ML091740105

From kanterella
Revision as of 03:09, 26 August 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Turkey Point, Initial Exam 2009-301 Final Simulator/In-Plant JPMs
ML091740105
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/23/2009
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
Download: ML091740105 (143)
v • d • e


Text

Appendix C Facility:

Task Title: Job Performance Measure Worksheet Turkey Point Task No: Align Safety Injection For Cold Leg Recirc JPM No: KIA

Reference:

006 A4.07 RO 4.4 SRO 4.4 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Form ES-C-1 01200021500 JPMA Simulated Performance X Actual Performance

Classroom

Simulator X --=-=-------

Plant -------------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • A LOCA is in progress on Unit 3
  • RHR is aligned to take suction from containment sump
  • 3A HHSI pump is operating taking suction from the Unit 3 RWST
  • 38 HHSI pump bearing has failed and has been placed in PTL.
  • 4A and 48 HHSI pumps suction aligned to the Unit 4 RWST Task Standard:
  • Core injection flow has been re-established using 3-EOP-ES-1.3 Transfer to Cold Leg Recirculation Required Materials:
  • 3-EOP-ES-1.3 Transfer to Cold Leg Recirculation General

References:

  • 3-EOP-ES-1.3 Transfer to Cold Leg Recirculation NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 10 Form ES-C-1 Initiating Cue:
  • You have been directed to transfer to Cold Leg Recirculation using 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation, starting at step 19. Time Critical Task: Yes Validation Time: 10 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 10 Form ES-C-1 I SIMULATOR SETUP Reset to IC # 22 Load Lesson
  • Open lesson, JPM A
  • Execute lesson
  • Trigger "Parent" step
  • Trigger "38 HHSI PUMP TRIP" OR go to Schematic, Safety System, Safety Injection Proc, Select 38 pump icon. Select SI pump 3 8 under table "0". Select TVMHP838 and set value to 1.0 and INSERT
  • Place 38 HHSI pump control switch in the "Stop" and Pull-To-Lock position Ensure Simulator Operator Checklist is complete
  • PLACE SIMULATOR IN RUN
  • ACKNOWLEDGE ALARMS
  • FREEZE SIMULATOR.
  • Provide a copy of 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation marked up as complete through step 18. On step 18, circle and draw a line to the RNO column.
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted. NUREG 1021 Rev 9 Appendix C .

Appendix C Page 4 of 10 Form ES-C-1 Denote critical steps with a check mark(T} Start Time ----STEP 1 Obtain required materials.

SAT --UNSAT --Standard:

Examinee obtains a copy of the required procedure.

Cue Provide the Examinee with a copy 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation marked up as complete through step 18. Comment Isolate RHR Cold Leg Injection.

STEP 2 (3-EOP-ES-1.3 Step 19) SAT --if UNSAT --Examinee places MOV-3-744A handswitch in the CLOSED position Standard:

AND Examinee places MOV-3-744B handswitch in the CLOSED position Comment EXAMINER Handswitches are located on VPB NOTE:

1021 Rev 9 Appendix C I Appendix C Page 5 of 10 Form ES-C-1 I Procedure Note: Note Steps 20 through 24 should be reviewed prior to performance to ensure a timely transition to cold leg recirculation.

STEP 3 CHECK RWST LEVEL -LESS THAN 60,000 GAL. SAT --(3-EOP-ES-1.3 Step 20) UNSAT --Standard:

Examinee observes L T 6583A RWST LEVEL less than 60,000 GAL. Comment Procedure Caution: Injection flow to the core shall NOT be interrupted for more than 2 Note minutes during performance of Steps 21 through 24. All SI pumps aligned to Unit 3 RWST are required to be placed in PULL-TO-LOCK to prevent pump auto start while its suction source is isolated.

STEP 4 PLACE CONTAINMENT SPRAY PUMPS IN PULL-TO-LOCK SAT --if (3-EOP-ES-1.3 Step 21 ) UNSAT --Standard:

Examinee places the 3A Containment Spray Pump handswitch in PULL-TO-LOCK Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 10 Form ES-C-1 STEP 5 PLACE BOTH UNIT 3 HIGH HEAD SI PUMPS IN PULL-TO-LOCK SAT --if (3-EOP-ES-1.3 Step 21) UNSAT --Standard:

Examinee places the 3A High Head SI Pump handswitch in PULL-TO-LOCK Comment EXAMINER The 3B High Head SI Pump handswitch was previously placed in NOTE: PULL-TO-LOCK during the setup. EXAMINER Ensure failure of 3A HHSI pump breaker "AS IS" is inserted after the NOTE: Control switch has been placed in PTL position.

Procedure Caution NOTE: Either MOV-3-864A or MOV-3-864B must be closed prior to continuing.

STEP 6 CLOSE RWST OUTLET VALVES SAT --if (3-EOP-ES-1.3 Step 22) UNSAT --Examinee places MOV-3-864A handswitch in the CLOSED position Standard:

AND Examinee places MOV-3-864B handswitch in the CLOSED position Comment EXAMINER The examinee should have both valves stroking closed at the same NOTE: time. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 10 Form ES-C-1 I STEP 7 Align RHR Pump Discharge To High-Head SI Pump Suction. SAT --T (3-EOP-ES-1.3 Step 23) UNSAT --1) Examinee verifies MOV-3-864A and MOV-3-864B CLOSED by observing the position indicating lights above the valve handswitches.

Standard:

2) Examinee places MOV-3-863A handswitch in the OPEN position AND 3) Examinee places MOV-3-864B handswitch in the OPEN position Comment EXAMINER NOTE: Only Standards 2 & 3 are critical to this element. EXAMINER NOTE: MOV-3-864A and MOV-3-864B were closed in the previous step. EXAMINER The examinee should have both 863 valves stroking open at the same NOTE: time. NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 10 Form ES-C-1 Procedure Caution: NOTE: If the operating High-Head SI Pump trips, the second High-Head SI Pump is required to be manually started. STEP 8 START ONE HHSI PUMP Aligned to Unit 3 SAT --(3-EOP-ES-1.3 Step 24) UNSAT --Standard:

Examinee attempts to start the 3A HHSI pump by placing the handswitch in START. Comment EXAMINER The 3A HHSI pump will NOT start due to an inserted malfunction.

NOTE: The 3B HHSI pump bearing has failed and was previously placed in PTL. STEP 9 Re-establish core flow using RHR SAT --if (3-EOP-ES-1.3 Step 24 RNO Step a 1) UNSAT --Examinee places MOV-3-744A handswitch in the OPEN position Standard:

AND Examinee places MOV-3-744B handswitch in the OPEN position Comment EXAMINER Annunciator H 6/2 RHR HX HI/LO FLOW will clear when flow is established.

NOTE: Terminating The task is complete when the Examinee establishes core flow by Cue: opening 3-MOV-744A and 7448 STOP Stop Time ___ _ NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 10 Form ES-C-1 I Verification of Completion Job Performance Measure No. JPM A Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _______________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • A LOCA is in progress on Unit 3
  • RHR is aligned to take suction from containment sump
  • 3AHHSI pump is operating taking suction from the Unit 3 RWST
  • 38 HHSI pump bearing has failed and has been placed in PTL.
  • 4A and 48 HHSI pumps suction aligned to the Unit 4 RWST INITIA TING CUE: You have been directed to transfer to Cold Leg Recirculation using 3-EOP-ES-1.3, Transfer to Cold Leg Recirculation, starting at step 19. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title: Job Performance Measure Worksheet

_T..:...;u::..:r.:,:.ke;::.Yr.....:.....P.::,;oi:.:...:n..:...t

______ Task No: Restore Accumulator Pressure JPM No: KJ A

Reference:

006 A 1.14 RO 4.5 SRO 4.7 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 1064005100 JPM 8 Method of testing: _____________________________

_ Simulated Performance X Actual Performance

Classroom

Simulator

Plant X ----=--:------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3(4) is in MODE 1
  • The 3(4)8 Accumulator pressure is greater than 665 psig.
  • Containment is closed with no personnel in containment.

Task Standard:

  • The 3(4)8 Accumulator pressure has been restored to between 625 and 665 psig Required Materials:

References:

  • You have been directed to vent the 3(4) B accumulator to the normal operating band (625 to 665 psig) using 3(4)-OP-064 Safety Injection Accumulators, section 7.5 and clear Annunciator H 214. The applicable prerequisites as listed in 3(4)-OP-064 Safety Injection Accumulators section 4.0 have been satisfied.

Another operator has addressed the alarm response for Annunciator H 2/4, ACCUM B HI/LO PRESS. Time Critical Task: No Validation Time: 15 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of9 Form ES-C-1 I SIMULATOR SETUP NlA NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 9 Form ES-C-1 Denote critical steps with a check mark(T) Start Time STEP 1 Obtain a copy of 3(4)-OP-064 Safety Injection Accumulators SAT --UNSAT --Standard:

Copy of 3(4)-OP-064 is obtained.

Cue Provide a marked up copy of 3(4)-OP-064 Safety Injection Accumulators, section 7.5. Comment STEP 2 Verify at least one Normal Containment Cooler is in service. SAT --(3(4)-OP-064 Step 7.5.1.2) UNSAT --Examinee verifies at least one normal containment cooler is in service Standard:

by observing the red indicating lights are ON for each running Normal Containment Cooler damper and fan on VP B. Comment STEP 3 Verify the ALL accumulator vent valves are closed. SAT --(3(4)-OP-064 Step 7.5.2.1) UNSAT --Examinee verifies ALL accumulator vent valves are closed by Standard:

checking the green closed indicating lights above the control switches (CV-3(4)-853A, B, & C) on VP B are ON. Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of9 Form ES-C-1 I Procedure Caution Technical Specifications require accumulator pressures to be maintained in the range of 600 to 675 psig. NOTE: During outages and with personnel inside containment, care must be taken when venting accumulators.

Depending on containment integrity, containment purge and normal containment coolers in service, nitrogen diffusion may occur slowly. Only one vent valve may be opened at a time if in Modes 1, 2, or 3 with RCS pressure greater than 1000 psig STEP 4 Open CV-3(4)-8538, accumulator vent valve. SAT --(3(4)-OP-064 Step 7.5.2.2.b)

T UNSAT --Standard:

Examinee places the handswitch for CV-3(4)-8538 to OPEN. CUES: When Examinee simulates placing CV-3(4)-8538 handswitch to OPEN provide the following cue, "CV-3(4)-8538 red light is ON, green light is OFF." Comment STEP 5 Slowly vent the 3(4)8 accumulator by throttling opening Accum Vent, SAT HIC-3(4)-936.

--T UNSAT (3(4)-OP-064 Step 7.5.2.4) --Standard:

Examinee vents the 48 Accumulator by rotating the potentiometer for HIC-936 clockwise slowly. CUES: When Examinee simulates rotating the potentiometer for HIC-3(4)-936 clockwise slowly provide the following cue, "Pressure indicated on PI-3(4)-925 and 927 are decreasing slowly." Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of9 Form ES-C-1 STEP 6 WHEN accumulator pressure decreases to zero (less than 10 psig) SAT OR to pressure directed by procedure, THEN close Accum Vent, HIC---T 3(4)-936.

UNSAT --(3(4)-OP-064 Step 7.5.2.5) Examinee closes the Accumulator Vent by rotating HIC-3(4)-936 fully counterclockwise.

AND Standard:

3(4) 8 Accumulator pressure is established from 625 to 665 psig AND Annunciator window H 2/4 is OFF CUES: Provide the following cue, Time compression is being used." "Pressure indicated on PI-3(4)-925 and 927 are now 665 psig and decreasing." "Annunciator window H 214 is OFF." CUES: When Examinee simulates rotating the potentiometer for HIC-3(4)-936 counter-clockwise slowly provide the following cue, "Accum Vent, HIC-3(4)-936 output is 0, pressure on Pressure indicated on PI-3(4)-925 and 927 is stable." Comment EXAMINER The examinee was directed to establish the 3(4)8 Accumulator NOTE: pressure from*625 to 665 psig in the initiating cue. STEP 7 Close CV-3(4)-8538, accumulator vent valve. SAT --(3(4)-OP-064 Step 7.5.2.6) T UNSAT --Standard:

Examinee places the handswitch for CV-3(4)-8538 to CLOSE. CUES: When Examinee simulates placing CV-3(4)-8538 handswitch to CLOSE provide the following cue, "CV-3(4)-8538 red light is OFF, green light is ON." Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 9 Form ES-C-1 I Terminating The task is complete when the Examinee simulates closing CV-Cue: 3(4)-8538.

STOP Stop Time ___ _ NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 9 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM B Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________________________

_ NUREG 1021 Rev 9 Appendix C JPM" BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3(4) is in MODE 1
  • The 3(4)8 Accumulator pressure is greater than 665 psig.
  • Containment is closed with no personnel in containment.

INITIA TING CUE:

  • You have been directed to vent the 3(4) 8 accumulator to the normal operating band (625 to 665 psig) using 3(4) -OP-064 Safety Injection Accumulators, section 7.5 and clear Annunciator H 214. The applicable prerequisites as listed in 3(4) 4-0P-064 Safety Injection Accumulators section 4.0 have been satisfied.

Another operator has addressed the alarm response for Annunciator H 2/4, ACCUM 8 HI/LO PRESS. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title:-Job Performance Measure Worksheet

_T-,-u.=.;r..;..:kc:...eY"--,,-P..::,.o,,,-,inc.:....t

______ Task No: Restore Accumulator Pressure JPM No: KIA

Reference:

006 A1.13 RO 3.5 SRO 3.7 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 1064005100 JPM8 Method of testing: _____________________________

_ Simulated Performance

________ Actual Performance

__________

_ Classroom Simulator X Plant ---------------------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3 is in MODE 1
  • Containment is closed with no personnel in containment.

Task Standard:

  • The 38 Accumulator pressure has been restored to between 625 and 665 psig Required Materials:

References:

  • You have been directed to vent the 38 accumulator to the normal operating band (625 to 665 psig) using 3-0P-064 Safety Injection Accumulators, section 7.5 and clear Annunciator H 2/3. The applicable prerequisites as listed in 3-0P-064 Safety Injection Accumulators section 3.0 have been satisfied.

