Rev.: 1

VI. SCENARIO

REFERENCES:

A. NC.TQ-DG.ZZ-0002 Conduct of Simulator Training.

B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. SH.OP-AS.ZZ-0001 Operations Standards J. SH.OP-AS.ZZ-0002 Shift Technical Advisor Program K. HC.OP-AP.ZZ-0108 Operability Assessment and Equipment Control Program L. HC.OP-AP.ZZ-0109 Equipment Operational Control M. HC.OP-SO.AE-0001 Feedwater System Operation N. HC.OP-SO.BF-0001 CRD Hydraulic System Operation

0. HC.OP-SO.ED-0001 Reactor Auxiliaries Cooling Water System Operation P. HC.OP-SO.GU-0001 Filtration, Recirculation, and Ventilation System Operation Q. HC.OP-AB.ZZ-0001 Transient Plant Conditions R. HC.OP-AB.RPV-0001 Reactor Power S. HC.OP-AB.RPV-0003 Recirculation System I Reactor Power Oscillations T. HC.OP-AB.RPV-0004 Reactor Level Control U. HC.OP-AB.CONT-0003 Reactor Building V. HC.OP-AB.ZZ-000 Reactor Scram W. HC.OP-EO.ZZ-0101 RPV Control X. HC.OP-EO.ZZ-0102 Primary Containment Control Y. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization Z. HC.OP-EO.ZZ-0206 RPV Flooding AA. NOTF 20149832 Feedwater Piping Wall Thickness NRC 2013 Scenario #1 Page 21 of27 Rev.: 1

VII. ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #1, Rev. 01 1.

Crew manually scrams the Reactor within 60 seconds following the loss of both Reactor Recirc pumps.

KIA 295001 Partial or Complete Loss of Forced Core Flow Circulation AAl Ability to operate and/or monitor the following as they apply toP ARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

AAl.Ol Recirculation system RO 3.5 SRO 3.6 AA2 Ability to determine and/or interpret the following as they apply toP ARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

AA2.01 Power/flow map RO 3.5 SRO 3.8 Without Recirc Drive flow through the Jet pumps, the only circulation in the Reactor core is natural circulation. When operating at power, natural circulation core flow is expected to be low enough to place us in the Scram Region of the Power to Flow Map, where the risk of power oscillations is great enough to warrant an immediate Reactor shutdown. This is procedurally driven as an Immediate Operator Action in AB.RPV-0003. It is expected that the Crew will recognize the imminent loss of the last recirc pump due to indications of pump degradation and proactively scram the reactor prior to the loss to prevent entering a potentially unstable power to flow condition. If the Crew fails to take action prior to the pump seizure, the loss will be accompanied with OHAs. In this case, 60 seconds is deemed adequate time to recognize the loss, and take the required Immediate Operator action. Scramming prior to the loss of the second reactor recirc pump, including scrams based on calculated entry into the Scram Region of the Power to Flow map, satisfies this critical task.

2.

When the Crew determines RPV water level cannot be maintained above -185 ", the Crew actuates at least five SRVs to Emergency Depressurize the Reactor before RPV level reaches -200", and restores RPV level to above -185".

KIA 295031 Reactor Low Water Level EAl. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL:

EAl.Ol Low Pressure Coolant Injection RO: 4.4 SRO 4.4 EA1.06 Automatic depressurization system RO 4.4 SRO 4.4 EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:

EA2.04 Adequate core cooling RO 4.6 SRO 4.8 When Reactor water level cannot be maintained above -185" with injection to the RPV, adequate core cooling cannot be assured (MSCRWL). EOPs direct action to initiate emergency depressurization when RPV water level reaches this value ifthere are injection sources available. To restore adequate core cooling, the Crew must Emergency Depressurize and restore level with low pressure ECCS. The lower limit of -200" provides an acceptable level of performance based upon the rate ofRPV water level decrease in this scenario. The term "Crew actuates at least five SRVs" takes into account the failure of the F013B which is already inserted.

NRC 2013 Scenario #1 Page 22 of27 Rev.: 1

3.

WHEN Emergency Depressurization is initiated and the PSV-F013B fails to remain open, THEN before RPV pressure drops below 50 psig, the Crew places the Control Switch for an additional SRVto OPEN to achieve five open SRVs.

KIA 295031 Reactor Low Water Level EAl. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL:

EA1.07 Safety/Relief Valves RO 3.7 SRO 3.7 The Minimum Number of SRV s required for Emergency Depressurization (MNSRED) is five. The MNSRED is utilized to assure the RPV will depressurize and remain depressurized when Emergency Depressurization is required. When the fuses for the PSV -FO 13B fail, the Crew needs to ensure an additional SRV control switch is in the OPEN position to achieve five SRVs for Emergency Depressurization. This is directed by both EOP-202 and AB.ZZ-000 1. SRV's are designed to open with a minimum differential pressure of 50 psid between the reactor vessel and the suppression chamber. Below this dip, they may not open. If the Crew does not attempt to open the fifth SRV before this minimum dip is lost, they cannot validate it's operation. This would prevent them from detecting the failure and pursuing the use of the Alternate Depressurization Systems in EOP-202.

4.

IF the Crew Sprays the Drywell, WITH Suppression Pool level above 124",

THEN consider this a Critical Task Failure.

KIA 223001 Primary Containment System and Auxiliaries A2 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.11 Abnormal suppression pool level RO 3.6 SRO 3.8 Suppression Pool level above 124" may result in the Torus to Drywell Vacuum breakers being submerged.

If drywell sprays are initiated in this condition, the non-condensables in the Torus air space may not migrate back to the drywell, and the drywell negative pressure limit may be exceeded as a result. EOP-1 02 directs verifying Suppression Pool level is 124" before initiating drywell sprays.

NRC 2013 Scenario # 1 Page 23 of27 Rev.: 1

2013 NRC Scenario #1, Rev. 01 HOPE CREEK ESG- PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE YIN EVENT EVENT Loss Of Offsite Power/SBO Internal Flooding y LOCA TRANSIENTS: LOSS OF SUPPORT SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss ofFeedwater Loss of Instrument Air Inadvertent MSIV Closure Inadvertent SRV Opening y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY EQUIPMENT Hard Torus Vent SLC HPCI CRD IE 4.16KV Bus IE 125VDC

_ _ _ SACS Hx/Pump EDG KEY SYSTEMS 120VAC 481/482 Inverter 500KV AC Power AIBRHR SRVs

_...:;..Y_ RCIC Condensate/F eedwater

_ _ _ SSWPump PCIG OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION Y Aligning RHR for Suppression Pool Cooling

- - - Emergency Venting of Primary Containment y Emergency Depressurize RPV W /0 High Pressure Injection

_ _ _ Initiating LP ECCS with No High Pressure Injection Available

_ _ _ Restoration of AC Power after a LOP (EDG I Offsite)

_ _ _ Monitoring and Control of SACS heat loads

- - - Preventing LVL 8 trip ofFeedwater during a transient

_ _ _ Align Core Spray Suction to CST when at NPSH limits

_ _ _ Cross-Tie De-Energized BID 125VDC Battery Charger to Energized Bus

- - - Inhibit ADS during ATWS Complete this evaluation form for each ESG.

NRC 2013 Scenario # 1 Page 24 of27 Rev.: 1

VIII. TURNOVER SHEET:

Rx Power: 100%

MWe (May vary slightly): 9%

WorkWeek: B Risk Color: Green Activities Completed Last Shift:

Major Activities Next 12 Hours:

Place A RACS pump liS and Secure B RACS pump for oil change Power reduction to 90% for rod pattern adjustment Protected Equipment:

HPCI/250VDC

'A' Channel EDG, SWGR, IE Logic Panels, Tagged Equipment:

RCIC NRC 2013 Scenario #1 Page 25 of27 Rev.: 1

IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST EXAMINATION SCENARIO GUIDE (ESG) REVIEWIV ALIDATION Note: This form is used as guidance for an examination team to conduct a review for the proposed exam scenario(s). Attach a separate copy of this form to each scenario reviewed.

SELF-CHECK ESG- Scenario #1 REVIEWER:

1. The scenario has clearly stated objectives in the scenario.

2. The initial conditions are realistic, equipment and/or Instrumentation may be out of service, but it does not cue crew into expected events.

3. Each event description consists of:

The point in the scenario when it is to be initiated

The malfunction(s) that are entered to initiate the event

The symptoms/cues that will be visible to the crew

The expected operator actions (by shift position)

The event termination point

___ 4. The use of non-mechanistic failures (e.g. pipe break) should be limited to one or a credible preceding event has occurred.

_ _ _ 5. The events are valid with regard to physics and thermodynamics.

Sequencing/timing of events is reasonable (e.g. the crew has time to respond to the malfunctions in an appropriate

- - - 6.

time frame and implements procedures and/or corrective actions).

7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

8. If time compression techniques are used, scenario summary clearly so indicates.

9. The simulator modeling is not altered.

10. All crew competencies can be evaluated.

11. Appropriate reference materials are available (SOERs, LERs, etc.)

12. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

13. Proper critical task methodology used lAW NRC procedures.

ESG-029 Page 26 of27 Rev.: 09

EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't ESG Validation:

Rev. Date Comments Note: The following criteria list scenario traits that are numerical in nature. A second set of numbers indicates a range to be met for a set of two scenarios. Therefore, to complete this part of the review, the set of scenarios must be available. The section below should be completed once per scenario set.

ESG: Scenario #1 ESG:

SELF-CHECK

1. Total malfunctions inserted: 4-8/10-14

_ _ _ 2. Malfunctions that occur after EOP entry: 1-4/3-6

- - - 3. Abnormal Events: 1-2/2-3

_ _ _ 4. Major Transients: 1-2/2-3

- - - 5. EOPs used beyond primary scram response EOP: 1-3/3-5

6. EOP Contingency Procedures used: 0-311-3

_ _ _ 7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8. EOP run time: 40-70% of scenario run time

- - - 9. Crew Critical Tasks: 2-5/5-8

10. Technical Specifications are exercised during the test

11. Events used in the two scenarios are not repeated (Only Applicable for an exam set)

12. The scenario sets for the exam week do not contain duplicate scenarios (Only Applicable for an exam set)

Comments:

ESG-029 Page 27 of27 Rev.: 09

SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Recirc Pump Seal Failure, ATWS with BPV Failure SCENARIO NUMBER: NRC 2013 Exam Scenario #2 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 60 minutes REVISION NUMBER: 01 PROGRAM: ~...-_ ___,1 L.O. REQUAL X I INITIAL LICENSE

...__ ___.I OTHER REVISION

SUMMARY

PREPARED BY:

Instructor DATE APPROVED BY:

LORT Group Lead or Designee DATE APPROVED BY:

Shift Operations Supervisor or Designee DATE

I. OBJECTIVE{S):

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an"*.")

