Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM … · 2012. 8. 31. · Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP NRC 2012 JPM S-1 Rev c.docx INITIAL CONDITIONS:

Appendix C JPM WORKSHEET Form ES-C-1

Page 1 of 6 CPNPP NRC 2012 JPM S-1 Rev c.docx

Facility: CPNPP JPM # NRC S-1 Task # RO1014 K/A # 003.AA1.02 3.6 / 3.4 SF-1 Title: Perform a Dropped Control Rod Recovery

Examinee (Print): Testing Method: Simulated Performance: Classroom: Actual Performance: X Simulator: X Alternate Path: X Plant: Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue. When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions: ABN-712, Rod Control System Malfunction, Section 3.0, Dropped or

Misaligned Rod in MODE 1 or 2, actions are complete through Step 3.3.15.e.

Control Bank D was last moved in the OUTWARD direction. Control Rod H8 is ready to be withdrawn.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following: RECOVER the dropped Control Rod per ABN-712, Rod Control System

Malfunction, Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2. START at Step 3.3.15.f.

Task Standard: Utilizing ABN-712, withdrew dropped Control Rod H8, and following a second dropped Control Rod tripped the Reactor from the Reactor Trip Switch on CB-10 and performed EOP-0.0A, Step 1 from memory.

Required Materials: ABN-712, Rod Control System Malfunction, Rev. 10-13. EOP-0.0A, Reactor Trip or Safety Injection, Rev. 8-7.

Validation Time: 5 minutes Completion Time: ________ minutes

Comments:

Result: SAT UNSAT

Examiner (Print / Sign): Date:



SIMULATOR SETUP BOOTH OPERATOR: INITIALIZE to IC-38 or any at 100% power Initial Condition and load Scenario File “LC20 NRC JPM 1”. PERFORM the following:

EXECUTE the following malfunctions: RD03H8, Dropped Control Rod. RP01, Automatic Reactor Trip Failure. RP13A, Manual Reactor Trip Switch at CB-07 DISABLED.

LOWER Turbine Load to1160 MWe and STABILIZE temperature. REMOVE Malfunction RD03H8, for Control Rod H8. EXECUTE remote function RDR03, PLACE and HOLD P/A Converter in MANUAL

position. ENSURE Control Bank D is at 215 steps. PERFORM any additional actions required per ABN-712, Steps 3.3.1 through

3.3.15.e. PLACE Control Rods D4, M12, D12, and M4 in DISCONNECT at the Rod

Disconnect Panel. EXECUTE the following during recovery actions:

During the rod recovery, EXECUTE malfunction RD03G13, Control Rod G13 Drop and RDO3H8, control Rod H8 Drop 5 seconds after Control Rod H8 Rod Bottom Light clears.

BOOTH OPERATOR NOTE:

After each JPM, RESET Rod Bank Update when Simulator is INITIALIZED. EXAMINER: PROVIDE the examinee with a copy of Procedure 1:

ABN-712, Rod Control System Malfunction. Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2. INITIAL through Step 3.3.15.e.

Appendix C JPM STEPS Form ES-C-1


- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-712, Section 3.0.

Perform Step: 1 3.3.15.f & 3.3.15.f.1)

WHEN moving affected rod for realignment, THEN perform the following:

Maintain TAVE within 2°F of TREF by controlling the following as necessary: Turbine Power Steam Dumps Boration Dilution

Standard: REVIEWED NOTE box in order to maintain TAVE within 2°F of TREF during Control Rod recovery.

Comment: SAT UNSAT

Perform Step: 2 3.3.15.f & 3.3.15.f.2)


Verify that only affected rod is moving.

Standard: VERIFIED that only Control Rod H8 moves during Control Rod recovery.

Comment: SAT UNSAT

Perform Step: 3 3.3.15.f & 3.3.15.f.3)


Ensure last movement of affected rod is in same direction as last movement of affected group.

Standard: VERIFIED per Initial Conditions that Control Bank D was last moved in the OUTWARD direction.

Comment: SAT UNSAT



Perform Step: 4 3.3.15.g

Slowly move affected rod until aligned with its group by DRPI indication.

Standard: WITHDREW Control Rod H8 to 215 steps as indicated on Control Bank D Demand Step Counter and PLACED 1/1-FLRM, CONTROL ROD MOTION CTRL to OUT position.

Comment: SAT UNSAT

Examiner Note: When the Rod Bottom Light for Control Rod H8 clears, two Control Rods (G13 and H8) will drop.

Perform Step: 5 RESPOND to Multiple Rod Control System Alarms.

Standard: DETERMINED Control Rods G13 and H8 have dropped and REFERRED to Step 3.3.1 RNO.

Comment: SAT UNSAT

Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 6 3.3.1.a) RNO

IF two or more rods dropped, THEN trip Reactor AND GO TO E0P-0.0A/B.

Standard: At CB-07, PLACED 1/1-RTC, RX TRIP Switch in TRIP and DETERMINED Reactor is NOT tripped.

Comment: SAT UNSAT

Perform Step: 7 3.3.1.a) RNO

IF two or more rods dropped, THEN trip Reactor AND GO TO E0P-0.0A/B.

Standard: At CB-10, PLACED 1/1-RT, RX TRIP Switch in TRIP and DETERMINED Reactor is tripped.

Comment: SAT UNSAT

Examiner Note: The following steps are from EOP-0.0A.

Perform Step: 8 1, 1.a, & 1st bullet

Verify Reactor Trip: Verify the following: Reactor trip breakers - AT LEAST ONE OPEN

Standard: OBSERVED 1/1-RTBAL & 1/1-RTBBL, RX TRIP BKR green OPEN lights LIT.

Comment: SAT UNSAT



Perform Step: 9 1, 1.a, & 2nd bullet

Verify Reactor Trip: Verify the following: Neutron flux - DECREASING

Standard: OBSERVED 1-NI-35B, IR CURRENT CHAN I and 1-NI-36B, IR CURRENT CHAN II are lowering.

Comment: SAT UNSAT

Perform Step: 10 1 & 1.b

Verify Reactor Trip: All control rod position rod bottom lights - ON

Standard: OBSERVED all Control Rods INSERTED on CTRL ROD POSN bezel.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT

STOP TIME:

Appendix C JPM CUE SHEET Form ES-C-1


INITIAL CONDITIONS: Given the following conditions:

ABN-712, Rod Control System Malfunction, Section 3.0, Dropped or Misaligned Rod in MODE 1 or 2, actions are complete through Step 3.3.15.e.

Control Bank D was last moved in the OUTWARD direction.

Control Rod H8 is ready to be withdrawn. INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

RECOVER the dropped Control Rod per ABN-712, Rod Control System Malfunction.

START at Step 3.3.15.f

CPNPP NRC 2012 JPM S-1 Procedure Rev c




Facility: CPNPP JPM # NRC S-2 Task # RO1305A K/A # 004.A2.02 3.2 / 3.2 SF-2 Title: Remove Excess Letdown from Service

Examinee (Print): Testing Method: Simulated Performance: Classroom: Actual Performance: X Simulator: X Alternate Path: Plant: Time Critical:


Initial Conditions: Given the following conditions: Excess Letdown was placed in service following closure of a Normal

Letdown Containment Isolation Valve. Excess Letdown flow was NOT aligned to the top of the Volume Control

Tank. A LCOAR was NOT initiated to track Excess Letdown flow. Seal Water Heat Exchanger flow does not require any adjustments.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following: REMOVE Excess Letdown from Service per SOP-103A, Chemical and

Volume Control System, Section 5.5.4, Removing Excess Letdown from Service.

Task Standard: Utilizing SOP-103A, removed Excess Letdown from service and adjusted Reactor Coolant Pump Seal Return flow.

Required Materials: SOP-103A, Chemical and Volume Control System, Rev. 17-26.


Comments:

Result: SAT UNSAT




SIMULATOR SETUP BOOTH OPERATOR: INITIALIZE to IC-37 or any at power Initial Condition and PERFORM the following:

PLACE Excess Letdown in service. ENSURE Excess Letdown NOT ALIGNED to the top of the VCT.

EXAMINER: PROVIDE the examinee with a copy of:

SOP-103A, Chemical and Volume Control System. Section 5.5.4, Removing Excess Letdown from Service.




Examiner Note: The following steps are from SOP-103A, Section 5.5.4.

Perform Step: 1 5.5.4.A

Place handswitch 1/1-8143, XS LTDN DIVERT VLV, in RCDT.

Standard: PERFORMED the following: PLACED 1/1-8143, XS LTDN DIVERT VLV to RCDT (critical). OBSERVED red RCDT light LIT (NOT critical).

Examiner Cue: Comment: SAT UNSAT

Perform Step: 2 5.5.4.B

IF excess letdown/seal water return flow was established to the top of the VCT (through the VCT Auxiliary spray nozzle), THEN realign flow to the charging pump suction header:

Standard: DETERMINED from Initial Conditions that Excess Letdown was NOT ALIGNED to the VCT.

Comment: SAT UNSAT

Perform Step: 3 5.5.4.C

CLOSE 1-HC-0123, XS LTDN HX FLO CTRL

Standard: ROTATED 1-HC-123, XS LTDN HX FLO CTRL potentiometer COUNTERCLOCKWISE to 0% position.

Comment: SAT UNSAT

Examiner Note: Closing either Excess Letdown Loop Isolation Valve meets the Critical Step requirements. Steps 4 and 5 may be performed in any order.