Another operator has addressed the alarm response for Annunciator H 2/3, ACCUM 8 HI/LO PRESS. Time Critical Task: No Validation Time: 15 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of8 Form ES-C-1 I SIMULATOR SETUP Reset to IC # 1 Ensure Simulator Operator Checklist is complete

  • PLACE SIMULATOR IN RUN
  • Open Lesson JPM B
  • Execute lesson
  • Trigger "Parenf' step
  • Trigger PCV-846 leakage
  • Open CV-3-855 & CV-3-853B
  • Close CV-3-853B

& CV-3-855

  • Delete PCV-846 leakage from the summary.
  • Verify the accumulator level is still in the. green band.
  • ACKNOWLEDGE ALARMS
  • FREEZE SIMULATOR.
  • Provide a copy of 3-0P-064 Safety Injection Accumulators, section 7.5
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted. NUREG 1021 Rev 9 Appendix C AppendixC Page 4 of8 Form ES-C-1 Denote critical steps with a check mark(T) Start Time STEP 1 Obtain a copy of 3-0P-064 Safety Injection Accumulators SAT --UNSAT --Standard:

Copy of 3-0P-064 is obtained.

Cue Provide a marked up copy of 3-0P-064 Safety Injection Accumulators, section 7.5. Comment STEP 2 Verify at least one normal containment cooler is in service. SAT --(3-0P-064 Step 7.5.1.2) UNSAT --Standard:

Examinee verifies at least one normal containment cooler is in service by observing the red indicating lights on VP B are ON. Comment STEP 3 Verify the ALL accumulator vent valves are closed. SAT --(3-0P-064 Step 7.5.2.1) UNSAT --Examinee verifies ALL accumulator vent valves are closed by Standard:

checking the green closed indicating lights above the control switches (CV-3-853A, B, & C) on VP B are ON. Comment NUREG 1021 Rev 9 Appendix C I AppendixC Page 5 of8 Form ES-C-1 I Procedure Caution Technical Specifications require accumulator pressures to be maintained in the range of 600 to 675 psig. NOTE: During outages and with personnel inside containment, care must be taken when venting accumulators.

Depending on containment integrity, containment purge and normal containment coolers in service, nitrogen diffusion may occur slowly. Only one vent valve may be opened at a time if in Modes 1, 2, or 3 with RCS pressure greater than 1000 psig STEP 4 Open CV-3-8538, accumulator vent valve. SAT --(3-0P-064 Step 7.5.2.2.b)

T UNSAT --Standard:

Examinee places the handswitch for CV-3-8538 to OPEN. , Comment STEP 5 Slowly vent the 38 accumulator by throttling opening Accum Vent, SAT HIC-3-936.

--T UNSAT (3-0P-064 Step 7.5.2.4) --Standard:

Examinee vents the 38 Accumulator by rotating the potentiometer for HIC-936 clockwise slowly. Comment NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 8 Form ES-C-1 STEP 6 WHEN accumulator pressure decreases to zero (less than 10 psig) SAT OR to pressure directed by procedure, THEN close Accum Vent,

--T 3-936. UNSAT --(3-0P-064 Step 7.5.2.5) Examinee closes the Accumulator Vent by rotating HIC-3-936 fully counterclockwise.

AND Standard:

38 Accumulator pressure is established from 625 to 665 psig AND Annunciator window H 2/3 is OFF Comment EXAMINER The examinee was directed to establish the 38 Accumulator pressure NOTE: from 625 to 665 psig in the initiating cue. STEP 7 Close CV-3-8538, 38 accumulator vent valve. SAT --(3-0P-064 Step 7.5.2.6) T UNSAT --Standard:

Examinee places the handswitch for CV-3-8538 to CLOSE. Comment Terminating Cue: The task is complete when the Examinee closes CV-853B. STOP Stop Time ___ _ NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 8 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM B Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _______________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3 is in MODE 1
  • Containment is closed with no personnel in containment.

INITIATING CUE:

  • You have been directed to vent the 38 accumulator to the normal operating band (625 to 665 psig) using 3-0P-064 Safety Injection Accumulators, section 7.5 and clear Annunciator H 2/3. The applicable prerequisites as listed in 3-0P-064 Safety Injection Accumulators section 3.0 have been satisfied.

Another operator has addressed the alarm response for Annunciator H 2/3, ACCUM 8 HI/LO PRESS. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title: Job Performance Measure Worksheet

______ Task No: Place RHR In Service JPM No:

KIA

Reference:

005 A4.01 RO 3.6 SRO 3.4 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 01050012100 JPMC Method of testing: ______________________________

_ Simulated Performance X Actual Performance

Classroom

Simulator X ----=--=------

Plant -------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • U-3 Mode 4
  • RCS Temperature is 345 deg
  • RCS Pressure is 400 psig
  • RCP Band C are in service
  • No equipment is OOS
  • 3-OP-050, Residual Heat Removal System is in progress, all steps up to and including step 5.2.2.20 have been complete.

Task Standard:

  • RHR has been placed in service and control of RCS Temperature has been demonstrated Required Materials:

References:

  • You have been directed to place RHR in service and initiate a cooldown using 3-0P-050, Residual Heat Removal System starting at step 5.2.2.21.
  • The Unit Supervisor has directed you to initiate RHR using the 3A RHR pump.
  • A Prestart check has been performed on the 3A RHR pump.
  • All pre-job briefings have already been performed.

Time Critical Task: No Validation Time: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I AppendixC Page 3 of 9 SIMULATOR SETUP Reset to IC # 14 Complete section 5.1 and 5.2 up through step 5.2.2.20 of 3-0P-050 OR Load IC 191 from the memory stick Ensure Simulator Operator Checklist is complete Place the following cold shutdown placards on VPB

  • 3-MOV-865 A, B, & C to yellow
  • 3-MOV-862 to white
  • 3-MOV-750 and 751 to white
  • 3-MOV-843 A and B to yellow
  • 3-MOV-869 to yellow
  • 3-MOV-866 A and B to yellow
  • PLACE SIMULATOR IN RUN
  • ACKNOWLEDGE ALARMS
  • LET STABILIZE AND FREEZE SIMULATOR
  • Saveas a temporary IC, if repeat runs of JPM will be desired. Form ES-C-1 I
  • PLACE SIMULATOR IN RUN, prior to student entering the simulator.
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of9 Form ES-C-1 Denote critical steps with a check mark(T) Start Time ----STEP 1 Obtain required materials.

SAT --UNSAT --Standard:

Examinee obtains a copy of the required procedure.

Cue Provide the Examinee with a copy of 3-0P-050, Residual Heat Removal System marked up through step 5.2.2.20.

Comment Procedure Caution: Flow through the RHR loop needs to be initiated slowly to avoid thermal shock. A warm up period at low flow is required before full flow is initiated through the loop. The Pump Outlet Temperatures should be approximately RCS temp prior to starting an RHR Pump. NOTE: Starting an RHR Pump with RHR boron concentration less than RCS boron concentration may cause a small increase in source range counts. Source Range channels need to be closely monitored during RHR Pump start and flow setting for indication of an uncontrolled or unexplained increase in source range counts and 3-0NOP-046.1, EMERGENCY BORATION, implemented, if necessary.

STEP 2 Start the 3A RHR Pump. SAT --T (3-0P-050 step 5.2.2.21.a)

UNSAT --. Standard:

Examinee places the handswitch for the 3A RHR Pump to START Comment EXAMINER NOTE: The Unit Supervisor directed the start of the A RHR pump. NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 9 Form ES-C-1 I STEP 3 Open, RHR Hx By-pass Flow Valve, FCV-3-605 to 5 percent demand SAT --(3-0P-050 step 5.2.2.22)

UNSAT --Standard:

The examinee places the controller for the RHR Hx By-pass Flow Valve, FCV-3-605 to between 5 to 10 percent OPEN demand Comment STEP 4 Monitor the RHR Temperature Recorder, TR-3-604 OR local indication SAT until the RHR temperature stabilizes.

--(3-0P-050 step 5.2.2.23)

UNSAT --Examinee observes the RHR Temperature Recorder, TR-3-604 OR Standard:

directs local indication to be monitored until RHR temperature stabilizes.

Cue If asked, provide the following cue as SNPO, "RHR temperature has stabilized." Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 9 Form ES-C-1 Procedure Note: NOTE: The RHR HI/LO FLOW alarm, H 6/2, should clear as RHR flow increases to greater than 3000 gpm. STEP 5 Adjust RHR Hx Bypass Flow Valve, FCV-3-605, to maintain between SAT 3500 and 3750 gpm RHR flow AND clear RHR HI/LO HX FLOW --T annunciator, H 6/2. UNSAT --(3-0P-050 step 5.2.2.24)

Examinee adjusts the HIC-3-605, controller for RHR Hx Bypass Flow Valve, FCV-3-605 to achieve the following:

Standard:

  • RHR flow between 3500 and 3750 gpm AND

UNSAT --Standard:

Examinee places 3-HIC-605, controller for RHR Hx Bypass Flow FC-3-605 to AUTO Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 9 Form ES-C-1 STEP 7 Throttle open RHR Hx Outlet Flow Valve, HCV-3-758, to commence SAT RCS cooldown.

--T UNSAT (3-0P-050 step 5.2.2.26)

--Examinee adjusts HIC-3-758 to achieve a throttled condition for RHR Hx Outlet Flow Valve, HCV-3-758 Standard:

AND Examinee commences RCS cooldown.

When the Examinee commences an RCS cooldown, provide the Cue following cue, "Another operator will complete the remaining steps of this procedure." Comment EXAMINER NOTE: HIC-3-758 is a reverse acting controller.

Terminating The task is complete when the Examinee commences an RCS Cue: cooldown.

STOP Stop Time ___ _ NUREG 1021 Rev 9 Appendix C AppendixC Page 8 of 9 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM C Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________________________

__ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • U-3 is in Mode 4
  • RCS Temperature is 345 deg
  • RCS Pressure is 400 psig
  • RCP 8 and C are in service
  • No equipment is OOS
  • 3-0P-050, Residual Heat Removal System is in progress, all steps up to and including step 5.2.2.20 have been complete.

INlTtA TING CUE:

  • You have been directed to place RHR in service and initiate a cooldown using 3-0P-050, Residual Heat Removal System starting at step 5.2.2.21.
  • The Unit Supervisor has directed you to initiate RHR using the 3A RHRpump.
  • A Prestart check has been performed on the 3A RHR pump.
  • All pre-job briefings have already been performed.

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C

TPwa* t-. Procedure No< Procedure Title: Page: 16 Approval Date: 3-0P-050 Residual Heat Removal System 7/29/07 5.2 Placing RHR in Operation for Cooldown INITIALS CK'D VERIF Date/Time Started: \0 f) 4'1 . /C KU.FI ON . . E!evatedradiation levels may be expected In the Auxiliary Sullding when performing this procedure.

RP should be notified to perform required surveys of affected areas.

I To minimize PZR level increase letdown ftowpath in service, only one I I charging pump should be operated until Substep 5.2.2,14.

I L _______________________

I 5.2.1 Initial Conditions

1. All applicable prerequisites listed in Section 3,0 are satisfied.

2, The ReS pressure is less than 450 psig. OR if auxiliary spray is in service, I less than 200 psig. 3. The ReS temperature is less than 350"F. 4, Subsection 5.1, Preparation for Placing RHR in Operatioi'!

for Cooldown is complete.

5. IF shutting down for a Refueling Outage, AND desired at this time, THEN perform 3-0SP-050.8; RHR MOVs 750, 862 AND 863 INTERLOCK TEST. (N/A if not desired at this time or not a Refueling Outage.) a. Document on QA Record Page whether the surveillance procedure was performed.

Procedure N(t: 3-0P-050 fNliIALS CK'D VERIF PrOl..'OOure Title: Residual Heat Removal System Page: 17 Approval Date: 9/8/06 5.2.2 Procedure Steps I I

  • 1. Close the foHowing valves: a. RHR Suction From RWST. MOV-3-862A
b. RHR Suction From RWST. MOV 862B 2. VerifY the following valves indicate closed on the Sl Valve Status Panel: a. Alt RHR. MOV
b. Alt RHR. MOV 863B 3. Open RHR Letdown to CVCS Valve, HCV-3-142, to equalize RHR and letdown pressure.

.., I Low Pressure Letdown Controller, is required to be maintained in MANUAL I until a RHR pump has been started. I I

  • The following step will essentially close PCV-3-145.

Subsequent steps to open I I MOV-3-750and MOV-3-751 need to be completed in a timely manner to minimize the I resulting pressurizer level increase.

L _______________________

J 4. Adjust Low Pressure Letdown Controller, PCV-3-i45 to match PI-3-145 to the RCSpressure.

1 0. I I MOV-3-750 must be fully open prior to . panfng MOV-3-7ot to avoid any trapped gases

  • I between MOVs from entering RHR pumps andlor heat exchangers.

I ...... _ .. _-----------_

.. _-.... _-----5. Open the following valves: a. Loop 3C RHR Pump Suction Stop Valve.

b. Loop 3C RHR Pump Suction Stop Valve, MOV-3-751
6. Adjust Low Pressure Letdown Controller, PCV-3-145, as required to control I pressurizer level. 7. Chemistry to sample both RHR loops for boron concentration. (N/A if ps have been sampled in the previous 14 days with no intervening evolutions to reduce RHR loop boron concentration.)

Procedure No,: 3-0P-050 INITiALS CK'D VERIF Procedure Title: 5.2.2 (Cont'd) Page: 18 Approval Date: Residual Heat Removal System 9/8/06 ,.-----------

--_ ...... -..... -----..., I I I HCV-3-758 has a mechanical'stop that prevents the valve from opening more than I l

____________________

J W97:JJC/clwJlfllcis

8. Perform fail safe test ofHCV 758 as follows: a. b. c. d. e. f. Observe position of valve based on valve stem position indicator.

Unlock and open HCV-3-758 Air SuppJy Isolation Valve, 40-1019. From the Control Room, close RHR Hx Outlet Flow Valve, HCV-3-758.

Close HCV-3-758 Air Supply Isolation Valve. 40-1019. Bleed off air pressure at petcock located on regulator supplying air to the valve positioner located on the top ofthe valve actuator.

Once air pressure has been bled off, verifY valve returns to the open I position observed in Substep 5.2.2.8.a.

0) IF valve does NOT open, THEN immediately notifY the Shift Manager AND 1ST Coordinator for evaluation.
g. ,Close regulator petcock. h. Open HCV-3-758 Air Supply Isolation Valve. 40-1019. 9.

OPEN and BACKSEAT the following valves: a. RHR Hx B By-Pass Hdr Isolation, 3-757C b. RHR Hx A By-Pass Hdr Isolation, 3-757D 10. Close RHR Hx: Outlet Flow valve, HCV 758. 11. Close RHR fIx Bypass Flow valve, FCV 605.

Procedure No.: Procedure Title: 19 Approval Date: 3-0P-050 Residual Heat Removal System 918/06 INITiALS CK'D VERIF 5.2.2 !Cont'd) ----12. Close LID From RXH Iso! Valve. eV-3-204.