II. MAJOR EVENTS:

A. Recirc Flow Unit Failure Downscale B. Loss of 1CD481 Inverter C Recirc Pump High Vibrations C. A TWS with ARI failure, RWCU and SLC Failure D. EHC Pump Failure-> BPVs Fail Close E. RHR Pump Fails to Start Ill. SCENARIO

SUMMARY

The scenario begins with the plant at 100% power; with 'A' EHC Pump OOS. N2 makeup to the Primary Containment is required. After establishing N2 makeup, the crew will be directed to lower power to 90% using Recirc pump flow to prepare for a rod pattern adjustment. The Recirc Loop Flow Summer 'C' then fails. After restoration, the 1CD481 inverter will fail. After the inverter failure, the 'A' Recirc pump will experience a seal failure and the crew will have to reduce power and the pump will be tripped & isolated. After single loop operation is established, power oscillations will occur, necessitating a reactor SCRAM. The SCRAM will not be successful and will result in a full core A TWS with an initial power level of about 40%. ARI will fail to operate.

RWCU will fail to isolate and both SLC pumps will trip when the crew manually isolates RWCU.

The crew will attempt to drive individual rods manually. Additional SCRAM attempts will not be successful. Pressure will be initially controlled with the BPVs, but the BPVs will gradually fail close subsequent to the EHC pump trip, requiring the crew to establish pressure control with the SRVs. When Torus cooling is placed into service, the RHR torus cooling valve fails to open.

Once torus cooling is placed in service and pressure and level are being maintained, SCRAM attempts will be successful and the scenario may be terminated.

2013 NRC Scenario #2 Page 2 of 31 Rev: 1

IV. INITIAL CONDITIONS:

I. C.

INITIALIZE the simulator to 100% power, 3840 MWth, MOL.

REDUCE reactor power to 84.5%.

REMOVE the 'C' RFPT from service lAW SO.AE-0001 Section 5.11 up through the point of reducing lube oil temperature to 90 degF.

lE N2 makeup to containment will be performed, THEN REDUCE drywell and suppression chamber pressure to approximately 0.30 psig.

ENSURE 'D' SACS pump is in service.

ENSURE 'B' CRD pump is in service.

ENSURE 'B' FPCC pump is in se1*vice.

ENSURE 'A' Control Room Vent Train is in service.

ENSURE BOTH Steam Tunnel unit Coolers are in service.

ENSURE 'A' EHC pump is in service.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers) ltnitial I Description INITIAL SO.AE-0001 Section 5.11 up through the point of reducing lube oil temperature to 90 degF.

PREPARE an SO.AE-0001 Attachment 3 for 'C' RFPT pump casing d/t.

INITIAL IO.ZZ-006 for the power reduction.

IF performing N2 Makeup, THEN INITIAL SO.GS-0001 up to the and including increasing vaporizer temperature to 100 degF (Step 5.2.8 of Rev 30).

ENSURE Data Collection is trending the following parameters:

W/R Reactor Water Level

Fuel Zone Reactor Water Level

W/R Reactor Pressure At a minimum review the Scenario Reference section and CLEAN the balded EOPs, ABs and SOPs listed.

- - - (80091396 0270)

COMPLETE the "Simulator Ready for Training/Examination" Checklist.

2013 NRC Scenario #2 Page 3 of 31 Rev: 1

EVENT FILE:

Initial ET#

Event code: rrp_rpm(l) <= 1400 II 'A' Recirc pump rpm

Description:

imf rr26a2 3 15 Increases malfunction vibration when Crew reduces recirc pump speed.

Event code: rhf27(1) >= 100 & rh_bkr(2) II 'A' RHR in Chamber Spray with 'B' RHR run

Description:

Trips AP202 RHR pump when placed in Chamber Spray if BP202 is still running Event code: rhf27(2) >= 100 & rh_bkr(1) // 'B' RHR in Chamber Spray with 'A' RHR run

Description:

Trips BP202 RHR pump when placed in Chamber Spray if AP202 is still running Event code: rhf21(1) >= 500 & rh_bkr(2) // 'A' RHR in Drywell Spray with 'B' RHR run

Description:

Trips AP202 RHR pump when placed in Drywell Spray if BP202 is still running Event code: rhf21 (2) >= 500 & rh_bkr(1) >= 1.0 II 'B' RHR in Drywell Spray with 'A' RHR run

Description:

Trips BP202 RHR pump when placed in Drywell Spray if AP202 is still running 2013 NRC Scenario #2 Page 4 of 31 Rev: 1

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None Insert malfunction ED09A1 on ET-2 Loss of 120 VAC class IE instr bus 1CD484 None --- Insert malfunction RR26A2 on ET-3 A' Recirc Pump High Vibration None Insert malfunction RP06 Half-core ATWS - left side None Insert malfunction QQ20 to SHORT RHR pump AP202 trip None Insert malfunction QQ20 to SHORT RHR pump AP202 trip None Insert malfunction QQ21 to SHORT RHR pump BP202 trip None Insert malfunction QQ21 to SHORT RHR pump BP202 trip 2013 NRC Scenario #2 Page 5 of 31 Rev: 1

REMOTE SCHEDULE:

Initial @Time Event Action Description

~P11 EOP-320 (step 5.2.2), RPS division 1 None None Insert remote EP11 to INSTALLED JUmper EP13 EOP-320 (step 5.2.3), RPS division 3 None None Insert remote EP13 to INSTALLED jumper Insert remote EP09 after 240 to EP09 EOP-320 (step 5.1.2), ARI valve fuses None None REMOVED on event 7 F6A/F5A Insert remote EP 10 after 240 to EPIO EOP-320 (step 5.1.4), ARI valve fuses None None REMOVED on event 7 F6B/F5B Insert remote EP12 after 720 to EP12 EOP-320 (step 5.2.4), RPS division 2 None None INSTALLED on event 7 jumper Insert remote EP14 after 720 to EP14 EOP-320 (step 5.2.5), RPS division 4 None None INSTALLED on event 7 jumper OVERRIDE SCHEDULE:

Initial @Time Event Action Description PUMP MOTOR OVER CURRENT-RHR A-None Insert override 1ODS40_A_ LO to On LOOP A (LO)

PUMP MOTOR OVER CURRENT-RHR A-None Insert override 1ODS40_A_LO to On LOOP A (LO)

PUMP MOTOR OVER CURRENT -RHR B-None Insert override 1ODS93_A_LO to On LOOP B (LO)

PUMP MOTOR OVER CURRENT-RHR B-None Insert override 1ODS93_A_LO to On LOOP B (LO) 2013 NRC Scenario #2 Page 6 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments N2 M/U to the Primary

CRS directs N2 Makeup to the Containment: Primary Containment.

Refer to SO.GS-0001 Section

PO conducts N2 makeup to the 5.2 and SUPPORT requests for Primary Containment lAW field manipulations with SO.GS-0001 Section 5.2 and appropriate reports. 5.3.

(The simulator does not model any of these functions. The N2 vaporizer is always lined up for make-up).

Power Reduction:

RO reduces and maintains recirc HPI USED:

Crew places lowers power to flow to establish 90% RTP (not to STARD 90% RTP using recirculation exceed 1%/min). PEER CHECK D pumps.

RECIRC LOOP FLOW

Crew monitors Reactor power, SUMMER 'C' FAILURE: pressure, and level and ensure At the discretion of the lead plant conditions are stable.

Examiner, Ensures no scram setpoints have TRIGGER ET-1 (RECIRC been exceeded.

LOOP FLOW SUMMER FAILURE to 0 percent).

2013 NRC Scenario #2 Page 7 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE

Event /Instructor Activity Expected Plant/Student Response Comments

Crew recognizes RPS % scram by:

=> OHA C3-A3 "REACTOR SCRAM TRIP LOGIC A2"

=> OHA C5-A 1 "NEUTRON MONITORING SYSTEM"

=> RPS Trip Logic A2 NORMAL/RESET status lights extinguished

=> Pilot Scram Valve Solenoid LOGIC A NORMAL status lights for all four groups extinguished.

=> GRIDS D2125 NEUTRON MON SYST SCRAM W

=> GRIDS D2131 "REACTOR SCRAM W TRIP"

=> GRIDS D2132 "REACTOR SCRAM YTRIP"

Crew recognizes 'A', 'C', and 'E' APRMs Upscale by:

=> OHA C3-C4 "APRM SYS A UPSCALE TRIP/INOP"

=> C3-D4 "APRM UPSCALE"

=> APRMs A,C, and E "UPSC TR OR INOP" status lights

=> APRM A,C, and E "UPSC ALARM" status lights

=> GRIDS D4303 "APRM CH A UPSCALE THERMAL TRIP"

=> GRIDS D4306 "APRM CH C UPSCALE THERMAL TRIP" 2013 NRC Scenario #2 Page 8 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

Crew recognizes 'C' RECIRC LOOP FLOW SUMMER FAILURE Downscale by:

~ FLOW UNIT C and A "COMPAR" status lights

~ APRM A, C, and E "UPSC ALARM" status lights

~ GRIDS C026 "EITHER RBM CHANNEL UPSCALE"

~ GRIDS C049 "RECIRC FLOW COMPR OUT LIMITS"

CRS implements AB.IC-0004:

~ Condition F

CRS references AB.IC-0003:

~ Condition B

RO bypasses 'C' Flow Unit. HPI USED:

STARD PEER CHECK D

CRS refers to DD.ZZ-0020 for a failed PPC Sensor.

CRS directs Reactor Engineering to evaluate the flow unit failure on the PPC.

IF directed to place the Flow

RO directs I&C to place the Unit C MODE Switch in the MODE Switch, on the applicable unlabeled position, THEN flow unit, to the "UNLABELED" CHANGE Malfunction NM12C position between STANDBY and Final value to 100%. ZERO.

RO verifies RPS trip clear.

2013 NRC Scenario #2 Page 9 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

RO resets RPS trip as follows: HPI USED:

~ TURN the affected RPS Trip STARD Logic key to RESET, AND PEER CHECK D RETURN to the NORMAL position.

~ VERIFY that RPS is reset.

CRS determine no Tech Spec actions required. Enter Tracking Action statement for:

~ Table 3.3.6-1 Function 6 Loss of CD481:

Crew recognizes loss of CD481 After the Crew assumes the by:

watch and at the discretion of ~ OHA D3-E3 "120VAC UPS the Lead Examiner, TROUBLE" TRIGGER ET-2 (Loss of ~ OHA C6-A1 "RSP/RSS CD481 120AC 1E Inverter). TAKEOVER"

~ Downscale indications for 'A' Channel DC systems and CD481 on 10C650D

~ 'C' Channel ECCS "TRIP UNIT OUT OF FILE OR PWR FAIL" lights

~ CRIDS page 167 indications

Crew recognizes loss of Reactor Building Ventilation by:

~ Supply/Exhaust Dampers HD-9370A AND HD-9414A closure

~ Fans trip

CRS implements AB.ZZ-0136.