Perform Step: 4 5.5.4.D & 1ST bullet

CLOSE the loop isolation valves to the excess letdown heat exchanger. 1/1-8153, XS LTDN ISOL VLV

Standard: PERFORMED the following: PLACED 1/1-8153, XS LTDN ISOL VLV in CLOSE (critical). OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT



Perform Step: 5 5.5.4.D & 2nd bullet

CLOSE the loop isolation valves to the excess letdown heat exchanger. 1/1-8154, XS LTDN ISOL VLV

Standard: PERFORMED the following: PLACED 1/1-8154, XS LTDN ISOL VLV in CLOSE (critical). OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT

Examiner Note: Perform Steps 6 and 7 may be completed in any order.

Perform Step: 6 5.5.4.E & 1st bullet

Ensure the following charging pump suction high point vent valves are OPEN.

1-HV-8220, U1 CHRG PMP SUCT HI PNT VNT VLV 8220

Standard: OBSERVED 1-ZL-8220, CHRG PMP SUCT HI POINT VENT VLV red light LIT.

Comment: SAT UNSAT

Perform Step: 7 5.5.4.E & 2nd bullet

Ensure the following charging pump suction high point vent valves are OPEN.

1-HV-8221, U1 CHRG PMP SUCT HI PNT VNT VLV 8221

Standard: OBSERVED 1-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV red light LIT.

Comment: SAT UNSAT

Perform Step: 8 5.5.4.F

IF LCOAR ODA-308-13.1.31-2 was initiated to track Excess Letdown in service to the top of the VCT, THEN exit the LCOAR.

Standard: DETERMINED from Initial Conditions that a LCOAR was NOT INITIATED to track Excess Letdown.

Comment: SAT UNSAT

Perform Step: 9 5.5.4.G

Ensure handswitch 1/1-8143, XS LTDN DIVERT VLV, is in VCT.

Standard: PERFORMED the following: PLACED 1/1-8143, XS LTDN DIVERT VLV to VCT (critical). OBSERVED red VCT light LIT (NOT critical).

Comment: SAT UNSAT



Perform Step: 10 5.5.4.H

Adjust CCW to the Seal Water Heat Exchanger by throttling 1CC-0341, SL WTR 1-01 CCW RET ISOL VLV per TDM-901A. (Letdown heat exchanger valve room).

Standard: DETERMINED step is N/A from Initial Conditions.

Comment: SAT UNSAT

Perform Step: 11 5.5.4.I

Ensure No. 1 seal injection flow is between 6 and 10 gpm for each RCP. 1-FI-145, RCP 1 SEAL WTR INJ FLO 1-FI-144, RCP 2 SEAL WTR INJ FLO 1-FI-143, RCP 3 SEAL WTR INJ FLO 1-FI-142, RCP 4 SEAL WTR INJ FLO

Standard: OBSERVED No. 1 seal injection flow between 6 and 10 GPM per Reactor Coolant Pump:

1-FI-145, RCP 1 SEAL WTR INJ FLO 1-FI-144, RCP 2 SEAL WTR INJ FLO 1-FI-143, RCP 3 SEAL WTR INJ FLO 1-FI-142, RCP 4 SEAL WTR INJ FLO

Terminating Cue: This JPM is complete. Comment: SAT UNSAT

STOP TIME:




Excess Letdown was placed in service following closure of a Normal Letdown Containment Isolation Valve.

Excess Letdown flow was NOT aligned to the top of the Volume Control Tank.

A LCOAR was NOT initiated to track Excess Letdown flow.

Seal Water Heat Exchanger flow does not require any adjustments.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

REMOVE Excess Letdown from Service per SOP-103A, Chemical and Volume Control System, Section 5.5.4, Removing Excess Letdown from Service.



Facility: CPNPP JPM # NRC S-3 Task # RO1412 K/A # 025.AA1.02 3.8 / 3.9 SF-4P Title: Respond to Shutdown Loss of Coolant



Initial Conditions: Given the following conditions: Unit 1 is in MODE 3 with a boron concentration of 2500 ppm. Reactor Coolant System temperature is approximately 358°F. Reactor Coolant System pressure is approximately 280 psig. Entry into MODE 4 is about to be performed.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following: RESPOND to a lowering Pressurizer level per ABN-108, Shutdown Loss

of Coolant.

Task Standard: Utilizing ABN-108, responded to a Shutdown Loss of Coolant, isolated Letdown, and secured Pressurizer Heaters.

Required Materials: ABN-108, Shutdown Loss of Coolant, Rev. 4-5.


Comments:

Result: SAT UNSAT




SIMULATOR SETUP BOOTH OPERATOR: INITIALIZE to IC-39 and load scenario file “LC20 NRC JPM 3”, or any at MODE 3 Initial Condition (with plant conditions prior to MODE 4 entry) and PERFORM the following:

VERIFY Unit is in MODE 3. EXECUTE malfunction RC17A, Hot Leg #1 leak at 2000 gpm and LOWER

Pressurizer Cold Calibrated Level to less than 30% but greater than 17%. DELETE malfunction RC17A. LOWER Charging flow to less than Letdown flow. RE-EXECUTE malfunction RC17A, Hot Leg #1 leak at 500 gpm. ENSURE all Pressurizer Heaters are ON. FREEZE Simulator and MAINTAIN until examinee is ready. When either Letdown Isolation Valve is closed, DELETE malfunction RC17A.


ABN-108, Shutdown Loss of Coolant.




Examiner Note: The following steps are from ABN-108, Section 2.0.

Perform Step: 1 2.3.1.a

Verify Reactor Tripped: Reactor Trip and Bypass breakers – OPEN

Standard: VERIFIED Reactor Trip and Bypass breakers – OPEN.

Comment: SAT UNSAT

Perform Step: 2 2.3.1.b

Verify Reactor Tripped: All DRPI Rod Bottom lights – ON

Standard: VERIFIED All DRPI Rod Bottom lights – ON.

Comment: SAT UNSAT

Perform Step: 3 2.3.2.a

Verify Charging flow and Letdown Flow Status: Verify Charging flow - AT DESIRED FLOW RATE AND

GREATER THAN LETDOWN FLOW.

Standard: PERFORMED the following: OBSERVED 1-FI-132, LTDN FLO at 73 GPM (NOT critical). OBSERVED 1-FI-121A, CHRG FLO at 60 GPM (NOT critical). DEPRESSED 1-FK-121, CCP FLO CTRL, red OUTPUT (▲)

pushbutton until Charging flow is greater than Letdown flow (critical).

Comment: SAT UNSAT

Perform Step: 4 2.3.2.b

Verify Charging flow and Letdown Flow Status: Verify Pressurizer level – GREATER THAN OR EQUAL TO 30%

Standard: OBSERVED Pressurizer level hot calibrated and cold calibrated instruments and DETERMINED Pressurizer level less than 30%.

Comment: SAT UNSAT



Examiner Note: The following steps represent the Alternate Path of this JPM.

Perform Step: 5 2.3.2.b RNO

IF Pressurizer level is decreasing, THEN perform the following:

Standard: DETERMINED Pressurizer level is lowering and REFERRED to RNO actions.

Comment: SAT UNSAT

Examiner Note: Steps 6 through 10 may be performed in any order.

Perform Step: 6 2.3.2.b.1) RNO 1ST bullet

Ensure Letdown isolated: 1/u-8149A, LTDN ORIFICE ISOL VLV (45 GPM) - CLOSED

Standard: PLACED 1/1-8149A, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT

Perform Step: 7 2.3.2.b.1) RNO 2nd bullet

Ensure Letdown isolated: 1/u-8149B, LTDN ORIFICE ISOL VLV (75 GPM) - CLOSED

Standard: PLACED 1/1-8149B, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT

Perform Step: 8 2.3.2.b.1) RNO 3rd bullet

Ensure Letdown isolated: 1/u-8149C, LTDN ORIFICE ISOL VLV (75 GPM) - CLOSED

Standard: PLACED 1/1-8149C, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT



Examiner Note: When either Letdown Isolation Valve is closed, the leak is isolated.

Examiner Note: Closing either Letdown Isolation Valve meets Critical Task requirements.

Perform Step: 9 2.3.2.b.1) RNO 4th bullet

Ensure Letdown isolated: 1/u-LCV-459, LTDN ISOL VLV - CLOSED

Standard: PLACED 1/1-LCV-459, LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT


Ensure Letdown isolated: 1/u-LCV-460, LTDN ISOL VLV - CLOSED

Standard: PLACED 1/1-LCV-460, LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT

Perform Step: 11 2.3.2.b RNO

Ensure Letdown isolated: IF LTDN is being supplied by the RHR SYSTEM, THEN CLOSE

u-PK-131, LTDN HX OUT PRESS CTRL AND u-HC-128 RHR LTDN FLO CTRL.

Standard: DETERMINED Residual Heat Removal System is NOT in operation.

Comment: SAT UNSAT

Examiner Note: Steps 12 and 13 may be performed in any order.

Perform Step: 12 2.3.2.b.2) RNO 1st bullet

Ensure Excess Letdown isolated: 1/u-8153, XS LTDN ISOL VLV - CLOSED

Standard: VERFIED 1/1-8153, XS LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT




Ensure Excess Letdown isolated: 1/u-8154, XS LTDN ISOL VLV - CLOSED

Standard: VERIFIED 1/1-8154, XS LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.

Comment: SAT UNSAT


Perform Step: 14 2.3.2.b.3) RNO 1st bullet

Ensure PRZR HTRs - OFF 1/u-PCPR, PRZR HTR GROUP C

Standard: PLACED 1/1-PCPR, PRZR HTR GROUP C in OFF.