13; Verify the following valves are open: a. 45 GPM LID Isolation Valve, CV-3-200A

b. 60 GPM LID Isolation Valve, ev 200B c. 60 GPM LID Isolation Valve, CV-3-200C

--.. '(Y"AAVt ION S 7

  • Letdown pressure should be monitored closely when adjusting Low Pressure Letdown Controller, PCV-3-145.

Pressure shall not exceed 600pslg as indicated on PI..3-145.

  • Letdown flow shall be limited to 120 gpm to prevent channeling of demineralizer resin. 14. Adjust Low Pressure Letdown Controller, PCV 145, as necessary to obtain adequate letdown flow to warm RHR system piping. 15. Using 3-0P-047, cves -CHARGIN.G AND LETDOWN, start additional charging pumps as required to match the increased letdown flow. . 16. Verify RHR loop boron concentration as follows: a. IF the RHR loops have been sampled in the previous 14 days with no Wervening evolutions to reduce RHR loop boron concentration, THEN verifY the sample boron concentration is equal to or greater than the current RCS boron concentration.
b. IF the RHR loops have NOT been sampied in the previous 14 days, THEN perform the following:

(1) (2) (3) Obtain RHR boron concentration results from Chemistry.

IF RHR loop boron concentration is less than the minimum required cold shutdown boron concentration.

THEN continue letting down to eves until RHR System concentration is greater than the minimum required cold shutdown boron concentration before continuing this procedure.

IF Unit 3 is in an action statement which prohibits positive reactivity changes, THEN continue letting down to evcs until RHR System boron concentration is within 20 ppm of the RCS before continuing this procedure. .

Procedure No.: 3-0P-050 INITIALS CK'D VER!F Procedure Title: 5.2.2 (Cont'd) Page: 20 Approval Date: Residual Heat Removal System 9/8/06 I The RHR HIILO HX FLOW alarm, H actuate when either MOV-3-744A or B is I I opened. I L ________ ____________ 17. Open the following valves AND verifY RHR HIILO HX FLOW alarm, H 6/2, actuates:

a. RHR Disch to Cold Leg 1501,
b. RHR Disch to Cold Leg Isol. MOV-3-744B
c. Annunciator H 6/2 actuated.

c A"'Uit ION A minimum of 200 psig across th:T:cp #1 seal needs to be maintained for continued RCP operation.

18. IF RCPs running. THEN verifY that the RCS pressure is between 325 and 400 p5lg. 19. Obtain the Assistant Operations Manager desired temperature for the RCS cool down. a. Desired RCS Temperature, __ 2_o_D .........

__ oF I Following an RHR pump start and flow adjustments, adjustments to I I PCV-3-145 will be necessary to compensate for RHR pump head changes and to maintain I the desired letdown pressure and flow. . I I -------------------------

20. Adjust Low Pressure Letdown Controller, to reduce letdown flow to less than 80 gpm.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

Turkey Point Task No: 01200053500 Manually Initiate Containment Task Title: Spray JPM No: JPM D KIA

Reference:

026 A4.01 RO 4.5 SRO 4.3 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance X Actual Performance

Classroom Simulator X Plant -----------------------------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • The Unit 3 Reactor has tripped due to a LOCA inside of Containment.
  • Safety Injection has occurred
  • Containment Isolation Phase A has occurred Task Standard:
  • The examinee manually isolates Containment Isolation Phase B components.

Required Materials:

  • 3-EOP-EO, Reactor Trip or Safety Injection Attachment 3 General

References:

  • You have been directed to complete 3-EOP-EO, Reactor Trip or Safety Injection Attachment 3 starting at step 14. Time Critical Task: No Validation Time: 10 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C . Page 3 018 Form ES-C-1 I SIMULATOR SETUP Reset to IC # 1 Load Lesson
  • Open lesson, JPM D
  • Execute lesson
  • Trigger "Parenf' step
  • Trigger step "Containment Spray Fails to Actuate". (TFL3S1 and TFL3S2, L3-S1 and S2 Fail to Actuate.)
  • Trigger step "Phase B Fails to Actuate". (TFL3B1 and 3B11, L3-CIB-1 and CIB-11 Fail to Actuate.)
  • PLACE SIMULATOR IN RUN
  • Trigger step "B" Cold Leg Break. (TVHHCLB 1)
  • Ensure 3-EOP-EO, Reactor Trip or Safety Injection Attachment 3 is complete up through step 13.
  • Ensure Containment Pressure is greater that 20 psig.
  • ACKNOWLEDGE ALARMS
  • FREEZE SIMULATOR.

Ensure Simulator Operator Checklist is complete

  • Provide a copy of 3-EOP-EO, Reactor Trip or Safety Injection Attachment 3 marked up as complete through step 13.
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, if a temporary IC has been deleted. NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of8 Form ES-C-1 Denote critical steps with a check mark(T} Start Time ----STEP 1 Obtain required materials.

SAT --UNSAT --Standard:

Examinee obtains a copy of the required procedure.

Cue Provide the Examinee with a copy 3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3 marked up as complete through step 13. Comment Reestablish RCP Cooling. STEP 2 (3-EOP-EO Attachment 3 Step 14.a) SAT --UNSAT --Standard:

Examinee observes no RCPs running and transitions to step 15. Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 50f 8 Form ES-C-1 I STEP 3 Monitor Containment Pressure To Verify Containment Spray NOT SAT Required.

--(3-EOP-EO Attachment 3 Step 15.a) UNSAT --Standard:

Examinee observes Containment pressure is greater than 20 psig on Containment pressure recorders.

Comment STEP 4 Manually initiate Containment Spray. SAT --(3-EOP-EO Attachment 3 Step 15 RNO a.1) T UNSAT --Examinee initiates one complete Train of Containment Spray by performing the following:

Places A Containment Spray pump handswitch to START AND places Standard:

MOV-3-880A handswitch to OPEN OR Places B Containment Spray pump handswitch to START AND places MOV-3-880B handswitch to OPEN Comment STEP 5 Manually initiate Containment Isolation Phase B. SAT --(3-EOP-EO Attachment 3 Step 15 RNO a.2) UNSAT --Standard:

Examinee attempts to manually initiate Containment Isolation Phase B by depressing both Containment Isolation Phase B push buttons. Comment EXAMINER NOTE: Containment Isolation Phase B is disabled as a part of the setup. NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of8 Form ES-C-1 STEP 6 Verify Containment Isolation Phase B valve white lights on VPB -ALL SAT BRIGHT. --(3-EOP-EO Attachment 3 Step 15 RNO a.3) UNSAT --Standard:

Examinee observes Containment Isolation Phase B valve white lights on VPB are OFF. Comment EXAMINER Containment Isolation Phase B is disabled as a part of the setup. NOTE: Containment Isolation Phase B valve white lights on VPB do NOT illuminate BRIGHT. STEP 7 Manually isolate affected containment penetration.

SAT --(3-EOP-EO Attachment 3 Step 15 RNO a.4) T UNSAT --Examinee manually places the handswitches for ALL of the following valves to CLOSE: Standard:

  • MOV-3-716B, CCW Inlet supply to RCP
  • MOV-3-626, RCP Thermal Barrier CCW Outlet
  • MOV-3-730, RCP Bearing CCW Outlet Comment EXAMINER The examinee must manually close all three MOV's in order to meet NOTE: the standard.

Terminating The task is complete when the Examinee establishes at least one Cue: train of Containment Spray and manually closes MOV-3-7168 STOP MOV-3-626 and MOV-3-730.

Stop Time ___ _ NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of8 Form ES-C-1 I Verification of Completion Job Performance Measure No. JPM D Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ______________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • The Unit 3 Reactor has tripped due to a LOCA inside of Containment.
  • Safety Injection has occurred
  • Containment Isolation Phase A has occurred INITIATING CUE:
  • You have been directed to complete 3-EOP-EO, Reactor Trip or Safety Injection Attachment 3 starting at step 14. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title: Job Performance Measure Worksheet

_____ --Task No: Manually Synchronize Main _G..::.:...::.e.:...:..ne:::.,:r-=a..:..:to:...:..r

_______ JPM No: KIA

Reference:

045 A4.02 RO 2.7 SRO 2.6 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 01002002100 JPM E Method of testing: _____________________________

_ Simulated Performance X Actual Performance

Classroom

Simulator X ----------

Plant -------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3 is in MODE 1, 5% power
  • The voltage regulator is in service
  • The Main Generator AUTO Synchronizing Circuit is NOT available.
  • The Shift Manager has given authorization to perform a manual synchronization of the main generator Task Standard:
  • The main generator has been synchronized to the grid and main generator load is raised to at least 10 with no reverse power trip. Required Materials:
  • 3-GOP-301, HOT STANDBY TO POWER OPERATION
  • Sync plug General

References:

  • 3-GOP-301, HOT STANDBY TO POWER OPERATION NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 9 Form ES-C-1 Initiating Cue:
  • You have been directed to manually synchronize the generator using 3-GOP-301 HOT STANDBY TO POWER OPERATION, step 5.54 and raise load to 10 MW.
  • All prerequisites and job briefings have already been completed.

Time Critical Task: No Validation Time: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 9 Saved to memory stick IC ,. If IC 193 is NOT available perform the following

  • Reset to IC # 56
  • Place the Gen Synchronizing East Bus Control in the OFF position.
  • Go to NO-OP, freeze the simulator for Steam Generator and Blowdown Ensure Simulator Operator Checklist is complete
  • PLACE SIMULATOR IN RUN Form ES-C-1 I
  • Ensure 3-GOP-301 HOT STANDBY TO POWER OPERATION steps 5.52.3 through 5.52.4 are complete
  • ACKNOWLEDGE ALARMS
  • Place the Gen Synchronizing East Bus Control in the OFF position.
  • Adjust turbine speed until the synchroscope is moving slowly in the SLOW direction.
  • FREEZE SIMULATOR.
  • Provide a copy of 3-GOP-301 HOT STANDBY TO POWER OPERATION marked up as complete through step 5.52. (step 5.53 is NlA).
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, if a temporary IC has been deleted. NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of9 Form ES-C-1 Denote critical steps with a check mark(T) Start Time ----Procedure Note: NOTE: The Manual Mode is only to be used by authorization of the Shift Manager. STEP 1 Obtain required materials.

SAT --UNSAT --Standard:

Examinee obtains a copy of the required procedure.

Cue Provide the Examinee with a copy 3-GOP-301 HOT STANDBY TO POWER OPERATION marked up as complete through step 5.52. Comment EXAMINER NOTE: 3-GOP-301 step 5.53 is N/A. STEP 2 Place the generator synchronization switch for the east generator GCB in SAT manual. --...; UNSAT (3-GOP-301 step 5.54.1) --STANDARDS:

Examinee places the generator synchronizing east bus control switch to MANUAL. Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 9 Form ES-C-1 I STEP 3 Verify the Inadvertent Protection Scheme Armed amber light above the SAT synchroscope is LIT. --(3-GOP-301 step 5.54.2) UNSAT --Standard:

Examinee observes the "Inadvertent protection Scheme Armed" amber light above the synchroscope is LIT. Comment STEP 4 Ensure synchroscope is rotating slowly in the FAST direction.

SAT --(3-GOP-301 step 5.54.3) UNSAT --Standard:

Examinee adjusts turbine speed using the governor, as indicated by the synchroscope to attain slow movement in the clockwise

[fast] direction.

Comment Procedure Caution: NOTE: DO NOT hold GCB control switch in CLOSED position beyond the 12 o'clock position.

STEP 5 WHEN the synchroscope is approximately 11 o'clock, THEN manually SAT hold closed the GCB Control Switch until either the GCB is closed or the --12 o'clock position is reached. UNSAT --(3-GOP-301 step 5.54.4) The examinee places and holds the generator East GCB handswitch to Standards:

CLOSE WHEN the synchroscope is between the 11 o'clock and 12 o'clock position on the synchroscope until either the GCB is closed or the 12 o'clock position is reached. Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 9 Form ES-C-1 Procedure Note: If East bus breaker fails to close, the Power Coordinator in Systems Operations needs to be notified prior to attempting to synchronize with the NOTE: Mid Bus Breaker, since realignment of the switchyard*may be required. (The Systems Operator/Power Coordinator evaluates system conditions to determine if the high line should be isolated before closing the Mid Bus Breaker, and will work with the plant to expedite any necessary switching).

[Commitment

-Step 2.3.1] STEP 6 Ensure East GCB closes. SAT --(3-GOP-301 step 5.54.5.1)

UNSAT --Standard:

Examinee observes the East Bus Breaker red indicating light is ON. Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 9 Form ES-C-1 I Procedure Note: NOTE: If the generator is motored at 2 MW or more for 30 seconds, the reverse power relay will initiate generator lockout. STEP 7 Raise Main Generator load to approximately 10 MW. SAT --..j (3-GOP-301 step 5.54.5.2)

UNSAT --Examinee raises Main Generator load by placing the Generator Governor Speed Changer Control to RAISE to approximately 10 MW Standard:

AND A reverse power trip does NOT occur Comment Terminating When the Examinee has attained a load of 10 to 20 MWE, inform Cue: the examinee the task has been completed STOP Stop Time ----NUREG 1021 Rev 9 Appendix C AppendixC Page 8 of9 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM E Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _______________________________

__ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3 is in MODE 1, 5% power
  • The voltage regulator is in service
  • The Main Generator AUTO Synchronizing Circuit is NOT available.
  • The Shift Manager has given authorization to perform a manual synchronization of the main generator INITIA TlNG CUE:
  • You have been directed to manually synchronize the generator using 3-GOP-301 HOT STANDBY TO POWER OPERATION, step 5.54.
  • All prerequisites and job briefings have already been completed.

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title: Job Performance Measure Worksheet

______ Task No: Respond to a L T -112 failure JPM No: KIA

Reference:

016 A2.01 RO 3.0* SRO 3.1

  • Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 01046045300 JPM F Method of testing: _____________________________

_ Simulated Performance X Actual Performance

Classroom

Simulator X ----'-"-------

Plant -------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3 is in MODE 1, 100% power
  • No equipment is out of service Task Standard:
  • Letdown is restored to the VCT by placing control switch to the VCT position.

Required Materials:

  • 3-0NOP-046.4 Malfunction of Boron Concentration Control System General

References:

  • 3-0NOP-046.4 Malfunction of Boron Concentration Control System NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 10 Form ES-C-1 Initiating Cue:
  • You have been directed to respond to plant conditions.