Crew verifies that 'B' Control Room vent train automatically starts.

Crew recognizes that TACS loops failed to automatically swap 2013 NRC Scenario #2 Page 10 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

CRS directs manually swapping TCAS pumps lAW HC.OP-AB.22-0001, Att 10.

Crew recognizes various other effects of CD481 loss:

=> AP210 SACS pump running

=> 'C' Channel LOCA LVL 2 load shed breakers open on 10C650E

=> PCIG valve isolations including common suction line isolation

=> HPCI suction swap to torus IF dispatched to CD481

Crew dispatches ABEO and inverter, Maintenance to CD481 inverter.

THEN REPORT:

The Inverter Output breaker CB10 is tripped.

The AC Reg Output breaker CB302 is tripped

There is an acrid odor coming from the static switch section

CRS implements AB.COMP-002:

=> Condition F IF dispatched to check the

RO/PO align BK202 PCIG HPI USED:

A/BK202 Safety Circuit, compressor to supply PCIG STARD THEN REPORT status lAW the through the Accident suction following Monitor Items:

AK202- ia_6cr

BK202- ia_6crb

=> False= reset

=> True = tripped IF directed to reset a compressor safety lockout, THEN TOGGLE associated Remote Function IA08/IA09 to RESET.

2013 NRC Scenario #2 Page 11 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

CRS implements AB.CONT-0002:

~ Condition B

CRS recognize the following Must restore CD481 Tech Spec actions apply: within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in

~ Distribution - Operating at least HOT 3.8.3.1 action a SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

CRS contacts Operations Management.

Recirc Pump Seal Failure:

Crew recognizes second stage First stage seal failure After loss of Inverter actions seal failure on 'A' Recirc pump will occur three minutes are complete, AND at the by: after the second stage.

discretion of the Lead ~ OHA C1-F5 "COMPUTER PT Examiner, IN ALARM" TRIGGER ET-3 ('A' Recirc ~ GRIDS D2924 "RECIRC Pump Dual Seal Failure). PUMP A SEAL LKG FLOW HI"

~ GRIDS D2926 "RECIRC PUMP A SEAL STAGE FLOW HILO"

~ Lowering second stage seal pressure

CRS implements AB.RPV-0003:

~ Condition D 2013 NRC Scenario #2 Page 12 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

!E dispatched to report local

Crew recognizes 'A' Recirc pump RECORD time dual seal pressures on 77' Rx Bldg, dual seal failure by: recirc pump seal failure THEN REPORT readings ~ OHA C1-F5 "COMPUTER PT is recognized OR OHA consistent with GRIDS IN ALARM" reflash C6-B1 is received (Page 85), ~ Changing seal pressures (whichever is first) for OR the following Monitor Items: ~ Rising seal temperatures ECG Classification.

(Monitor Items are psia) ~ OHA C6-B1 "OLD SYSTEM Time: - - - -

'A' Recirc lnbd (#1) Seal ALARM/TRBL" rrpsl1 (1} - 15 = psig ~ RM11 9AX317/318/320 OLD

'A' Recirc Outbd (#2) Seal CCM alarms rrpsl2(1} -15 = psig ~ RM11 9AX314 OLD Floor Drain Flow alarm

~ Rising drywell pressure

CRS implements AB.CONT-001:

~ Condition A

RO/PO ensure drywell cooling is HPI USED:

maximized. STARD Monitor Items:

CREW trips and isolates the RECORD drywell

HV-F023A 'A' RR pump before DRWL pressure when 'A' rrvf23(1} pressure reaches 1.68 psig by Reactor Recirc pump is

HV-F100 closing the: isolated:

cuvf100 HV-F023A

HV-F031A HV-F100 Drywell Pressure: __

rrvf31(1} HV-F031A

CRS implements AB.RPV-0006:

~ Condition B

~ Condition C IF the Crew scrams during the

Crew validates successful recirc seal failure, isolation by:

THEN proceed to the ATWS. ~ Seal pressures and Power Oscillations NOT be temperatures observed. ~ Trending OLD flows

~ Trending drywell pressure and temperature 2013 NRC Scenario #2 Page 13 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

Crew monitors plant response to the transient.

Power Oscillations

Crew recognizes power At the discretion of the lead oscillation and locks the mode evaluator, insert Trigger ET-4 switch in Shutdown lAW Power Oscillations AB.RPV-00031mmediate Operator Actions ATWS >4%:

Crew recognizes Scram RECORD time of Mode Full core electrical ATWS w/ Condition and Reactor Power Switch to SHUTDOWN failure of ARI. Above 4% EOP entry condition: or Turbine Trip

=> APRM indications (whichever was first) for

=> Absence of rod FULL IN lights 15 min ECG on the Full Core Display Classification.

=> Rod position indications Time: - - - -

STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

RO performs scram actions lAW HPI USED:

AB.ZZ-0001 Attachment 1. STARD Reactor Scram Reports HARD CARD D Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status lAW HC.OP-AB.ZZ-0001. Crew personnel should hold all other non-essential communications until after the initial scram report is complete. The Control Room Supervisor should silence alarms during the scram report and the SM/CRS is not required to make a statement directing the NCO to check the overhead alarms, since these actions are already expected immediately following the scram.

During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff lAW HC.OPAB.ZZ-0001.

2013 NRC Scenario #2 Page 14 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL

CRS implements EOP-101A.

TRANSIENT MITIGATION

Prioritize the Power Leg to establish SLC injection as soon as possible.

Terminating and Preventing HPCI in a timely manner is critical in order to reduce reactor power by establishing and maintaining a -

50" to -100" RPV level band.

Maximize steam loads lAW with the post scram pressure control hard card actions when reactor power exceeds bypass valve capability.

Although Abnormal Operating Procedure HC.OPAB. BOP-0002 guidance for tripping the turbine should still be followed, the impact of tripping the turbine on RPV pressure control should be evaluated and actions taken ahead of time to minimize the impact of the loss of the turbine (e.g., all other steam demands are maximized, turbine parameters are closely monitored to provide the longest time possible for other reactor shutdown actions to be implemented prior to tripping the turbine). If reactor power is within the capability of the turbine bypass valves, the turbine should be tripped without any additional delay.

After Terminating and Preventing low pressure ECCS, place RHR in suppression pool cooling in order to mitigate reaching 11 0 degrees Fin the Torus with SRVs cycling.

With limited injection sources, if RPV level stabilizes below -185",

the decision on whether reactor level can be restored above -185" will be based on the time required to insert sufficient negative reactivity to allow reactor level to stabilized above -185".

As control rods are inserted, reduce injection flow to maintain reactor level low in the assigned band to reduce reactor power.

2013 NRC Scenario #2 Page 15 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL

PO stabilizes and maintains RPV TRANSIENT MITIGATION For ATWS conditions where reactor level as directed by CRS.

power remains >4% RTP, the CRS should direct the PO to remain at feedwater to stabilize RPV level.

Under these conditions, the Recirc pumps are already tripped and RWCU has already isolated and the PO should be assigned the action to initiate SLC. The RO, following completion of the post scram hard card ATWS mitigation actions (manual scram and ARI initiation),

should be directed to Terminate and Prevent HPCI injection prior to implementing any other EOP-101A actions such as inhibiting ADS or inserting control rods. The basis for this direction is; 1) to facilitate PO control of RPV level; 2) mitigate the reactor power excursion due to the cold water HPCI injection inside the shroud; and 3) ensure that the main turbine remains available to facilitate RPV pressure control.

CRS directs:

=> Initiating SLC

=> Verifying RWCU Isolates

RO/PO initiate SLC and verify HPI USED:

RWCU isolates. STARD PEER CHECK D RWCU Failure to Auto Isolate

Crew recognizes failure of RWCU to isolate by: If RWCU is isolated

=> OHA C1-A2 "RWCU DIFF before differential flow FLOW HI" setpoint is reached,

=> GRIDS D5870 "RWCU DIFF isolation will not be FLOW CH D" received.

=> GRIDS D5872 "RWCU DIFF FLOW CH A" 2013 NRC Scenario #2 Page 16 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments InSight Items:

RO/PO close RWCU HV-F001 HPI USED:

A' Channel Isolation and HV-F004. STARD cu_k6a09 Immediate Operator

'D' Channel Isolation action lAW cu_k6d11 AB. CONT-0002.

HV-F001 cuvf001

HV-F004 cuvf004

Crew initiates closure of RECORD time between RWCU HV-F001 OR HV-F004 C1-A2 and initiating before OHA C1-A2 "RWCU closure.

DIFF FLOW HI" has been in for Time: - - - -

two minutes. Closing the RWCU HV-F001 OR HV-F004 prior to receiving OHA C1-A2 satisfies this Critical Task.

Crew isolates RWCU lAW HPI USED:

SO.BG-0001. STARD

CRS implements AB.CONT-002: Condition A applies if

~ Condition A C1-A2 is received.

~ Condition B

STA/IA monitors AB.CONT-0002 implementation.

Crew validates isolation by trending:

~ RWCU differential flow

~ Offsite release rates

CRS recognize primary References to UFSAR Continuous Conductivity section 5.2.3.2.2.2 can Monitoring is lost, contact Shift be found in:

Chern Tech to ensure

ARP for OHA C1-F2 compliance with UFSAR section

SO.BG-0001 5.2.3.2.2.2 2013 NRC Scenario #2 Page 17 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

Crew starts AP208 SLC pump ENTER Supp Pool before Suppression Pool temp when AP208 SLC temperature reaches 110 pump is started:

degrees. Temp: _ __

Trip of both SLC Pumps:

Crew recognizes trip of AP208 &

-30sec after crew manually BP208 SLC pumps by:

isolates RWCU or -2mins after ~ OHA C1-B1 "SLC A TWS if crew fails to manually PUMP/VALVE 0/PF" isolate RWCU, and at the ~ OHA C1-F1 "SLC/RRCS discretion of the Lead INITIATION FAILURE" Examiner, TRIGGER ET-5 ~ GRIDS D3023 "SLC INJ PMP (Trip of AP208 & BP208 SLC BP208 TROUBLE TRBL" Pumps). ~ GRIDS D3023 "SLC INJ PMP AP208 TROUBLE TRBL"

~ Flashing STOP light for AP208 and BP208 IF dispatched to investigate trip

Crew dispatches NEO and of AP208 & BP208, Maintenance to investigate trip of THEN REPORT that both AP208 & BP208 SLC pumps.

motors are hot to the touch and the breakers will not reset.