Comment: SAT UNSAT


Ensure PRZR HTRs - OFF 1/u-PCPR1, PRZR HTR GROUP A

Standard: PLACED 1/1-PCPR1, PRZR HTR GROUP A in OFF.

Comment: SAT UNSAT

Perform Step: 16 2.3.2.b.3) RNO 3rd bullet

Ensure PRZR HTRs - OFF 1/u-PCPR2, PRZR HTR GROUP B

Standard: PLACED 1/1-PCPR2, PRZR HTR GROUP B in OFF.

Comment: SAT UNSAT


Ensure PRZR HTRs - OFF 1/u-PCPR3, PRZR HTR GROUP D

Standard: PLACED 1/1-PCPR3, PRZR HTR GROUP D in OFF.

Comment: SAT UNSAT



Perform Step: 18 2.3.2.c

Verify Pressurizer level – STABLE OR INCREASING.

Standard: DETERMINED Pressurizer level stable or rising.


Comment: SAT UNSAT

STOP TIME:




Unit 1 is in MODE 3 with a boron concentration of 2500 ppm.

Reactor Coolant System temperature is approximately 358°F.

Reactor Coolant System pressure is approximately 280 psig.

Entry into MODE 4 is about to be performed. INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

RESPOND to a lowering Pressurizer level per ABN-108, Shutdown Loss of Coolant.

COMANCHE PEAK NUCLEAR POWER PLANT

UNIT 1 AND 2

ABNORMAL CONDITIONS PROCEDURES MANUAL

FOR EMPLOYEE USE: ||||||LATEST PCN/EFFECTIVE DATE |

||| DATE VERIFIED/INITIALS ||/ |||

|5 |/ |9-27-2011 1200 |

|||||||||||

QUALITY RELATED

SHUTDOWN LOSS OF COOLANT

PROCEDURE NO. ABN-108

REVISION NO. 4

EFFECTIVE DATE: 10/17/07 1200

PREPARED BY (Print): J.D. STONE EXT: 0564

TECHNICAL REVIEW BY (Print) JIM BRAU EXT: 5443

APPROVED BY: Alan Hall for Dave Kross DATE: 10/4/07 DIRECTOR, OPERATIONS

CPNPP NRC JPM S-3 Procedure Rev c


CPNPPABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2

PROCEDURE NO.ABN-108

SHUTDOWN LOSS OF COOLANT REVISION NO. 4 PAGE 2 OF 63

1.0 APPLICABILITY

This procedure describes actions for excessive Reactor Coolant System leakage in MODE 3 (below1000 psig), 4, or 5 (RCS not drained). ( RCS loops are filled when RCS level is greater than 872'10” |(866'3") which is approximately 35% (17%) Cold Calibrated Pressurizer Level AND RCS Pressure | >100 psig. |

This procedure is common to both units. The specific unit designator (1 or 2) is represented withinthese instructions by the symbol "u". The appropriate unit digit may be substituted for this symbol toobtain the unit specific equipment number. (Example u-FK-121 represents 1-FK-121 for Unit 1 and2-FK-121 for Unit 2.)

Other differences between units may be identified by including Unit 2 information in parenthesesimmediately after Unit 1 information.

NOTE: The symbol [R] has been located throughout this procedure where real or potential radiationhazards are positively identified. This identification technique should not preclude the workerfrom following good radiation work practices throughout this procedure to ensure his or heroccupational exposure is maintained As Low As Is Reasonably Achievable (ALARA).

NOTE: The applicable recovery procedures for RCS leakage in various operational MODEs are asfollows:

! MODEs 1, 2, 3 (RCS Press ABN-103, Excessive Reactor Coolantgreater than 1000 psig) Leakage

! MODE 3 (RCS press less than ABN-108, Shutdown Loss of Coolant1000 psig) MODES 4, 5,(RCS Loops filled)

! MODE 5 (RCS Loops NOT filled ABN-104, Residual Heat Removalincluding anytime at reduced System Malfunctioninventory)

! MODE 6 (Cavity NOT filled) ABN-104, Residual Heat Removal SystemMalfunction

! MODE 6 (Cavity flooded) ABN-909, Spent Fuel Pool/Refueling CavityLeakage

! Shutdown Loss of Coolant (Section 2.0)






Section 2.0

2.0 SHUTDOWN LOSS OF COOLANT

2.1 Symptoms

a. Annunciators

! CNTMT SMP 1 FILL RATE INCREASE (2A-1.6)

! CNTMT SMP 1 LVL HI-HI (2A-1.7)

! CNTMT SMP 2 LVL HI-HI (2A-1.8)

! CNTMT SMP 2 FILL RATE INCREASE (2A-2.6)

! RX CAV SMP LVL HI-HI (2A-2.7)

! ANY CNTMT SMP PMP RUN (2A-2.8)

! CNTMT FN CLR 3 & 4 CNDS FILL RATE HI (2B-3.12)

! CNTMT FN CLR 1 & 2 CNDS FILL RATE HI (2B-4.12)

! CCW SRG TK TRN A LVL HI-HI/LO (3B-2.4)

! ANY RCP THBR CLR CCW RET TEMP HI (3B-2.11)

! CCW SRG TK TRN B LVL HI-HI/LO (3B-3.4)

! ANY RCP THBR CLR CCW RET FLO LO (3B-3.11)

! ANY RCP THBR CLR CCW RET FLO HI (3B-4.11)

! PRZR PORV OUT TEMP HI (5B-3.1)

! PRZR LVL LO (5B-3.6)

! PRZR ANY SFTY RLF VLV OUT TEMP HI (5B-4.1)

! PRZR LVL DEV LO (5C-1.2)

! RV HEAD/PRZR VENT OUT TEMP HI (5C-4.4)

! CHRG FLO HI/LO (6A-3.4)

! SG 1 LVL DEV (8A-1.12)

! SG 2 LVL DEV (8A-2.12)

! SG 3 LVL DEV (8A-3.12)

! SG 4 LVL DEV (8A-4.12)






Section 2.1

2.1 b. Plant Indications

! Containment humidity dew point high or increasing

! Containment radiation levels high or increasing

! Containment temperature high or increasing

! Containment pressure high or increasing

! Reactor coolant makeup increased frequency

! VCT level decreasing

! Charging flow increasing

! Pressurizer relief and safety valves temperature high

! Component cooling water surge tank level increasing

! Component cooling water radiation levels high or increasing

! Steam generator blowdown radiation level increasing

! PRT pressure, level or temperature increasing

! Pressurizer level decreasing

! Condenser off gas radiation level increasing

! Mismatch between steam flow and auxiliary feedwater flow

! Incore instrument leakage alarm

2.2 Automatic Actions

a. IF pressurizer level decreases to 17%, THEN letdown will isolate and pressurizer heaters willdeenergize.

b. IF VCT level decreases to 2%, THEN charging pump suction will transfer to the RWST.

c. IF SI actuates with RWST level less than 33%, THEN RHR suction valves from Containment Sumpwill open.

d. RCP thermal barrier heat exchanger failure will isolate CCW from all thermal barrier heatexchangers on high temperature (182.5°F).






2.3 Operator Actions

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

Section 2.3

CAUTION: The RHR Pump suction valves automatically open if RWST level is less than 33% with aSafety Injection signal. This will occur even if RHR is aligned in the Shutdown CoolingMode.

1 Verify Reactor Tripped:

Q a. Reactor Trip and Bypass breakers -OPEN

Q b. All DRPI Rod Bottom lights - ON

Manually trip Reactor.

2 Verify Charging flow and Letdown FlowStatus:

Q a. Verify Charging flow - AT DESIREDFLOW RATE AND GREATER THANLETDOWN FLOW

a. Increase Charging flow to at least 15 gpmgreater than Letdown flow.

Q b. Verify Pressurizer level - GREATERTHAN OR EQUAL TO 30%

b. IF Pressurizer level is less than 30% butincreasing, THEN GO TO Step 3.

IF Pressurizer level is decreasing, THENperform the following:

“Step continued next page”








Section 2.3

2 b. 1) Ensure Letdown isolated:

! 1/u-8149A, LTDN ORIFICE ISOLVLV (45 GPM) - CLOSED

! 1/u-8149B, LTDN ORIFICE ISOLVLV (75 GPM) - CLOSED

! 1/u-8149C, LTDN ORIFICE ISOLVLV (75 GPM) - CLOSED

! 1/u-LCV-459, LTDN ISOL VLV -CLOSED

! 1/u-LCV-460, LTDN ISOL VLV -CLOSED

IF LTDN is being supplied by the RHRSYSTEM, THEN CLOSE u-PK-131,LTDN HX OUT PRESS CTRL ANDu-HC-128 RHR LTDN FLO CTRL.

2) Ensure Excess Letdown isolated:

! 1/u-8153, XS LTDN ISOL VLV -CLOSED

! 1/u-8154, XS LTDN ISOL VLV -CLOSED

3) Ensure PRZR HTRs - OFF

! 1/u-PCPR, PRZR HTR GROUP C

! 1/u-PCPR1, PRZR HTR GROUP A

! 1/u-PCPR2, PRZR HTR GROUP B

! 1/u-PCPR3, PRZR HTR GROUP D

Q c. Verify Pressurizer level - STABLEOR INCREASING.

c. Start an additional charging pump perSOP-103A/B.