Time Critical Task: No Validation Time: 10 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 10 Form ES-C-1 I SIMULATOR SETUP Reset to IC # 1 Load Lesson

  • Open & execute lesson JPM F
  • Verify lesson step "LC-112 stays in AUTO" triggers.

(1 DB1 LAUU)

  • Ensure Simulator Operator Checklist is complete
  • PLACE SIMULATOR IN RUN
  • ACKNOWLEDGE ALARMS
  • LET STABILIZE AND FREEZE SIMULATOR
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN, prior to student entering the simulator.
  • When directed by the examiner, trigger lesson step "LT-112 failure HIGH". (TFB1LTHW)
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 10 Form ES-C-1 Denote critical steps with a check mark(T) Start Time Lowering VCT level as indicated on U-115 due to L T -112 failing high. STEP 1 SAT --UNSAT --Examinee observes lowering VCT level on U-115 with no change in Standard:

charging or letdown flows. Examinee observes LCV-115A open indication on VP A. Comment EXAMINER Direct the facility booth operator to trigger lesson step "L T -112 failure NOTE: HIGH" when ready The instrument malfunction results in Letdown being diverted to the EXAMINER holdup system, away from the VCT resulting in an AUTO makeup to the VCT. NOTE: No alarms occur directly as a result of the instrumentation failure. The only alarms are those associated with the Auto Makeup to the VCT. EXAMINER The examinee must eventually diagnose the instrumentation failure to NOTE: correctly enter 3-0NOP-046.4, Malfunction Of Boron Concentration Control System. Transition to 3-0NOP-046.4, Malfunction Of Boron Concentration Control STEP 2 System. SAT --T UNSAT --Standard:

Examinee transitions to 3-0NOP-046.4, Malfunction Of Boron Concentration Control System. Comment EXAMINER Examinee enters 3-0NOP-046.4 Malfunction Of Boron Concentration NOTE: Control System due to an unexplained deviation of VeT level indication between U-3-115 and U-3-112. NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 10 Form ES-C-1 I Check boric acid or primary water flow rates-abnormal.

STEP 3 (3-0NOP-046.4 Step 1) SAT --UNSAT --Examinee observes boric acid and primary flowrates normal by observing Standard:

the indications on FR-3-113 and transitions to RNO column and then to step 28. Comment EXAMINER FR-3-113 is located on the Operator Console, near the controls for VCT NOTE: Makeup. Procedure Note: L T 112 and L T 115 share a common wet variable leg and a common dry reference leg. A false high level will be produced if the common dry NOTE: reference leg fails. Steps 28 through 38 assume stable charging and letdown flow; therefore, a transient could mask the symptoms being used to determine which level transmitter has failed. Check For VCT Level Transmitter, LT-3-115 Failing Or Failed High. STEP 4 (3-0NOP-046.4 Step 28) SAT --UNSAT --Standard:

Examinee observes LI-3-115 normal and transitions to RNO column and then to step 31 Comment EXAMINER LI-3-115 VCT Level indication is located on VPA, left side. All VCT NOTE: level indicators LI-3-115 and LI-3-112 are available on ERDADS. NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 10 Form ES-C-1 Check For VCT Level Transmitter, LT-3-115 Failing Or Failed Low. STEP 5 (3-0NOP-046.4 Step 31) SAT --UNSAT --Standard:

Examinee observes L T 115 indicates normal and transitions to RNO column and then to step 34 Comment STEP 6 Check for L T 112 failing or failed high SAT --U-3-112 abnormally high UNSAT --OR U-3-115 decreasing due to LCV-3-115A diverting or increasing after auto makeup actuated.

(3-0NOP-046,4 Step 34) Examinee verifies L T 112 has failed high by observing the following:

Observing U-3-112 abnormally high on ERDADS or from local verification.

Standard:

OR U-3-115 decreasing due to LCV-3-115A diverting or increasing after auto makeup actuated by observing the increased rate of makeup to the VCT. Cue If asked, provide the following cue from the SNPO "U-112 indicates offscale high." Comment EXAMINER Operator may dispatch field operator to check L T -112 indication.

The NOTE: indication of l T-112 is available on ERDADS. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 10 Form ES-C-1 I Procedure CAUTION NOTE With no operator action, LT-3-112 failed high with makeup flow less than letdown flow will result in loss of suction to the charging pumps. Procedure NOTE Failure of LT-3-112 high will result in the following:

  • LCV-3-115A modulating to full divert. NOTE Auto makeup when actual VCT level reaches 17 percent. *
  • Annunciator alarm A 4/6 VCT HIILO LEVEL if actual level reaches 12 percent.
  • No auto swap over to the RWST if actual level reaches 4 percent. STEP 7 Place LC-3-112, VCT Level Controller Auto-Manual Station, In MANUAL. SAT --(3-0NOP-046.4 Step 35) UNSAT --Standard:

Examinee depresses the "MANUAL" pushbutton on LC-3-112 VCT Level Controller.

Comment EXAMINER LC-3-112 VCT Level Controller Auto-Manual Station will NOT shift to NOTE: MANUAL due to a previously inserted malfunction.

EXAMINER With no operator action, VCT level will continue to cycle perpetually NOTE: between the VCT AUTO Makeup setpoints.

NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 10 Form ES-C-1 STEP 8 Direct Flow To The VCT By Manually Adjusting VCT Level Controller, LC-SAT 3-112, To Adjust LCV-3-115A Position.

--(3-0NOP-046.4 Step 36) UNSAT --Standard:

Examinee attempts to close LCV-3-115A by adjusting the AUTO setpoint on LC-3-112.

Comment EXAMINER The LC-3-112, VCT Level Controller will not be able to fully close LCV-3-NOTE: 115A. EXAMINER NOTE: Examinee proceeds to the RNO column step. STEP 9 Place the UD DIVERT FROM VCT TO HOLDUP TANK, LCV-3-115A, SAT control switch to the VCT position.

--T UNSAT (3-0NOP-046.4 Step 36 RNO) --Standard:

Examinee places the handswitch for LCV-3-115A, UD DIVERT FROM VCT TO HOLDUP TANK to "VCT'. Comment EXAMINER Letdown will be restored to the VCT once the LCV-3-115A control switch NOTE: is placed to VCT. Terminating The task is complete when the examinee restores Letdown to the Cue: VCT. STOP Stop Time ----NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 10 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM F Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________________________

__ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3 is in MODE 1, 100% power
  • No equipment is out of service INITIA TING CUE:
  • You have been directed to respond to plant conditions.

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title: Job Performance Measure Worksheet

______ Task No:

....... p_o_nd_to_a_C_C_W_L_e_a_k

__ JPM No: KIA

Reference:

008 A2.02 RO 3.2 SRO 3.5 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 01030008300 JPMG Method of testing: _____________________________

_ Simulated Performance X Actual Performance

Classroom

Simulator X --:....:.------

Plant -------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3 is in MODE 3
  • Shutdown Banks have been withdrawn, awaiting management permission to commence the Reactor Startup.
  • No equipment is out of service Task Standard:
  • The Unit 3 Reactor is tripped AND
  • 3-0NOP-030, Component Cooling Water Malfunction General

References:

  • 3-0NOP-030, Component Cooling Water Malfunction NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 12 Initiating Cue:
  • You have been directed to respond to plant conditions.

Time Critical Task: No Validation Time: 15 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! Form ES-C-1 NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 12 Form ES-C-1 I SIMULATOR SETUP Reset to IC # 8 Load Lesson

  • Open lesson, JPM G
  • Execute lesson
  • Trigger "Parent" step
  • Ensure Simulator Operator Checklist is complete
  • PLACE SIMULATOR IN RUN
  • ACKNOWLEDGE ALARMS
  • LET STABILIZE AND FREEZE SIMULATOR
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN, prior to student entering the simulator.
  • When directed by the examiner, trigger lesson step "CCW Header Leak". (TVKAL 835 0.15)
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 12 Form ES-C-1 Denote critical steps with a check mark{T} Start Time STEP 1 CCW HEAD TANK HI/LO LEVEL annunciator response, SAT --(3-ARP-097.CR Annunciator Window H 8/6 page 446) UNSAT --Standard:

Examinee responds to alarm using 3-ARP-097.CR Control Room Annunciator Response Cue Comment STEP 2 Verify alarm by checking CCW Head Tank Level Indication, U-3-614A SAT (VPB) --(3-ARP-097.CR Annunciator Window H 8/6 page 446 step 1.a) UNSAT --Standard:

Examinee verifies alarm by checking CCW Head Tank Level Indication, U-3-614A decreasing Comment Both CCW Head Tank Level Indication, U-3-fil14A AND EXAMINER CCW Surge Tank level indication, U-3-613A NOTE: are BOTH decreasing.

CCW Head Tank Level Indication, U-3-614A will be the first alarm received.

NUREG 1021 Rev 9 Appendix C I Appendix C . Page 5 of 12 Form ES-C-1 I STEP 3 IF low level, THEN open fill valve, MOV-3-832, and restore level to SAT normal (10% to 85% in the CCW Head Tank for normal CCW System --requirements. ) UNSAT --(3-ARP-097.CR Annunciator Window H 8/6 page 446 step 3.a) Standard:

Examinee places the handswitch for CCW fill valve, MOV-3-832 to OPEN. Cue If asked provide the following cue, "Understand alarm I 5/6, PRI WATER STANDBY PUMP RUNNING is expected." Comment EXAMINER Alarm 15/6, PRI WATER STANDBY PUMP RUNNING can be NOTE: expected to come on when the Examinee opens MOV-3-832.

EXAMINER The leak is of such magnitude that CCW Head Tank level continues to NOTE: decrease.

STEP 4 Check CCW System for possible leaks and isolate the source of SAT leakage. --(3-ARP-097.CR Annunciator Window H 8/6 page 446 step 3.b) UNSAT --Standard:

Examinee dispatches an operator to look for the source of CCW leakage. Cue If asked provide the following cue, "SNPO acknowledges to look for the source of CCW leakage." Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 12 Form ES-C-1 STEP 5 IF CCW Head Tank level cannot be maintained, THEN refer to 3-SAT ONOP-030, Component Cooling Water. --T UNSAT (3-ARP-097.CR Annunciator Window H 8/6 page 446 step 3.c) --Standard:

Examinee transitions to 3-0NOP-030, Component Cooling Water. Comment Procedure Note: NOTE: Foldout page should be monitored throughout this procedure.

STEP 6 Verify Power To 4KV Bus 3D SAT --(3-0NOP-030 step 1) UNSAT --Standard:

Examinee verifies power to 4KV Bus 3D available by observing bus supply breakers 3A006 and 3AB19 CLOSED. Comment EXAMINER The examinee may refer to the foldout page of 3-0NOP-030, Component Cooling Water. Time validation showed actions contained NOTE: within the foldout page are in addition to those contained within the standard are of no direct consequence to this task. EXAMINER NOTE: "0" 4kv bus power supply breakers are located on VPA. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 12 Form ES-C-1 I STEP 7 Verify Component Cooling Water pumps in service. SAT --(3-0NOP-030 step 2) UNSAT --Examinee verifies Component Cooling Water pumps are in service by Standard:

observing "8":CCW pump amps and pump breaker CLOSED indication.

Comment STEP 8 Verify Flow In 80th Component Cooling Water Headers -NORMAL. SAT --(3-0NOP-030 step 3) UNSAT --Standard:

Examinee verifies Flow In 80th Component Cooling Water Headers -NORMAL by observing FI-3-613 A and FI-3-6138.

Comment The flow indicators are located on VP 8 EXAMINER FT-3-613A for header A NOTE: FT-3-6138 for header 8 NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 12 Form ES-C-1 Procedure notes: The top of the component cooling water surge tank divider plate is located at approximately 25% indicated level. If a cross tie valve between the units is leaking or open, the surge tank on the opposite unit may be experiencing level control problems.

NOTE: If in Modes 1 through 3, and CCW System level is NOT maintained within the CCW Head Tank, restore CCW System level to be within the CCW Head Tank within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. U-3-613A and U-3-614A are NOT overlapping (Le., U-3-614A will go off scale low before U-3-613A comes off its high peg with decreasing level). STEP 9 Verify Component Cooling Water Surge Tank Level Being Maintained SAT greater than 25% --T AND UNSAT --Stable or increasing.

(3-0NOP-030 step 4.a) Standard:

Examinee verifies Component Cooling Water Surge Tank Level DECREASING by CCW Head Tank Level by observing U-3-614A.

Comment If asked provide the following cue,"SNPO reports a large leak on the Cue discharge header of the pumps. SNPO will attempt to isolate the leak but it will take an additional 5 minutes to enter the area safely to do so". EXAMINER Component Cooling Water Surge Tank Level, U-3-613A is located on NOTE: VPB EXAMINER NOTE: Decreasing level requires transition to step 4 RNO EXAMINER The leak is of such magnitude that CCW Head Tank level continues to NOTE: decrease.

NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 12 Form ES-C-1 STEP 10 Open Component Cooling Water Surge Tank Makeup, MOV-3-832 as SAT necessary to add makeup. --(3-0NOP-030 step 4 RNO 1) UNSAT --Standard:

Examinee places the handswitch for CCW fill valve, MOV-3-832 to OPEN. Comment EXAMINER Direction to open Component Cooling Water Surge Tank Makeup NOTE: MOV-3-832 was provided in the alarm response and should already be opened. NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 12 Form ES-C-1 STEP 11 IF Component Cooling Water Surge Tank Level can NOT be SAT maintained, THEN perform the following:

--T UNSAT Trip the reactor. --Stop all RCPs. Perform 3-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure.

(3-0NOP-030 step 4 RNO 2) Examinee performs the following:

Places the Reactor Trip switch to TRIP. Standard:

AND THEN Places the handswitches for all RCPs to STOP. Comment If the examinee proceeds to 3-EOP-E-0, REACTOR TRIP OR Cue SAFETY INJECTION after tripping the reactor provide the following cue, "Another operator has verified the first four steps of to 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION are complete." EXAMINER The guidance provided by 3-0NOP-030 Component Cooling Water Malfunction requires transition to 3-EOP-E-O, REACTOR TRIP OR NOTE: SAFETY INJECTION.

This aspect will not be measured within this task. The examinee may take additional actions from foldout page of 3-EXAMINER ONOP-030, Component Cooling Water if the Reactor is not tripped NOTE: prior to CCW Pump cavitation occurring.