(52-2221 01)

CRS determines a SAE Classification is required lAW EGG Section 553.1 (An automatic scram failed to shutdown the reactor as indicated by reactor power > 4%

AND Manual scram actions taken at the reactor control console (mode switch, manual scram pushbuttons, manual ARI actuation) DO NOT shutdown the reactor as indicated by reactor power> 4%).

2013 NRC Scenario #2 Page 18 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

CRS declares SAE lAW ECG RECORD time SAE Section SS3.1. declared.

(Note: declaration may be completed Time after scenario termination at lead Declared: - - -

evaluators discretion)

CRS directs inhibiting ADS.

RO/PO inhibit ADS lAW HPI USED:

AB.ZZ-0001 Att. 13. STARD HARD CARD 0

CREW prevents an This Critical Task is not uncontrolled depressurization applicable if RPV level during A TWS conditions by never reaches -129".

preventing ADS ACTUATION. See justification for failure criteria.

2013 NRC Scenario #2 Page 19 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments REFER to the appropriate EOP

CRS directs performance of the The timing, order, and and SUPPORT Crew requests following EOPs: priority of the EOP for EOPs lAW with the ~ EO.ZZ-0320 "Defeating ARI performance may vary.

following. Validated execution and RPS Interlocks" time delays are built-in: ~ EO.ZZ-0301 "Bypassing EOP-301: ET-5 MSIV Isolation Interlocks" EOP-311: ET-6 ~ EO.ZZ-0311 "Bypassing EOP-319: ET-7 Primary Containment EOP-320: ET-8 Instrument Gas Isolation EOP-322: ET-9 Interlocks"

~ EO.ZZ-0319 "Restoring STRATEGIES FOR SUCESSFUL Instrument Air in an TRANSIENT MITIGATION Emergency" Promptly initiate actions lAW the 300 ~ EO.ZZ-0322 "Core Spray series EOPs to shutdown the reactor.

Timely actions will reduce the Injection Valve Override" potential continued challenges to containment. In addition, once the post scram hard card actions have been completed and RPV level has stabilized in the required band, an NCO should be assigned the responsibility to insert control rods lAW the post ATWS CRD operation hard card and CRAM move sheets.

When control room portions of EOP-320 have been completed and the NCO is ready to re-insert a manual scram, the NCO should perform a crew update and utilize the post scram hard card to implement the applicable post scram actions following the manual scram attempt.

CRS directs terminating and preventing injection to the RPV with the exception of:

~ SLC

~ CRD

~ RCIC

RO/PO terminate and prevent HPI USED:

injection lAW AB.ZZ-0001: STARD

~ Attachment 16 (1 OC651) HARD CARD D

~ Attachment 17 (1 OC650) 2013 NRC Scenario #2 Page 20 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

CRS directs maintaining RPV Typically, the lower end water level between -50" and of the level band is set

-185". above -129".

RO/PO control level as directed HPI USED:

by CRS with: STARD

=> Feedwater lAW AB.ZZ-0001 HARD CARD D Att. 14 If the turbine trips

=> RCIC lAW AB.ZZ-0001 Att. 6 before the reactor is

=> HPCI lAW EOP-322 scrammed, an RRCS feedwater runback may occur.

Crew lowers RPV level to -50",

and ensures adequate core cooling by maintaining or restoring RPV level above -

185" without Emergency Depressurizing.

CRS directs bypassing the RWM and commencing manual rod insertion.

RO/PO align CRD for ATWS HPI USED:

operation lAW AB.ZZ-0001 STARD Attachment 18. HARD CARD D

RO/PO bypass RWM and insert HPI USED:

control rods lAW RE-AB.ZZ-0001 STARD Attachment. 1. HARD CARD D Total Loss of EHC:

Crew recognizes trip of the '8'

-4min after the plant is tripped, EHC pump by:

and at the discretion of the => OHA D3-F5 "TURB HYDR Lead Examiner, TRIGGER PUMP TROUBLE" ET-6 (Trip of the '8' EHC pump).

Note: the BPVs will fail close

-3min after total loss of EHC.

2013 NRC Scenario #2 Page 21 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

Crew recognizes turbine bypass valves failing shut by:

=> OHA D3-D5 "EHC UNIT PANEL 10C363"

=> DEHC Bypass Valve Positioning Error alarms

=> Reactor pressure rising above Pressure Setpoint STRATEGIES FOR SUCESSFUL When pressure control

CRS directs stabilizing pressure TRANSIENT MITIGATION Pressure Leg below 1037 psig with: swaps to SRVs, Direct initial pressure control as => Main Steam Line Drains maintaining RPV water Stabilize pressure 800 psig to 1000 => SRVs level between -50" and psig. The lower limit of 800 psig will => RPFT -129" will be very not complicate RPV level challenging due to maintenance and will prevent an unwanted cooldown. The upper limit shrink and swell and of 1000 psig is a round number below changing reactor 1047 psig. pressure with the RFPTs in MAN.

RO/PO control pressure as HPI USED:

directed by CRS with: STARD

=> Main Steam Line Drains lAW HARD CARD D AB.ZZ-0001 Att. 15

=> SRVs lAW AB.ZZ-0001 Att. 13

=> RFPTs

Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

=> OHA C8-F1 "SUPPR POOL TEMP HIGH"

=> Flashing 95 degree status light on 1OC650C

=> RM11 9AX833/834 alarm

=> Various Suppression Pool temperature indicators 2013 NRC Scenario #2 Page 22 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments Strategies For Successful Transient Mitigation

CRS implements EOP-1 02 .

Torus Temperature Leg Start all available Torus cooling as soon as possible to remove heat from containment.

CRS directs placing AP202 RHR pump in Suppression Pool Cooling and Suppression Chamber Spray.

RO/PO place AP202 RHR pump HPI USED:

in Suppression Pool Cooling and STARD Suppression Chamber Spray HARD CARD D lAW AB.ZZ-0001 Att. 3.

STRATEGIES FOR SUCESSFUL

WHEN Suppression Chamber TRANSIENT MITIGATION pressure exceeds 9.5 psig, EOP-102 Primary Containment THEN CRS directs initiating Control.

Primary Containment Pressure Leg drywell spray.

When controlling Primary Containment Pressure and it becomes apparent that the PSP curve is going to be exceeded and Torus level is in the normal band, the Control Room Supervisor should pick 15 psig Torus Pressure to determine if the pressure can be maintained below the PSP limit. The 15 psig limit is below the PSP limit and will allow sufficient time to evaluate further actions needed such as EOP-202 RPV blowdown. If no systems are available to restore and maintain Torus Pressure, it is expected that you would enter EOP-202 and blowdown prior to exceeding PSP.

RO/PO place AP202 RHR pump HPI USED:

in Drywell Spray lAW STARD AB.ZZ-0001 Att. 2. HARD CARD D BP202 is not available due to 1OD420 failure.

2013 NRC Scenario #2 Page 23 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments Failure of RHR Torus Cooling

Crew recognizes failure of Valve to Open HV-F021A by:

=:> OHA A6-B1 "RHR LOOP A TROUBLE"

=:> Flashing OVLD/PWR FAIL

=:> Loss of position indication

=:> No indication of drywell spray flow

=:> GRIDS D4465 "RHR CONT SPY OUTBD HV-F021 A OPF"

!E dispatched to investigate trip

Crew dispatches NEO and of HV-F021A breaker, Maintenance to breaker for THEN REPORT the breaker is HV-F024A (52-451 062).

tripped and will not reset.

RO/PO opens HV-F021A and HPI USED:

initiates Suppression Chamber or STARD Drywell Spray lAW AB.ZZ-0001 HARD CARD D Att. 2 or 3.

!E dispatched to investigate trip

Crew dispatches NEO and of HV-F021A breaker, Maintenance to breaker for THEN REPORT the breaker is HV-F024A (52-451 062).

tripped and will not reset.

!E Suppression Pool temperature is >11 0 degrees, AND Reactor power is >4%,

AND SRVs are open or cycling, THEN Crew terminates and prevents injection to the RPV with the exception of SLC, CRD, and RCIC, UNTIL Reactor power is <4%,

OR RPV level reaches -129",

OR SRVs remain closed.

2013 NRC Scenario #2 Page 24 of 31 Rev: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

IF RPV level reaches -129", HPI USED:

THEN RO/PO terminate and STARO prevents injection from Core HARD CARD 0 Spray lAW AB.ZZ-0001 Attachment 16.

WHEN the Crew has reset

WHEN EOP-320 Section 5.1 and HPI USED:

RPS, 5.2 are complete, STARO THEN DELETE Malfunction THEN the Crew implements PEER CHECK 0 RP07 to allow full rod insertion EOP-320 Section 5.3 and reset on the next scram. RPS.

At the Lead Examiners

WHEN OHA C6-E4 clears, HPI USED:

discretion, MODIFY InSight THEN the Crew initiates a STARO Item lclsdv to accelerate manual scram lAW EOP-320 PEER CHECK 0 draining of the SDV. Section 5.3.

CREW fully inserts all control rods via RMCS and/or manual scram(s) lAW HC.OP-EO.ZZ-0320.

Crew recognizes the reactor is shutdown by:

=> SPDS ALL RODS IN

=> RWM Confirm Shutdown

=> CRIDS Rod positions Termination Requirement:

CRS exits EOP-101A, enters The scenario may be EOP-1 01.

terminated at the discretion of the Lead Examiner when:

RPV Level is being maintained above -185" AND

All rods are fully inserted 2013 NRC Scenario #2 Page 25 of 31 Rev: 1

VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1003 Use of Procedures M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-1 01-111-1004 Operations Standards

0. OP-AA-1 01-112-1002 On-Line Risk Assessment P. OP-AA-106-101-1001 Event Response Guidelines Q. OP-HC-1 08-106-1001 Equipment Operational Control R. OP-AA-1 08-114 Post Transient Review S. OP-HC-1 08-115-1001 Operability Assessment and Equipment Control Program T. HC.OP-SO.AE-0001 Feedwater System Operation U. HC.OP-SO.EC-0001 Fuel Pool Cooling and Cleanup System V. HC.OP-SO.SF-0003 Rod Worth Minimizer Operation W. HC.OP-AB.ZZ-0001 Transient Plant Conditions X. HC.OP-AB.CONT-0001 Drywell Pressure Y. HC.OP-AB.CONT-0001 Drywell Leakage Z. HC.OP-AB.COOL-0003 Reactor Auxiliary Cooling AA. HC.OP-EO.ZZ-0311 Bypassing Primary Containment Instrument Gas Isolation Interlocks BB. HC.OP-EO.ZZ-0319 Restoring Instrument Air in an Emergency CC. HC.OP-EO.ZZ-0320 Defeating ARI and RPS Interlocks DO. HC.OP-EO.ZZ-0322 Core Spray Injection Valve Override EE. HC.OP-EO.ZZ-01 01 RPV Control FF. HC.OP-EO.ZZ-0101A ATWS-RPV Control GG. HC.OP-EO.ZZ-0102 Primary Containment Control 2013 NRC Scenario #2 Page 26 of 31 Rev: 1

VII.ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #2, Rev 01 1.