Section 2.3

Q 3 Verify Pressurizer level - STABLE ORINCREASING

Ensure letdown flow stopped, closing thefollowing as appropriate:

! u-PK-131, LTDN HX OUT PRESS

CTRL

! u-HC-128, RHR LTDN FLO CTRL

! u-HC-123, XS LTDN HX FLO CTRL

4 Evacuate Containment.

Q a. Announce over Plant Page:ATTENTION ALL PERSONNEL INUNIT-u CONTAINMENT. EVACUATE CONTAINMENTIMMEDIATELY THROUGHPERSONNEL AIRLOCK. ASSEMBLE IN HALLWAY OUTSIDEPERSONNEL AIRLOCK.

Q b. Sound Containment RADIATIONALERT Alarm.

Q c. Repeat announcement.Q d. Dispatch Operator(s) to inspect the

following areas AND ensureContainment closure:

! Personnel Hatches

! Equipment Access Door

! Penetration areas








Section 2.3

5 Verify Containment Ventilation Isolation: Manually actuate containment ventilationisolation.

Q a. Verify appropriate portions ofu-MLB-45A and 45B windows - LIT(GREEN WINDOWS).

IF dampers NOT closed, THEN manually aligncomponents per Attachment 2.

Q b. Verify pressure boundary perAttachment 8.

Q 6 Continuously Monitor Equipment perAttachment 1, during performance of thisprocedure

AND

Perform actions outlined in Attachment 1,as necessary.

Q 7 Refer to EPP-201.








Section 2.3

8 Check RCS Status: Perform the following:

Q a. Verify RCS subcooling - GREATERTHAN 25°F:

! u-TI-3611-1, RCS SATMARGIN


Q b. Verify Pressurizer Level - STABLEOR INCREASING

1) Dispatch operators to rack in the breaker toaffected units non-operating CCP OR ONEsafety injection pump.

! 1EA1/11/BKR, 1APCH1,CENTRIFUGAL CHARGING PUMP1-01 MOTOR BREAKER

! 1EA2/12/BKR, 1APCH2,CENTRIFUGAL CHARGING PUMP1-02 MOTOR BREAKER

! 2EA1/7/BKR, 2APCH1, CENTRIFUGALCHARGING PUMP 2-01 MOTORBREAKER

! 2EA2/6/BKR, 2APCH2, CENTRIFUGALCHARGING PUMP 2-02 MOTORBREAKER

OR! 1EA1/10/BKR, 1APSI1, SAFETY

INJECTION PUMP 1-01 MOTORBREAKER

! 1EA2/9/BKR, 1APSI2, SAFETYINJECTION PUMP 1-02 MOTORBREAKER



2) Ensure 1/u-8835, SI TO CL 1-4 INJ ISOLVLV, OPEN.

3) Stop both RHR pumps AND place HSs inPULL-OUT:! 1/u-APRH1, RHRP 1! 1/u-APRH2, RHRP 2

4) Close 1/u-8701A, RHRP 1 HL RECIRCISOL VLV AND 1/u-8702B, RHRP 2 HLRECIRC ISOL VLV.

5) Identify AND Isolate Leak per Attachment 7,while continuing this procedure.

6) GO TO step 11.








Section 2.3

Q 9 Identify AND Isolate Leak per Attachment7, while continuing this procedure.

Q 10 Go To IPO-005A/B to Initiate a UnitShutdown.

CAUTION: Reactor Coolant System pressure should be maintained less than the Cold OverpressureProtection Curve of TDM-301A/B, "RCS Temperature & Pressure Limits", when thePressurizer PORVs are providing Low Temperature Overpressure Protection, OR less than400 psig when the RHR system is lined up in the shutdown cooling mode. Pressure shouldbe monitored on computer points P0498A or P0499A, P6498A or P6499A to ensure the mostrestrictive limit is not exceeded.

Q 11 Verify RWST level - GREATER THAN33%:

GO TO Attachment 6.

! u-LI-932, RWST LVL CHAN III! u-LI-933, RWST LVL CHAN IV

12 Establish Flow Through High HeadSafety Injection Flow Path:

Q a. Verify ONE CCP - RUNNING: a. Manually start/stop a CCP.

Q b. STOP 1/u-APPD, PDP.

Q c. Verify CCP suction aligned fromRWST:

! 1/u-LCV-112D RWST TO CHRGPMP SUCT VLV - OPEN

! 1/u-LCV-112E, RWST TOCHRG PMP SUCT VLV - OPEN

! 1/u-LCV-112B, VCT TO CHRGPMP SUCT VLV - CLOSED

! 1/u-LCV-112C, VCT TO CHRGPMP SUCT VLV - CLOSED

c. Operate valves as necessary.









Section 2.3

12 Q d. Verify the following valves -CLOSED:

! u-ZL-8220, CHRG PMP SUCTHI POINT VENT VLV - CLOSED

! u-ZL-8221, CHRG PMP SUCTHI POINT VENT VLV - CLOSED

! 1/u-8210A, H2/N2 SPLY VLV -CLOSED

! 1/u-8210B, H2/N2 SPLY VLV -CLOSED

! 1/u-8202A, VENT VLV -CLOSED

! 1/u-8202B, VENT VLV -CLOSED

d. Close valves as necessary.

Q e. Align CCP injection:! 1/u-8801A, CCP SI ISOL VLV -

OPEN

! 1/u-8801B, CCP SI ISOL VLV -OPEN

Q f. Verify ECCS flow:! u-FI-917, CCP SI FLO

f. GO TO Step 13.








Section 2.3

13 Manually Initiate Containment Phase AIsolation.

Q a. Place 1/u-CIPAA1, CNTMT ISOL -PHASE A/CNTMT VENT ISOL MANACT, switch to ACT.

Q b. Verify containment Phase A isolation- IN EFFECT:

b. Manually align components per Attachment3, as necessary.

1) Verify appropriate MLB REDwindows - DARK:

! u-MLB-1A1

! u-MLB-1A2

! u-MLB-1B1

! u-MLB-1B2

2) Verify appropriate MLB REDwindows - LIT:

! u-MLB-4A1

! u-MLB-4A2

! u-MLB-4B1

! u-MLB-4B2

! u-MLB-4A3

! u-MLB-4B3

! u-MLB-45A

! u-MLB-45B

3) Dispatch an Operator ANDRadiation Protection to inspectthe following areas to verifyContainment closure:

! Penetration Areas

! Personnel Hatches

! Equipment Access Door








Section 2.3

Q 14 Verify Reactor Coolant Pump Number 1Seal Differential Seal Pressure -GREATER THAN 220 PSID:

! u-PI-153A, RCP 1 SEAL 1 )P




Stop affected Reactor Coolant Pump(s).

Q 15 Verify Station Service Water Pumps -RUNNING:

Manually start Station Service Water Pump(s), asnecessary.

! u-HS-4250A, SSWP 1

! u-HS-4251A, SSWP 2

Q 16 Verify Component Cooling Water Pumps -RUNNING:

! u-HS-4518A, CCWP 1

! u-HS-4519A, CCWP 2

Manually start Component Cooling WaterPump(s) as necessary.








Section 2.3

17 Check RCS Status:

Q a. Verify RCS subcooling - GREATERTHAN 25°F:



Q b. Pressurizer level - GREATER THAN13%:

! u-LI-462, PRZR LVLCOLD CAL

Align ONE available safety injection pump for coldleg injection, as follows:

1) Ensure the following valves OPEN:

! 1/u-8806, RWST TO SIP SUCT VLV(Key Lock)

! 1/u-8923A, SIP 1 SUCT VLV

! 1/u-8923B, SIP 2 SUCT VLV

! 1/u-8813, SIP 1 & 2 MINIFLO RETVLV (Key Lock)

! 1/u-8814A, SIP 1 MINIFLO VLV

! 1/u-8814B, SIP 2 MINIFLO VLV

! 1/u-8821A, SIP 1 XTIE VLV

! 1/u-8821B, SIP 2 XTIE VLV

! 1/u-8835, SI TO CL 1"4 INJ ISOL VLV(Key Lock)

2) Start one Safety Injection Pump:

! 1/u-APSI1, SIP 1

! 1/u-APSI2, SIP 2

3) Verify safety injection pump flow:

! u-FI-918, SIP 1 DISCH FLO

! u-FI-922, SIP 2 DISCH FLO








Section 2.3

18 Verify Containment Spray - NOTREQUIRED:

Q a. Containment pressure has remained- LESS THAN 18 PSIG:

! u-ALB-2B 1.8, CS ACT - NOTLIT

AND

! u-ALB-2B 4.11, CNTMT ISOLPHASE B ACT - NOT LIT

AND

! Containment Pressure - LESSTHAN 18 PSIG

a. Perform the following:

1) Verify containment spray is actuated. IF NOT, THEN manually actuate.

2) Verify CONT SPRAY/PHASE Bportions of u-MLB-4A3 AND 4B3 LIT(Blue and Orange Windows). IF NOT,THEN manually actuate.

IF valves NOT aligned, THENmanually align per Attachment 4.

3) Verify Containment Spray flow:

! u-FI-4772-1, CSP 1 DISCH FLO




4) Stop ALL RCPs.

5) GO TO Step 19.

Q b. Verify containment spray heatexchanger outlet valves - CLOSED:

! u-HS-4776, CS HX 1 OUTVLV

! u-HS-4777, CS HX 2 OUTVLV

b. Manually close valve(s):








Section 2.3

CAUTION: Starting an RHR Pump in injection mode with hot leg recirc suction line temperatures greaterthan 210°F could cause pump damage due to flashing.