These actions are in addition to those contained within the standard and are of no consequence to this task. Terminating The task is complete when the Examinee trips the Reactor and Cue: trips the Reactor Coolant pumps. STOP Stop Time ----NUREG 1021 Rev 9 Appendix C I Appendix C Page 11 of 12 Form ES-C-1 I Verification of Completion Job Performance Measure No. JPM G Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's Signature and date: ________________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3 is in MODE 3
  • Shutdown Banks have been withdrawn, awaiting management permission to commence the Reactor Startup.
  • No equipment is out of service INITIA TING CUE:
  • You have been directed to respond to plant conditions.

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C AppendixC Facility:

Task Title: Job Performance Measure Worksheet*

_T_u_r_k_ey"--P_o_in_t

_______ Task No: Terminate a Waste Gas Release JPM No: ------------

KIA

Reference:

071 A4.03 RO 3.9 SRO 3.8 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Form ES-C-1 1061050300 JPM H Simulated Performance X Actual Performance

Classroom

Simulator X --'--'------

Plant -------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3 is in MODE 1 100% power
  • No equipment is out of service.
  • The SNPO has initiated a "8" Waste Gas release using 0-OP-061.14 Waste Gas Disposal System Controlled Radioactive Gas Release step 7.1.2.9. Task Standard:
  • Direction to locally isolate the "8" Waste Gas Decay Tank has been given. Required Materials:
  • 0-OP-061.14 Waste Gas Disposal System Controlled Radioactive Gas Release *. 3-0NOP-067, Radioactive Effluent Release

References:

  • 0-OP-061.14 Waste Gas Disposal System Controlled Radioactive Gas Release
  • 3-0NOP-067, Radioactive Effluent Release
  • 0-NCOP-004 Preparation of Gas Release Permits NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 12 Form ES-C-1 Initiating Cue:
  • You have been directed to monitor the Waste Gas release as described in step 7.1.2.8 of 0-OP-061.14, Waste Gas Disposal System Controlled Radioactive Gas Release. When the release is complete, notify the Unit Supervisor.

Time Critical Task: No Validation Time: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE A T THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 12 Form ES-C-1 I SIMULATOR SETUP Reset to IC # 1

  • Open & execute lesson JPM H Execute lesson
  • Execute lesson
  • Trigger "Parenf' step
  • Trigger step "Override R-g' (actuates CMRI090 -.57791877)
  • Trigger step "GR Release Setup" (actuates TAAAV291 and TVAVLK31 0.5)
  • Ensure Simulator Operator Checklist is complete
  • PLACE SIMULATOR IN RUN
  • ACKNOWLEDGE ALARMS
  • LET STABILIZE AND FREEZE SIMULATOR
  • Save as a temporary IC, if repeat runs of JPM will be desired.
  • PLACE SIMULATOR IN RUN, prior to student entering the simulator.
  • When directed by the examiner, trigger lesson step"
  • After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 12 Form ES-C-1 Denote critical steps with a check mark(T) Start Time ----STEP 1 Obtain required materials.

SAT --UNSAT --Standard:

Examinee obtains a copy of the required procedure.

Provide the Examinee with a copy of 0-OP-061.14 Waste Gas Disposal System Controlled Radioactive Gas Release marked up as complete Cue through step 7.1.2 9. Provide the Examinee with a copy of the current Gas Release Permit. Comment STEP 2 Monitor Gas Release. SAT --(0-OP-061.14 step 7.1.2 8.a) UNSAT --Examinee monitors the waste gas release by observing either: PRMS R-14 Monitor Drawer Standard:

ANDIOR ERDADS indications for R-14 and/or Plant Vent SPING Comment EXAMINER When ready, direct the Booth Operator to trigger step 'WGDT Radiation NOTE: Increase" (actuates TAAARI112(00)

NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 12 Form ES-C-1 I STEP 3 WGDT Radiation Increase Above Limits. SAT --(0-OP-061.14 step 7.1.2 9.c) UNSAT --Examinee observes the increasing output by either: PRMS R-14 Monitor Drawer Standard:

ANDIOR ERDADS indications for R-14 and/or Plant Vent SPING The examinee may direct the SNPO to terminate the release, if Cue directed provide the following cue, "Understand, SNPO acknowledges terminate the release." Comment STEP 4 PRMS HI RADIATION Alarm, window H 1/4 for High R-14 Alarm. SAT --(3-ARP-097.CR page 402 step 1) UNSAT --*Standard:

Examinee verifies R-14 HIGH alarm by observing R-14 HIGH ALARM LIGHT ON. Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 12 Form ES-C-1 STEP 5 Verify automatic actions have occurred SAT --(3-ARP-097.CR page 402 step 2) UNSAT --Examinee responds to the PRMS Hi Radiation by the following:

Implementing the alarm response corrective actions Standard:

OR Transitions to 3-0NOP-067, Radioactive Effluent Release. Comment EXAMINER The examinee may directly transition to 3-0NOP-067, Radioactive NOTE: Effluent Release. If the examinee transitions directly to 3-0NOP-067, go to step 9. STEP 6 Verify valid alarm on affected PRMS channel SAT --(3-ARP-097.CR page 402 step 3.a) UNSAT --Examinee validates alarm by performing the following:

1. Check FAILJrEST light not lit. Standard:
2. Push FAILJrEST light pushbutton
3. Push SOURCE CHECK light pushbutton (meter will NOT increase due to the max output of R-14). 4. Push HIGH ALARM light pushbutton.

Comment NOTE: These actions are duplicated in to 3-0NOP-067, Radioactive Effluent Release step 2. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 12 Form ES-C-1 I STEP 7 Verify or manually initiate required automatic actions SAT --(3-ARP-097.CR page 402 step 3.b) UNSAT --Standard:

Examinee attempts to implement actions to terminate the waste gas release. The examinee may direct the SNPO to verify RCV-014 CLOSED, if Cue directed provide the following cue, "The loader signal for RCV-014 has been reduced to 0 but RCV-014 is still OPEN." Comment EXAMINER These actions are duplicated in 3-0NOP-067, Radioactive Effluent NOTE: Release step42 and Foldout Page step 2.b. Procedure note: NOTE Foldout page shall be monitored throughout this procedure.

STEP 8 Notify plant personnel of any potentially hazardous effluent release via SAT the plant page. --(3-0NOP-067 Foldout page step 1) UNSAT --Standard:

Examinee makes a plant page announcement to notify plant personnel of any potentially hazardous effluent release via the plant page. Comment EXAMINER If during step 6 the examinee transitioned to 3-0NOP-067, NOTE: Radioactive Effluent Release directly, start here. NUREG 1021 Rev 9 Appendix C AppendixC Page 8 of 12 Form ES-C-1 Procedure note: NOTE Foldout page shall be monitored throughout this procedure.

STEP 9 Verify RCV-014, Gas Decay Tank Discharge Valve -CLOSED. SAT --(3-0NOP-067 Foldout page step 2.b) UNSAT --Standard:

Examinee directs the SNPO to verify RCV-014, Gas Decay Tank Discharge Valve -CLOSED Cue If directed the SNPO will provide the following cue, The loader signal for RCV-014 has been reduced to 0 but RCV-014 is still OPEN." Comment EXAMINER NOTE: These actions are duplicated in 3-ARP-097.CR page 402 step 2 STEP 10 Check R-14 High Alarm On. SAT --(3-0NOP-067 step 1) UNSAT --Standard:

Examinee verifies R-14 HIGH alarm by observing R-14 HIGH ALARM LIGHT ON. Comment NOTE These actions are duplicated in 3-ARP-097.CR page 402 step 1 NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 12 Form ES-C-1 I STEP 11 Check R-14 alarm VALID SAT --(3-0NOP-067 step 2) UNSAT --Examinee validates alarm by performing the following:

1. Checks readout on R-14 GREATER THAN OR EQUAL TO ALARM SETPOINT 2. Depresses and holds FAIUTEST pushbutton for R-14 and checks Standard:

readout -EQUAL TO 288K OR 289K 3. Releases FAIUTEST pushbutton

4. Pushes SOURCE CHECK light pushbutton (meter will NOT increase due to the max output of R-14). 5. Checks for PRMS channel failure Comment EXAMINER NOTE: These actions are duplicated in 3-ARP-097.CR page 402 step 3.a. STEP 12 Perform Corrective Action For PRMS HIGH ALARM SAT --(3-0NOP-067 step 3) UNSAT --Standard:

Examinee checks R-14 alarm is ON and transitions to step 42. Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 12 Form ES-C-1 STEP 13 Verify RCV-014 -CLOSED SAT --(3-0NOP-067 step 42) UNSAT --Standard:

The examinee directs the SNPO to verify RCV-014 CLOSED and implements RNO actions. Cue If directed the SNPO will provide the following cue, The loader signal for RCV-014 has been reduced to 0 but RCV-014 is still OPEN." Comment EXAMINER NOTE: These actions are duplicated in 3-ARP-097.CR page 402 step 3.b STEP 14 Locally close RCV-014 Isolation valve, 46388 SAT --T (3-0NOP-067 step 42 RNO a) UNSAT --Standard:

Examinee directs the SNPO to locally close "8" Waste Gas Decay Tank Isolation, 46388. Cue If directed to locally close "8" Waste Gas Decay Tank Isolation, 46388 wait one minute and respond as SNPO,"The 8 Waste Gas Decay Tank Isolation, 46388 is CLOSED." Comment EXAMINER NOTE: . These actions are duplicated in 3-ARP-097.CR page 402 step 3.b Terminating The task is complete after the Examinee directs the SNPO to Cue: locally close RCV-014 Isolation valve, 46388. STOP Stop Time ----NUREG 1021 Rev 9 Appendix C I Appendix C Page 11 of 12 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM H ----------------------------------------------------

Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3 is in MODE 1 100% power
  • No equipment is out of service.
  • The SNPO has initiated a "8" Waste Gas release using 0-OP-061.14 Waste Gas Disposal System Controlled Radioactive Gas Release step 7.1.2.9. INITIA TING CUE:
  • You have been directed to monitor the Waste Gas release as described in step 7.1.2.8 of 0-OP-061.14, Waste Gas Disposal System Controlled Radioactive Gas Release. When the release is complete, notify the Unit Supervisor.

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Procedure No.: Procedure Title: 19 Approval Date: GAS DECAY TANK Gas Decay Tank: PARTU: Limits Preparation of Gas ReleasePerntits ATTACHMENT 1 (Page lofl) GAS DECAY TANK RELEASE PERMIT FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT RADIOACTIVE GAS RELEASE PERJ..1IT Ref:O:"OP-06U 4 Approx. Act. to be Released, ,. '2 1. Count time shal! be within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of R-14 Alarm Setpoint= /(cpm (N/A ifR*14 isOOS) " Release Rate Limit: RCV-OI4 Loader Setting"'" I/)() % is exceeded Gas Release No. GRp. OJ-(;> { Date: !DDIt Technician 10/5/07 Radiochemistry Supervisor Shift Manager ormed by: Every 15 minutes Stop J/cc Procedure No.: Procedure Title: Page: O-OP-061.14 Waste Gas Disposal System Radioactive Gas Release 8 Approval Date; 9127/07 3.0 PREREQUISITES

\N97: 3.1 3.2 3.3 Prior to performing a gas release of a Gas Decay Tank, the tank shall be sampled and I analyzed and a Gas Release Permit shaH be issued and approved by the Shift Manager. If PJant Vent Monitor R-14 is inoperable, then I&C Maintenance will be required to* install I and remove jumpers as directed by this procedure-.

Plant Vent Ga.s Monitor R-14 shall be operable.

OR 3.4 If Plant Vent Gas Monitor R-14 is inoperable, then verify Chemistry Department personnel are performing the required actions of 0 .. NCCP-21 0, SPING and DAM Monitor Channel Check. [Commitment

-Step 2.3.1] 3.5 Plant Vent SPING-4 shall be operable.

OR 3.6 If Plant Vent is inoperable, then verify Chemistry Department personnel are performing the required actions of 0-NCCP-210, SPINO and DAM Monitor Channel Check. [Commitment

-Step 2.3.1] 3.7 Plant Vent SPING-4, Channel 10 should be operable.

3.8 If Plant Vent SPING-4 Channe1lO is i be estimated using Enclosure 1 (ODCM rabIe, then the Plant Vent flowrate will need to I. Ie 3.1-1). 3.9 A minimum of one Auxiliary Building Ventilation Exhaust Fan is in service. 3.10 The following systems are operable or in operation to support the Gas Decay Tank release: 3.10.1 Instrument Air System 3.10.2 120V DC Electrical System 3.10.3 480V AC Electrical System 3.11 The Operations Manager has been notified if the Plant Vent Monitor and the Plant! Vent SPING-4 monitor are both inoperable.

Procedure No.: Procedure Title: Page: 9 Approval Date: 0.,OP-061.14 Waste Gas Disposal System Controlled Radioactive Gas Release 9/27/07 4.0 PRECAUTIONSILIMITATIONS . 4.1 4.2 43 4.4 4.5 4.6 4.7 4.8 4.9 The maximum allowable RCV-014 loader setting and the maximum expected value for the Plant Vent Gas Monitor should be monitored closely to prevent exceeding the release limits. Plant Vent Gas Monitor R-14 or an alternate monitor (may require a dedicated operator if utilizing local instrumentation) should be monitored at least once per 5 minutes during the gas release to assure the count rate is not approaching the alarm setpoint.

If the observed count rate exceeds the maximum expected readIng listed in Part II of the Release Permit, then terminate the release and contact the Chemistry Department for corrective actions. If the high setpoint on R-14 actuates; then physically verify RCV-014 is closed, close the Gas Decay Tank to the Plant Vent Manual Valve 40-907, verify the count rate is decreasing on R-14, and perform the required actions of 3-0NOP-067, Radioactive Effluent Release. If the high setpoint on R-14 actuates, verify the Gas Decay Tank that was being released is isolated from the rest of the Waste Gas System. Do not re-initiate the gas release until authorized by the Shift Manager. If the high setpoint on R-14 actuates, then loading pressure on PCV-014 must be reduced to zero in order to reset RCV-014. If the Auxiliary Building Ventilation System fan configuration requires alteration or is altered. then terminate the release and contact the Chemistry Department to recalculate the .' R-14 high setpoint and expected count rates for the new flowrates as required.

When the Reactor Operator has completed the initial portion of this procedure (steps marked RO). then the remaining actions required to initiate the release should progress without delays to maintain continuity in the operation and initiating data. During a Gas Decay Tank release. the pressure on the non-affected Gas Decay Tanks shaH be monitored.

If the pressure decreases in a tank other than the Gas Decay Tank being released and the reason for the pressure decrease is not known, then the release shall be terminated until the cause of the decreasing pressure is identified and corrected.

4.10 Plant Vent SPfNG-4, Channel 5 shan not be used to satisfy the minimum channel I operability requirements or in lieu of the sampling requirements ofOCDM, Table 3.1-1. W97:JEClevlmaicls Procedure NQ.: Procedure Title: Page; 12 Waste Gas Disposal System Approval Date; O-OP-061.14 Controlled Radioactive Gas Release 9/27/07 7.0 OPERATIONS 7.1 Controlled Radioactive Gas Release INfTIALS CK'D VERIF Daterrime Started: __

RO 7.1.2 Initial Conditions

1. Applicable prerequisites as in Section 3.0 are satisfied.
2. Record the number of the approved Gas Release Permit AND the Gas Decay Tank (GOT) on the QA Record Page. 3. Release of the Gas Decay Tank has been approved by the I Shift Manager. Procedure SteI2s L Reset the Process Radiation Monitor High Alarm setpoint AND Warning Limit by performing the following (Mark N/A if R-14 is inoperable); . a. Slide R-14 drawer forward to gain access to the thumbwheel switches.

i -------------------: I

  • The thumbwheef switch settings are used to select the setpoint as fof!ows: I I 1. Forward switch setting =: digit I I I 2. Middle switch setting:::;

decimal and digit I 3. Rear switch setting = exponent I I

  • For example: a setting of 4.03 is equal to 4.0 X 1rr or 4 Kcpm; a setting of 1.05 is I I equa/to 1.0X 1e1 or 100 Kcpm. I '--'------------------_

.........

--_. b. c. d, Position High Alarm thumbwheeI switches t? the R-14 HIgh Alarm specified on the Gas Release permIt. Position the Waming Limit thumbwheel switches to the R-14 maximum expected monitor reading specified on the Gas I Release Permit. I Close the R*14 drawer. W97' JE;C/evlmaJcls Prooedure 1'h: O-OP-061.14 ,INITIALS CK'D VERI.t Procedure Title: Page: 13 Waste Gas Disposal System Approval Date: Controlled Radioactive Gas Release 9/27/07 7.1,2.1 (Cont'dl e. Depress the HIGH ALARM pushbutton AND verify the digital display Cprv1 indication equals the High Alarm setpoint on the Gas Release Permit [ Release the HIGH ALARM pushbutton.

g. h. Depress the WARNING LIMIT pushbutton AND verify the digital display CPM indication equals the maximum expected monitor reading 1 on the Gas Release Pennit. I Release the WARNING LIMIT pushbutton.
i. Depress the SOURCE CHECK pushbutton AND verify the digital display CPM indication responds to the source. CAUTIONS .. Plant Vent SPING-4, Channel 5 shall not be used to satisfy the minimum channel operability requirements of the Offsite Dose Calculation Manual, Tab/e 3.1*1. .. Plant Vent SPING-4, Channel 5 readings shall not be used in lieu of the required sampling specified in the Off site Dose Calculation Manual, Table 3.1-1, W97:JECfevlmalc!s
2. n: Plant Vent Monitor R-14 is inoperable, N verify that Chemistry personnel have completed the required sa ng requirements AND verified 3. the release calculations as specified in Offsite Dose Calculation Manual, Table 3.1-1. I}'" Plant Vent Monitor R-14 is inoperable, THEN direct I&C Maintenance to I install the following jumpers on RT-14 in QR-66: a. b, c. On TB600 from Terminal 1 to Relay K850 Cl On TB600 from Terminal 2 to Relay K850 C2 ",rHEN the jumpers are installed, THEN place a CAUTION tag on front of the drawer to alert the operators that a jumper is installed.

Procedure No,; O-OP-061.14 INITIALS CK'D VERIF JL S'N1'O £ SNPO JLAJ SNPO SNPO f) SNPO SNPO Procedure Title: Page: Waste Gas Disposal System Controlled Radioactive Gas Release 14 Approval Pate: 9/27/07 7.L2(Confd)

4. 5. 6. Perform a channel check on Plant Vent SPING-4 Channel 10 (Effluent System Flowrate MeasuringDevice) as follows: a. Set the selector thumbwheel to 10 at the Plant Vent SPING-4 (located in the Auxiliary Building Fan Room). b. Check the green NORMAL light to be illuminated.

Complete Part A of the appropriate attachment for the Gas Decay Tank to be aligned for release. Review the Radioactive Gas Release Permit to verify the tank alignment performed matches the tank specified on the Radioactive Gas Release Permit AND document this review on the QA Record Page. @1J;MQ*N.

""'-......-

The Independent Verification of Substep 7.1.2.5 and 7.1.2.6 above are required to be completed prior to continuing with this procedure. SNPO b --81\1'0 () --SNPO C SNPO C SNPO W91:JEC/ev/matcls

7. Record the following information on the Radioactive Gas Release Permit (Attachment 1 ofO-NCOP-004, Preparation of Gas Release Permits):
a. Number of Auxiliary Building Exhaust Fans operating
b. Wind speed and direction (obtain from the Control Room) c. Meteorological Delta (L1) T (obtain from the Control Room) d. IF the green NORMAL light on the Plant Vent SPING-4 did not illuminate in Substep 7. L2.4.b, THEN calculate the estimated flow using Enclosure 1 as required by Offaite Dose Calculation Manual, Table 3.1-1. e. Initial Gas Decay Tank pressure.
f. Initial Gas Decay Tank Pressures for aU remaining Gas Decay Tanks Attachment 7 (prior to Release).

Procedure No.: 0-OP-061.14 SNPO SNPO SNPO SNPO SNPO W97:,JEC!evlmafci Procedure Title: Page: 15 Waste Gas Disposal System f\.ppwyal Date: Controlled Radioactive Gas Release 9/27/07 7.1.2 (Cont'd) the Reactor Operator to initiate the required monitoring of the gas by at least one of the following methods: a. PRMS 14 Monitor Drawer b. EROADS indication for RAD-6304 as follows: (1) Select EMERG RESP on the EROADS Display PaneL (2) Select METEORLOGICAL AND RAD DATA. (3) Read values under PLANT VENT SPING. c. Dedicated operator at the local SPING-4 display panel with constant communications with the Unit 3 Reactor Operator.

9. Initiate the gas release as follows: a. Slowly increase the RCV-014 loader setting to the maximum allowed b, c. setting as given in Part II ofthe Radioactive Release Permit. the release flowrate has been established, THEN verify that the oated reading obtained in Substep 7.1,2.8 does not exceed the maximum expected value given in Part II of the Radioactive Gas Release Permit. IF the indicated reading exceeds the maximum expected value stated on the Radioactive Gas Release Permit, THEN terminate the release. d. Record the initial set of readings on the Data Table in Part IV of the Radioactive Gas Release Permit. e. Record all Gas Decay Tank Pressures every 15 minutes while reieaseis in progress. (Attachment
7) 10. Record a complete set of readings every 15 minutes on the Data Table in Part IV o1'tl1e Radioactive Gas Release Permit. II. WHEN the ressure of the Gas Decay Tank being released reaches 6 to 8 psig, terminate the release as follows: a. Close RCV-014 by reducing the hand loader pressure to zero. b. Verify the valve stem position indicator on RCV-0l4 indicates the valve is fully closed. c. Record final set of readings on the Data Tabie in Part IV of the Radioactive Gas Re!ease Permit. d. Record final set of Gas Decay Tank Pressures (Attachment 7),

... "." Procedure No.: Procedure Title: Page: 16 Waste Gas Disposal System Approval Date: O-OP-061.14 Controlled Radioactive Gas Release 9/27/07 INITIALS CK'D VERIF ----SNPOSNPO SNPO RO 7.1,2 (Conrd) 12. Restore the Gas Decay Tank alignment using Part B of the attachment completed in Substep 7.1.2.5 above. 13. Return the completed Radioactive Release Permit to the Chemistry Department upon completion of the release. 14. IF 4 is operable.

THEN reset the

p. rocess Radl.'ation Monitor R-14 High I Alarm setpoint AND Warning Limit by performing the following.
a. Slide R-14 drawer forward to gain access to the thumbwheel switches.

I NOTES. I RO RO RO RO til The thumbwheel switch settings are used to select the setpofnt as follows: I I I " I 1. Forward switch setting = digit 2. Middle switch setting::::

decimal and digit I I 3. Rear switch setting::::

exponent For example: a setting of 4.03 is equal to 4.0 X 1cT or 4 Kcpm; a setting of 1.05 is I equal to 1.0 X 10 5 or 100 Kcpm.

b. Position the High Alann setpoint thumbwheel switches to the R-14 High Alarm specified on the R*14 drawer. c. Position the Warning Limit thumbwheel switches to the R-14 Warning Limit specified on the R-14 drawer. d. Close the R-14 drawer. e. Depress the HIGH ALARM pushbutton ANDyerifY the digital display CPM indication equals the High Alarm setpoint on the R-14 drawer. f. Release the HIGH ALARM pushbutton.
g. Depress the WARNING LIMIT pushbutton D verifY the digital display CPM indication equals the Warning Imit on the drawer. W97'JE I {m Ids Procedure No.:

.. 061.14 INITIALS CK'D VERlF RO RO Procedure Title: Page: 17 Waste Gas Disposal System Approyal Date: Controlled Radioactive Gas Release 9/27/07 7.1.2.14 (Cont'd) h. Release the W ARNINO LIMIT pushbutton.

i. Depress the SOURCE CHECK pushbutton AND verify the digital display CPM indication responds to the Source. 15. IF Plant Vent Monitor Channel is inoperable AND no more gas releases are to be performed.

THEN dIrect I&C Maintenance to remove the following jumpers on in QR-66. a. TB600 from Terminal 1 to Relay K850 Cl. b. TB600 from Terminal 2 to Relay K850 C2. c. WHEN the jumpers are removed. THEN remove the CAUTION tag from the front of the drawer. . 16. Ensure log entries specified in Subsection 2.2 are recorded.

17. Ensure the QA Record Page is completed for this subsection.

I .

Procedure No.: Procedure Title: Page: 18 Waste Gas Disposal System Approval Date: O-OP-061.14 Controlled Radioactive Gas Release 9127/07 II QA RECORD PAGE II (Page I of 1) Procedure Revision Date 5 I 11 / OJ 7,1 Controlled Radioactive Gas 7.1.1.2 Gas Release Permit Number: Q"'t -tJl Gas Decay Tank A(!} C 0 E F (Circle one) 7.1.2,6 Gas Release Permit er: 0<=r-"1 Gas Decay Tank A C D E F (Circle one) REMARKS: Datetrime Started I Daternme Completed:

/ PERFORMED BY {Print) INITIALS INDEPENDENT VERIFY (Print) INITIALS I have reviewed this procedure subsection and it has been satisfactorily performed.

Deviations Of OTSCs used to perform this procedure are listed under Remarks. REVIEWED BY: Date: Reactor Operator or Designee END OF TEXT iN97; ,Ids Appendix C Facility:

Task Title: Job Performance Measure Worksheet

_T-'--u=:.:rc.:...:k:.=.ey.L....:-P--=o.;.:.in.:..:,.t

_______ Task No: _R_es--Lp_o_n_d_to_A_TW_S_Lo_c_a_lIL-y

__ JPM No: KIA

Reference:

001 A2.13 RO 4.4 SRO 4.6 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Form ES-C-1 14028009500 JPM I Simulated Performance X Actual Performance

Classroom Simulator Plant X -----------------------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • 4-EOP-FR-S.1 Response to Nuclear Power Generation/ATWS, is in progress on UNIT 4 Task Standard:
  • Local actions have been implemented to trip the Unit 4 Reactor Required Materials:
  • None General

References:

  • 4-EOP-FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS NUREG 1021 Rev 9 Appendix C AppendixC Page 2 of 8 Form ES-C-1 Initiating Cue: You have been directed to proceed to the Unit 4B MCC room and take local actions to trip the Unit 4 Reactor.
  • Open the 4A and 4B MG set generator output breakers.
  • Open the 4A and 4B MG set motor input breakers.

Time Critical Task: No Validation Time: 10 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I AppendixC Page 3 of 8 Form ES-C-1 I Denote critical steps with a check mark(T) Start Time , STEP 1 Examinee proceeds to the Unit 4B MCC Room SAT --UNSAT --Standard:

Examinee proceeds to the Unit 4B MCC Room Comment STEP 2 Examinee locates the Unit 4 Reactor Trip Breakers SAT --UNSAT --Standard:

The Unit 4 Reactor Trip Breakers have been located When asked, provide the following cue for the Unit 4 A and B Reactor Trip Breakers:

Cue The red "CLOSED" flag is indicated for the Unit 4 A and B Reactor Trip Breakers.

Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of8 Form ES-C-1 STEP 3 Examinee locally opens the Unit 4 Reactor Trip Breakers.

SAT --T (4-EOP-FR-S.1 RNO Step 7a) UNSAT --The Unit 4A and B Reactor Trip Breakers have been opened by Standard:

depressing the TRIP button on the front of the Unit 4A and B Reactor Trip Breakers When the examinee demonstrates opening each of the breakers by Cue depressing the trip button on the front of the Unit 4A and B Reactor Trip Breakers, provide the following cue: The red "CLOSED" flag is off, the green "OPEN" flag is indicated.

Comment EXAMINER NOTE: The Unit 4 A and B Reactor Trip Breakers may be opened in any order STEP 4 Examinee locates the Unit 4 Reactor Trip Bypass Breakers SAT --UNSAT --Standard:

The Unit 4 Reactor Trip Breakers Bypass have been located Comment NUREG 1021 Rev 9 Appendix C I AppendixC Page 5 of8 Form ES-C-1 I STEP 5 Examinee verifies the Unit 4 Reactor Trip Bypass Breakers are SAT opened. --(4-EOP-FR-S.1 RNO Step 7a) UNSAT --Standard:

The Unit 4A and B Reactor Trip Bypass Breakers have been verified opened When asked, provide the following cue for the Unit 4A and B Reactor Trip Bypass Breakers:

Cue "The Unit 4A and B Reactor Trip Bypass Breakers are withdrawn from the cubicle as shown; the green "OPEN" flag is indicated." Comment EXAMINER NOTE: The Unit 4 Reactor Trip Breakers are normally racked out STEP 6 Examinee locates the Unit 4A and B MG Set Input and Output SAT Breakers --UNSAT --Standard:

The Unit 4 A and B MG Set Input and Output Breakers have been located When asked, provide the following cue individually for the Unit 4A and Cue B MG Set Input and Output Breakers:

The red "CLOSED" light is ON, the green "OPEN" light is OFF Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 8 Form ES-C-1 STEP 7 Examinee opens the Unit 4A and B MG set generator output breakers.

SAT --T (4-EOP-FR-S.1 RNO Step 7a) UNSAT --Standard:

The Unit 4A and B MG set generator output breakers have been opened by turning each of the breaker control switches to TRIP, When the examinee demonstrates opening the breaker by turning the breaker control switch to "TRIP", provide the following cue for each of Cue the Unit 4A and B MG set generator output breakers:

The red "CLOSED" light is OFF, the green "OPEN" light is ON Comment EXAMINER The Unit 4 A and B MG set generator output breakers may be opened NOTE: in any order STEP 8 Examinee opens the Unit 4 A and B MG set motor input breakers.

SAT --T (4-EOP-FR-S.1 RNO Step 7a) UNSAT --Standard:

The Unit 4A and B MG set generator input breakers have been opened by turning each of the breaker control switches to "TRIP", When the examinee demonstrates opening the breaker by turning the breaker control switch to "TRIP", provide the following cue for each of Cue the Unit 4A and B MG set generator input breakers:

The red "CLOSED" light is OFF, the green "OPEN" light is ON Comment EXAMINER The Unit 4A and B MG set motor input breakers may be opened in any NOTE: order Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner.

STOP Stop Time ___ _ NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 8 Form ES-C-1 I Verification of Completion Job Performance Measure No. JPM I Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • 4-EOP-FR-S.1 Response to Nuclear Power Generation/ATWS, is in progress on UNIT 4 INITIA TING CUE: You have been directed to proceed to the Unit 4B MCC room and take local actions to trip the Unit 4 Reactor.
  • Open the 4A and 4B MG set generator output breakers.
  • Open the 4A and 4B MG set motor input breakers.

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C W97/daj/ev/ab Florida Power & Light Company Turkey Point Nuclear Plant . Unit 4 Title: Response to Nuclear Power Generation/ATWS Safety Related Procedure Responsible Department:

Revision Approval Date: Operations 1/23/06C RTSs 94-1295P, 96-0878P, 97-0716P.

97-1055P, 97-1522P, 98-0633P 98-0855P, 98-1130P, 05-0627P PCIM92-073 Procedure Noo: Procedure Title: Page: 2 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/ATWS 1I23/06C LIST OF EFFECTIVE PAGES Revision Page Date 1 01l23/06C 2 01l23/06C 3 01123/06 4 01123/06 5 01123/06 6 01123/06 7 01123/06 8 01l23/06C 9 01123/06 10 01123/06 11 01123/06 12 01123/06 W97/da o/ev/ab Procedure Noo: Procedure Title: Page: 3 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/ATWS 1123/06 1.0 PURPOSE 1.1 This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shutdown.

1.2 This procedure is applicable when directed by EOP entry conditions.

2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 This procedure is entered from: 2.1.1 E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1, when reactor trip is not verified and manual trip is not effective.

2.1.2 F-O.l, SUB CRITICALITY Critical Safety Function Status Tree on either a RED or an ORANGE condition.

3.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS 3.1 References W97/da o/ev/ab 3.1.1 Technical Specifications for Turkey Point Unit 3 and Unit 4 3.1.2 Turkey Point Unit 3 and Unit 4 Final Safety Analysis Report 3.1.3 As-built plant drawings 3.1.4 Procedures

1. SACRG-1, Severe Accident Control Room Guideline Initial Response 2. 4-0P-075, Auxiliary Feedwater System 3.1.5 Plant ChangelModifications
1. PCIM 92-073, Addition of Reverse Power Relays and Main Generator Protection Modifications.

Procedure No.: Procedure Title: Page: 4 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/ATWS 1123/06 3.1.6 Miscellaneous Documents

1. Generic Technical Guidelines developed by the Westinghouse Owners Group (WOG), Revision 2. This consists of the following documents:
a. Low pressure version of the WOG Optimal Recovery Guidelines, Status Trees, and Functional Restoration Guidelines
b. Background documents for each low pressure version Optimal Recovery Guidelines, Status Trees, and*Functional Restoration Guidelines
c. WOG Emergency Response Guidelines Executive Volume d. WOG Emergency Response Guidelines Maintenance Program Summary 2. PTN-ENG-SENS-98-047, AFW Pump Low-Flow Operating Restrictions 3.2 Records Required 3.2.1 None 3.3 Commitment Documents 3.3.1 None W97lda*/ev/ab Procedure No.: Procedure Title: Page: 5 Approval Date: 4-EOP-FR-S.1 Response to Nuclear Power GenerationlATWS 1/23/06 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Reps should not be tripped with reactor power GREA TER THAN 5%.

I I Steps 1 and 2 are IMMEDIA TE ACTION steps. I -------------------------

1 Verify Reactor Trip

  • Rod bottom lights -ON
  • Heactor trip and bypass breakers -OPEN
  • Rod position indicators

-AT ZERO

  • Neutron flux -DECREASING 2 Verify Turbine Trip 3 W97/daj/ev/ab
a. All turbine stop valves -CLOSED b. Verify Moisture Separator Steam Valves -CLOSED
  • Reheater Timing Valves
  • MSR Purge Steam Valves Check AFW Pumps -All RUNNING Perform the following:
a. Manually trip reactor. b. IF reactor will NOT trip, THEN ensure control rod insertion in Auto or Manual. a. Perform the following: 1 ) Manually trip the turbine. 2) IF turbine will NOT trip, THEN close main steamline isolation and bypass valves. 3) Go to Step 3. b. Perform the following:
1) Manually close valves. 2) IF any MSR valve can NOT be closed, THEN close main steamline isolation and bypass valves. Manually open steam supply valves.

Procedure No.: Procedure Title: Page: 6 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power GenerationlATWS 1/23/06 1 STEP r 1 ACTION/EXPECTED RESPONSE r 1 RESPONSE NOT OBTAINED r 4 Initiate Emergency Boration Of ReS a. Verify charging pumps -AT LEAST ONE RUNNING IN MANUAL b. Stop makeup system c. Manually start Boric Acid Pump 4A or 4B c. Align charging pump suction to the RWST as follows: 1) Hold closed LCV-4-115C control switch. 2) Direct an operator to open Breaker 40669 for LCV-4-115C.

3) WHEN 40669 is open, THEN release LCV-4-115C control switch. 4) Go to Step 4e. d. Open Emergency Boration Valve, d. Perform the following:

MOV-4-350

1) Open Boric Acid To Blender, FCV-4-113A.
2) Open Blender Flow To Charging Pump, FCV-4-113B.
3) Locally open Manual Emergency Boration Valve, 4-356. 4) WHEN Manual Emergency Boration Valve, 4-356, is open, THEN close Blender To Charging Pump, FCV-4-113B.
5) Continue with Step 4e. e. Open Charging Flow To Regen Heat Exchanger, HCV-4-121
f. Verify Loop A Charging Isolation, f. Open Loop C Charging Isolation, CV-4-310A

-OPEN CV-4-310B.

g. Establish emergency boration flow g. Start additional charging pumps AND
  • FI-4-110 -GREATER THAN 60 GPM align valves as necessary to establish emergency boration flow.
  • FI-4-122A

-GREATER THAN 45 GPM W97/daj/ev/ab Procedure No.: Procedure Title: Page: 7 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generationl ATWS 1/23/06 5 ACTION/EXPECTED RESPONSE Check PRZ Pressure -LESS THAN 2335 PSIG 6 Verify Containment Ventilation -ISOLATED W97/daj/ev/ab

a. Verify Unit 4 containment purge exhaust and supply fans -OFF b. Verify Containment Purge Supply and Exhaust Isolation valves -CLOSED
  • POV-4-2600
  • POV-4-2601
  • POV-4-2602
  • POV-4-2603
c. Verify Containment Instrument Air Bleed Isolation valves -CLOSED
  • CV-4-2819
  • CV-4-2826 RESPONSE NOT OBTAINED Perform the following:
a. Verify PRZ PORVs and block valves open. b. IF PRZ PORVs and block valves are NOT open, THEN open PRZ PORVs and block valves until PRZ pressure less than 2135 psig. b. IF any purge valve can NOT be closed, THEN pull fuse(s) for any open purge valve(s) from behind VPB:
  • XEP for POV-4-2600
  • XLAG for POV-4-2601
  • XEQ for POV-4-2602
  • XLAH forPOV-4-2603
c. IF neither valve can be closed, THEN locally close Containment Air Ble.ed to Purge Air Return Line Isolation, MPAS-4-005.

Procedure No.: Procedure Title: Page: 8 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power GenerationlATWS 1I23/06C ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If an SI signal exists or occurs and the reactor is subcritical, proper safeguards equipment alignment is required to be verified using Attachment 3 of 4-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure.

7 Check If The Following Trips Have Occurred W97/daj/ev/ab

a. Reactor trip b. Turbine trip c. Mid and East GCBs -OPEN (Normally 30 seconds delay) a. In 4B MCC room, locally trip reactor as follows:
  • Open AlB MG set generator output breakers.
  • Open AlB MG set motor input breakers.
b. Locally trip turbine at turbine front standard.
c. Perform the following:
1) Manually open breakers.
2) IF breakers do NOT open THEN actuate Emergency Gen Bkr Trip Switch for the affected breaker(s).
3) IF breaker position indication is NOT available AND turbine speed is NOT decreasing, THEN direct Field Operator to perform the following:

a) Obtain key 17 from the Shift Manager key locker. b) Locally trip Mid and East GCBs from the switchyard.

  • 8W88
  • 8W65 Procedure No.: Procedure Title: Page: 9 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/ATWS 1123/06 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I NOTE I I When adverse containment conditions exist, Gamma-Metrics indication needs to be used. I 8 Monitor Reactor Subcritical
a. Power range channels -LESS THAN 5% b. Intermediate range channels -NEGATIVE STARTUP RATE c. Observe Caution prior to Step 17 and go to Step 17 CAUTION a. Observe Caution prior to Step 9 and go to Step 9. b. Observe Caution prior to Step 9 and go to Step 9. If CST level decreases to less than 10%, makeup water sources for CST will be necessary to maintain secondary heat sink. 9 Monitor S/G Levels W97/daj/ev/ab
a. Narrow range level in at least one GREATER THAN 6%[32%] b. Control feed flow tO'maintain narrow range level between 15%[32%] and 50% a. Perform the following:
1) Establish total feedwater flow greater than 750 gpm. 2) IF feed flow NOT greater than 750 gpm, THEN manually start pumps and align valves to establish greater than 750 gpm. 3) Maintain total feedwater flow greater than 750 gpm until narrow range level greater than 6% [32%] in at least one S/G.

Procedure No.: Procedure Title: Page: 10 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/ATWS 1/23/06 1 STEP r 1 ACTION/EXPECTED RESPONSE 10 Verify All Dilution Paths -ISOLATED 11 12 a. Check FR-4-113 -NO PRIMARY WATER FLOW Check For Reactivity Insertion From Uncontrolled RCS Cooldown *

  • RCS temperatures

-DECREASING IN AN UNCONTROLLED MANNER OR Any S/G pressure -DECREASING IN AN UNCONTROLLED MANNER Check Main Steamline Isolation AND Bypass Valves -CLOSED 13 Identify Faulted S/G(s) W97/daj/ev/ab

a. Check pressures in all S/Gs *
  • ANY S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR ANY S/G COMPLETELY DEPRESSURIZED r 1 RESPONSE NOT OBTAINED a. Perform the following:
1) Close Demin Water To Blender, FCV-4-114A.
2) Locally close the following valves:
  • Primary Water To Chemical Addition Tank 4-359A
  • Primary Water From Chemical Addition Tank 4-272
  • Manual Dilution Valve, 4-353A Perform the following:
a. Stop any controlled cooldown.
b. Go to Step 15. Manually close valves. a. Go to Step 15. r Procedure No.: Procedure Title: Page: 11 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/ATWS 1123/06 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTIONS
  • At least one S/G must be maintained available for ReS cooldown.
  • If all S/Gs are faulted, at least 25 gpm feed flow should be maintained to each S/G.
  • If the AFW pumps are the only available source of feed flow, the steam supply to the AFW pumps must be maintained from at least one S/G. 14 Isolate Faulted S/G{s) W97/daj/ev/ab
a. Isolate main feed line
  • Close feedwater bypass valve b. Isolate AFW flow c. Verify SI -RESET d. Verify steam supply aligned to both trains of AFW pumps from intact S/G(s) e. Locally perform the following
1) Open AFW pump steam supply MOV breaker on faulted S/G(s) 2) Close AFW pump steam supply MOV on faulted S/G(s) f. Verify S/G dump to atmosphere valve -CLOSED g. Verify S/G blowdown isolation CLOSED h. Verify S/G sample lines -ISOLATED*
a. Locally isolate main feedline.
b. Locally isolate. c. Reset SI. d. Reposition AFW steam supply connect valves to provide steam from intact S/G(s) to all AFW pumps. Maintain steam flow to AFW pumps while repositioning cross-connect valves.
  • AFSS-4-006
  • AFSS-4-007
f. Perform the following:
1) Place steam dump to atmosphere controller in manual and close the steam dump to atmosphere valve. 2) IF steam dump to atmosphere can NOT be closed, THEN locally isolate steam dump to atmosphere valve.

Procedure No.: Procedure Title: Page: 12 Approval Date: 4-EOP-FR-S.l Response to Nuclear Power Generation/

ATWS 1123/06 15 16 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTIONS

  • These cautions apply to AFW pump operation throughout all of the EOPs.
  • If two AFW pumps are operating on a single train, one of the pumps needs to be shut down within one hour of the initial start signal using 4-0P-075, AUXILIARY FEEDWA TER SYSTEM, Subsection 6.2.
  • If two AFW trains are operating and one of the AFW pumps has been operating with an average flow of less than 60 gpm, the pump should be shut down within one hour of operating at less than 60 gpm using 4-0P-075, AUXILIARY FEEDWATER SYSTEM, Subsection 6.2. Check Core Exit TCs -LESS THAN 1200°F Verify Reactor Subcritical
a. Power range channels -LESS THAN 5% b. Intermediate range channels -NEGATIVE STARTUP RATE CAUTION IF core exit temperatures greater than 1200°F and increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, Step 1. Perform the following:
1) Continue to borate. 2) IF boration NOT available, THEN allow RCS to heat up. 3) Perform actions of other Function Restoration Procedures in effect which do NOT cool down or otherwise add positive reactivity to the core. 4) Return to Step 4. Soration should continue during subsequent actions until adequate shutdown margin is obtained.

17 Return To Procedure And Step In Effect END OF TEXT FINAL PAGE W97/daj/ev/ab Appendix C Facility:

Task Title: Job Performance Measure Worksheet Turkey Point Task No: Realign Opposite Units HHSI Pumps JPM No: KIA

Reference:

006 A4.05 RO 3.9 SRO 3.8 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Form ES-C-1 24050032500 JPMJ Method of testing: _____________________________

_ Simulated Performance

________ Actual Performance

__________

_ Classroom Simulator Plant X ---------------------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Both Unit 3 and 4 are in MODE 3 following a Loss of Offsite Power.
  • Unit 3 A Diesel Generator is OOS for maintenance.
  • Unit 3 B Diesel Generator has sustained an electrical fault resulting in an 86 lockout.
  • A Small Break LOCA is in progress in Unit 3.
  • Both Unit 3 HHSI pumps are unavailable.
  • The Unit 3 Unit Supervisor has implemented 3-EOP-ECA-0.2, Loss of All AC Power Recovery with SI Required Task Standard:
  • 3-EOP-ECA-0.2 Loss of All AC Power Recovery with SI Required, ATTACHMENT 1 is complete.

Required Materials:

  • 3-EOP-ECA-0.2 Loss of All AC Power Recovery with SI Required, ATTACHMENT
1. General

References:

  • 3-EOP-ECA-0.2 Loss of All AC Power Recovery with SI Required, ATTACHMENT
1. NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 9 Form ES-C-1 Initiating Cue:
  • You have been directed to perform 3-EOP-ECA-0.2 ATTACHMENT 1, REALIGNMENT OF UNIT 4 HIGH-HEAD SI PUMP SUCTION TO UNIT 3 RWST Time Critical Task: No Validation Time: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of9 Form ES-C-1 I SIMULATOR SETUP NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 9 Form ES-C-1 Denote critical steps with a check mark(T) Start Time Obtain required materials.

STEP 1 SAT --UNSAT --Standard:

Procedure, ladder and Unit 4 ICCS keys are obtained.

Provide the Examinee with a copy of 3-EOP-ECA-0.2 ATTACHMENT 1, Cue REALIGNMENT OF UNIT 4 HIGH-HEAD SI PUMP SUCTION TO UNIT 3 RWST. Comment EXAMINER Once Examinee identifies the location of the ladder and Unit 41CCS NOTE: keys, tell the Examinee that it is not necessary to obtain the keys and ladder for this simulation.

Open SI pump suction inter-tie valves STEP 2 SAT --T (3-EOP-ECA-0.2 Attachment 1 Step 1.a) UNSAT --Standard:

Examinee opens 870A, High-Head SI Pump Suction Header Sectionalizing Valve and 870B, SI Pump Suction Cross-Connect Valve" When asked provide the following cue, "870A, High-Head SI Pump Suction Header Sectionalizing valve stem Cue has fully risen and has reached the end of the stroke, the valve operated smoothly." "870B, SI Pump Suction Cross-Connect Valve both valve stem has fully risen and has reached the end of the stroke, the valve operated smoothly." Comment EXAMINER Both 870A, High-Head SI Pump Suction Header Sectionalizing valve NOTE: AND 870B, SI Pump Suction Cross-Connect Valve are located under the deck plate immediately north of the Unit 4A HHSI pump. NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of9 Form ES-C-1 I STEP 3 Unlock and open high-head SI Pump Mini Flow Recirc Cross-Connect SAT Valves 892A and 8928. --if (3-EOP-ECA-0.2 Attachment 1 Step 1.b) UNSAT --Standard:

Examinee unlocks and opens both of the High-Head SI Pump Mini Flow Recirc Cross-Connect Valve 892A and 8928 When asked provide the following cue, "High-Head SI Pump Mini Flow Recirc Cross-Connect Valve 892A valve Cue stem has fully risen and has reached the end of the stroke, the valve operated smoothly." "High-Head SI Pump Mini Flow Recirc Cross-Connect Valve 8928 valve stem has fully risen and has reached the end of the stroke, the valve operated smoothly." Comment Unlock and close Unit 4 RWST Outlet valve 4-864C. STEP 4 (3-EOP-ECA-0.2 Attachment 1 Step 1.c) SAT --if UNSAT --Standard:

Examinee unlocks and closes Unit 4 RWST Outlet valve 4-864C Cue When asked provide the following cue, "Unit 4 RWST Outlet valve 4-864C has been unlocked and the valve stem has fully lowered and has reached the end of the stroke, the valve operated smoothly." Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 9 Form ES-C-1 STEP 5 Turn ON control power AND close Unit 4 High-Head SI Pump Recirc SAT To RWST valves MOV-4-856A and MOV-4-8568.

--(3-EOP-ECA-O.2 Attachment 1 Step 1.d) UNSAT --Examinee simulates making notification to the Control Room to turn Standard:

ON control power AND close Unit 4 High-Head SI Pump Recirc To RWST valves MOV-4-856A and MOV-4-8568 When asked provide the following cue, "The Control Room reports the Cue Unit '4 High-Head SI Pump Recirc To RWST valves MOV-4-856A and MOV-4-8568 control power has been turned ON and both valves are CLOSED." Comment STEP 6 Turn OFF control power to Unit 4 High-Head SI Pump Recirc To SAT RWST valves MOV-4-856A and MOV-4-856B.

--(3-EOP-ECA-0.2 Attachment 1 Step 1.e) UNSAT --Examinee simulates making notification to the Control Room to turn Standard:

OFF control power to Unit 4 High-Head SI Pump Recirc To RWST valves MOV-4-856A and MOV-4-8568 When asked provide the following cue, "The Control Room reports the Cue Control Power to Unit 4 High-Head SI Pump Recirc To RWST valves MOV-4-856A and MOV-4-8568 has been turned OFF." Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 9 Form ES-C-1 I STEP 6 Notify Unit 3 RCO That The Attachment Has Been Completed.

SAT --(3-EOP-ECA-0.2 Attachment 1 Step 2) UNSAT --Standard:

Examinee simulates making notification the attachment has been completed Comment Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner.

STOP Stop Time ----NUREG 1021 Rev 9 Appendix C AppendixC Page 8 of 9 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM J Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________________________

_ NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Both Unit 3 and 4 are in MODE 3 following a Loss of Offsite Power.
  • Unit 3 A Diesel Generator is OOS for maintenance.
  • Unit 3 B Diesel Generator has sustained an electrical fault resulting in an 86 lockout.
  • A Small Break LOCA is in progress in Unit 3.
  • Both Unit 3 HHSI pumps are unavailable.
  • The Unit 3 Unit Supervisor has implemented 3-EOP-ECA-0.2, Loss of All AC Power Recovery with SI Required INITIA TlNG CUE:
  • You have been directed to perform 3-EOP-ECA-0.2 ATTACHMENT 1, REALIGNMENT OF UNIT 4 HEAD SI PUMP SUCTION TO UNIT 3 RWST Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Task Title: Job Performance Measure Worksheet

_T_ur_k_e"-y---:P_o_in_t

_______ Task No: Locally Start a Diesel Generator JPM No: -------------

KIA

Reference:

064 A4.01 RO 4.0 SRO 4.3 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Form ES-C-1 14200014300 JPM K Simulated Performance X Actual Performance Classroom Simulator Plant X ----------------------Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

  • Unit 3 and Unit 4 are both in MODE 3 following a trip from 100%
  • The Control Room has been evacuated using 0-ONOP-1 05, Control Room Evacuation Task Standard:
  • The 48 Diesel Generator placed in LOCAL AND.
  • The 48 Diesel Generator is running AND
  • The 48 4kv bus is energized from the 48 Diesel Generator.

Required Materials:

  • 0-ONOP-105, Control Room Evacuation, Attachment 6
  • Synchronization plug General

References:

  • 0-ONOP-105, Control Room Evacuation, Attachment 6 NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 11 Form ES-C-1 Initiating Cue:
  • You have been directed to perform 0-ONOP-105, Control Room Evacuation, Attachment 6 steps 16 and 17.
  • 0-ONOP-105, Control Room Evacuation, Attachment 6 step 16.a has been completed by the Unit 4 RO.
  • You have already been obtained a Radio, the NLO key ring, and a high voltage kit. Time Critical Task: No Validation Time: 30 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I AppendixC Page 3 of 11 Form ES-C-1 I SIMULATOR SETUP NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 11 Form ES-C-1 Denote critical steps with a check mark(T) Start Time STEP 1 Obtain required materials SAT --UNSAT --Standard:

Examinee obtains 0-ONOP-105, Control Room Evacuation, Attachment 6 i Cue Provide the Examinee with a copy of 0-ONOP-105, Control Room Evacuation, page 4 and 5 of Attachment

6. Comment STEP 2 Place 48 EDG Master Control Switch, CS-1, to LOCAL. SAT --T (0-ONOP-105, Attachment 6 step 16.b) UNSAT --Standard:

Examinee places the Master Control Switch CS-1 to the LOCAL position Cue When the examinee places CS-1 to local, provide the following cue: "Master Control Switch CS-1 has been placed to LOCAL". Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 11 Form ES-C-1 I STEP 3 Place Isolation Switch, CS-19, to ISOLATE SAT --if (0-ONOP-105, Attachment 6 step 16.c) UNSAT --Standard:

Examinee places the Isolation Switch CS-19 to the ISOLATE position When the examinee places Isolation Switch CS-19 to ISOLATE, provide Cue the following cue: "Isolation Switch, CS-19, has been placed to ISOLATE" Comment STEP 4 Place Isolation Switch, CS-18, to ISOLATE SAT --if (0-ONOP-105, Attachment 6 step 16.d) UNSAT --Standard:

Examinee places the Isolation Switch CS-18 to the ISOLATE position When the examinee places Isolation Switch CS-18 to ISOLATE, provide Cue the following cue: "Isolation Switch, CS-18, has been placed to ISOLATE" Comment NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 11 Form ES-C-1 STEP 5 Check 4B EDG -running SAT --T (0-ONOP-105, Attachment 6 step 17) UNSAT --Standard:

Examinee observes the 4B EDG is NOT running Cue When asked provide the following cue, "The 4B Diesel room is quiet, 4B Diesel Generator output voltage is 0, 4B Diesel Generator frequency is 0." Comment EXAMINER Examinee verifies the 4B Diesel Generator NOT running and NOTE: transitions to step 17 RNO column. STEP 6 Verify 4B EDG 186G UO Relay -RESET. SAT --T (0-ONOP-105, Attachment 6 step 17 RNO a) UNSAT --Standard: Examinee places the 4B EDG 186 G Lockout Relay switch to RESET. Cue When asked provide the following cue, "The Lockout Relay handle positioned to the left at a 45° angle with an ORANGE flag displayed. (Indicating the Lock-out Relay is TRIPPED) After the examinee has simulated resetting the Diesel Generator Cue Lockout Relay by turning the switch to the right provide the following cue, "Lockout Relay handle is at a 90° angle and locked into place, the flag indicates BLACK." (Indicating the Lock-out Relay is RESET) Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 11 Form ES-C-1 I STEP 7 Restart 4B EDG using Emergency Start pushbutton.

SAT --T (O-ONOP-105, Attachment 6 step 17 RNO b) UNSAT --Standard:

Examinee starts the 4B EDG by pushing the Emergency Start Pushbutton After the examinee has simulated starting the Diesel Generator by Cue pushing the Emergency Start Pushbutton provide the following cue, "The 4B Diesel engine has started, speed is 900 rpm, 4160 volts and 60 Hz." Comment STEP 8 Place synchronizing switch for diesel output breaker to ON. SAT --T (O-ONOP-105, Attachment 6 step 17 RNO c) UNSAT --Standard:

Examinee places the Synchronizing switch for diesel output breaker to ON. After the examinee has simulated placing the synchronizing switch for Cue diesel output breaker to ON provide the following cue, "The synchroscope in at 12, the synchronizing lights are OFF." Comment EXAMINER There is only one (1) synchronization plug to operate the sync switch, it may be located at the other Unit 4 EDG control room. NOTE: The Unit 4B EDG will be connected to a de-energized bus. NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 11 Form ES-C-1 STEP 9 Verify with the Shift Manager in the TSC actions are complete prior to SAT energizing the 4B 4kv bus. --(0-ONOP-105, Attachment 6 step 17 RNO d) UNSAT --Standard:

Examinee simulates consulting the TSC as to the status of completion of 0-ONOP-1 05 steps. Cue When asked provide the following cue, "Steps 1 through 23 of Attachment 5 and Steps 1 through 5 of Attachment 8 are complete." Comment EXAMINER The Shift Manager would normally be in the TSC coordinating Control NOTE: Room evacuation efforts at this time. STEP 10 Close 4B EDG Breaker Control4C12B, for 4AB21. SAT --T (0-ONOP-105, Attachment 6 step 17 RNO e) UNSAT --Standard:

Examinee places the 4B EDG Breaker 4AB21 handswitch to CLOSE When examinee simulates placing the 4B EDG Breaker Control Cue 4C12B to close, provide the following cue for the 4B EDG Breaker 4AB21 , "Red light is "ON" and the Green light is "OFF" and an orange flag is indicated above the control switch. Comment NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 11 Form ES-C-1 I STEP 11 Place synchronizing switch for diesel output breaker to OFF. SAT --(O-ONOP-105, Attachment 6 step 17 RNO f) UNSAT --Standard:

Examinee places the synchronizing switch for diesel output breaker to OFF. After the examinee has simulated placing the synchronizing switch for Cue diesel output breaker to OFF provide the following cue, "The synchronizing lights are OFF and the synchroscope is at the 10 o'clock position." Comment STEP 12 Notify Unit 4 RO to reload equipment as required by Attachment

4. SAT --(O-ONOP-105, Attachment 6 step 17 RNO g) UNSAT --Standard:

Examinee simulates notification of the Unit 4 RO to reload equipment as required by Attachment

4. Cue When asked provide the following cue, "The Unit 4 RD acknowledges to reload equipment as required by Attachment
4. Comment Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner.

STOP Stop Time ----NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 11 Form ES-C-1 Verification of Completion Job Performance Measure No. JPM K Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ----------------------------------

NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • Unit 3 and Unit 4 are both in MODE 3 following a trip from 100%
  • The Control Room has been evacuated using 0-ONOP-1 OS, Control Room Evacuation INITIA TING CUE:
  • You have been directed to perform 0-ONOP-105, Control Room Evacuation, Attachment 6 steps 16 and 17.
  • 0-ONOP-105, Control Room Evacuation, Attachment 6 step 16.a has been completed by the Unit 4 RO.
  • You have already been obtained a Radio, the NLO key ring, and a high voltage kit. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C
Retrieved from "https://kanterella.com/w/index.php?title=ML091740105&oldid=982781"