CREW prevents an uncontrolled depressurization during A TWS conditions by preventing ADS ACTUATION.

KIA 218000 Automatic Depressurization System A4 Ability to manually operate and/or monitor in the control room:

A4.04 ADS inhibit RO 4.1 SRO 4.1 Given the current A TWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor. EOPs direct this action under the current conditions.

This critical task is only applicable if RPV water level goes below -129". Failure to satisfactorily complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure by 300 psig.

2.

CREW maintains or restores adequate core cooling by restoring/maintaining Reactor water level to >-185"/AW HC.OP-EO.ZZ-0101A without Emergency Depressurizing.

KIA 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA2.02 Reactor water level RO 4.1 SRO 4.2 Maintaining adequate Core cooling under ATWS conditions is accomplished by maintaining/restoring level above -185". HPCI and RCIC are capable of maintaining level under the current conditions. AB.ZZ-0001 provides directions on manual initiation of HPCI which will mitigate the automatic initiation failure. An Emergency Depressurization is not warranted and would result in a large injection of cold water and the potential displacement of boron from the core.

3.

CREW fully inserts all control rods via RMCS and/or manual scram(s) JAW HC.OP-EO.ZZ-0320.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA 1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA1.01 Reactor Protection System RO 4.6 SRO 4.6 EA 1.07 RMCS RO 3.9 SRO 4.0 Manually inserting all control rods, OR, implementing HC.OP-EO.ZZ-0320, provides the only methods for control rod insertion and substantial negative reactivity addition. It is critical for the crew to implement one of these methods to insert control rods and shut the reactor down. Failure to initiate these actions may result in requiring RPV level to be lowered to or below TAF to reduce power to <4%. This represents a significant challenge to maintaining adequate core cooling.

2013 NRC Scenario #2 Page 27 of 31 Rev: 1

2013 NRC Scenario #2, Rev 01 HOPE CREEK ESG- PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT

- - - Loss Of Offsite Power/SBO Internal Flooding

- - - LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY KEY EQUIPMENT KEY SYSTEMS HPCI SRVs

_ _ _ RCIC

- - - Condensate/Feedwater

_ _ _ B/DEDG ___ ssw

_ _ _ AlB RHR Pump

- - - RPS

_ _ _ AlB SACS Loop 1E4.16KVBus 1E 480 VAC Bus

_ _ _ 120VAC 481 Inverter

_ _ _ 1E 125VDC

- - - Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION

- - - Manual Depressurization of the RPV w/ no HP Injection Available

_ _ _ Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi OW Press. Signal

_ _ _ Control RPV Water Level w/ HP Injection during ATWS Sequence

_ _ _ Align Portable Power Supply to Battery Chargers

_ _ _ Venting of Primary Containment

- - - Restore Switchgear Cooling

- - - Restart Condensate

- - - Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG.

2013 NRC Scenario #2 Page 28 of 31 Rev: 1

VIII. TURNOVER SHEET:

ONLINE RISK: GREEN WORK WEEK CHANNEL: A PROTECTED EQUIPMENT None REACTIVITY I Plant Status 100% Power ESF/SAFETY SYSTEMS None COOLING WATER None BOP

'A' EHC Pump tagged for planned maintenance ELECTRICAL None ADVERSE CONDITION MONITORING None Initiate & secure N2 makeup to the primary containment to test the flow recorder (a calibration was just performed) 2013 NRC Scenario #2 Page 29 of 31 Rev: 1

IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG: Scenario 2 SELF-CHECK

1. Total malfunctions inserted: 4-8

___ 2. Malfunctions that occur after EOP entry: 1-4

- - - 3. Abnormal Events: 1-2

___ 4. Major Transients: 1-2

___ 5. EOPs used beyond primary scram response EOP: 1-3

___ 6. EOP Contingency Procedures used: 0-3

___ 7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

- - - 8. EOP run time: 40-70% of scenario run time

- - - 9. Crew Critical Tasks: 2-5

- - - 10. Technical Specifications are exercised during the test: _:::1 Comments:

ESG-074 Page 30 of 31 Rev.: 09

EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't)

Crew Validation Rev: 01 Date Validated: - - - -

Validation Comments Disposition Crew Validation Rev: Date Validated:

Validation Comments Disposition Crew Validation Rev: Date Validated: _ _ __

Validation Comments Disposition ESG-074 Page 31 of 31 Rev.: 09

SIMULATOR EXAMINATION SCENARIO GUIDE APRM Upscale, Single Rod Scram, Loss of Drywell Clg, Loss of SCENARIO TITLE:

1OB430, HPCI Steam Leak, ED SCENARIO NUMBER: Scenario #3 2013 NRC Exam EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 60 minutes REVISION NUMBER: 01 PROGRAM: .___ ____.I L.O. REQUAL X I INITIAL LICENSE L------'1 OTHER REVISION

SUMMARY

2013 Initial NRC Exam PREPARED BY: 01/22/13 NRC Examiner DATE Reviewed BY:

Chief Examiner DATE APPROVED BY:

OLB Branch Chief DATE

I. OBJECTIVE(S):

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Critical tasks within this examination scenario guide are identified with an"*.")

II. MAJOR EVENTS:

A. APRM channel C Upscale w/Single Rod Scram B. Loss of T8 Chilled water C. Loss of 108430 D. HPCI Steam Leak w/Failure to Isolate E. FRVS Vent Fan Trips F. Trip of EHC Pumps w/Turbine Bypass Valves Failing Shut G. RCIC Pump Room High Temperature Ill. SCENARIO

SUMMARY

The scenario begins with the plant at 75% power and TACS on the 'B' SACS loop. The DK111 Turbine Chiller is CIT for a freon leak and CP161 is CIT for a bearing oil leak. The turnover directed the crew to raise power using recirc flow. After the power maneuver, C APRM fails upscale causing a half scram. Due to a mispositioned SRI Test Toggle switch, a single rod will scram in when the RPS half scram occurs. After Tech Specs have been referenced, the AP161 will trip due to a bearing problem. The 8P161 goes into runout and trips shortly thereafter. This results in a loss of TB Chilled water, which will require the Crew to align RACS to cool the drywell and vent the drywell to restore pressure back below 0. 75 psig. After the Loss of Drywell Cooling has been addressed, the 108430 1E 480 VAC Unit Substation will be lost due to a transformer failure. This will result in a loss of the operating CRD pump and the CP228 ECCS jockey pump.

After these failures are addressed, a steam leak develops in the HPCI room. The inboard steam isolation valve is not available due to the loss of the 1OB430 Substation, and the outboard steam isolation valve binds and will not close. The leak will impact the RCIC room, due to the door between HPCI and RCIC not being properly dogged shut. When HPCI room temperature reaches 200 degrees, the door will pop open, admitting steam to the RCIC room. The unisolable leak will require the Crew to scram. RPS and the mode switch will fail to SCRAM the unit, requiring ARI for successful shutdown. The rising temperatures in the HPCI and RCIC rooms will ultimately require Emergency Depressurization.

2013 NRC Scenario #3 Page 2 of 31 Rev.: 1

IV. INITIAL CONDITIONS:

I. C.

Initial INITIALIZE the simulator to 100% power, MOL.

MAKEUP N2 to the drywell until drywell and Suppression Chamber pressure are 0.53-0.57 psig.

ENSURE BOTH Steam Tunnel unit Coolers are in service.

ENSURE the 'A' CRD pump is in service.

ENSURE the 'A' EHC pump is in service.

ENSURE T ACS is being supplied by the 'B' SACS loop.

ENSURE the 'B' Control Room Vent Train is in service.

ENSURE the 'C' SSW pump is in standby.

ENSURE the 'C' SACS pump is in standby.

CIT CP161 TB Chilled water eire pump as follows:

ENSURE CP161 is not in service .

PLACE CP161 in MAN .

CIT DK111 as follows:

ENSURE DK111 is not in service

PRESS DK111 STOP pushbutton

ENSURE HV-95030 is CLOSED ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description PLACE red bezel cover on DK111.

PLACE red bezel cover on HV-95030.

PLACE red bezel cover on CP161.

PREPARE a Fire Alarm for FA015 Fire Zone 4109.

At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed. (80091396 0270)

TREND plant parameters needed for Critical Task determination:

0 HPCI Room Temperature 0 RCIC Room Temperature 0 Reactor Pressure 0 Wide Range RPV Level COMPLETE "Simulator Ready-for-Training/Examination Checklist".

2013 NRC Scenario #3 Page 3 of 31 Rev.: 1

EVENT FILE:

Initial ET#

Event code: hpvv(1) <= 0.90 II HPCI HV-F003 valve position 6

Description:

Trips breaker for HPCI HV-F003 when closure is attempted from the Control Room.

Event code: hvtr4111 > 160 II HPCI Room Temp 7

Description:

Triggers RCIC Steam leak to allow raising RCIC Room temp.

Event code: crqnmi <= 15 II Reactor Power 8

Description:

Inserts HPCI Steam Leak at 40% on reactor scram.

Event code: rrprv < 650 II Reactor Pressure in psia 9

Description:

Raises severity of HPCIIeak if Crew depressurizes Event code: hvtr4111 > 200 II HPCI Room Temp 10

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 210 II HPCI Room Temp 11

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 220 II HPCI Room Temp 12

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 230 II HPCI Room Temp 13

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 240 II HPCI Room Temp 14

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 250 II HPCI Room Temp 15

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 255 II HPCI Room Temp 16

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 260 II HPCI Room Temp 17

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 265 II HPCI Room Temp 18

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 270 II HPCI Room Temp 19

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 271 II HPCI Room Temp 20

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 272 II HPCI Room Temp 21

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 273 II HPCI Room Temp 22

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 274 II HPCI Room Temp 23

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 275 II HPCI Room Temp 24

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 276 II HPCI Room Temp 25

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 277 II HPCI Room Temp 26

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 278 II HPCI Room Temp 27

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code:

Description:

2013 NRC Scenario #3 Page 4 of 31 Rev.: 1

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description CRYWOLF ANN E5Fl CHILLED WTR None None Insert malfunction AN-E5Fl SYSTEM TROUBLE HPCI steam isolation valves F002 & F003 None None Insert malfunction HP 10 failure to auto close ADS/Relief valve F013D (MS LINE D)

None None Insert malfunction AD02DC sticks close None None Insert malfunction NM21C to 100 on event 2 APRM C failure None None Insert malfunction CD060227 after 1 on event 2 Control Rod 02-27 SCRAM None None Insert malfunction CW18A on event 3 Chilled water eire pump AP 161 trip Insert malfunction CW18B after 5 on None None Chilled water eire pump BP 161 trip event 3 None None Insert malfunction ED 13C 1 on event 4 Loss of 480 V AC essential bus C 10B430 Insert malfunction HP09 from 5.00000 to HPCI steam line break inside HPCI Room None None 40.00000 in 60 on event 5 4111 CRYWOLF ANN A2A5-FIRE PROT None None Insert malfunction AN-A2A5 on event 5 PANEL 10C67l None None Insert Malfunction '???? on event 6 FR VS Vent Fan Trip Insert malfunction RC09 to 1.00000 on RCIC steam line break inside the RCIC None None event 7 ROOM4110 None None Insert malfunction TC07 A on event 7 EHC pump A trip Insert malfunction TC07B after 60 on None None EHC pump B trip event 8 Insert malfunction TCO 1-10 after 120 on None None All turbine bypass valves fail closed event 8 None None Insert malfunction CD030227 on event 16 Control Rod 02-27 stuck 2013 NRC Scenario #3 Page 5 of 31 Rev.: 1

REMOTE SCHEDULE:

Initial @Time Event Action Description HP04 GROUP SA HV-F002 HPCI Steam None None Insert remote HP04 to FAIL OPEN Supply Isol Insert remote HP06 to RACK OUT on HP06 GROUP SA HV-F003 HPCI Steam None None event 6 Supply Isol Insert remote CX11 after 120 to OPEN on CX11 CX valve AP-V041 to Core Spray None None event 3 header A None None Insert remote CX15 to OPEN on event 3 CX15 CX valve AP-V044 to RHR header A Insert remote CX 17 after 60 to OPEN on None None CX17 CX valve AP-V047 to RHR header C event 3 None None Insert remote HV06 to STOP on event 5 HV06 RBVS Supply fan C Insert remote HV05 after 1 to STOP on None None HV05 RBVS Supply fan B event 5 Insert remote HV04 after 1 to STOP on None None HV04 RBVS Supply fan A event 5 Insert remote HV03 after 2 to STOP on None None HV03 RBVS Exhaust fan C event 5 Insert remote HV02 after 3 to STOP on None None HV02 RBVS Exhaust fan B event 5 Insert remote HV01 after 3 to STOP on None None HV01 RBVS Exhaust fan A event 5 CW33 Turbine Bldg chiller CK111 None None Insert remote CW33B to 50 Winterization 2013 NRC Scenario #3 Page 6 of 31 Rev.: 1

OVERRIDE SCHEDULE:

Initial @Time Event Action Description INOP-CHILLED WATER CPRSR DC 111-None None Insert override 1A181 - A2 - LO to On CPRSR MOT (LO)

DK111 START-CHILLEDWATERCPRSR None None Insert override 1A181- D- DI to Off DC111-CPRSR MOT (DI)

SAFETY CKT COMPLETE/ON-CHILLED None None Insert override 1A181 - E1 - DI to Off WATER CPRSR DK111 (DI)

STOP-CHILLED WATER CPRSR DC 111-None None Insert override 1A 181 -F-LO to Off CPRSR MOT (LO)

HV-9503D OPEN-CH W DISCH SHUTOFF V None None Insert override 1A182-E-DI to Off (DI)

HV -9503D CLOSE-CH W DISCH SHUTOFF None None Insert override 1A182 F LO to Off V (LO)

None None Insert override 1Al36- A2 - LO to On INOP-CH W CIRC PUMP CP161 (LO)

None None Insert override 1Al36- D- DI to Off AUTO-CH W CIRC PUMP CP 161 (DI)

None None Insert override 1Al36-E-DI to Off START-CH W CIRC PUMP CP161 (DI)

None None Insert override 1Al36-F-LO to Off STOP-CH W CIRC PUMP CP161 (LO) 2013 NRC Scenario #3 Page 7 of 31 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments Raise Power Using Recirc Flow:

CRS directs ATC to raise power 5% using Recirc Flow.

After the crew assumes the watch they will raise power per ATC adjusts Recirc flow and maneuvering sheet. monitors Reactor power, pressure, and level and ensure plant conditions are stable.

APRM C Upscale w/Single

Crew monitors Reactor power, Rod Scram: pressure, and level and ensure After the Crew raises power, plant conditions are stable.

OR, Ensures no scram setpoints have at the discretion of the Lead been exceeded

Examiner, TRIGGER ET-1.

Crew recognizes RPS % scram by:

=> OHA C3-A3 "REACTOR SCRAM TRIP LOGIC A2"

=> RPS Trip Logic A2 NORMAL/RESET status lights extinguished

=> Pilot Scram Valve Solenoid LOGIC A NORMAL status lights for all four groups extinguished.

=> GRIDS D2132 "REACTOR SCRAM Y TRIP" GRIDS D2115 "REAC VESSEL HI PRESS SCRAM Y" 2013 NRC Scenario #3 Page 8 of 31 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

Crew recognizes APRM C Upscale by:

=? C5-A 1 NEUTRON MONITORING SYSTEM

=? C3-C4 APRM SYS A TRIP/INOP

=? C3-D4 APRM UPSCALE

=? D2143 APRM CHANNEL C UPSCALE TRIP

=? D4306 APRM CH C UPSCALE THERMAL TRIP

=? C023 APRM INOPERATIVE

Crew recognizes single rod scram by:

=? OHA C6-E3 "ROD DRIFT"

=? Rod 02-27 "DRIFT",

"SCRAM", and "FULL IN" lights on Full Core display

=? RWM "DR 02-27" indication

=? GRIDS C078 "ROD DRIFT ALARM ALM"

Crew ensures only one rod is drifting.

2013 NRC Scenario #3 Page 9 of 31 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments WHEN requested,

CRS implements AB.IC-0001 THEN as RE, REPORT: Condition C

Thermal Limits are SAT.

All other control rods are at target their position.

There is no immediate problem with leaving 02-27 inserted.

You will develop a recovery plan to withdraw 02-27.

!E dispatched to troubleshoot Crew dispatches RBEO to 02-27 rod 02-27 scram, HCU.

THEN REPORT you found the

'B' S.R.I. test toggle on the

Crew contacts Rad Pro to survey 02-27 HCU out of "Normal".

scram discharge volume due to There are workers change in radiological conditions.

decontaminating the HCU bank, and one of them

RO resets the Rod Drift alarm remembers bumping lAW HC.OP-AR.ZZ-0020.

something. (02-27 is in the North HCU bank by HPCI pipechase. See EOP-303 map.)

RO bypasses APRM C.

RO resets RPS half scram.

Crew contacts Maintenance to troubleshoot APRM C failure.

SM contacts Operations Management 2013 NRC Scenario #3 Page 10 of 31 Rev.: 1

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event /Instructor Activity Expected Plant/Student Response Comments

!E directed to electrically

CRS determine Tech Spec For both T/S, still meet disarm rod 02-27, actions required. Enter Action the Minimum Operable THEN TRIGGER ET-16 to statement for: Channels per Trip INSERT Malfunction cd030227 ~ Reactor Protection System Function. Tracking (stuck rod). Instrumentation Action statement only.

3.3.1

~ Control Rod Block Instrumentation 3.3.6 (Crew may declare rod 02-27 inoperable until cause of scram is determined and enter TIS 3.1.3.1).

2013 NRC Scenario #3 Page 11 of 31 Rev.: 1

Loss of Drywell Cooling:

Loss of Drywell Cooling by: Drywell pressure will After TS call has been ~ OHA E5-E1 "CHILLED WTR peak at less than 1.2 addressed or at the discretion PANEL 10C152" psig; however, of the Lead Examiner, ~ OHA E5-F1 "CHILLED WTR IF the Crew manually TRIGGER ET-2 (Loss of TB SYSTEM TROUBLE" scrams during the Loss Chilled Water/Drywell Cooling). ~ OHA A4-F5 "COMPUTER of Drywell Cooling, POINT IN ALARM" THEN the HPCI Steam

~ Flashing "OVLD/PWR FAIL", Leak will be "HI/LOW FLOW", and "STOP" automatically inserted.

lights on AP161 and BP161 The HPCI HV-F002 is TB Chilled Water Circ pumps failed open to prevent

~ Loss of "START" lights on isolation of HPCI in this AK111/BK111 TB Chillers event since the 1OB430

~ GRIDS 05608 "CHW PUMP will still have power.

AP161 MALFUNCTION"

~ GRIDS 05609 "CHW PUMP BP161 MALFUNCTION"

~ CRI DS 04053 "WTR CHILLER AK111 REMOTE PANEL TRBL"

~ GRIDS 04054 "WTR CHILLER BK111 REMOTE PANEL TRBL"

~ Rising drywell temperature

~ Rising drywell pressure

CRS implements AB.CONT-001:

~ Condition A

~ Condition B

Crew announces loss of Turbine Building Chilled Water on the plant page.

RO/PO ensure drywell cooling is maximized.

2013 NRC Scenario #3 Page 12 of 31 Rev.: 1

!E dispatched to investigate

Crew dispatches TBEO and loss of TB Chilled Water, Maintenance to investigate.

THEN REPORT:

AK111 and BK111 have Evaporator Low Water Flow alarms in

AP161 and BP161 have Discharge Flow Hi/Low alarms in

Both AP161 and BP161 motors are hot to the touch

AP161 inboard pump bearing is hot to the touch

RO/PO align RACS to supply drywell cooling lAW Drywell pressure will AB.CONT-0001 Condition B. begin to drop as soon as the RACS and Chilled Water valves start to swap. The 9532-1/2 are not in the RACS flowpath.

IF directed to prepare a release * !E Drywell Pressure is not permit, restored below 0.75 psig, THEN REPORT it will take THEN CRS implements about 30 minutes and AB.CONT-0001:

REQUEST the Crew to record => Condition C start and stop times for the release.

IF directed, THEN PO Vents the dryweiiiAW AB.CONT-001 Condition C.

CRS contacts Operations Management to initiate a Prompt Investigation and ERT callout.

Loss of 108430 Unit Sub:

Crew monitors Reactor power, After the Crew aligns RACS to pressure, and level and ensures cool the drywell, plant conditions are stable.

OR, at the discretion of the Lead Examiner, TRIGGER ET-3.

2013 NRC Scenario #3 Page 13 of 31 Rev.: 1

Crew recognizes loss of AP207 CRD pump by:

~ OHA C6-F2 "CRD SYSTEM TROUBLE"

~ AP207 "OVLD/PWR FAIL" light

~ AP207 flashing "STOP" light

~ GRIDS D2244 "CRD WATER PUMP A MOTOR TRBL"

Crew recognizes loss of CP228 RHR and Core Spray ECCS Jockey pump by: Low Pressure alarms

~ OHA A6-C3 "ECCS JOCKEY will not be received if PUMP 1CP228 TROUBLE" Condensate Transfer is

~ Jockey pump indications on lined up before 10C650A discharge header

~ OHA A6-B1 "RHR LOOP A pressures decay to TROUBLE" alarm setpoints.

~ OHA A6-B2 "RHR LOOP C (::::11 minutes)

TROUBLE"

~ OHA B3-C1 "CORE SPRAY LOOP A TROUBLE"

~ GRIDS D4434 "ECCS JOCKEY PMP CP228 OPF"

~ GRIDS D4373 "RHR PUMP A DISCHARGE PRESSURE HILO"

~ GRIDS D4397 "RHR PUMP C DISCHARGE PRESSURE HILO"

~ GRIDS D3157 "CS LOOP A INJECTION LINE PRESSURE HILO"

Crew recognizes loss of AK202 Instrument gas PCIG compressor by: pressure is not actually

~ OHA A1-A1 "INST GAS low. The alarm is the SYSTEM A TROUBLE" result of a loss of power

~ OHA A1-A3 "INST GAS to the AC213 panel.

RECEIVER A PRESSURE LO"

~ OHA A1-A5 "INST GAS PANEL AlB C213"

~ Loss of "START" and "STOP" indication for AK202 2013 NRC Scenario #3 Page 14 of 31 Rev.: 1

Crew recognizes loss of 1OB430 Unit Substation by:

==:. OHA E3-E3 "USS FEEDER BRKR TRBL"

==:. OHA E3-F2 "4.16KV FOR TO USS XFMR BRKR MALF"

==:. GRIDS 04565 "4.16KV BUS A403 FOR CKT BRKR TRBL"

==:. GRIDS 04611 "UNIT SUBSTA 1OB430 FOR CKT BRK TRBL"

==:. Flashing TRIP light on 40310 breaker

==:. Various OVLD/PWR FAIL lights on 'C' Channel equipment

Crew announces loss of the 1OB430 bus on the plant page.

!E dispatched to 1OB430,

Crew dispatches ABEO and THEN REPORT: Maintenance to investigate the

52-40310 has 51 B and 51 C loss of the 1OB430 bus.

Time overcurrent trip flags dropped

CX400 xfmr is very warm with acrid odor and telltale in the red zone

CRS implements AB.ZZ-0172.

SUPPORT any requests for

Crew places BP207 CRD pump Accumulator trouble BP207 discharge valve in service lAW either: alarms will begin to manipulations with Remote ==:. SO.BF-0001 Sect 5.2 come in after about 14 Function CD02. OR minutes with no CRD

==:. HC.OP-AB.22-0001 Hardcard pump in service.

OR

==:. ARP for GRIDS 02244 AVERAGE HCU accumulator

CRS directs aligning Condensate pressure can be read with Transfer keepfill to 'A' Core InSight Item lcpac. Spray loop and NC RHR loops.

INDIVIDUAL HCU accumulator pressures can be read with InSight Item lcpaccx(n). See Sim Op Manual under Reactor Building Operator for "n" value.

2013 NRC Scenario #3 Page 15 of 31 Rev.: 1

!E any HCU accumulators become inoperable with no CRD pump 1/S, THEN CRS implements AB.IC-0001:

=> Condition A

!E dispatched to align AP to 'A'

RO/PO coordinate with RBEO to Core Spray and A & C RHR align Condensate Transfer lAW THEN: SO.BC-0001 for removal of

REFER to SO.BC-0001 CP228 from service.

Section 5.9

TRIGGER ET-3 to open AP-V044N04 7/V041

Crew places BK202 PCIG compressor in AULD.

CRS/STA recognize the following Must re-energize Tech Spec applies: 108430 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

=> Distribution - Operating or be in at least HOT 3.8.3.1 action a SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

May cascade to T/S 3.8.2.1.a due to loss of CD444 battery charger (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO)

!E any HCU accumulators Within 20 minutes of become inoperable with no CRD discovery, restore pump 1/S, charging water THEN CRS recognize the pressure >= 940 psig or following Tech Spec applies: place Mode switch in

=> Control Rod Scram SHUTDOWN.

Accumulators 3.1.3.5 action a.2.a

!E directed to perform fill and

CRS refer to OP-HC-1 08-115- Actions required for vent. 1001 for loss of CP228 ECCS jockey pump are THEN REPORT no air found. jockey pump AND for SSW to dependent on whether RACS isolation valves. discharge header low pressure alarms were received for Core Spray and RHR loops.

2013 NRC Scenario #3 Page 16 of 31 Rev.: 1

CRS contacts Operations Management to initiate an ERT callout.

Inadvertent HCPI Initiation:

Crew recognizes inadvertent After loss of 108430 actions HPCI initiation by:

are complete ~ Insert OHAs OR ~ Insert OHAs At the discretion of the lead ~ Insert OHAs evaluator, TRIGGER ET-4 Inadvertent HPCI Initiation

Crew implements HC.OP-AB.RPV-0001, Section C

Crew verifies Reactor Level > -

38" AND Drywell Pressure <

1.68#

Crew terminates AND Prevents HPIC Injection lAW HC.OP-AB.ZZ-0001

Crew DEPRESSES the initiation Logic RESET PB AND VERIFIES HV-F006 is CLOSED (if required, override and close lAW Att 2)

Steam Leak in HPCI Room:

Crew recognizes a steam line B1-A5 and ISLN INIT After actions for inadvertent break in the HPCI room by: status lights will be HPCI initiation are completion, ~ OHA B1-A5 "HPCI STEAM received when the leak OR at the discretion of the LINE DIFF PRESSURE HI" severity reaches 23%

Lead Examiner, ~ OHA A2-A5 "FIRE PROT (about 30 seconds)

TRIGGER ET-5 AND PANEL 10C671" PROVIDE Fire Computer ~ Fire Comp Pt FA015 "RM indication of point FA015 (Fire 4111 HPCI PUMP AND Computer point may be TURBINE ROOM" provided by Examiner or by ~ HPCI room temperature Fire Computer Simulation). trending up (Rm 4111)

~ Lowering Main Gen MWe

~ Offsite release rate trending up

~ HPCI Turbine Inlet Pressure on PI-R602.

~ ISLN INIT status lights InSight Items:

Crew announces steam leak in

HPCI Room Temp HPCI room on plant page.

hvtr4111

RCIC Room Temp hvtr4110 2013 NRC Scenario #3 Page 17 of 31 Rev.: 1

!E dispatched to HPCI Room,

Crew recognizes failure of HPCI The HV-F002 is THEN REPORT the room is to isolate by: powered from the filled with steam. =:> HV-F002 power failure 10A403 bus.

=:> F003 valve position

=:> HPCI room temperature trending up (Rm 4111)

PO attempts to close HV-F003 Immediate Operator using Control Room keylock Action lAW switch. AB.CONT-0002

Crew recognizes failure of RECORD time when HV-F003 to close by: switch for HV-F003 is in

=:> OHA B1-F3 "HPCI CLOSE AND OHA COMPONENT 0/PF" B 1-A5 is in alarm for 15

=:> OVLD/PWR FAIL light min ECG Classification.

=:> GRIDS D3513 "HPCI ST Time: - - -

LINE ISLN HV-F003 OPF"

=:> HPCI room temperature continuing to trending up (Rm 4111)

=:> Main Gen MWe continuing to trend down

=:> Offsite release rate continuing to trend up

!E dispatched to reclose

Crew dispatches RBEO and ARP for D3513 gives breaker 52-212053, Maintenance to breaker for breaker number.

THEN REPORT the breaker HV-F003 (52-212053) will not close.

!E dispatched to the HV-F003 valve, THEN REPORT the valve is bound and will not close.

2013 NRC Scenario #3 Page 18 of 31 Rev.: 1

CRS determines an SAE Classification is required lAW ECG Section:

~ RB3.L VALID isolation signal exists with an UNISOLABLE Break outside primary containment (after isolation from the Control Room has or should have been attempted) in ANY of the following systems: HPCI steam line (5 pts.)

~ CB3.L UNISOLABLE leakage outside primary containment (after isolation from the Control Room has or should have been attempted)

AND Direct downstream pathway to the environment exists. (3 pts.) OR

~ CB5.L UNISOLABLE primary system leakage outside primary containment (after isolation from the Control Room has or should have been attempted) as indicated by exceeding EITHER of the following: (3 pts.)

ANY EOP 103 Reactor Bldg room temp Table 1, Column 2 (Max Safe)

ANY Reactor Bldg rad level > 1000 times normal 2013 NRC Scenario #3 Page 19 of 31 Rev.: 1

STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

WHEN HPCI Room temperature EOP-1 03 Secondary Containment reaches 115 degrees, Control. THEN CRS implements

1. It is impossible to predict all EOP-103.

possible break points in a system and proceduralize all possible points of isolation. Therefore, for reasons of system isolation as directed by EOP-1 03, the operator does not need written guidance beyond EOP-103 direction to isolate faulted systems.

2. It is important to remember it takes 2 or more areas (as defined in the EOP) with max safe Rads or Temps or Levels AND a Primary system discharging into the Reactor Building to enter EOP-202 RPV Slowdown.

3. Verification of "discharging" can be by either of the following:

a. Visual verification of a leak or break in an area.

b. Rising temperatures and/or rising radiation levels in an area.

4. Post scram, if the main condenser and sufficient RPV feed sources are available, the Control Room Supervisor should consider depressurizing the reactor within the cooldown limits (to approximately 500-600 psig) to reduce the driving head of the leak. If EOP-202 implementation is anticipated, then the depressurization is allowed to exceed the cooldown rate.

CRS implements AB.CONT-004:

=:> Condition A

=:> Condition C IF dispatched to secure Rx

PO places FRVS in service lAW Bldg Ventilation, SO.GU-0001 Section 5.3.

THEN:

REFER to SO.GU-0001 Section 5.3

TRIGGER ET-6 to secure fans 2013 NRC Scenario #3 Page 20 of 31 Rev.: 1

STRATEGIES FOR SUCESSFUL

BEFORE HPCI Room TRANSIENT MITIGATION Reactor Scram Reports temperature reaches 250 Following a Reactor scram, the NCO degrees, should make an initial scram report THEN CRS directs reducing by announcing reactor status lAW recirc pumps to minimum speed HC.OP-AB.ZZ-0001.

and locking the Mode Switch in Crew personnel should hold all other non-essential communications until SHUTDOWN after the initial scram report is complete.

The Control Room Supervisor should silence alarms during the scram report and the SM/CRS is not required to make a statement

RO reduces recirc pumps to directing the NCO to check the minimum speed and locks the overhead alarms, since these actions Mode Switch in SHUTDOWN.

are already expected immediately following the scram.

During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff lAW HC.OPAB.ZZ-0001.

Before HPCI Room temperature exceeds 250 °F by Control Room indication, the Crew places the Mode Switch in SHUTDOWN.

Crew recognizes Scram RECORD time of Mode Condition and Reactor Power Switch to SHUTDOWN Above 4% EOP entry condition. OR RPV LVL 3 (whichever was first) for 15 min EGG Classification.

Time: - - - -

2013 NRC Scenario #3 Page 21 of 31 Rev.: 1

STRATEGIES FOR SUCESSFUL

RO performs scram actions lAW HPI USED:

TRANSIENT MITIGATION STARD Reactor Scram Reports AB.ZZ-0001 Att. 1.

Following a Reactor scram, the NCO HARD CARD D should make an initial scram report The Mode Switch will by announcing reactor status lAW not actuate A1/A2 RPS, HC.OP-AB.ZZ-0001. but the Arm & Depress Crew personnel should hold all other Pushbuttons will.

non-essential communications until after the initial scram report is ARI will not complete. automatically initiate, The Control Room Supervisor should but can be manually silence alarms during the scram initiated.

report and the SM/CRS is not required to make a statement directing the NCO to check the overhead alarms, since these actions are already expected immediately following the scram.

During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff lAW HC.OPAB.ZZ-0001.

Before Reactor Water Level RECORD the RPV level reaches L VL 1, the Crew at which RPS or ARI is manually actuates RPS and/or actuated.

ARI to shutdown the reactor. RPV Level: - - -

Crew recognizes RPV Level Below 12.5" EOP entry condition by:

=> OHA C5-A4 "RPV WATER LEVEL LO"

=> OHA A7-D5 "RPV LEVEL 3"

=> Various water level indicators

CRS implements EOP-1 01.

PO stabilizes and restores level lAW AB.ZZ-0001 Att. 14 as directed by CRS.

Crew recognizes lowering reactor pressure by:

=> OHA C8-B3 "NSSSS ISLN SIG - MN STM PRESSURE LO"

=> Various reactor pressure indications 2013 NRC Scenario #3 Page 22 of 31 Rev.: 1

!E reactor pressure lowers to 550 psig, THEN CRS enters AB.RPV-0005:

=> Retainment Override

STA monitors AB.RPV-0005 implementation and Retainment Override applicability.

CRS directs closing:

=> MSIVs

=> HV-F016

=> HV-F019

RO/PO close:

=> MSIVs

=> HV-F016

=> HV-F019

Crew recognizes rising temperature in the RCIC pump room by:

=> OHA B1-A1 "RCIC TURBINE TRIP"

=> OHA 81-82 "RCIC OUT OF SERVICE"

=> OHA D3-A2 "RCIC/RHR B AREA LEAK TEMP HI"

=> RCIC Logic B/D "ISLN INIT" lights

=> RCIC HV-F00?/8 closing

=> SPDS Room temp indication 2013 NRC Scenario #3 Page 23 of 31 Rev.: 1

HPCI Room temperature needs

WHEN HPCI AND RCIC room to be 275 degF before reactor temperatures exceed 250 pressure drops below 200 psig. degrees (Max Safe Op),

IF necessary, THEN CRS implements THEN manually raise HPCI EOP-202 to Emergency Room temperature using Depressurize.

InSight Item hvtr4111:

Raise to 270 degrees in 5 degree increments

Raise from 270 to 277 degrees in 1 degree increments (RCIC Room temp will reach 250 when HPCI room temp reaches 275)

RO/PO opens five SRVs lAW AB.ZZ-0001 Att. 13.

Crew actuates five SRVS RECORD time from within two minutes of RCIC RCIC reaching 250 room temperature exceeding degrees to SRV 250 degrees by Control Room actuation.

indication (SPDSICRIDS).

TIME: _ __

RECORD RPV pressure at which fifth SRV is opened.

PRESSURE: _ __

Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

~ OHA C8-F1 "SUPPR POOL TEMP HIGH"

~ Flashing 95 degree status light on 1OC650C

~ RM11 9AX833/834 alarm

~ Various Suppression Pool temperature indicators

CRS enters EOP-1 02.

CRS directs placing all available RHR pumps in Suppression Pool Cooling.

2013 NRC Scenario #3 Page 24 of 31 Rev.: 1

RO/PO place RHR in Supp Pool Cooling lAW AB.ZZ-0001 Att. 3.

RO/PO align SACS to support second RHR Hx lAW SO.EG-0001 Section 5.9.

Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when the reactor has been depressurized.

2013 NRC Scenario #3 Page 25 of 31 Rev.: 1

VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-1 01 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. HU-AA-1 081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-1 01-111-1 004 Operations Standards M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines

0. OP-AA-1 08-114 Post Transient Review P. OP-HC-1 08-115-1001 Operability Assessment and Equipment Control Program Q. OP-HC-108-106-1001 Equipment Operational Control R. HC.OP-SO.AE-0001 Feedwater System Operation S. HC.OP-SO.SF-0001 Reactor Manual Control T. HC.OP-SO.SF-0003 Rod Worth Minimizer Operation U. HC.OP-AB.ZZ-0001 Transient Plant Conditions V. HC.OP-AB.RPV-0005 Reactor Pressure W. HC.OP-AB.IC-0001 Control Rod X. HC.OP-AB.CONT-0001 Drywall Pressure Y. HC.OP-AB.CONT-0002 Primary Containment Z. HC.OP-AB.CONT-0004 Radioactive Gaseous Release AA. HC.OP-AB.ZZ-0172 Loss of 4.16 KV Bus 10A403 C Channel BB. HC.OP-AB.ZZ-000 Reactor Scram CC. HC.OP-EO.ZZ-0101 RPV Control DD. HC.OP-EO.ZZ-0102 Primary Containment Control EE. HC.OP-EO.ZZ-0103 Reactor Building Control FF. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization GG. HC.RE-AB.ZZ-0001 Insertion of Control Rods in Response to an ATWS HH. HC.OP-IO.ZZ-0006 Power Changes During Operation II. Strategies For Successful Transient Mitigation 2013 NRC Scenario #3 Page 26 of 31 Rev.: 1

VII.ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #3, Rev. 0 1.

Before HPCI Room temperature exceeds 250 °F by Control Room indication, the Crew places the Mode Switch in SHUTDOWN.

K/A 295032 High Secondary Containment Area Temperature EK3 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK3.02 Reactor SCRAM RO 3.6 SRO 3.8 EA2 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EA2.01 Area temperature RO 3.8 SRO 3.8 The steam leak from HPCI cannot be isolated. Since isolation cannot be accomplished, the only remaining course of action is to remove the energy input to the RCS by scramming the reactor. 250aF is the Max Safe Op temperature for the HPCI Room (4111 ), and EOP-103 directs reducing recirc to minimum and initiating a manual scram. In this scenario, the rate of rise in room temperature provides ample time to implement the guidance in EOP-103. Reducing recirc to minimum is not critical to shutting down the reactor, and is not included as part of this critical task. The first action AB.ZZ-0001 directs for initiating a manual scram is to LOCK the Mode Switch in SHUTDOWN. For the purposes of shutting down the reactor, LOCKING the Mode Switch in SHUTDOWN is not required, only initiating a scram is critical.

2.

Crew actuates five SRVS within two minutes of RCIC room temperature exceeding 250 degrees by Control Room indication (SPDSICRIDS).

K/A 295032 High Secondary Containment Area Temperature EK3 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK3.01 Emergency/normal depressurization RO 3.5 SRO 3.8 EA2 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EA2.01 Area temperature RO 3.8 SRO 3.8 The steam leak in the HPCI room is now affecting a second area. The reactor must be depressurized to place it in it's lowest energy state due to the potential for multiple inoperable safety systems, to reduce the driving head for the leak, and to reject decay heat to the suppression pool rather than the Reactor Building. The term "Crew actuates five SRVs" takes into account the F013D failure, which is already inserted. Two minutes is deemed adequate time to recognize the condition and implement EOP-202 and AB.ZZ-0001 Att. 13.

3.

2013 NRC Scenario #3 Page 27 of 31 Rev.: 1

2013 NRC Scenario #3, Rev. 0 HOPE CREEK ESG- PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE EVENT EVENT

- - - Loss Of Offsite Power/SBO Internal Flooding y LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT KEY SYSTEMS

_...:...Y_ HPCI SRVs

_...:...Y_ RCIC - - - Condensate/Feedwater

--- B/D EDG ___ ssw

_ _ _ AlB RHR Pump

- - - RPS

_ _ _ AlB SACS Loop 1E4.16KVBus 1E 480 VAC Bus 120VAC 481 Inverter

_ _ _ 1E 125VDC

- - - Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE OPERATOR ACTION

_ _ _ Manual Depressurization of the RPV w/ no HP Injection Available

_ _ _ Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi OW Press. Signal

_ _ _ Control RPV Water Level w/ HP Injection during ATWS Sequence

_ _ _ Align Portable Power Supply to Battery Chargers

- - - Venting of Primary Containment

_ _ _ Restore Switchgear Cooling

- - - Restart Condensate

_ _ _ Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG.

2013 NRC Scenario #3 Page 28 of 31 Rev.: 1

VIII. TURNOVER SHEET:

ONLINE RISK: GREEN WORK WEEK CHANNEL: C PROTECTED EQUIPMENT None REACTIVITY I Plant Status 75% Power ESF/SAFETY SYSTEMS None COOLING WATER None BOP DK111 for freon leak CP161 for bearing oil leak ELECTRICAL None ADVERSE CONDITION MONITORING None 2013 NRC Scenario #3 Page 29 of 31 Rev.: 1

IX. SIMULATOR ESG REVIEWNALIDATION CHECKLIST EXAMINATION SCENARIO GUIDE (ESG) REVIEWNALIDATION Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG: Scenario 3 SELF-CHECK

- - - 1. Total malfunctions inserted: 4-8

- - - 2. Malfunctions that occur after EOP entry: 1-4

- - - 3. Abnormal Events: 1-2

___ 4. Major Transients: 1-2

___ 5. EOPs used beyond primary scram response EOP: 1-3

___ 6. EOP Contingency Procedures used: 0-3

___ 7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

- - - 8. EOP run time: 40-70% of scenario run time

- - - 9. Crew Critical Tasks: 2-5

___ 10. Technical Specifications are exercised during the test: ~1 Comments:

2013 NRC Scenario #3 Page 30 of 31 Rev.: 1

EXAMINATION SCENARIO GUIDE (ESG) REVIEW/VALIDATION (con't)

Crew Validation Rev: 01 Date Validated: - - - -

Validation Comments Disposition

~~~

Crew Validation Rev: Date Validated: - - - -

Validation Comments Disposition

~~~

Crew Validation Rev: Date Validated: - - - -

Validation Comments Disposition 2013 NRC Scenario #3 Page 31 of 31 Rev.: 1

v t e Letter Sequence Draft Other
TAC:U01872, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML13267A380, ML13267A389, ML13267A415, ML13267A422, ML14010A064
MONTHYEAR2013-08-19 [Table View]

ML13227A127

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