19 Check RCS status:

Q a. RCS Subcooling - GREATER THAN25°F:



Q b. Pressurizer level - GREATER THAN13%:

! u-LI-462, PRZR LVLCOLD CAL

Q c. RCS pressure - GREATER THAN325 PSIG:

! PO498A (P6498A),PRESSURIZER PRESSURE(Plant Computer)

! PO499A (P6499A),PRESSURIZER PRESSURE(Plant Computer)

Perform the following:

1) Identify the RHR Train(s) with hot leg recircsuction line temperature less than or equalto 210°F.

2) IF RWST level is less than or equal to 33%,THEN GO TO Attachment 6.

3) Ensure RHR pumps STOPPED AND HSs inPULL-OUT:

! 1/u-APRH1, RHRP 1! 1/u-APRH2, RHRP 2

4) CLOSE RHR hot leg recirc valves:

! 1/u-8701A, RHRP 1 HL RECIRCISOL VLV

! 1/u-8702B, RHRP 2 HL RECIRCISOL VLV

5) Ensure selected RHR pump RWST suctionvalve - OPEN:

! 1/u-8812A, RWST TO RHRP 1SUCT ISOL VLV

! 1/u-8812B, RWST TO RHRP 2SUCT ISOL VLV

6) OPEN the selected RHR heat exchangerCCW return valve:

! u-HS-4572, RHR HX 1 CCW RET VLV! u-HS-4573, RHR HX 2 CCW RET VLV

7) IF either train of RHR was aligned forShutdown Cooling, THEN ensure RHRP 1AND RHRP 2 XTIE VLVs - CLOSED:! 1/u-8716A, RHRP 1 XTIE VLV! 1/u-8716B, RHRP 2 XTIE VLV

8) START the selected RHR pump:! 1/u-APRH1, RHRP 1! 1/u-APRH2, RHRP 2









Section 2.3

19 9) Verify RHR injection flow for the selectedtrain:! u-FI-618, RHR TO CL 1&2 INJ FLO! u-FI-619, RHR TO CL 3&4 INJ FLO

10) IF NO RHRP injection flow, THEN GO TOStep 20.

11) GO TO Step 21

NOTE: Step 20 is a Continuous Action Step.

Q 20 Manually Operate ECCS Pumps toMaintain the following:

! PRZR LVL - GREATERTHAN 13%

AND

! RCS subcooling -GREATER THAN 25°F

21 Verify Steam Generator Levels:

Q a. Verify narrow range level -GREATER THAN 43(10)%:

! u-FR-510, SG 1 NR LVL




Q b. Control AFW flow to maintain50(40)% to60(50)% narrow rangelevel in all intact steam generators.

a. Start AFW pumps AND align valves to intactsteam generators, as necessary.








Section 2.3

NOTE: Step 22 is a Continuous Action Step.

Q 22 Initiate RCS Cooldown - AT LESSTHAN 100°F/hr.

a. IF steam dumps in operation, THENdump steam to condenser u-PK-507,STM DUMP PRESS CTRL

OR

b. IF RHR aligned in Shutdown Coolingmode, THEN throttle open RHR HXoutlet valves:

! u-HC-606, RHR HX 1 FLOCTRL

! u-HC-607, RHR HX 2 FLOCTRL

Manually or locally dump steam using SGatmospheric relief valves:

! u-PK-2325, SG 1 ATMOS RLF VLV CTRL




CAUTION: If offsite power is lost after SI reset, manual action may be required to restart safeguardsequipment.

Q 23 Check SI-ACTUATED:! SI actuation as indicated on the First

Out Annunciator u-ALB-6C.

! SI Actuated blue status light(PCIP 1.8) - ON

GO TO Step 28.

24 Check Emergency Diesel GeneratorStatus.

Q a. Diesel Generators - RUNNINGQ b. Place BOTH Emergency DG

STOP/START handswitches in -START.

! CS-uDG1E, DG EMERSTOP/START

! CS-uDG2E, DG EMERSTOP/START

a. GO TO Step 25.








Section 2.3

25 Reset the following:

a. SI Signals:

Q !1/u-SIRA, SI RESETQ !1/u-SIRB, SI RESETQ !1/u-CIPARA, CNTMT

ISOL-PHASE A RESET

Q !1/u-CIPARB, CNTMTISOL-PHASE A RESET

Q !1/u-CIPBRA, CNTMTISOL-PHASE RESET

Q !1/u-CIPBRB, CNTMTISOL-PHASE B RESET

Q !1/u-CSRA, CS RESETQ !1/u-CSRB, CS RESET

Q b. SI Sequencers26 Establish Instrument Air to Containment

by opening u-HS-3487, CNTMT INSTAIR ISOL VLV:

Q a. Verify a least one air compressor -RUNNING

! u-HS-3451, INSTR AIRCOMPR 1

! u-HS-3463, INSTR AIRCOMPR 2

! X-ZL-3452, INSTR AIRCOMM COMPR1 (1-CB-01)

! X-ZL-3463, INSTR AIRCOMM COMPR2 (1-CB-01)

a. Manually start air compressor(s)

AND

Align valves per SOP-509A/B asappropriate.

Q b. Verify u-PI-3488, INSTR AIRAFTFILT OUT PRESS - GREATERTHAN 80 PSIG AND STABLE ORRISING

Q c. OPEN u-HS-3487, CNTMT INST AIRISOL VLV

b. Perform ABN-301 while continuing thisprocedure at Step 27.








Section 2.3

27 Establish Nitrogen to Containment.

Q a. Verify u-HC-943, ACCUM 1-4 VENTCTRL - CLOSED.

Q b. OPEN 1/u-8880, SI/PORV ACCUMN2 ISOL VLV.

a. Manually close valve.

Q 28 Verify ALL AC Buses - ENERGIZED BYOFFSITE POWER

Restore offsite power to AC buses per ABN-601OR ABN-602 while continuing this procedure atStep 29.

Q 29 Verify RCS subcooling - GREATERTHAN 25°F:

! u-TI-3611-1, RCS SAT MARGIN

! u-TI-3612-1, RCS SAT MARGIN

Perform the following, as necessary:

1) Ensure CCP safety injection flow is atmaximum for conditions.

! u-FI-917, CCP SI FLO

2) Ensure SIP safety injection flow:

! u-FI-918, SIP 1, DISCH FLO

! u-FI-922, SIP 2, DISCH FLO

IF NO SI flow is indicated, THEN return toStep 17.

3) Ensure RHR supplying injection fromRWST:

! At least one RHR pump running

AND

! RWST suction valves to RHR pump(s)- OPEN.

IF NO injection flow from RWST is indicated,THEN return to Step 19.

4) Continue RCS cooldown.

WHEN RCS subcooling is GREATER THAN25°F, THEN continue this procedure.








Section 2.3

CAUTION: A cooldown rate of 100°F in one hour in the pressurizer should not be exceeded.

30 Depressurize RCS to Minimize BreakFlow AND Refill Przr.

Q a. Verify normal Pressurizer Spray -AVAILABLE:

! u-PK-455B, RC LOOP 1 PRZRSPR VLV CTRL

! u-PK-455C, RC LOOP 4 PRZRSPR VLV CTRL

a. GO TO Step 31.

Q b. Spray Pressurizer with maximumavailable spray until either of thefollowing conditions satisfied:

! RCS Subcooling - LESS THAN25°F

OR

! PRZR LVL - GREATER THAN50%

Q c. WHEN either condition is met,THEN close spray valves.

c. Stop RCP(s) supplying failed spray valve.

Q d. GO TO Step 32.








Section 2.3

31 Depressurize RCS Using Przr PORV toMinimize Break Flow and Refill Przr.

Q a. Verify at least ONE Przr PORV -AVAILABLE:

! 1/u-PCV-455A, PRZR PORV

! 1/u-PCV-456, PRZR PORV

a. Perform the following:

1) Spray Przr with maximum AuxiliarySpray until either of the followingconditions satisfied:

! RCS Subcooling - LESS THAN25°F

OR


2) WHEN either condition is met, THENclose spray valve.

3) GO TO step 32.

Q b. OPEN one Przr PORV until either ofthe following conditions satisfied:

! RCS Subcooling - LESS THAN 25°F

OR


Q c. WHEN either condition met, THENCLOSE Przr PORV.

c. Close Przr PORV Block Valve:

! 1/u-8000A, PRZR PORV BLK VLV

! 1/u-8000B, PRZR PORV BLK VLV








Section 2.3

Q 32 Continue RCS Cooldown at less than100°F/hr.

Q 33 Verify PRZR LVL - GREATER THAN30%


a. Locally rack in affected Unit's breaker tonon-operating SIP.





b. Start an additional safety injection pump.

c. Return to Step 29.








Section 2.3

NOTE: ! After stopping any ECCS pump, RCS pressure should be allowed to stabilize OR increasebefore stopping another ECCS pump.

! CCPs and SI pumps should be stopped on alternate ECCS trains when possible.

34 Check if One Charging Pump Should BeStopped:

Q a. Verify TWO CCPs - RUNNING a. GO TO Step 35.

Q b. Determine required RCS subcoolingfrom Table 1.

TABLE 1

SI PUMP REQUIRED SUBCOOLING (°F)

STATUS ANY RCP RUNNING NO RCP RUNNING

NORMAL NORMAL

NONE RUNNING

85°F 95°F

ONERUNNING

60°F 65°F

TWO RUNNING

60°F 65°F

Q c. Verify RCS subcooling - GREATERTHAN REQUIRED SUBCOOLING.


Q d. STOP ONE CCP.








Section 2.3

35 Check if ONE SI pump should bestopped:

Q a. Any SI pump - RUNNING. a. GO TO Step 36.

Q b. Determine required RCS subcoolingfrom Table 2.

TABLE 2

SI PUMP

STATUS

RCS SUBCOOLING (°F)

ONE CCP RUNNING NO CCPs RUNNING

ANY RCP RUNNING NO RCPRUNNING

ANY RCPRUNNING

NO RCPRUNNING

NORMAL NORMAL NORMAL NORMAL

ONE RUNNING

130°F 145°F

TWO RUNNING

55°F 60°F 70°F 75°

Q c. Verify RCS subcooling - GREATERTHAN REQUIRED SUBCOOLING.


Q d. Verify PRZR level - GREATERTHAN 30%.

d. Do NOT stop SI Pump. Return to Step 29.

Q e. STOP ONE SI Pump.Q f. Return to Step 35a.








Section 2.3

36 Check if Normal Charging Should BeEstablished:

a. Verify the following:

Q ! BOTH SI pumps - STOPPEDQ ! CCP pumps - ALL BUT ONE

STOPPED

a. Do NOT isolate CCP injection line. GOTO step 40.

b. RCS subcooling -

Q ! ANY RCP RUNNING -GREATER THAN 55°F

OR

Q ! NO RCP RUNNING - GREATERTHAN 60°F

b. GO TO Step 40.

Q c. Verify pressurizer level - GREATERTHAN 30%.

c. Do NOT isolate CCP injection line. Returnto Step 29.








Section 2.3

[R] 37 Isolate CCP Injection Line Flow Path:

Q a. OPEN CCP miniflow valves:! 1/u-8110, CCP 1 & 2

MINIFLO VLV

! 1/u-8111, CCP 1 & 2MINIFLO VLV

Q b. CLOSE CCP emergency recircisolation valves:

! 1/u-8511A, CCP 1 ALTMINIFLO ISOLVLV

! 1/u-8511B, CCP 2 ALTMINIFLO ISOLVLV

Q c. Place u-FK-121, CCP CHRG FLOCTRL, in MANUAL AND adjust SealInjection flow to approximately 6GPM/RCP

NOTE: The following area is normally a radiation area, but if accident involves failed fuel, it may become a high radiation area.

Q d. CLOSE CCP SI isolation valves:! 1/u-8801A, CCP SI ISOL VLV

! 1/u-8801B, CCP SI ISOL VLV


1) Ensure CCW flow from RCP thermalbarriers.

2) Stop operating CCP.

3) Close CCP SI isolation Valves.

IF CCP SI isolation valves will NOT close,THEN locally close valves (SFGD 810 Rmu-077B).

4) Start CCP and verify RCP seal injectionflow.








Section 2.3

CAUTION: After a charging flow or RCS pressure change, u-HC-182, RCP SEAL WTR PRESS CTRL,should be adjusted to maintain operating RCP seal injection flow between 6 and 13 gpm toeach RCP.

38 Establish Charging Flow Path:

Q a. Ensure u-HC-182, RCP SEAL WTRPRESS CTRL - 20% DEMAND

Q b. Ensure u-FK-121, CCP CHRG FLOCTRL, in MANUAL AND adjust SealInjection flow to approximately 13GPM/RCP

Q c. OPEN BOTH charging line isolationvalves:

! 1/u-8105, CHRG PMP TORCS ISOL VLV

! 1/u-8106, CHRG PMP TORCS ISOL VLV

Q d. Ensure ONE loop charging valve -OPEN

! 1/u-8147, RCS LOOP 1CHRG VLV

OR

! 1/u-8146, RCS LOOP 4CHRG VLV

Q e. Adjust charging flow control valve toestablish charging flow.

Q f. Verify Seal Injection Flow to eachRCP - BETWEEN 6 GPM AND 13GPM:

! u-FI-145, RCP 1 SEAL WTRINJ FLO


! u-FI-143, RCP 3 SEAL WTR INJ FLO


f. Restore Seal Injection per Attachment 5.

Q g. Place u-FK-121, CCP CHRG FLOCTRL in AUTO








Section 2.3

39 Verify Adequate Shutdown Margin:

Q a. Contact Chemistry to sample RCS.

Q b. Verify adequate Shutdown Marginper TDM-105A/B.

b. Borate as necessary.

40 Verify ECCS Flow - NOT Required:

Q a. RCS subcooling - GREATER THAN25°F

a. Manually operate ECCS pumps asnecessary AND GO TO Step 41.

Q b. PRZR level - GREATER THAN 13% b. Manually operate ECCS pumps asnecessary AND return to Step 17.

41 Check if Diesel Generators Should BeStopped:

Q a. Verify AC safeguards buses -ENERGIZED BY OFFSITEPOWER.

a. Restore offsite power to AC safeguardsbuses per ABN-601 OR ABN-602 whilecontinuing this procedure at Step 42.

Q b. STOP any unloaded dieselgenerator and place in Standby perSOP-609A/B.








Section 2.3

NOTE: The following area is normally a radiation area, but if the accident involves failed fuel, it maybecome a high radiation area.

[R] 42 Check if RCP Seal Return Flow ShouldBe Established:

Q a. Check RCP Cooling - NORMAL: a. Establish RCP Cooling per Attachment 5AND GO TO Step 44.

! RCP seal injection flow

! RCP CCW return temperatureAND flows

Q b. Verify CCW flow to seal water heatexchanger (u-ALB-3B 1.16 -DARK).

b. GO TO Step 44.

Q c. OPEN seal water return isolationvalves:

! 1/u-8100, RCP SEAL WTRRET ISOL VLV

! 1/u-8112, RCP SEAL WTRRET ISOL VLV

Q d. Verify 1/u-8143, XS LTDN DIVERTVLV - IN VCT








Section 2.3

43 Check if RCPs Must Be Stopped:

a. Verify the following: a. GO TO Step 44.

Q 1) Number 1 seal differentialpressure - LESS THAN 200PSID:

! u-PI-153A, RCP 1 SEAL1 )P




OR

Q 2) Number 1 seal leakoff flow-LESS THAN 0.2 GPM:

! u-FR-157, RCP 1 SEALLKOFF FLO




Q b. STOP affected RCP(s).








Section 2.3

44 Check if RHR System Can Be Placed inShutdown Cooling Mode.

Continue RCS Cooldown. WHEN RHR systemis placed in Shutdown Cooling Mode, THENGO TO Step 45.

Q a. Verify the following:1) RCS temperature - LESS

THAN 350°F:

! u-TI-413A, HL 1 TEMP(WR)

! u-TI-423A, HL 2 TEMP(WR)

2) RCS pressure - LESS THAN350 PSIG

Q b. Place RHR in Shutdown CoolingMode per SOP-102A/B.

45 Evaluate Long Term Plant Status:

Q a. Maintain cold shutdown conditions.Q b. Consult with Engineering.

Q 46 Initiate Repair per STA-606.

Q 47 Submit a SMART Form per STA-421, asapplicable.

END OF SECTION





Facility: CPNPP JPM # NRC S-4 Task # RO3301C K/A # 059.A4.10 3.9 / 3.8 SF-4 Title: Place 2nd Main Feedwater Pump in Service

Examinee (Print): Testing Method: Simulated Performance: Classroom: Actual Performance: X Simulator: X Alternate Path: Plant: Time Critical:


Initial Conditions: Given the following conditions: Main Feedwater Pump A is in service. Main Feedwater Pump B is running at 2000 rpm.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following: PLACE Main Feedwater Pump B in service per IPO-003A, Power

Operations, Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

START at Step 5.4.18.

Task Standard: Utilizing IPO-003A, aligned Main Feedwater Pump B and placed in parallel operation with Main Feedwater Pump A.

Required Materials: IPO-003A, Power Operations, Rev. 28-9.


Comments:

Result: SAT UNSAT




SIMULATOR SETUP BOOTH OPERATOR: INITIALIZE to IC-37 or any 45% power Initial Condition with the 2nd Feedwater Pump ready to be placed in service and PERFORM the following:

PLACE the Digital Feedwater System (DFS) Summary Screen in service. ENSURE B MFW Pump is at ~2000 rpm. ENSURE MFWP Drain Valves 1-HS-2173 and 1-HS-2176 are CLOSED.

EXAMINER: PROVIDE examinee with a copy of:

IPO-003A, Power Operations. Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

INITIAL Step 5.4.17.




Examiner Note: The following steps are from IPO-003A, Section 5.4.

Perform Step: 1 5.4.18 Note

Review NOTE prior to Step 5.4.18.

Standard: REVIEWED Note at Step 5.4.18.

Comment: SAT UNSAT

Perform Step: 2 5.4.18.A & 1st bullet

Verify the following controllers are in AUTO: 1-SK-509A, FWP MASTER SPEED CTRL.

Standard: VERIFIED 1-SK-509A, FWPT MASTER SPEED CTRL in AUTO with white AUTO light LIT.

Comment: SAT UNSAT


Perform Step: 3 5.4.18.A & 2nd bullet

Verify the following controllers are in AUTO: 1-SK-509B, FWPT A AUTO SPD CTRL.

Standard: VERIFIED 1-SK-509B, FWPT A AUTO SPD CTRL in AUTO with white AUTO light LIT.

Comment: SAT UNSAT

Perform Step: 4 5.4.18.A & 3rd bullet

Verify the following controllers are in AUTO: 1-SK-509C, FWPT B AUTO SPD CTRL.

Standard: VERIFIED 1-SK-509C, FWPT B AUTO SPD CTRL in AUTO with white AUTO light LIT.

Comment: SAT UNSAT



Perform Step: 5 5.4.18.B & 2nd bullet

Place the oncoming FWP recirculation valve in MANUAL and open it as required to obtain 5000 gpm suction flow, or fully open the valve (100% demand) if 5000 gpm cannot be achieved.

1-FK-2290, SG FW PMP B RECIRC CTRL

Standard: PERFORMED the following: DEPRESSED 1-FK-2290, SG FW PMP B RECIRC CTRL amber

MAN pushbutton (critical). OBSERVED amber MAN light LIT and white AUTO light OFF

(NOT critical). DEPRESSED 1-FK-2290, SG FW PMP B RECIRC CTRL red

OUTPUT ▲ pushbutton until 1-FI-2290, FWP B SUCT FLO reads ~5000 GPM (critical).

Comment: SAT UNSAT

Examiner Note: Annunciator 1-ALB-6D, Window 1.10 – AVE TAVE - TREF DEV, will alarm because of the increased efficiencies with the B MFWP Recirculation Valve close.

Perform Step: 6 5.4.18.C

Perform the following steps alternately in controlled, incremental steps until the recirc valve for the oncoming FWP is closed.

Adjust speed on the oncoming FWP to approach that of the running FWP while maintaining its speed at or below that of the running FWP. 1-SC-2112B FWPT B MAN SPD CTRL

Close down on the oncoming FWP recirc valve as much as possible without decreasing flow for the oncoming FWP below 5000 gpm.

Standard: PERFORMED the following: PLACED 1-SC-2112B FWPT B MAN SPD CTRL in SLOW

RAISE or FAST RAISE position and OBSERVED 1-SI-2112F, FWPT B SPD rising.

DEPRESSED 1-FK-2290, SG FW PMP B RECIRC FLO CTRL green LOWER ▼ pushbutton as necessary to maintain 1-FI-2290, FWP B SUCT FLO at 5000 GPM.

Comment: SAT UNSAT



Perform Step: 7 5.4.18.D & 2nd bullet

When the oncoming FWP Recirc Valve indicates closed, place the controller in AUTO:

1-FK-2290, SG FW PMP B RECIRC CTRL

Standard: PERFORMED the following: DEPRESSED 1-FK-2290, SG FW PMP B RECIRC CTRL white

AUTO pushbutton (critical). OBSERVED white AUTO light LIT and amber MAN light OFF

(NOT critical).

Comment: SAT UNSAT

Perform Step: 8 5.4.18.E & 2nd bullet

When the oncoming FWP FW REF and SPD CMD are approximately the same on the DFS screen, depress the FWPT SPD CTRL MODE SELECT AUTO pushbutton.

1-HS-2112B, FWPT B SPD CTRL MODE SELECT - AUTO

Standard: PERFORMED the following: DEPRESSED 1-HS-2112B, FWPT B SPD CTRL MODE SELECT

black AUTO pushbutton (critical). OBSERVED white AUTO light LIT (NOT critical).

Comment: SAT UNSAT

Perform Step: 9 5.4.18.F & 2nd bullet

Adjust the FWPT AUTO SPD CTRL Pots as required to balance load and flow.

1-SK-509C, FWPT B AUTO SPD CTRL

Standard: As required, ADJUSTED POT Setpoint on 1-SK-509C, FWPT B AUTO SPD CTRL to balance both Main Feedwater Pump flows.


Comment: SAT UNSAT

STOP TIME:




Main Feedwater Pump A is in service. Main Feedwater Pump B is running at 2000 rpm.


PLACE Main Feedwater Pump B in service per IPO-003A, Power Operations, Step 5.4.18, Perform the following to place the FWPT speed controls in AUTO.

START at Step 5.4.18.



Facility: CPNPP JPM # NRC S-5 Task # RO2002B K/A # 026.A4.01 4.5 / 4.3 SF-5 Title: Transfer Containment Spray From Injection to Recirculation

Examinee (Print): Testing Method: Simulated Performance: Classroom: Actual Performance: X Simulator: X Alternate Path: Plant: Time Critical: X


Initial Conditions: Given the following conditions: A Large Break LOCA has occurred. EOS-1.3A, Transfer to Cold Leg Recirculation, is in progress. Refueling Water Storage Tank level is LESS THAN 6%.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following: TRANSFER Containment Spray to the Containment Sumps per

EOS-1.3A, Transfer to Cold Leg Recirculation. PERFORM Attachment 1.H, Containment Spray Switchover Criterion.

Task Standard: Utilizing EOS-1.3A, transferred Containment Spray from the Injection Mode to the Recirculation Mode from the Containment Sumps within 70 seconds.

Required Materials: EOS-1.3A, Transfer to Cold Leg Recirculation, Rev. 8-3.

Time Critical: 70 seconds Completion Time: ________ seconds Validation Time: 2 minutes Completion Time: ________ minutes

Comments:

Result: SAT UNSAT




SIMULATOR SETUP BOOTH OPERATOR: INITIALIZE to IC #36 and or any Post LOCA with RHR Swapover completed IC. If IC #36 is not available, RESET to any at power IC and PERFORM the following:

INSERT malfunction RC08A2 (or equivalent LB LOCA). PLACE Simulator in RUN. REDUCE AFW Flow to all SGs. RESET SI, SIS, Containment and Isolation Phases A & B and Containment Spray. STOP both Emergency Diesel Generators. STOP all Reactor Coolant Pumps. When RWST level reaches LO-LO level, TRANSFER ECCS to Cold Leg

Recirculation by performing Steps 1-3 of EOS-1.3A. FREEZE simulator when RWST level is LESS THAN 6%.


EOS-1.3A, Transfer to Cold Leg Recirculation. Attachment 1.H, Containment Spray Switchover Criterion.



- Check Mark Denotes Critical Step CRITICAL START TIME:

Examiner Note: The following steps are from EOS-1.3, Attachment 1.H. Examiner Note: After the examinee signals they are ready to begin, CUE the Booth

Operator to PLACE the Simulator in RUN.

Perform Step: 1 4.a.

Check RWST level – LESS THAN 6%.

Standard: OBSERVED 1-LI-930, RWST LVL CHAN 1 or 1-LI-931, RWST LVL CHAN 2 and VERIFY level is less than 6%.

Standard:

Comment: SAT UNSAT

Examiner Note: Steps 2 and 3 may be performed in any order or simultaneously.

Perform Step: 2 4.b.1) & 1st bullet

Realign Containment Spray System as follows: Open CNTMT SMP TO CSP 1 & 3 AND 2 & 4 SUCT ISOL VLVs:

1-HS-4782

Standard: PERFORMED the following: PLACED 1-HS-4782, CNTMT SMP TO CSP 1 & 3 to OPEN

(critical). OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT

Perform Step: 3 4.b.1) & 2nd bullet

Realign Containment Spray System as follows: Open CNTMT SMP TO CSP 1 & 3 AND 2 & 4 SUCT ISOL VLVs:

1-HS-4783

Standard: PERFORMED the following: PLACED 1-HS-4783, CNTMT SMP TO CSP 2 & 4 to OPEN

(critical). OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT



Examiner Note: Steps 4 and 5 may be performed in any order or simultaneously.

Perform Step: 4 4.b.2) & 1st bullet

Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs: 1-HS-4758

Standard: PERFORMED the following: PLACED 1-HS-4758, RWST TO CSP 1 & 3 to CLOSE (critical). OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT

Perform Step: 5 4.b.2) & 2nd bullet

Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs: 1-HS-4759

Standard: PERFORMED the following: PLACED 1-HS-4759, RWST TO CSP 2 & 4 to CLOSE (critical). OBSERVED green CLOSE light LIT (NOT critical).

Examiner Note: Steps 1 through 6 must be performed within 70 seconds.

Comment: SAT UNSAT

CRITICAL STOP TIME:

Perform Step: 6 4.b.3)

IF containment spray pumps have been stopped due to RWST level, THEN perform the following:

Standard: DETERMINED Containment Spray Pumps were NOT stopped due to low RWST Level.

Comment: SAT UNSAT

Perform Step: 7 4.b.4)

Verify containment spray flows.

Standard: OBSERVED Containment Spray flows on: 1-FI-4772-1, CSP 1 DISCH FLO at ~3700 GPM. 1-FI-4773-1, CSP 2 DISCH FLO at ~3700 GPM. 1-FI-4772-2, CSP 3 DISCH FLO at ~3700 GPM. 1-FI-4773-2, CSP 4 DISCH FLO at ~3700 GPM.


Comment: SAT UNSAT

STOP TIME:




A Large Break LOCA has occurred. EOS-1.3A, Transfer to Cold Leg Recirculation, is in

progress. Refueling Water Storage Tank level is LESS THAN 6%.


TRANSFER Containment Spray to the Containment Sumps per EOS-1.3A, Transfer to Cold Leg Recirculation.

PERFORM Attachment 1.H, Containment Spray Switchover Criterion.

TIME CRITICAL JPM

CPSESCPSESCPSESEMERGENCY RESPONSE GUIDELINESEMERGENCY RESPONSE GUIDELINESEMERGENCY RESPONSE GUIDELINES

PROCEDURE NO.PROCEDURE NO.PROCEDURE NO.UNIT 1UNIT 1UNIT 1 EOS-1.3AEOS-1.3AEOS-1.3A

TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATION REVISION NO. 8REVISION NO. 8REVISION NO. 8 PAGE 17 OF 53PAGE 17 OF 53PAGE 17 OF 53

ATTACHMENT 1.HATTACHMENT 1.HATTACHMENT 1.H PAGE 1 OF 3 PAGE 1 OF 3 PAGE 1 OF 3

CONTAINMENT SPRAY SWITCHOVER CRITERIONCONTAINMENT SPRAY SWITCHOVER CRITERIONCONTAINMENT SPRAY SWITCHOVER CRITERION

CAUTIONCAUTIONCAUTION: Any Containment Spray pump taking suction from the RWST : Any Containment Spray pump taking suction from the RWST : Any Containment Spray pump taking suction from the RWST should be stopped when RWST level reaches 0% should be stopped when RWST level reaches 0% should be stopped when RWST level reaches 0%

STEP STEP STEP ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED RESPONSE NOT OBTAINED RESPONSE NOT OBTAINED

4. 4. 4. Align Containment Spray System Align Containment Spray System Align Containment Spray System For Recirculation: For Recirculation: For Recirculation:

a.a.a. Check RWST level - LESS Check RWST level - LESS Check RWST level - LESS a.a.a. Perform the following:Perform the following:Perform the following:THAN 6%THAN 6%THAN 6%

1) 1) 1) IFIFIF Containment Spray Containment Spray Containment Spray

ACTUATED, ACTUATED, ACTUATED, THENTHENTHEN continue continue continuewith Step 5. with Step 5. with Step 5. WHENWHENWHEN RWST RWST RWSTlevel less than 6%,level less than 6%,level less than 6%,THENTHENTHEN perform Step 4b. perform Step 4b. perform Step 4b.

2)2)2) IFIFIF Containment Spray Containment Spray Containment Spray NOTNOTNOTACTUATED, ACTUATED, ACTUATED, THENTHENTHEN perform the perform the perform thefollowing to align following to align following to align Containment Spray System:Containment Spray System:Containment Spray System:

A)A)A) Stop containment sprayStop containment sprayStop containment spraypumps and place inpumps and place inpumps and place instandby.standby.standby.

B)B)B) Open CNTMT SMP TO CSP 1Open CNTMT SMP TO CSP 1Open CNTMT SMP TO CSP 1& 3 & 3 & 3 ANDANDAND 2 & 4 SUCT ISOL 2 & 4 SUCT ISOL 2 & 4 SUCT ISOLVLVs:VLVs:VLVs:

1-HS-47821-HS-47821-HS-4782

1-HS-47831-HS-47831-HS-4783

C)C)C) Close RWST TO CSP 1 & 3Close RWST TO CSP 1 & 3Close RWST TO CSP 1 & 3ANDANDAND 2 & 4 SUCT VLVs: 2 & 4 SUCT VLVs: 2 & 4 SUCT VLVs:

1-HS-47581-HS-47581-HS-4758

1-HS-47591-HS-47591-HS-4759 - CONT 4 -- CONT 4 -- CONT 4 -

CPNPP NRC JPM S-5 Procedure Rev c1








D)D)D) Notify Plant Staff ofNotify Plant Staff ofNotify Plant Staff ofContainment Spray Containment Spray Containment Spray alignment and currentalignment and currentalignment and currentRWST levelRWST levelRWST level

b.b.b. Realign Containment SprayRealign Containment SprayRealign Containment SpraySystem as follows:System as follows:System as follows:

1)1)1) Open CNTMT SMP TO CSP 1 &Open CNTMT SMP TO CSP 1 &Open CNTMT SMP TO CSP 1 & 1)1)1) IFIFIF CNTMT SMP TO CSP VLV(s) CNTMT SMP TO CSP VLV(s) CNTMT SMP TO CSP VLV(s)3 3 3 ANDANDAND 2 & 4 SUCT ISOL VLVs: 2 & 4 SUCT ISOL VLVs: 2 & 4 SUCT ISOL VLVs: can can can NOTNOTNOT be open, be open, be open, THENTHENTHEN

perform the following:perform the following:perform the following:

1-HS-47821-HS-47821-HS-4782A) Place affected CSPs inA) Place affected CSPs inA) Place affected CSPs in

PULL-OUT.PULL-OUT.PULL-OUT.1-HS-47831-HS-47831-HS-4783

B)B)B) Place affected CS HXPlace affected CS HXPlace affected CS HXOUT VLV(s) in PULL-OUT.OUT VLV(s) in PULL-OUT.OUT VLV(s) in PULL-OUT.

C)C)C) Consult Plant Staff toConsult Plant Staff toConsult Plant Staff todetermine contingencydetermine contingencydetermine contingencyactions.actions.actions.

2)2)2) Close RWST TO CSP 1 & Close RWST TO CSP 1 & Close RWST TO CSP 1 & 3 3 3 ANDANDAND 2 & 4 SUCT VLVs: 2 & 4 SUCT VLVs: 2 & 4 SUCT VLVs:

1-HS-47581-HS-47581-HS-4758

1-HS-47591-HS-47591-HS-4759

- CONT 4 - - CONT 4 - - CONT 4 -









3)3)3) IFIFIF containment spray containment spray containment spraypumps have been stoppedpumps have been stoppedpumps have been stoppeddue to RWST level, due to RWST level, due to RWST level, THENTHENTHENperform the following:perform the following:perform the following:

A)A)A) Ensure CS HX 1 Ensure CS HX 1 Ensure CS HX 1 ANDANDAND2 OUT VLVs closed 2 OUT VLVs closed 2 OUT VLVs closed and handswitches inand handswitches inand handswitches inPULL-OUT:PULL-OUT:PULL-OUT:

1-HS-47761-HS-47761-HS-4776

1-HS-47771-HS-47771-HS-4777

B)B)B) Perform Steps C) and Perform Steps C) and Perform Steps C) and D) simultaneously.D) simultaneously.D) simultaneously.

C)C)C) Open CS HX 1 Open CS HX 1 Open CS HX 1 ANDANDAND 2 2 2OUT VLVs:OUT VLVs:OUT VLVs:

1-HS-47761-HS-47761-HS-4776

1-HS-47771-HS-47771-HS-4777

D)D)D) WHENWHENWHEN CS HX OUT CS HX OUT CS HX OUTVLVs begin to open,VLVs begin to open,VLVs begin to open,THENTHENTHEN start CS PUMPS: start CS PUMPS: start CS PUMPS:

1-HS-4764 1-HS-4764 1-HS-4764 ANDANDAND1-HS-47651-HS-47651-HS-4765

1-HS-4766 1-HS-4766 1-HS-4766 ANDANDAND1-HS-47671-HS-47671-HS-4767

4)4)4) Verify containment sprayVerify containment sprayVerify containment sprayflows.flows.flows.





Facility: CPNPP JPM # NRC S-6 Task # RO4215 K/A # 064.A4.07 3.4 / 3.4 SF-6 Title: Restore Safeguards Bus 1EA1 to Offsite Power



Initial Conditions: Given the following conditions: Unit 1 is in MODE 1. Emergency Diesel Generator (EDG) 1-01 is supplying the 6.9 kV

Safeguards Bus 1EA1 due to post-work testing of the EDG. Power from Transformer XST1 is available to the 6.9 kV Safeguards Bus

1EA1. Transformer XST2 is NOT available.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following: RESTORE Offsite Power to 6.9 kV Safeguards Bus 1EA1 from

Transformer XST1 per SOP-609A, Diesel Generator System, Section 5.7, Transferring From DG Supplying Alone to Normal or Alternate Supply.

Task Standard: Utilizing SOP-609A, restored Offsite Power to 6.9 kV Safeguards Bus 1EA1 from Transformer XST1 and opened the Train A EDG Breaker when an overload condition occurred.

Required Materials: SOP-609A, Diesel Generator System, Rev. 20-5.


Comments:

Result: SAT UNSAT




SIMULATOR SETUP BOOTH OPERATOR: INITIALIZE to IC #35 and load scenario file “LC20 NRC JPM 6, 7” or any at-power Initial Condition and PERFORM the following:

LOAD the EDG per SOP-609A, Section 5.6, Supplying 6.9 KV SFGD Busses with DG Alone.

EXECUTE remote function EDR13, to REMOVE 480 VAC MCC Undervoltage Load Shedding fuses (if Step 5.7.I is reached, the fuses will be reinstalled).

OPEN both Offsite Power Breakers CS-1EA1-1 and CS-1EA1-2 for Bus 1EA1. PLACE CS-1EA1-1, Incoming Breaker 1EA1 in PULLOUT and HANG a Red Tag. ENSURE EDG and Safeguards Bus voltages are NOT matched prior to SNAP of IC. When the 1EA1-2 Feeder Breaker is CLOSED at Step 5.7.E, EXECUTE malfunction

ED09, Grid Frequency Disturbance at 58.2 Hertz and 90 second ramp {DIED1EA12.iivPanel=3} IMF ED09 f:58.2 r:90.

BOOTH OPERATOR NOTE:

After each JPM, VERIFY the Synchroscope Switch is moved to a different position.


SOP-609A, Diesel Generator System. Section 5.7, Transferring From DG Supplying Alone to Normal or Alternate

Supply.




Examiner Note: The following steps are from SOP-609A, Section 5.7.

Perform Step: 1 5.7.A & 2nd bullet

TURN the synchroscope for the selected breaker ON. SS-1EA1-2 BKR 1EA1-2 SYNCHROSCOPE

Standard: PLACED SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE to ON and OBSERVED the synchroscope move approximately to the 12 o'clock position.

Comment: SAT UNSAT

Perform Step: 2 5.7.B

Using the DG VOLT CTRL, ADJUST running voltage to MATCH incoming voltage.

Standard: ADJUSTED 90-1EG1, DG 1 VOLT CTRL to RAISE or LOWER DG Output Voltage to match Running Volts

Documents

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM … · 2012. 8. 31. · Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP NRC 2012 JPM S-1 Rev c.docx INITIAL CONDITIONS: