ML031280253

Emergency Operating Procedures

ML031280253
Person / Time
Site:	Ginna
Issue date:	04/30/2003
From:	Widay J Rochester Gas & Electric Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031280253 (92)

Text

Ri ASubsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORATION

• 89 EASTAVENUE, ROCHESTER, N Y 146490001

• 716-771-3250 wwwrge corn JOSEPH A WIDAY VICE PRESIDENT& PLANT MANAGER GINNA STATION April 30, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, ea.L) sepA. Widay JAW/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

AP Index ATT Index ATT-14.1, Rev 6 AP-RCS.4, Rev 14 AP-RHR. 1, Rev 19 AP-RHR.2, Rev 13 AP-TURB.4, Rev 17 Xd0

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NPSP0200 Ginna Nuclear Power Plant Wed 4/30/2003 11:03:56 am WRIGHTJ PROCEDURE INDEX Page 1 of 16 2aT trsvt- i nrye~r~wft.

• S~~  : tsrr e.._rlY - tIxtvTs - - - ~ t S S ~ ~ - i '-r X> e t e 1,i - -.m ^< wX >X

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INPUT PARAMETERS: TYPE: PRATT. PRAP, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY:

¶1 7 , 4 - 2 sr X--rb-_Y IrrV A ABNRA. i ROCED P .rE4 PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCW 1 LEAKAGE INTO THE COMPONENT COOLING LOOP 015 06/26/2002 06/26/2002 06/26/2007 EF AP-CCW 2 LOSS OF CCW DURING POWER OPERATION 017 11/19/2002 06/26/2002 06/26/2007 EF AP-CCW 3 LOSS OF CCW - PLANT SHUTDOWN 015 11/19/2002 06/26/2002 06/26/2007 EF AP-CR 1 CONTROL ROOM INACCESSIBILITY 019 02/25/2003 06/26/2002 06/26/2007 EF AP-CVCS 1 CVCS LEAK 013 06/26/2002 06/03/2002 06/03/2007 EF AP-CVCS 3 LOSS OF ALL CHARGING FLOW 003 06/26/2002 02/26/1999 02/26/2004 EF AP-CW 1 LOSS OF A CIRC WATER PUMP O11 06/26/2002 04/16/2003 04/16/2008 EF AP-ELEC 1 LOSS OF 12A AND/OR 12B BUSSES 024 02/25/2003 06/26/2002 06/26/2007 EF AP-ELEC 2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 010 06/26/2002 06/26/2002 06/26/2007 EF AP-ELEC 3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 011 06/26/2002 06/26/2002 06/26/2007 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 004 06/26/2002 06/26/2002 06/26/2007 EF AP-ELEC 17/18 LOSS OF SAFEGUARDS BUS 17/18 004 06/26/2002 06/26/2002 06/26/2007 EF AP-FW 1 ABNORMAL MAIN FEEDWATER FLOW 014 07/25/2002 06/26/2002 06/26/2007 EF AP-IA 1 LOSS OF INSTRUMENT AIR 018 06/26/2002 04/16/2003 04/16/2008 EF AP-PRZR 1 ABNORMAL PRESSURIZER PRESSURE 013 06/26/2002 06/26/2002 06/26/2007 EF AP-RCC 1 CONTINUOUS CONTROL ROD WITHDRAWALANSERTION 008 06/26/2002 04/16/2003 04/16/2008 EF AP-RCC 2 RCC/RPI MALFUNCTION 010 06/26/2002 01/22/2002 01/22/2007 EF AP-RCC 3 DROPPED ROD RECOVERY 006 02/25/2003 02/25/2003 02/25/2008 EF AP-RCP 1 RCP SEAL MALFUNCTION 014 06/26/2002 04/24/2003 04/24/2008 EF AP-RCS 1 REACTOR COOLANT LEAK 016 06/26/2002 04/16/2003 04/16/2008 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW O11 06/26/2002 04/16/2003 04/16/2008 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 010 06/26/2002 04/01/2002 01/22/2007 EF AP-RCS 4 SHUTDOWN LOCA 014 04/30/2003 04/30/2003 04/30/2008 EF AP-RHR.1 LOSS OF RHR 019 04/30/2003 04/30/2003 04/30/2008 EF AP-RHR 2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS 013 04/30/2003 04/30/2003 04/30/2008 EF AP-SG 1 STEAM GENERATOR TUBE LEAK 003 11/21/2002 06/26/2002 06/26/2007 EF AP-SW 1 SERVICE WATER LEAK 017 06/26/2002 04/21/2003 04/21/2008 EF AP-SW 2 LOSS OF SERVICE WATER 002 06/26/2002 10/31/2001 10/31/2006 EF AP-TURB I TURBINE TRIP WITHOUT RX TRIP REQUIRED O11 06/26/2002 06/26/2002 06/26/2007 EF AP-TURB 2 TURBINE LOAD REJECTION 018 06/26/2002 06/26/2002 06/26/2007 EF

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(7 (7 (7 NPSP0200 Ginna Nuclear Power Plant Wed 4/30/2003 11 03 56 am WRIGHTJ PROCEDURE INDEX Page 2 of 16 INPUT PARAMETERS: TYPE: PRATT, PRAP, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB 3 TURBINE VIBRATION 011 06/26/2002 06/26/2002 06/26/2007 EF AP-TURB 4 LOSS OF CONDENSER VACUUM 017 04/30/2003 04/30/2003 04/30/2008 EF AP-TURB 5 RAPID LOAD REDUCTION 006 06/26/2002 06/26/2002 06/26/2007 EF PRAP TOTAL: 33

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NPSP0200 Ginna Nuclear Power Plant Wed 4/30/2003 11 03:56 am WRIGHTJ PROCEDURE INDEX Page 3 of 16 INPUT PARAMETERS: TYPE: PRATT, PRAP, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY:

PRATT- -- ATTAC Trr t. ~.v-T-S- -. -rI EOP----,"--.-prv -, ,- -'I I PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT REV DATE REVIEW REVIEW ST NUMBER PROCEDURE TITLE ATT-1 0 ATTACHMENT AT POWER CCW ALIGNMENT 003 02/12/2003 02/12/2003 02/12/2008 E:

ATT-1 1 ATTACHMENT NORMAL CCW FLOW 000 05/18/2000 05/18/2000 05/18/2005 E:

ATT-2 1 ATTACHMENT MIN SW 005 02/01/2001 02/03/2003 02/03/2008 E:

EF ATT-2 2 ATTACHMENT SW ISOLATION 008 03/06/2002 03/27/2003 03/27/2008 E:

EF ATT-2 3 ATTACHMENT SW LOADS IN CNMT 004 03/06/2002 12/31/1999 12/31/2004 E:

EF ATT-2 4 ATTACHMENT NO SW PUMPS 001 01/08/2002 10/31/2001 10/31/2006 EF ATT-2 5 ATTACHMENT SPLIT SW HEADERS 000 06/26/2002 06/26/2002 06/26/2007 EF ATT-3 0 ATTACHMENT CVCVI 006 03/06/2002 01/06/1999 01/06/2004 EF ATT-3 1 ATTACHMENT CNMT CLOSURE 004 03/06/2002 01/25/1999 01/25/2004 EF ATT-4 0 ATTACHMENT CNMT RECIRC FANS 003 07/26/1994 03/27/2003 03/27/2008 EF ATT-5 0 ATTACHMENT COND TO S/G 005 03/06/2002 12/31/1999 12/31/2004 EF ATT-5 1 ATTACHMENT SAFW 008 05/30/2002 12/31/1999 12/31/2004 EF ATT-5 2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 01/14/1999 01/14/1999 01/14/2004 EF ATT-6 0 ATTACHMENT COND VACUUM 003 12/18/1996 02/03/2003 02/03/2008 EF ATT-7 0 ATTACHMENT CR EVAC 006 03/06/2002 02/03/2003 02/03/2008 EF ATT-8 0 ATTACHMENT DC LOADS 006 03/22/1999 01/14/1999 01/14/2004 EF ATT-8 1 ATTACHMENT D/G STOP 005 03/06/2002 02/03/2003 02/03/2008 E:

EF ATT-8 2 ATTACHMENT GEN DEGAS 008 06/20/2002 08/17/1999 08/17/2004 E:

EF ATT-8 3 ATTACHMENT NONVITAL 004 03/06/2002 02/03/2003 02/03/2008 E:

ATT-8 4 ATTACHMENT SVUV 005 03/06/2002 02/03/2003 02/03/2008 ATT-8 5 ATTACHMENT LOSS OF OFFSITE POWER 000 05/02/2002 05/02/2002 05/02/2007 ATT-9 0 ATTACHMENT LETDOWN 008 03/06/2002 03/06/2002 03/06/2007 EF ATT-9 1 ATTACHMENT EXCESS LID 005 03/06/2002 10/31/2001 10/31/2006 ATT-10 0 ATTACHMENT FAULTED S/G 006 03/06/2002 03/27/2003 03/27/2008 EF ATT-11 0 ATTACHMENT IA CONCERNS 002 04/07/1997 03/27/2003 03/27/2008 EF ATT-11 1 ATTACHMENT IA SUPPLY 003 03/06/2002 03/27/2003 03/27/2008 EF ATT-11 2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/2002 03/10/2003 03/10/2008 EF ATT-12 0 ATTACHMENT N2 PORVS 005 02/12/2003 02/12/2003 02/12/2008 EF ATT-13 0 ATTACHMENT NC 003 02/12/2003 02/12/2003 02/12/2008 ATT-14 0 ATTACHMENT NORMAL RHR COOLING 003 03/06/2002 09/23/1999 09/23/2004

( ( C *'Y' NPSP0200 Ginna Nuclear Power Plant Wed 4/30/2003 11.03:56 am WRIGHTJ PROCEDURE INDEX Page 4 of 16 INPUT PARAMETERS: TYPE: PRATT, PRAP, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY:

PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER

• PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-14 1 ATTACHMENT RHR COOL 006 04/30/2003 01/08/2002 01/08/2007 EF ATT-14 2

• ATTACHMENT RHR ISOL 003 02/12/2003 02/12/2003 02/12/2008 EF ATT-14 3 ATTACHMENT RHR NPSH 003 03/06/2002 01/06/1999 01/06/2004 ATT-14 5 ATTACHMENT RHR SYSTEM 003 03/20/2003 02/03/2003 02/03/2008 EF ATT-14 6 ATTACHMENT RHR PRESS REDUCTION 002 03/06/2002 01/1411999 01/14/2004 EF ATT-15 0 ATTACHMENT RCP START 009 03/06/2002 03/17/2000 03/17/2005 EF ATT-15 1 ATTACHMENT RCP DIAGNOSTICS 003 04124/1997 02/03/2003 02/03/2008 ATT-15 2 ATTACHMENT SEAL COOLING 005 03/06/2002 02/03/2003 02/03/2008 ATT-16 0 ATTACHMENT RUPTURED SIG 011 07/18/2001 01/11/2000 01/11/2005 ATT-16 1 ATTACHMENT SGTL 002 03/06/2002 09/08/2000 09/08/2005 EF ATT-16 2 ATTACHMENT RCS BORON FOR SGTL 002 04/09/2002 09/0812000 09/08/2005 EF ATT-17 0 ATTACHMENT SD-i 014 06/20/2002 02/29/2000 02/28/2005 EF ATT-17 1 ATTACHMENT SD-2 006 03/06/2002 01/30/2001 01/30/2006 EF ATT-18 0 ATTACHMENT SFP - RWST 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-20 0 ATTACHMENT VENT TIME 003 07/26/1994 02/03/2003 02/03/2008 EF EF ATT-21 0 ATTACHMENT RCS ISOLATION 002 03/06/2002 02/03/2003 02/03/2008 EF ATT-22 0 ATTACHMENT RESTORING FEED FLOW 003 05/02/2002 01/22/2002 01/22/2007 EF ATT-23 0 ATTACHMENT TRANSFER 4160V LOADS 000 02/26/1999 02/26/1999 02/26/2004 ATT-24 0 ATTACHMENT TRANSFER BATTERY TO TSC 000 09/08/2000 09/08/2000 09/08/2005 ATT-26 0 ATTACHMENT RETURN TO NORMAL OPERATIONS 000 10/31/2001 10/31/2001 10/31/2006 PRATT TOTAL: 50

EOP: TITLE:

REV: 6 ATT-14.1 ATTACHMENT RHR COOL PAGE 1 of 6 Responsible Manager __ _ Date 3o OLC)

NOTE: Maintain operating RCP #1 seal DP greater than 220 psid.

1. Maintain RCS Temp < 3500F AND align the RHR system for shutdown operations as follows:

2. Open RHR Heat Exchanger bypass (HCV-626) isolation valves:-

• V-712A

• V-712B

3. Ensure closed the following valves:

• RHR PUMP DISCHARGE TO RX VESSEL DELUGE MOV-852A

• RHR PUMP DISCHARGE TO RX VESSEL DELUGE MOV-852B

4. Open RHR Pump discharge crosstie valves

• V-709C

• V-709D

5. Open RHR PUMP DISCHARGE TO SI PUMP SUCTION MOV-857C

6. Verify RHR PUMP SUCTION FROM RWST MOV-856 open.

NOTE: WHEN the next step is performed, THEN Annunciator A-20 will light.

7. Start one RHR Pump AND locally throttle open RHR PUMP DISCHARGE TO SI PUMP SUCTION valves MOV-857A and 857B to maintain combined flow of < 1500 GPM as read on FI-931A and 931B.

• RHR Pump Started

• MOV-857A Throttled

• MOV-857B Throttled

8. Throttle RHR Flow control valves to 50% open

• HCV-624 Throttled

• HCV-625 Throttled

• HCV-626 Throttled

9. AFTER the RHR Pump has run 10 minutes, THEN obtain a sample

-of RHR:System to verify Boron Concentration is greater than RCS Boron Concentration. If not, .continue running RHR- Pump until RCS Boron Concentration is acceptable.

NOTE: WHEN the next step is performed, THEN Annunciator A-20 will extinguish.

10. Stop the running RHR PUMP.

11. Place RHR suction from RWST MOV-856 Key Switch to ON.

12. Close RHR PUMP SUCTION FROM RWST MOV-856.

13. Close RHR PUMP DISCHARGE TO SI PUMP SUCTION MOVs

• MOV-857A

• MOV-857B

• MOV-857C NOTE: DO NOT remove fuses.

14. Open the following breakers (Bkr):

• MOV-857A (MCC C Pos 7M) Bkr

• MOV-857B (MCC D Pos 7M) Bkr

• MOV-857C (MCC C Pos 15J) Bkr

15. Close RHR Flow control valves

• HCV-624

• HCV-625

• HCV-626

16. Close RHR PUMP SUCTION FROM CNMT SUMP B MOV-851A breaker (MCC C Pos 10M).

17. Close RHR PUMP SUCTION FROM CNMT SUMP B MOV-851B breaker (MCC D Pos 10M).

18. Close RHR PUMP SUCTION FROM CNMT SUMP B MOVs. IF MOV-851A and/or MOV-851B will NOT close, THEN consult Plant Staff to determine if MOV-850A and/or MOV-850B should be closed.

• MOV-851A

• MOV-851B NOTE: DO NOT remove fuses.

19. Open RHR PUMP SUCTION FROM CNMT SUMP B MOV-851A breaker (MCC C Pos 10M).

EDP: TITLE: R V hEOP:REV: 6 ATT-14.1 ATTACHMENT RHR COOL I PAGE 3 of 6

20. Open RHR PUMP SUCTION FROM CNMT SUMP B MOV-851B breaker (MCC D Pos 10M).

21. WHEN Primary System pressure reaches 350 to 360 psig, THEN perform the following:

22. To prevent flashing in the CCW System, start a second Component Cooling Water Pump and put a second Component Cooling Water Heat Exchanger into service.

NOTE: IF FI-619 (PPCS point F0619) is > 4900 gpm, THEN notify the Shift Supervisor (Flow induced vibration concern).

23. With two CCW HX's in service, ensure CCW flow is < 4900 gpm.

24. Control RCS pressure using PRZR heaters and spray as follows:

24.1 IF at least one RCP is running, THEN reduce RCS pressure to approximately 325 psig and stabilize pressure, unless otherwise directed by procedure in effect.

24.2 IF NO RCP running, THEN stabilize RCS pressure between 350 and 360 psig, unless otherwise directed by procedure in effect.

25. Enable LTOP RCS pressure alarms associated with Annunciator F-29 as follows:

25.1 Replace annunciator window F-29 with LTOP RCS pressure alarm window.

25.2 On PPCS, substitute a value of one (1) for point ID KPLTOP.

25.3 Substitute a value for P0420 or P0420A greater than 390 psig.

25.4 Verify that annunciator F-29 alarms.

25.5 Restore selected point to processing.

25.6 Verify that annunciator F-29 clears.

25.7 Substitute a value for P0420 or P0420A less than 300 psig.

25.8 Verify that annunciator F-29 alarms.

25.9 Restore selected point to processing.

25.10 Verify that annunciator F-29 clears.

EOP: TITLE: REV: 6 ATT-14.1 ATTACHMENT RHR COOL PAGE 4 of 6

26. Open CCW to RHR HX A MOV-738A.

27. Open CCW to RHR HX B MOV-738B.

NOTE: IF FI-619 (PPCS point F0619) is > 4900 gpm, THEN notify the Shift Supervisor (Flow induced vibration concern).

28. AFTER MOV-738A and MOV-738B are open, verify CCW flow is

< 4900 gpm on FI-619.

29. Verify LOW PRESS LTDN PRESS PI-135 PCV-135 setpoint set to 300 psig.

30. Open RHR HX BYPASS HCV-626 to 25% to ensure RHR System pressure equalization.

31. Station an Auxiliary Operator at RHR pressure indicator PIC-629 (South of Spent Fuel Pool Pump A).

32. IF letdown NOT in service, THEN perform the following:

a. Place switches for AOV-200A, 200B, 202 to CLOSE

b. Open AOV-427 (reset XY relays, if necessary)

c. Open AOV-200A

d. Go to Step 34

33. Ensure CVCS letdown aligned up to PCV-135.

34. SLOWLY open RHR LETDOWN TO CVCS HCV-133 to 100% to fill AND pressurize the RHR system.

35. Verify RHR pressure (PIC-629) is within 200 psig of RCS pressure (P-420 or P-420A). Additional letdown orifice valves may be opened to help equalize pressure.

36. Remove AND reinsert control power fuses for RHR PUMP SUCTION FROM LOOP A HOT LEG MOV-700. (MCC C Pos 7F)

37. Close MOV-700 breaker (MCC C Pos 7F).

38. Remove AND reinsert control power fuses for RHR PUMP SUCTION FROM LOOP A HOT LEG MOV-701. (MCC D Pos 7F)

39. Close MOV-701 breaker (MCC D Pos 7F).

40. Open RHR PUMP SUCTION FROM LOOP A HOT LEG MOVs.

• MOV-701

• MOV-700

EOP- ' TITLE:

REV: 6 ATT-14.1 ATTACHMENT RHR COOL PAGE 5 of 6

41. Verify closed RHR HX flow control valves.

• HCV-626

• HCV-625

• HCV-624 NOTE: IF letdown in service, THEN it may be necessary to close down PCV-135 following RHR Pump start to maintain < 70 gpm Letdown flow. This can be done by raising PCV-135 AUTO setpoint OR taking MANUAL control of PCV-135 AND closing.

NOTE: IF letdown in service, THEN PI-135 may read 100 psi greater than PI-420 due to RER Pump shutoff head.

NOTE: Annunciator A-20 will light.

42. Start one RHR PUMP.

NOTE: DO NOT run two (2) RER pumps with the discharge crossties open AND flow < 1200 gpm.

43. IF letdown in service, THEN adjust Low Press LTDN Press PCV-135 to establish desired Letdown flow (FI-134).

NOTE: PCV-135 (Letdown flow) determines the amount of flow during this temperature equalization.

44. Maintain flow at a minimum through HCV-624 and HCV-625 for 5 minutes to equalize the temperature of the RHR Loops.

45. Perform the following to establish the RHR System as a heat sink and secure the Steam Generators as heat sinks:

NOTE: To prevent flashing in the CCW System, ensure 2 CCW Pumps and 2 CCW Heat Exchangers are in service.

45.1 Remove AND reinsert control power fuses for RHR PUMP DISCHARGE TO LOOP B COLD LEG MOV-720.

45.2 Close MOV-720 breaker (MCC C Pos 7C).

45.3 Remove AND reinsert control power fuses for RHR PUMP DISCHARGE TO LOOP B COLD LEG MOV-721.

45.4 Close MOV-721 breaker (MCC D Pos 7C).

EOP TITLE: REV 6 ATT-14.1 ATTACHMENT RHR COOL PAGE 6 of 6 45.5 Open RHR PUMP DISCHARGE TO LOOP B COLD LEG.

• MOV-720

• MOV-721 45.6 Manually increase RHR flow and adjust HCV-624, HCV-625, and HCV-626; while simultaneously reducing Steam Generator feeding AND steaming rate to control RCS temperature.

NOTE: Maximizing feeding and steaming during subsequent cooldown on RHR will assist in SG cooling, and allow access as soon as possible.

45.7 WHEN Steam Generator feeding AND steaming has been reduced to the desired rate or secured, THEN continue increasing RHR flow AND/OR adjust HCV-624, HCV-625, and HCV-626 as necessary to establish the desired cooldown rate.

45.8 IF letdown in service, THEN readjust Low Press LTDN Press PCV-135 to re-establish desired letdown flow.

NOTE: FI-626 flow indication will be lost during reset of flow alarm.

45.9 Notify I&C to reset RHR flow alarm to 400 gpm.

45.10 WHILE I&C resets the RHR flow alarm, THEN place RHR HX BYPASS HCV-626 in MANUAL.

45.11 Open RHR LETDOWN TO CVCS HCV-133.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __3 RESPONSIBLE \t NAGER EF CI-

-F3 AToo EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions for protecting the reactor core in the event of a loss of coolant accident (LOCA) that occurs during Mode 3 after the SI accumulators are isolated or Mode 4.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. AP-RHR.1, LOSS OF RHR, when RCS leak is indicated with RCS temperature greater than 2000F.

2. SYMPTOMS - The symptoms of shutdown loss of coolant accident during Modes 3 and 4 are:

a. Uncontrolled decrease in PRZR level, or

b. Uncontrolled decrease in RCS subcooling, or

c. Radiation alarms in CNMT, or

d. CNMT sump level alarms

NOTE: o Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

o Adverse CNMT conditions should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

• 1 Monitor RCS Conditions: Perform the following:

o RCS subcooling based on core a. Stop RHR pumps and place in PULL exit T/Cs - GREATER THAN 00 F STOP.

FIG-1.0, FIGURE MIN SUBCOOLING

b. Close RHR discharge valves to SI o PRZR level - GREATER THAN 5% pump suction

[30% adverse CNMT]

• MOV-857A

• MOV-857B

• MOV-857C 2 Isolate RCS Letdown:

a. Close letdown isolation. AOV-427

b. Place letdown orifice valve switches to CLOSE (AOV-200A.

AOV-200B, and AOV-202)

c. Close letdown isolation, AOV-371

d. Close RHR letdown to CVCS.

HCV-133

e. Place letdown pressure controller. PCV-135, in MANUAL and close valve (demand at 100%)

f. Close excess letdown isolation valve, AOV-310

ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl NOTE: IF the RCS is water solid. THEN charging should be controlled to maintain RCS pressure.

3 Establish Required RCS Injection Flow:

a. Charging pumps - ANY RUNNING a. Perform the following:

1) IF CCW flow is lost to any RCP thermal barrier OR any #1 seal outlet temperature offscale high, THEN dispatch AO to locally isolate seal injection to affected RCP.

• RCP A, V-300A

. RCP B, V-300B

2) Ensure HCV-142 open, demand at 0%.

b. Align charging pump suction to b. IF LCV-112B can NOT be opened.

RWST: THEN dispatch AO to locally open V-358, manual charging pump o LCV-112B -OPEN suction from RWST (charging pump room).

o LCV-112C -CLOSED IF LCV-112C can NOT be closed, THEN perform the following:

1) Direct AO to locally open V-358. manual charging pump suction from RWST (charging pump room).

2) Verify charging pump A NOT running and place in PULL STOP.

3) WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).

c. Start charging pumps (75 kw) and adjust charging flow to maintain PRZR level

4 Verify Charging Flow Adequate:

a. Check the following: a. Go to Step 5.

o RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING FIG-l.O. FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%

[30% adverse CNMT]

o PRZR level - STABLE OR INCREASING

b. Verify charging flow needed to b. Go to Step 7.

maintain PRZR level stable -

LESS THAN 75 gpm (PPCS point FCHG)

c. Go to AP-RCS.1. REACTOR COOLANT LEAK

CAUTION o IF RWST LEVEL DECREASES TO LESS THAN 28%. THEN THE SI SYSTEM SHOULD BE ALIGNED FOR SUMP RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEPS 1 THROUGH 14.

o RP TECH SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.

• * * * * * * * * * * * * * * * * * * * * * * * *

• A * * * * * * * * * * * * *

• 5 Verify SI Injection Capability:

a. Check RCS temperature - LESS a. Perform the following:

THAN 3500 F

1) Ensure SI pump discharge valves to RCS cold legs - OPEN

. SI Pump A. MOV-878B 2 SI Pump B. MOV-878D

2) Go to Step 5c.

b. SI pump discharge valves to RCS b. Manually open valves. Dispatch

- OPEN AO to locally restore power to the following if necessary

• SI pump A. MOV-878A and (locked valve key required):

MOV-878B

. SI pump B. MOV-878C and

• MOV-878A. MCC C position 8C MOV-878D

• MOV-878B. MCC D position 8C

• MOV-878C, MCC C position 8F

. MOV-878D, MCC D position 8F

c. SI pumps - AT LEAST TWO PUMPS c. Dispatch AO to restore power to AVAILABLE at least two SI pump(s). if necessary.

• SI pump A. Bus 14 position 20A

• SI pump B. Bus 16 position 12A

. SI pump C. Bus 14 position 19A OR Bus 16 position 13A

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish SI Flow:

a. Verify the following valves - a. Manually open valves.

OPEN

. RWST outlet valves (MOV-896A and MOV-896B)

. SI pump C suction valves (MOV-1815A and MOV-1815B)

b. Open SI pump suction valves from b. Ensure at least one SI pump RWST: suction valve from RWST open.

. MOV-825A . MOV-825A

. MOV-825B . MOV-825B

c. Start ONE SI pump 7 Initiate Actions To Protect Personnel In CNMT:

a. Evacuate personnel from CNMT

b. Periodically monitor CNMT radiation

ACTION/EXPECTED RESPONSE SP RESPONSE NOT OBTAINED 8 Establish Required CNMT Conditions:

a. Depress MANUAL CNMT ISOLATION pushbutton

b. Verify CI/CVI valves - CLOSED b. Manually close CI and CVI valves. IF valves can NOT be verified closed by MCB indication. THEN dispatch AO to locally close valves (Refer to ATT-3.0, ATTACHMENT CI/CVI).

c. Start all available CNMT RECIRC fans (205 kw each)

d. Dispatch AO to locally fail open CNMT RECIRC fan cooler SW outlet valves (INT BLDG basement by MG sets)

. FCV-4561

• FCV-4562

• 9 Monitor RCP Operation:

a. RCPs - ANY RUNNING a. Go to Step 10.

b. Check RCP #1 seal D/P - GREATER b. Stop affected RCP(s) and go to THAN 220 PSID Step 9d.

c. Check RCP #1 seal leakoff - c. IF RCP #1 seal failure is WITHIN THE NORMAL OPERATING suspected. THEN stop affected RANGE OF FIG-4.0, FIGURE RCP RCP(s).

SEAL LEAKOFF

d. Ensure PRZR spray valves - CLOSED

• PCV-431A

• PCV-431B

10 Check RHR Pump Status:

a. RHR pumps aligned for injection a. Go to Step 11.

mode:

o RWST to RHR pump suction valve. MOV-856 - OPEN o RHR suction valves from loop A hot leg (MOV-700 and MOV-701) - CLOSED

b. Go to Step 12

ACTIN/EXNCTE OBTAINNSE NOTE: Continue with this procedure starting at Step 13 while aligning RHR for injection. WHEN RHR aligned, THEN do Step 12.

11 Establish RHR Injection Alignment:

a. Stop any running RHR pump

b. Close RHR normal cooling valves: b. Ensure at least one suction valve and one discharge valve o RHR suction valves from loop closed.

A hot leg (MOV-700 and MOV-701) - CLOSED o RHR discharge valves to loop B cold leg (MOV-720 and MOV-721) - CLOSED

c. Verify alignment of RHR suction valves from sump B:

1) MOV-850A and MOV-850B 1) Close MOV-850A and MOV-850B.

(outside CNMT) - CLOSED Do NOT continue until valves closed.

2) MOV-851A and MOV-851B (inside 2) Open MOV-851A and MOV-851B.

CNMT) - OPEN

d. Verify open RHR pump suction d. Manually open valves.

valves (MOV-704A and MOV-704B)

e. Check RHR pump suction e. Go to Step 13.

temperature - LESS THAN 2800F (PPCS point T0684A or T0684B)

f. Open RWST to RHR pump suction valve, MOV-856 (energize DC control power key switch)

g. Place RHR Hx bypass valve.

HCV-626, to MANUAL and close valve

h. Open RHR Hx flow control valves (HCV-624 and HCV-625)

i. Open RHR core deluge valves (MOV-852A and MOV-852B)

12 Check If RHR Injection Flow Required:

a. RCS subcooling based on core a. Perform the following: I exit T/Cs - GREATER THAN 00 F USING FIG-1.0. FIGURE MIN 1) Open RHR core deluge valves I SUBCOOLING

• MOV-852A

. MOV-852B

2) Start one RHR pump. I 13 Verify Adequate SI Flow:

a. Check RVLIS - AVAILABLE a. IF PRZR level greater than 5%

[30% adverse CNMT] and stable or increasing, THEN go to Step 13c.

IF NOT, THEN start to SI pumps to restore PRZR level to greater than 5% [30% adverse CNMT] and stable or increasing and go to Step 14.

b. Check RVLIS indication: b. Start SI pump(s) to restore RVLIS level (no RCPs) or fluid o Level (no RCPs) - GREATER fraction (any RCP running) and THAN 77% [82% adverse CNMT] go to Step 14.

-OR-o Fluid fraction (any RCP running) - GREATER THAN 84%

c. Core exit T/Cs - STABLE OR c. Start SI pump(s) to stabilize or DECREASING decrease core exit T/Cs.

ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl 14 Check RCS Hot Leg Control steam dump (or ARVs) and Temperatures - STABLE total feed flow to stabilize RCS temperature.

15 Initiate Evaluation Of Plant Status:

a. Attempt to identify and isolate RCS break

b. Check AUX BLDG radiation - NORMAL b. Attempt to identify and isolate leakage to AUX BLDG (Refer to

. Plant vent iodine (R-1OB) AP-RCS.1. REACTOR COOLANT LEAK).

• Plant vent particulate (R-13)

. Plant vent gas (R-14)

• CCW liquid monitor (R-17)

• CHG pump room (R-4)

c. Direct RP to obtain the following samples:

. RCS boron

• RCS activity

• CNMT hydrogen

. CNMT sump

d. Evaluate and operate equipment as necessary:

. CCW pumps

• SW pumps

. Charging pumps

. CNMT RECIRC fans

• Steam dump/ARVs

• VCT makeup system

EOP: TITLE:

REV: 14 AP-RCS.4 SHUTDOWN LOCA PAGE 13 of 35 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 16 Reset SI 17 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED 18 Verify Adequate Service Water Flow:

a. Check at least two SW pumps - a. Manually start pumps as power RUNNING supply permits (257 kw each).

b. SW header pressure - GREATER b. Manually align valves to restore THAN 40 PSIG IN EACH LOOP SW pressure greater than 40 psig in each loop. (Refer to AP-SW.2. LOSS OF SERVICE WATER)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Establish IA To CNMT:

a. Verify non-safeguards busses a. Restore IA supply as follows:

energized from offsite power

1) IF electric air compressor is o Bus 13 normal feed - CLOSED desired. THEN perform the following:

-OR-a) Close non-safeguards bus o Bus 15 normal feed - CLOSED tie breakers:

. Bus 13 to Bus 14 tie

. Bus 15 to Bus 16 tie b) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT. THEN evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS).

c) WHEN bus 15 restored. THEN reset control room lighting.

d) Go to step 19b.

2) IF diesel air compressor is desired, THEN restore IA supply using the diesel air compressor. (Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

b. Verify turbine building SW b. Manually align valves.

isolation valves - OPEN

. MOV-4613 and MOV-4670

• MOV-4614 and MOV-4664 This Step continued on the next page.

(Step 19 continued from previous page)

c. Verify adequate air c. Manually start air compressors compressor(s) - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as -

necessary.

IF electric air compressor can NOT be started. THEN use diesel air compressor. (Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

d. Check IA supply: d. Perform the following:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 20. WHEN IA restored, THEN do Steps 19e and f.

e. Reset both trains of XY relays for IA to CNMT AOV-5392

f. Verify IA to CNMT AOV-5392 - OPEN 20 Check PRZR PORV Block Valves:

a. Power to PORV block valves - a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

• MOV-515, MCC D position 6C

• MOV-516, MCC C position 6C

b. Block valves - AT LEAST ONE OPEN b. Open one block valve unless it was closed to isolate an open PORV.

• * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• a

• CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRESSURE, THEN STEP 21 SHOULD BE PERFORMED AFTER PRESSURE DECREASES TO LESS THAN THE APPLICABLE PORV SETPOINT.

21 Monitor PRZR PORV Status:

a. Check Reactor Vessel a. Go to Step 21d.

overpressure protection system -

IN SERVICE

b. Check RCS pressure - LESS THAN b. Verify at least one PRZR PORV 410 PSIG open. Continue with Step 22.

WHEN pressure less than setpoint. THEN do Step 21e.

c. Go to Step 21e

d. Check PRZR pressure - LESS THAN d. Verify at least one PRZR PORV 2335 PSIG open. Continue with Step 22.

WHEN pressure less than setpoint. THEN do Step 21e.

e. Verify PRZR PORVs - CLOSED e. Manually close PORVs. IF any PORV can NOT be closed. THEN manually close its block valve.

ATONEPETDRESPONSE NTOAIEI CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT]. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

• 22 Monitor If RHR Pumps Should Be Stopped:

a. RHR Pump running in injection a. Go to Step 23.

mode

b. Check RCS pressure: b. Go to Step 23.

1) Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]

2) Pressure - STABLE OR INCREASING

c. Stop RHR pumps and place AUTO

ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDI CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1. ALTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

23 Monitor S/G Levels:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 17% [25%

adverse CNMT] in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in any SIG narrow range level between 17% continues to increase. THEN stop

[25% adverse CNMT] and 50% feed to that S/G.

24 Check If RCS Overpressure Protection Should Be Placed In Service:

a. Check the following: a. Go to Step 25.

o RCS cold leg temperature -

LESS THAN 3500 F o RCS pressure - LESS THAN 400 psig [300 psig adverse CNMT]

b. Place RCS overpressure protection in service (Refer to 0-7. ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check core exit T/Cs - Go to Step 27.

GREATER THAN 2000F NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to FIG-2.0, FIGURE SDM).

26 Initiate RCS Cooldown To Cold Shutdown:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 100OF/HR

b. Use RHR system if in service

c. Dump steam to condenser from S/Gs c. Manually or locally dump steam using S/G ARVs.

27 Check RCS Subcooling Based On Go to Step 46.

Core Exit T/Cs - GREATER THAN 0-F USING FIG-1.0, FIGURE MIN SUBCOOLING 28 Check If SI In Service: Go to Step 38.

o SI pumps - ANY RUNNING

-OR-o RHR pumps - ANY RUNNING IN INJECTION MODE

EOP: TITLE:

REV: 14 AP-RCS.4 SHUTDOWN LOCA PAGE 20 of 35

.~ ~ .

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 29 Place PRZR Heater Switches In The Following Positions:

o PRZR proportional heaters - PULL STOP o PRZR backup heaters - OFF 30 Check PRZR level - LESS THAN Go to Step 32.

13% [40% adverse CNMT]

CAUTION RCS SUBCOOLING MAY BE LOST TEMPORARILY WHILE PERFORMING DEPRESSURIZATION TO RESTORE PRZR LEVEL.

NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o WHEN using a PRZR PORV. THEN select one with an operable block valve.

31 Depressurize RCS To Refill PRZR:

a. Depressurize using normal PRZR a. IF normal spray NOT available, spray if available THEN use one PRZR PORV. IF IA NOT available. THEN refer to ATT-12.0. ATTACHMENT N2 PORVS.

IF NO PORV available. THEN use auxiliary spray valve (AOV-296).

b. PRZR level - GREATER THAN 13% b. Continue with Step 32. WHEN

[40% adverse CNMTI level greater than 13% [40%

adverse CNMT]. THEN do Step 31c.

c..Stop RCS depressurization

ACTION/EXPECTED RESPONSE STP e lRESPONSE NOT OBTAINEDl 32 Check If An RCP Should Be Started:

a. Both RCPs - STOPPED a. Perform the following:

1) Stop all but one RCP.

2) Place spray valve controller for idle RCP in MANUAL at 0%

demand.

3) Go to Step 33.

b. RCS subcooling based on core b. Go to Step 46.

exit T/Cs - GREATER THAN 00 F USING FIG-l.0, FIGURE MIN SUBCOOLING

c. PRZR level - GREATER THAN 13% c. Return to Step 30.

[40% adverse CNMT]

d. Try to start an RCP d. IF an RCP can NOT be started.

THEN perform the following:

1) Establish conditions for starting an RCP 1) Ensure at least one control rod shroud fan running a) Bus 11A or 11B energized (45 kw).

b) Refer to ATT-15.0. 2) Ensure one Rx compartment ATTACHMENT RCP START cooling fan running (23 kw).

2) Start one RCP

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Check RCS Cold Leg Go to Step 37.

Temperature - GREATER THAN 2850F CAUTION IF RHR PUMP SUCTION TEMPERATURE IS GREATER THAN 2500F (PPCS POINT ID T0684A OR T0684B). THEN CONSULT TSC BEFORE STARTING AN RHR PUMP.

34 Check SI Pump Status:

a. Three SI pumps - RUNNING a. Go to Step 35.

b. RCS subcooling Based on core b. IF RCS hot leg temperature exit T/Cs - GREATER THAN 350 F greater than 320°F [310'F

[900F adverse CNMT] using adverse CNMT] OR IF RHR normal FIG-1.O. FIGURE MIN SUBCOOLING cooling in service, THEN go to Step 46.

IF RHR normal cooling NOT in service AND RCS hot leg temperature less than 320'F

[3100F adverse CNMT]. AND RHR pump suction temperature less than 2500 F. THEN ensure at least one RHR pump running in injection mode and go to Step 34c. IF no RHR pump can be operated in injection mode.

THEN go to Step 46.

c. PRZR level - GREATER THAN 13% c. DO NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

d. Stop one SI pump

ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINEDl 35 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 36.

b. Determine required RCS subcooling from table Charging Pump RCS Subcooling Criteria Availability NONE 120'F [200'F adverse CNMT]

ONE 115'F [190'F adverse CNMT]

TWO 1050F [1800F adverse CNMT]

THREE 100'F [1750F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperature exit T/Cs - GREATER THAN VALUE greater than 320'F [310'F FROM TABLE ABOVE USING FIG-1.0. adverse CNMT] OR IF RHR normal FIGURE MIN SUBCOOLING cooling in service, THEN go to Step 46.

IF RHR normal cooling NOT in service AND RCS hot leg temperature less than 3200F

[3100F adverse CNMT], AND RHR pump suction temperature less than 250'F. THEN ensure at least one RHR pump running in injection mode and go to Step 35d. IF no RHR pump can be operated in injection mode.

THEN go to Step 46.

d. PRZR level - GREATER THAN 13% d. DO NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

e. Stop one SI pump

ACTION/EXPECTED RESPONSE STP RESPONSE NOT OBTAINED 36 Check If Last SI Pump Should Be Stopped:

a. Any SI pump - RUNNING a. Go to Step 38.

b. Determine required RCS subcooling from table Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 2550 F [2950F adverse CNMT]

TWO 2350 F [2850F adverse CNMT]

THREE 210'F [2700F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperature exit T/Cs - GREATER THAN greater than 320'F [3100F REQUIRED SUBCOOLING USING adverse CNMT] OR IF RHR normal FIG-l.O. FIGURE MIN SUBCOOLING cooling in service, THEN go to Step 46.

IF RHR normal cooling NOT in service AND RCS hot leg temperature less than 320'F

[3100F adverse CNMT]. AND RHR pump suction temperature less than 250'F. THEN ensure at least one RHR pump running in injection mode and go to Step 36d. IF no RHR pump can be operated in injection mode.

THEN go to Step 46.

d. PRZR level - GREATER THAN 13% d. DO NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

e. Stop SI pump

f. Go to Step 38

ACTION/EXPECTED RESPONSE PONSE NOT OBTAINED 37 Check If SI Pump Should Be Stopped:

a. Any SI pump - RUNNING a. Go to Step 38.

b. RCS pressure - GREATER THAN b. Go to Step 46.

295 psig [510 psig adverse CNMT]

c. PRZR level - GREATER THAN 13% c. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

d. Stop one SI pump

e. Return to Step 37a 38 Check If Charging Flow Should Be Controlled To Maintain PRZR Level:

a. Check RHR pumps - ANY RUNNING IN a. Start charging pumps and control INJECTION MODE charging flow to maintain PRZR level and go to Step 39.

b. Go to Step 46.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 39 Check RCP Status:

a. RCPs - AT LEAST ONE RUNNING a. Try to start one RCP

1) Establish conditions for starting an RCP a) Bus 11A or 11B energized b) Refer to ATT-15.0, ATTACHMENT RCP START

2) Start one RCP. IF an RCP can NOT be started., THEN verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC). IF natural circulation NOT verified, THEN increase dumping steam.

3) Go to Step 40.

b. Stop all but one RCP

EOP. TITLE: REV: 14 AP-RCS.4 SHUTDOWN LOCA PAGE 27 of 35 ACTION/EXPECTED RESPONSE STEP 1RESPONSE NOT OBTAINED CAUTION DEPRESSURIZING THE RCS MAY RESULT IN LOSING THE MINIMAL RCP #1 SEAL OPERATING CONDITIONS. THIS WILL REQUIRE THE RCPS TO BE TRIPPED.

NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o WHEN using a PRZR PORV, THEN select one with an operable block valve.

40 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR a. IF normal spray NOT available.

spray if available THEN use one PRZR PORV. IF IA NOT available, THEN refer to ATT-12.0. ATTACHMENT N2 PORVS.

IF NO PORV available. THEN use auxiliary spray valve (AOV-296).

b. Energize PRZR heaters as necessary

c. Depressurize RCS until EITHER of the following conditions satisfied:

o PRZR level - GREATER THAN 75%

[65% adverse CNMT]

-OR-o RCS subcooling based on core exit T/Cs - LESS THAN 10'F USING FIG-1.0. FIGURE MIN SUBCOOLING

d. Stop RCS depressurization

41 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS for boron concentration

b. Verify boron concentration - b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIG-2.0. FIGURE SDM 42 Check If Letdown Can Be Established:

a. PRZR level - GREATER THAN 13% a. Go to Step 46.

[40% adverse CNMT]

b. Charging flow - LESS THAN 20 GPM b. Go to Step 46.

43 Establish Normal Letdown IF RCP seal return has been (Refer to ATT-9.0, ATTACHMENT established, THEN establish excess LETDOWN) letdown (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D)

IF RCP seal return NOT established, THEN consult TSC to determine if excess letdown should be placed in service.

RESPONSE NOT OBTAINED 44 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm

b. Adjust RMW flow control valve in AUTO to 40 gpm

c. Ensure the following:

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

d. Check VCT level: d. Manually increase VCT makeup flow as follows:

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- RMW pumps running. IF NOT, THEN reset MCC C and MCC D UV o Level - STABLE OR INCREASING lockouts.

2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow until VCT level greater than 20% OR stable or increasing.

EOP- TITLE:

REV: 14 AP-RCS.4 SHUTDOWN LOCA PAGE 30 of 35 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 45 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:

1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed

2) Continue with Step 46. WHEN VCT level greater than 40%.

THEN do Step 45.

b. Align charging pumps to VCT o LCV-112C - OPEN o LCV-112B - CLOSED

• 46 Monitor RCS Inventory:

a. Check the following: a. Perform the following:

o RCS subcooling based on core 1) Manually operate SI pumps to exit T/Cs - GREATER THAN 0 0F restore inventory and/or USING FIG-1.0, FIGURE MIN subcooling. DO NOT operate SUBCOOLING more than two SI pumps.

o PRZR level - GREATER THAN 5% 2) Go to Step 47.

[30% adverse CNMT]

b. Go to Step 48

EOP. TITLE:

REV: 14 AP-RCS.4 SHUTDOWN LOCA t

PAGE 31 of 35 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 47 Verify Adequate SI Flow:

a. Check RVLIS - AVAILABLE a. IF PRZR level greater than 5%

[30% adverse CNMT] and stable or increasing. THEN go to Step 47c.

IF NOT. THEN start SI pumps as necessary to restore PRZR level to greater than 5% [30% adverse CNMTI and stable or increasing and go to Step 48.

b. Check RVLIS indication: b. Start SI pumps as necessary to restore RVLIS level (no RCPs) or o Level (no RCPs) - GREATER fluid fraction (any RCP running)

THAN 77% [82% adverse CNMT] and go to Step 48.

-OR-o Fluid fraction (any RCP running) - GREATER THAN 84%

c. Core exit T/Cs - STABLE OR c. Start SI pumps as necessary to DECREASING stabilize or decrease core exit T/Cs.

48 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).

o Emergency D/G output breakers

- OPEN o AC emergency bus voltage -

GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

b. Stop any unloaded emergency D/G and place in standby-M(Rfer to ATT-8.1. ATTACHMENT D/G STOP)

ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl 49 Check RCP Cooling: Establish normal cooling to RCPs (Refer to ATT-15.2, ATTACHMENT SEAL

a. Check CCW to RCPs COOLING).

o Annunciator A-7, RCP A CCW RETURN HIGH TEMPERATURE OR LOW FLOW - EXTINGUISHED o Annunciator A-15, RCP B CCW RETURN HIGH TEMPERATURE OR LOW FLOW - EXTINGUISHED

b. Check RCP seal injection o Labyrinth seal D/P - GREATER THAN 15 INCHES o RCP seal injection flow -

GREATER THAN 6 GPM

PACTION/EXPECTED RESPONSE RPONSE NOT OBTAINED 50 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D - a. Restore power to instrument bus ENERGIZED D from MCC B or MCC A (maintenance supply).

b. Verify RCP #1 seal outlet b. Go to Step 51.

temperature - LESS THAN 2350F

c. Verify RCP SEAL DISCH VLVS - OPEN

• AOV-270A

• AOV-270B

d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

e. Open RCP seal return isolation e. Perform the following:

valve MOV-313

1) Place MOV-313 switch to open.

2) Dispatch AO to locally open MOV-313.

f. Verify RCP #1 seal leakoff flow f. Perform the following:

- LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve.

• RCP A. AOV-270A

. RCP B. AOV-270B IF both RCP SEAL DISCH VLVS closed. THEN go to Step 51

g. Verify RCP #1 seal leakoff flow g. Refer to AP-RCP.1. RCP SEAL

- GREATER THAN 0.8 GPM MALFUNCTION.

EOP TITLE:

REV: 14 AP-RCS.4 SHUTDOWN LOCA PAGE 34 of 35

)I STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in step 51.

51 Check CNMT Hydrogen Concentration:

a. Direct RP to start CNMT hydrogen monitors as necessary

b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.

52 Check If Normal RHR Cooling Can Be Established:

a. Check the following: a. Go to Step 53.

o RCS cold leg temperature -

LESS THAN 3500 F o RCS pressure - LESS THAN 400 psig [300 psig adverse CNMT]

b. Place RCS overpressure protection in service (Refer to 0-7. ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)

c. Consult plant staff to determine if RHR normal cooling should be established using ATT-14.1.

ATTACHMENT RHR COOL

'- - I I-EOP. TITLE.

REV: 14 AP-RCS.4 SHUTDOWN LOCA PAGE 35 of 35 l

ACTION/EXPECTED RESPONSEINED 53 Check core exit T/Cs - LESS Return to Step 22.

THAN 2000F 54 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions

b. Consult plant staff NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

55 Notify Higher Supervision

-END-

AP-RCS.4 APPENDIX LIST TITLE

1) FIGURE MIN SUBCOOLING (FIG-1.0)

2) FIGURE SDM (FIG-2.0)

3) FIGURE RCP SEAL LEAKOFF (FIG-4.0)

4) ATTACHMENT RHR COOL (ATT-14.1)

5) ATTACHMENT RCP START (ATT-15.0)

6) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)

7) ATTACHMENT NC (ATT-13.0)

8) ATTACHMENT SEAL COOLING (ATT-15.2)

9) ATTACHMENT D/G STOP (ATT-8.1)

10) ATTACHMENT N2 PORVS (ATT-12.0)

11) ATTACHMENT CI/CVI (ATT-3.0)

12) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

13) ATTACHMENT EXCESS L/D (ATT-9.1)

14) ATTACHMENT LETDOWN (ATT-9.0)

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE(1 ANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides guidance in the event of a loss of RHR cooling at or above normal loop levels.

(i.e. RCS loop levels of 64 inches or greater)

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from;

a. FR-C.3, RESPONSE TO SATURATED CORE COOLING, or

b. AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 3500F), when RHR flow can NOT be restored, or

c. AP-CCW.3, LOSS OF CCW - PLANT SHUTDOWN when CCW is inadequate for RHR cooling

2. SYMPTOMS - The following are symptoms of LOSS OF RHR;

a. No RHR pumps running, or

b. Annunciator A-20, RESIDUAL HEAT REMOVAL LOOP LO FLOW 2900 GPM (Set at 400 GPM per 0-2.2 in RHR Cooling mode), lit, or

c. Unexpected increase in temperature while on RHR cooling, or

d. Erratic or no flow on FI-626, RHR Loop Flow, or

e. Annunciator J-9, SAFEGUARD BREAKER TRIP, lit.

EOP: TITLE:

REV: 19 AP-RHR.1 - - LOSS OF RHR .

PAGE 3 of 14 NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Check PRZR Wide Range Level - IF RCS loop level indicator in GREATER THAN 0 INCHES service and loop level less than 64 inches. THEN go to AP-RHR.2.

LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.

2 Check RHR Pumps - AT LEAST IF running pump tripped due to loss ONE RUNNING of NPSH. THEN go to step 4.

IF NOT, THEN go to step 10.

ACTI~ON/XETE RESPONSE I CAUTION IF BOTH RHR PUMPS RUNNING WITH DISCHARGE CROSSTIES OPEN. THEN TOTAL RHR FLOW SHOULD BE MAINTAINED GREATER THAN 1200 GPM.

3 Check If RHR Pump(s) Should Be Stopped:

a. RHR pump - ANY RUNNING a. Go to Step 4.

b. Check RHR pump flow - LESS THAN b. Manually decrease RHR flow to 1500 GPM PER OPERATING PUMP less than 1500 gpm per operating pump. IF RHR flow can NOT be controlled from the MCB, THEN perform the following:

1) Stop running RHR pump.

2) Dispatch an AO with a locked valve key to locally close RHR Hx outlet valves.

. A RHR Hx, HCV-625 handwheel

. B RHR Hx, HCV-624 handwheel

3) Start an RHR pump.

4) Direct AO to locally adjust RHR flow to less than 1500 gpm.

c. RHR pumps cavitating: c. Go to Step 19.

o RHR pump flow - OSCILLATING

-OR-o RHR pump NPSH - APPROXIMATELY ZERO (PPCS Group Display NPSH)

d. Stop RHR pumps.

CAUTION o DO NOT INITIATE ANY ACTIONS WHICH MAY ADD POSITIVE REACTIVITY TO THE CORE.

o NOTIFY S/G OFFICE THAT CNMT BREATHING AIR MAY BE LOST.

o IF REFUELING IN PROGRESS. THEN STOP REFUELING OPERATIONS (NOTIFY REFUELING SRO).

NOTE: Personnel remaining in CNMT to assist in event mitigation should consult Health Physics for changes in radiological concerns.

4 Initiate Actions To Protect Personnel In CNMT:

a. Evacuate non-essential personnel from CNMT

b. Verify all available CNMT RECIRC b. Manually start available CNMT fan(s) - RUNNING RECIRC fans.

c. Initiate monitoring of CNMT area c. Refer to appropriate alarm and process radiation monitors response procedures for required actions.

d. Verify CNMT penetrations with d. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. close all CNMT direct access to outside penetrations to outside atmosphere - CLOSED (Refer to atmosphere.

ATT-3.1. ATTACHMENT CNMT CLOSURE)

ACTIN/EXECTE R E S P O N S EI CAUTION SYSTEM MAY BE PRESSURIZED. EXTRA CARE SHOULD BE EXERCISED WHEN OPERATING THE RHR VENT VALVE.

NOTE: If adequate time to completely vent the RHR system is not available.

then air can be swept out of the RHR lines by running an RHR pump at a flowrate between 1200 gpm and 1400 gpm.

5 Vent RHR System As Necessary

a. Check vent hose at RHR suction a. Go to step 6.

V-2764 - INSTALLED

b. Check RCS temperature - LESS b. Go to step 6.

THAN 2000 F

c. Maintain RCS level while venting RHR system

d. Direct AO to vent RHR suction line from loop A at V-2764 (in CNMT by loop A) 6 Check RHR Cooling Valve Manually or locally align valves as Alignment - NORMAL (Refer to necessary.

ATT-14.0, ATTACHMENT NORMAL RHR COOLING)

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl CAUTION THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.

• * * * * *

• a * * * * * * * * * *

• a * * * * *

• a * * * * * * * * * * * * *

• 7 Check IA Available For RHIR Perform the following:

Flow Control:

a. Manually start adequate air o Verify adequate air compressors compressors (75 kw each). IF

- RUNNING air compressors can NOT be started manually, THEN dispatch o Verify IA pressure - GREATER AO to locally reset and start THAN 60 PSIG compressors (75 kw each).

o IA available to HCV-624 AND IF electric air compressor(s)

HCV-625 can NOT be restored, THEN start diesel air compressor. (Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)

b. IF IA pressure can NOT be restored, THEN perform the following:

1) Dispatch AO with a locked valve key to locally close RFR Hx outlet valves.

• A RHR Hx. HCV-625 handwheel

. B RHR Hx, HCV-624 handwheel

2) WHEN conditions permit, THEN refer to AP-IA.1, LOSS OF INSTRUMENT AIR, to restore IA.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 8 Monitor RCS Temperature - Perform the following:

GREATER THAN 200 0 F

a. Notify Plant Staff to attempt to establish CUiMT integrity AND CNMT heat removal capability.

b. Go to step 10.

CAUTION o CHANGES IN RCS PRESSURE COULD RESULT IN INACCURACIES IN RCS LOOP LEVEL INDICATION o UNSTABLE OR FLUCTUATING LEVEL INSTRUMENTS SHOULD NOT BE RELIED ON FOR INDICATION OF RCS INVENTORY.

9 Verify RCS Intact: Perform the following:

o PRZR level - GREATER THAN 5% AND a. Verify charging line flow STABLE control valve. HCV-142, open as necessary.

o RCS pressure - STABLE

b. Ensure charging line valve to o RCS subcooling based on core loop B cold leg. AOV-294. open.

exit T/Cs - GREATER THAN 00 F USING FIG-l.0. FIGURE M'IN c. Start charging pumps as SUBCOOLING necessary.

o RCS vent paths - CLOSED d. Control charging pump speed and letdown flow to stabilize RCS conditions.

• PRZR pressure

• PRZR level

• Loop level IF charging flow greater than 75 gpm with letdown isolated OR unable to verify RCS inventory.

THEN go to AP-RCS.4. SHUTDOWN LOCA.

10 Establish Conditions To Start RHR Pump:

a. RHR pump - AVAILABLE a. Perform the following:

1) Start trending core exit TCs

2) IF RCS closed, THEN go to Step 12. IF RCS open to atmosphere, THEN go to Step 18.

b. Verify CCW cooling to RHR system b. Perform the following:

in service

1) Increase SW from CCW Hx o CCW pumps - ENSURE AT LEAST ONE RUNNING . CCW Hx A. V-4619

• CCW Hx B. V-4620 o CCW to RHR Hxs. MOV-738A AND MOV-738B - ADJUSTED TO OBTAIN 2) Adjust MOV-738A and MOV-738B DESIRED COOLING to obtain desired cooling.

o Check CCW flow < 4900 gpm 3) IF > 4900 gpm CCW flow (FI-619) required for desired RHR cooling. THEN notify the Shift Supervisor.

IF CCW can NOT be restored, THEN continue with Step 11 while attempting to restore CCW (Refer to AP-CCW.3. LOSS OF CCW - PLANT SHUTDOWN).

c. Close RHR pump flow control valves (controllers at 100%

demand)

• HCV-624

• HCV-625

d. Place RHR Hx bypass valve, HCV-626, to MANUAL and close valve

ACTI~ON/XETE RESPONSE I A * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• CAUTION STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL OR PRESSURE DECREASE DUE TO SHRINK OR VOID COLLAPSE.

• R

• es r * *

• Fl o w * * * * * * * * * * * * * * * * *

• f * * * *

• f

• f 11 Restore RHR Flow:

a. Start one RHR pump - RHR PUMP a. Go to Step lie.

RUNNING

b. Check RHR flow - LESS THAN b. Manually adjust RHR flow to less 1500 GPM PER PUMP than 1500 gpm per pump.

c. Adjust RHR Hx bypass flow control valve. HCV-626. to desired flowrate

d. Place RHR Hx bypass flow control valve, HCV-626, controller in AUTO

e. RHR flow - RESTORED e. Perform the following:

1) Start trending core exit T/Cs.

2) IF RCS closed. THEN go to Step 12. IF RCS vented to atmosphere. THEN go to Step 18.

f. Adjust RER Hx outlet valves to control RCS temperature

• HCV-624

• HCV-625

ACTIONEXPECTED RESPONSENOT OBTAINED 12 Monitor RCS Temperature:

a. RCS temperature - STABLE OR a. IF RCS closed, THEN go to DECREASING Step 13. IF RCS open to atmosphere. THEN go to Step 18.

b. Go to Step 21 13 Check Any S/G Level - GREATER Verify at least 200 gpm AFW flow THAN 17% available. IF NOT, THEN go to Step 19.

14 Check RCS Pressure - GREATER Increase RCS pressure to greater THAN 300 PSIG than 300 psig. IF RCS pressure can NOT be increased, THEN go to Step 19.

15 Check RCP Status - ANY RCP Perform the following:

RUNNING

a. Establish conditions for starting an RCP.

o Verify bus 11A or 11B energized.

o Refer to ATT-15.0. ATTACHMENT RCP START.

b. Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation. (Refer to ATT-13.0. ATTACHMENT NC)

IF natural circulation NOT verified. THEN increase dumping steam.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 16 Establish Condenser Steam Dump Manual Control:

a. Verify condenser available: a. Perform the following:

o Any MSIV - OPEN 1) Place S/G ARV controller in MANUAL and adjust ARVs to o Annunciator G-15, STEAM DUMP stabilize RCS temperature.

ARMED - LIT

2) Go to Step 17.

b. Place condenser steam dump controller HC-484 in MANUAL

c. Place steam dump mode selector switch to MANUAL

d. Adjust steam dump valves to stabilize RCS temperature 17 Monitor RCS Temperature:

a. RCS temperature - STABLE OR a. IF dumping steam does NOT DECREASING provide adequate cooling. THEN perform the following:

1) Initiate S/G blowdown from both S/Gs.

2) Maintain both S/G levels stable by controlling AFW flow.

3) Go to Step 19.

b. Go to Step 20

ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 18 Check RCS Conditions:

a. Rx vessel head - REMOVED a. Go to Step 19.

b. Stop refueling operations if in progress

c. Verify Refueling Cavity Level - c. Increase refueling cavity level GREATER THAN 23 FEET ABOVE to greater than 23 feet (Refer VESSEL FLANGE to 0-15.3. FILLING REFUELING CANAL).

d. Verify refueling cavity sweep d. Locally start refueling cavity fans - RUNNING sweep fans if available.

19 Check CCW System Operation: To restore CCW cooling to RHR Hxs.

perform the following:

o CCW pumps - AT LEAST ONE RUNNING

a. Ensure the standby CCW pump is o RCS temperature - STABLE OR running.

DECREASING

b. Increase SW from CCW Hx o Annunciator A-21. COMP COOLING HX OUT HI TEMP - EXTINGUISHED . CCW Hx A. V-4619

. CCW Hx B. V-4620 o Annunciator A-22, CCW PUMP DISCHARGE LO PRESS - EXTINGUISHED c. Adjust MOV-738A and MOV-738B to maintain RCS temperature stable o Annunciator A-30. CCW PUMP INLET or decreasing.

HEADER HI TEMP - EXTINGUISHED

d. IF > 4900 gpm CCW flow required o CCW flow < 4900 gpm (FI-619) for desired RHR cooling (FI-619), THEN notify the Shift Supervisor.

IF CCW can NOT be restored. THEN continue attempts to restore CCW (Refer to AP-CCW.3. LOSS OF CCW -

PLANT SHUTDOWN).

EOP: TITLE:

REV: 19 AP-RHR.1 LOSS OF RHR PAGE 14 of 14 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED NOTE: Consult with Plant Staff to determine alternatives for long term cooling.

20 Monitor RHR Cooling: Perform the following:

o RHR cooling - RESTORED a. Evaluate alternatives for long term cooling (Consult Plant o RCS temperature - STABLE OR Staff)

DECREASING

. Consider establishing secondary heat sink

• Refer to ER-RHR.1. RCDT PUMP OPERATION FOR CORE COOLING

• Consider RCS feed and bleed

b. Continue attempts to restore RHR to operable.

c. Return to Step 2.

21 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

22 Notify Higher Supervision 23 Return to Procedure Or Guidance In Effect

-END-

AP-RHR.1 APPENDIX LIST TITLE

1) FIGURE MIN SUBCOOLING (FIG-1.0)

2) ATTACHMENT NORMAL RHR COOLING (ATT-14.0)

3) ATTACHMENT RCP START (ATT-15.0)

4) ATTACHMENT NC (ATT-13.0)

5) ATTACHMENT CNMT CLOSURE (ATT-3.1)

6) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

.l I ILL:

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 1 of 17

========u ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER _2 _

RESPONSIBLE 1AGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

TITLE:

-I LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 13 I-RHR.2 INVENTORY CONDITIONS PAGE 2 of 17 A. PURPOSE - This procedure provides guidance necessary for maintaining core cooling and protecting the reactor core in the event that RHR cooling is lost during RCS reduced inventory operation, (i.e., at indicated Loop Levels of less than 64 inches with fuel in the vessel).

B. ENTRY CONDITIONS/SYMPTOMS

1. SYMPTOMS - The following symptoms are indicative of LOSS OF RHR AT RCS REDUCED INVENTORY CONDITIONS:

a. No RHR pumps running, or

b. Annunciator A-20, RESIDUAL HEAT REMOVAL LOOP LO FLOW 2900 GPM (Set at 400 GPM per 0-2.2 in RHR Cooling mode) lit, or

c. Unexpected increase in RCS temperature while on RHR cooling at low loop levels, or

d. Erratic or no flow on FI-626

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED

- INVENTORY CONDITIONS PAGE 3 of 17 ACTION/EXPECTED RESPNOT OBTAINE CAUTION o CHANGES IN RCS PRESSURE COULD RESULT IN INACCURACIES IN RCS LOOP LEVEL INDICATIONS.

o SHOULD CORE BOILING OCCUR, "SURGE LINE FLOODING" MAY RESULT IN RCS PRESSURIZATION AND ERRONEOUS HIGH LOOP LEVEL INDICATION.

o IA TO CNMT MAY BE REQUIRED FOR RCS MAKEUP AND SHOULD NOT BE ISOLATED UNTIL DIRECTED BY THIS PROCEDURE.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Check If RCS Draindown Should Be Stopped:

a. Check RCS draindown - IN PROGRESS a. Go to step 2.

b. Stop draining RCS (Refer to 0-2.3.1. DRAINING AND OPERATION AT REDUCED INVENTORY OF THE REACTOR COOLANT SYSTEM) 2 Check RHR Pumps - AT LEAST IF the running pump has tripped due ONE RUNNING to loss of NPSH. THEN go to step 3.

IF NOT, THEN go to step 17. I

I RTPX7- 1 LOSS OF RHR WHILE OPERATING AT RCS REDUCED I --

INVENTORY CONDITIONS PAGE 4 of 17 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 3 Initiate CNMT Closure (Refer to O-2.3.1A, CONTAINMENT CLOSURE CAPABILITY IN TWO HOURS DURING RCS REDUCED INVENTORY OPERATION)

. 4 Check If RHR Pumps Should Be Stopped: .

a. RHR pump - ANY RUNNING a. Go to Step 5.

b. Check RCS level: b. Stop RHR pumps and go to Step 5.

o Level - GREATER THAN 6 INCHES o Level - STABLE

c. RHR flow - LESS THAN 500 GPM c. Perform the following:

1) IF BOTH RHR pumps running with discharge crossties open, THEN stop one RHR pump.

2) Reduce RHR flow to less than 500 gpm.

d. RHR pumps cavitating: d. Go to Step 20.

o RHR pump flow - OSCILLATING

-OR-o RHR pump NPSH - APPROXIMATELY ZERO (PPCS Group Display NPSH)

e. Stop RHR pumps

EOP: TITLE:

LOSS OF RHR WHILE OPERATING ATRCS REDUCED REV: 13 INVENTORY CONDITIONS PAGE 5 of 17 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 5 Isolate Letdown And Known Drain Paths

a. Verify the following valves - a. Manually close valves.

CLOSED

• RCDT pump suctions from sump B, MOV-1813A and MOV-1813B

. Letdown isolation, AOV-427

. Low pressure letdown pressure control valve, PCV-135

. RHR letdown flow control valve. HCV-133

• Excess letdown isolation valve. AOV-310

b. Evaluate normal drain lineups

c. Evaluate maintenance activities affecting RCS or RHR system 6 Start Available CNMT RECIRC Fans NOTE: Personnel remaining in CNMT to assist in event mitigation should consult Radiation Protection for changes in radiological concerns.

7 Initiate Actions To Protect Personnel In CNMT:

a. Evacuate non-essential personnel from CNMT

b. Periodically monitor CNMT radiation

II LL:

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 6 of 17 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED CAUTION o PERSONNEL WORKING IN CNMT SHOULD BE WARNED BEFORE REFILLING THE RCS TO AVOID INADVERTENT CONTAMINATION OF PERSONNEL WORKING NEAR RCS OPENINGS.

o THE S/G OFFICE SHOULD BE NOTIFIED BEFORE RAISING LOOP LEVEL.

o ONLY BORATED WATER SHOULD BE ADDED TO THE RCS TO MAINTAIN ADEQUATE SDM.

• 8 Check RCS Temp Go to Step 13.

o Core Exit TCs - LESS THAN 2001F o No visual steam at RCS vents 9 Check RCS Loop Level - LESS Go to Step 14 THAN 30 INCHES

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 7 of 17 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I NOTE: o The next four steps are sequenced to indicate the preferred order of RCS refill methods if core boiling is not occurring.

o Gravity feed through MOV-856 is expected at approximately 12 turns open.

10 Refill The RCS By Gravity Feed From The RWST

a. Dispatch AO to locally throttle open RHR pump suction from RWST, MOV-856

b. Close RHR pump discharge valve to loop B cold leg, MOV-720

c. Verify MOV-856 indicates c. Perform the following:

midposition

1) Open MOV-720.

2) Go to Step 11.

d. Verify RCS loop level - d. Perform the following:

INCREASING AS EXPECTED

1) Close MOV-856.

2) Open MOV-720.

3) IF RCS loop level greater than 6 inches. THEN go to Step 11. IF NOT. THEN go to Step 13.

e. Check RCS loop level - GREATER e. Continue filling RCS. WHEN RCS THAN 30 INCHES loop level greater than 30 inches. THEN do Steps 10f through h.

f. Manually close MOV-856 f. Direct AO to locally close valve.

g. Open RHR pump discharge valve to g. IF MOV-720 does NOT open, THEN B loop cold leg, MOV-720 open core deluge valves MOV-852A and MOV-852B.

h. Go to Step 14

TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 13 INVENTORY CONDITIONS PAGE 8 of 17 ACTION/EXPECTED RESPONSENOT OBTAINED 11 Refill The RCS By Charging To B Loop Cold Leg:

a. Verify IA to CNMT. AOV-5392 - a. Manually open valve.

OPEN

b. Open and verify open charging b. Open alternate charging line to line valve to loop B cold leg, loop A cold leg, AOV-392B, and AOV-294 go to Step lid.

c. Ensure HCV-142 demand at 0%

d. Start operable charging pump and increase flow to maximum

e. Verify charging flow - GREATER e. Perform the following:

THAN ZERO

1) Stop operating charging pump.

2) Close AOV-294.

3) Go to Step 12.

f. Verify RCS loop level - f. Perform the following:

INCREASING AS EXPECTED

1) Open or verify open alternate charging line to loop A cold leg, AOV-392B.

2) Close AOV-294.

3) Verify loop level increasing as expected. IF NOT. THEN perform the following:

a) Stop operating charging pump.

b) Close AOV-392B.

c) Close IA to CNMT. AOV-5392.

d) Go to Step 12.

g. Check RCS loop level - GREATER g. Continue filling RCS. WHEN loop THAN 30 INCHES level greater than 30 inches, THEN do Steps llh through j.

h. Stop running charging pump

i. Close or verify closed charging line Valve~to loop B cold leg, AOV-294 and.AOV-392B

j. Go to Step 14

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 9 of 17 ACTION/EXPECTED RESPONSEREPNEOTBAID 12 Refill RCS Using SI Pumps To Cold Legs:

a. Open the appropriate SI pump a. Ensure at least one valve open.

discharge valves to loop cold legs IF valves can NOT be opened.

THEN dispatch AO to check

. A SI Pump - MOV-878B breakers.

. B SI Pump - MOV-878D

. C SI Pump - MOV-878B AND/OR . MOV-878B. MCC D position 8C MOV-878D . MOV-878D. MCC D position 8F

b. Open SI pump suction valves from b. Ensure at least one valve open.

RWST IF valves can NOT be opened.

• MOV-825A THEN dispatch AO to check

• MOV-825B breakers.

. MOV-825A. MCC C position 9J

. MOV-825B. MCC D position 9J

c. Start operable SI pump

d. Verify the following: d. Perform the following:

o SI flow - GREATER THAN ZERO 1) Stop operating SI pump.

o RCS loop level - INCREASING 2) Close loop cold leg inlet AS EXPECTED valves.

. MOV-878B a MOV-878D

3) Go to step 13.

e. Check RCS loop level - GREATER e. Continue filling RCS. WHEN loop THAN 30 INCHES level greater than 30 inches.

THEN do steps 12f through h.

f. Stop running SI pump

g. Close SI discharge valves to loop cold legs, MOV-878B and MOV-878D

h. Go to Step 14

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 10 of 17 NOTE: SI Pump makeup should not be secured when core boiling is indicated.

13 Refill RCS Using SI Pumps To Hot Legs:

a. Open the appropriate SI pump a. Ensure at least one valve open.

discharge valves to loop hot legs IF valves can NOT be opened.

• A SI Pump - MOV-878A THEN dispatch AO to check

. B SI Pump - MOV-878C breakers.

. C SI Pump - MOV-878A AND/OR MOV-878C

• MOV-878A, MCC C position 8C

• MOV-878C, MCC C position 8F

b. Open SI pump suction valves from b. Ensure at least one valve open.

RWST IF valves can NOT be opened.

. MOV-825A THEN dispatch AO to check

. MOV-825B breakers.

• MOV-825A, MCC C position 9J

. MOV-825B. MCC D position 9J

c. Start operable SI pump

d. Verify the following: d. Perform the following:

o SI flow - GREATER THAN ZERO 1) Stop operating SI pump.

o RCS loop level - INCREASING 2) Close loop hot leg inlet AS EXPECTED valves.

. MOV-878A

. MOV-878C

3) Ensure makeup flow is initiated

. Gravity feed from RWST

. Charging pumps

. SI pumps to cold legs

. VCT overpressure

. RWST purification pump

e. Operate SI Pump as necessary to e. IF core exit TC's continue to maintain the following increase. THEN return to Step 11 parameters: to establish additional charging or SI flow to the RCS cold legs.

o Core Exit TC's - LESS THAN 2000F o No visual steam-at RCS vehts o RCS loop level - GREATER THAN 30 INCHES

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 11 of 17 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 14 Identify And Isolate Any RCS Leakage NOTE: If adequate time to completely vent the RHR system is not available.

then air can be swept out of the RHR lines by running an RHR pump at a flowrate between 1200 gpm and 1400 gpm.

15 Vent RHR System As Necessary

a. Check RCS temperature - LESS a. Go to step 16.

THAN 2000 F

b. Maintain RCS level while venting RHR system

c. Direct AO to vent RHR suction line from loop A at valve V-2764 (in CNMT by loop A)

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 12 of 17 ACTON/XPETEDTESOBANSE I

• * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• i CAUTION THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.

16 Check IA Available For RHR Reset and start adequate air Flow Control: compressors (75 kw each).

o Verify adequate air compressors IF electric air compressor not

- RUNNING available, THEN start diesel air compressor (Refer to ATT-11.2.

o Verify IA pressure - GREATER ATTACHMENT DIESEL AIR COMPRESSOR)

THAN 60 PSIG IF IA pressure can NOT be restored, o IA available to HCV-624 AND THEN perform the following:

HCV-625

a. Dispatch AO with locked valve key to locally close RHR Hx outlet valves

. A RHR Hx, HCV-625 handwheel

. B RHR Hx, HCV-624 handwheel

b. WHEN conditions permit, THEN refer to AP-IA.1, LOSS OF INSTRUMENT AIR, to restore IA.

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 13 of 17 ACTION/EXPECTED RESPONSENOT OBTAINED 17 Establish Conditions To Start RHR Pump:

a. Check RHR cooling valve a. Manually or locally align valves alignment - NORMAL (Refer to as necessary.

ATT-14.0. ATTACHMENT NORMAL RHR COOLING)

b. Verify CCW cooling to RHR system b. Perform the following:

in service

1) Increase SW from CCW Hx

1) CCW pumps - ENSURE AT LEAST ONE RUNNING

• CCW Hx A. V-4619

. CCW Hx B. V-4620

2) CCW to RHR Hxs, MOV-738A AND MOV-738B - ADJUSTED TO OBTAIN 2) Adjust MOV-738A and MOV-738B DESIRED COOLING to obtain desired cooling.

3) Check CCW flow < 4900 gpm 3) IF > 4900 gpm CCW flow (FI-619) required for desired RHR cooling. THEN notify the Shift Supervisor.

IF CCW can NOT be restored. THEN continue with step 18 while attempting to restore CCW (Refer to AP-CCW.3. LOSS OF CCW - PLANT SHUTDOWN).

c. Verify the following RCS c. Perform the following:

conditions:

1) Start trending core exit TCs.

o Core exit TC's - LESS THAN 200°F 2) Return to Step 7.

o No visual steam at RCS vents o RCS loop level - GREATER THAN 30 INCHES

d. RHR pump - AVAILABLE d. Perform the following:

1) Start trending core exit TCs.

2) Place RCDT pumps in service (Refer to ER-RHR.1. RCDT OPERATION FOR CORE COOLING).

3) Return to Step 7.

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 14 of 17 ACTION/EXPECNTE RESPONSE =Idm CAUTION STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL DECREASE DUE TO SHRINK OR VOID COLLAPSE.

18 Restore RHR Flow:

a. Close RHR pump flow control a. IF IA NOT available, THEN ensure valves AO has locally closed RHR Hx outlet valves and go to step 18c.

• HCV-624

. HCV-625

b. Place RHR Hx bypass valve, HCV-626, to MANUAL and close valve

c. Start one RHR pump

d. Ensure RHR flow - LESS THAN d. IF IA NOT available, THEN 1500 GPM dispatch AO with locked valve key to locally adjust flow using RHR Hx outlet valves.

. A RHR Hx, HCV-625 handwheel

. B RHR Hx. HCV-624 handwheel

e. Check RCS loop level - GREATER e. Establish adequate makeup flow THAN 30 INCHES to stabilize RCS loop level at greater than 30 inches.

f. Gradually increase RHR bypass flow to desired flowrate

g. RHR flow - RESTORED g. Perform the following:

1) Start trending core exit T/Cs.

2) Place RCDT pumps in service (Refer to ER-RHR.1. RCDT OPERATION FOR CORE COOLING).

3) Return to Step 7.

h. Establish desired RCS cooldown rate

TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 13 INVENTORY CONDITIONS PAGE 15 of 17 NOTE: Consult with Plant Staff to determine alternatives for long term cooling.

19 Establish Stable Plant Conditions:

a. Verify Core Exit TC's - LESS a. Continue cooling with RHR.

THAN 200 0F Return to Step 18d.

b. Check RCS loop level: b. IF RCS loop level increasing, THEN reduce makeup rate to o Level - GREATER THAN 30 INCHES stabilize level. IF RCS loop level decreasing, THEN return to o Level - STABLE Step 10.

c. Stop any running SI pump

d. Stop any running charging pump

e. Maintain RCS level stable using e. Initiate makeup to the RCS using RWST gravity feed either of the following:

o One charging pump at maximum flow

-OR-o One SI pump

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 16 of 17 ACTION/EXPECTED RESPONSET OBTAI 20 Check CCW System Operation: To restore CCW cooling to RHR Hxs.

perform the following:

o CCW pumps - AT LEAST ONE RUNNING

a. Ensure the standby CCW pump is o RCS temperature - STABLE OR running.

DECREASING

b. Increase SW from CCW Hx o Annunciator A-21, COMP COOLING HX OUT HI.TEMP - EXTINGUISHED

• CCW Hx A. V-4619

. CCW Hx B. V-4620 o Annunciator A-22, CCW PUMP DISCHARGE LO PRESS - EXTINGUISHED c. Adjust MOV-738A and MOV-738B to maintain RCS temperature stable o Annunciator A-30. CCW PUMP INLET or decreasing.

HEADER HI TEMP - EXTINGUISHED IF > 4900 gpm CCW flow required for o Check CCW flow < 4900 gpm desired RHR cooling (FI-619). THEN (FI-619) notify the Shift Supervisor.

IF CCW can NOT be restored. THEN continue attempts to restore CCW (Refer to AP-CCW.3, LOSS OF CCW -

PLANT SHUTDOWN).

21 Check Core Exit TCs: Continue cooling with RHR. Return to Step 18d.

o Temperature - LESS THAN 1400F o Temperature - STABLE OR DECREASING

EOP: TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 13 AP-RHR.2 INVENTORY CONDITIONS PAGE 17 of 17 PAG 17of1 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDl 22 Initiate Monitoring of RCS Temperature 23-Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

24 Notify Higher Supervision 25 Return To Procedure Or Guidance In Effect

-END-

REV: 13 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 2- _-

PAGE 1 of 1 AP-RHR.2 APPENDIX LIST TITLE

1) ATTACHMENT NORMAL RHR COOLING (ATT-14.0)

2) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

TITLE:

EOP EOP- l TITLE:REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM

. l PAGE 1 of 11.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __

RESPONSIBL AGER f-o3a -2 0Žoo EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides the necessary actions to control the plant with decreasing condenser vacuum.

B. ENTRY CONDITIONS/SYMPTOMS

2. SYMPTOMS - The symptoms of LOSS OF CONDENSER VACUUM are;

a. Low or decreasing condenser vacuum, or

b. Annunciator H-7, CONDENSER HI PRESSURE 25.5" HG, lit, or

c. PPCS high condenser backpressure alarm, or

d. Unexplained decreasing generator output, or

e. Annunciator I-18, CONDENSER EXP JOINT A LO LEVEL, or

f. Annunciator I-19, CONDENSER EXP JOINT B LO LEVEL.

TITLE:

EOP EOP: ITLE:REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM P 17 3Eof

. . PAGE 3 of 11 l STE P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Check Condenser Circulating IF a loss of circulating water has Water System occurred, THEN go to AP-CW.1. LOSS OF A CIRC WATER PUMP.

o CW pump discharge valves - BOTH OPEN o CW pumps - BOTH RUNNING

EOP. TITLE. REV: 17 K

AP-TURB.4 LOSS OF CONDENSER VACUUM VPAGE 4 of 11 ACTONEX ECT D ESOT NSTIE I CAUTION o TURBINE LOAD DECREASE SHOULD BE COMPLETED AS QUICKLY AS POSSIBLE WHILE MINIMIZING THE AMOUNT OF STEAM DUMP OPERATION.

o EXCESSIVE BACK PRESSURE MAY RESULT IN SEVERE TURBINE BLADE VIBRATION.

MINIMIZE TIME OUTSIDE THE SATISFACTORY OPERATION REGION.

• * * * * * * * * * * *

• a* * * * * * * * * * * * * * * * * * * * * * * * * * *

• 2 Check Condenser Indications:

a. Turbine back pressure - EACH a. IF back pressure is in the DO CONDENSER WITHIN THE NOT OPERATE region for SATISFACTORY OPERATING REGION OF > 5 minutes. THEN perform the FIG-13.0, FIGURE BACK PRESSURE following:

o IF power > P-9, THEN trip the reactor and go to E-O.

REACTOR TRIP OR SAFETY INJECTION.

o IF power < P-9. THEN trip the turbine and go to AP-TURB.1.

TURBINE TRIP WITHOUT RX TRIP REQUIRED.

IF in the AVOID region, THEN adjust turbine load to return to the SATISFACTORY OPERATING REGION.

b. Condenser vacuum - STABLE OR b. WHILE continuing with this IMPROVING procedure, decrease turbine load to stabilize condenser vacuum.

(Refer to AP-TURB.5, RAPID LOAD REDUCTION)

IF condenser vacuum can NOT be stabilized, THEN perform the following:

1) Decrease turbine load to less than 15 MW.

2) Trip turbine.

3) Go to AP-TURB.1. TURBINE TRIP WITHOUT RX TRIP REQUIRED.

EOP. TITLE: REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM

.I_ . f PAGE 5 of 11 ACTION/EXPECTED RESPONSE l[RESPONSE STP NOT OBTAINED 3 Dispatch AO To Perform Local Actions To Attempt To Restore Condenser Vacuum (Refer to ATT-6.0, ATTACHMENT COND VACUUM)

CAUTION o DIP LIMITS ON THE GENERATOR HYDROGEN COOLER AND CONDENSATE COOLER SHOULD NOT BE EXCEEDED (DIP LIMITS INDICATED AT D/P METERS AT MCB REAR).

o CLOSELY MONITOR FEED PUMP SUCTION PRESSURE WHEN ADJUSTING CONDENSATE COOLING VALVES.

4 Check Condensate Temperature Perform the following:

- LESS THAN 1000F (PPCS point ID T2053) a. Place S/G blowdown and sample valve master isolation switch to CLOSE.

b. IF condensate cooler in service.

THEN perform the following:

1) Place generator hydrogen temperature controller in MANUAL at 50%.

2) Dispatch AO to throttle close condensate cooler bypass valve to control condensate temperature.

3) Adjust hydrogen temperature controller and condensate cooler manual bypass valve to establish maximum condensate cooling.

[EOP: TIRE: REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM

[I gPAGE 6 of 11 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 5 Dispatch AO To Check IF condenser inleakage is detected.

Condenser For Air Inleakage - THEN isolate if possible.

NO INLEAKAGE DETECTED

• Vacuum breaker

. Condenser boot area

. Condenser areas a Blowdown Tank area I 6 Determine If Load Reduction Can Be Stopped:

a. Monitor condenser indications: a. Return to Step 2.

o Condenser back pressure -

EACH CONDENSER WITHIN THE SATISFACTORY OPERATING REGION OF FIG-13.0. FIGURE BACK PRESSURE o Vacuum - STABLE OR IMPROVING

b. Stop the load reduction

[iEOP. TITLE:

REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM

.- PAGE 7 of 11 NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3)

• 7 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref, THEN restore Tavg to Tref by one or more of the following:

. Insert control rods

• RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:

• Withdraw control rods

• Reduce turbine load

. Dilution of RCS

b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:

. 431K in MANUAL

. Manual control of PRZR heaters and sprays IF pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.

c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL

2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually, THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

This Step continued on the next page.

EOP: TITLE: REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM

.I ePAGE 8 of 11 (Step 7 continued from previous page)

d. MFW regulating valves - d. Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO 1) Place affected S/G(s) MFW regulating valve in MANUAL

2) Restore S/G level to 52%

IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

. EOP: TITLE:

REV: 17 v AP-TURB.4 LOSS OF CONDENSER VACUUM

. PAGE 9 of 11

- I STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Establish Normal Plant Operation:

a. Check condenser indications a. Return to Step 2.

o Condenser pressure - EACH CONDENSER WITHIN THE SATISFACTORY OPERATING REGION OF FIG-13.0. FIGURE BACK PRESSURE o Vacuum - STABLE OR IMPROVING

b. Restore EH controls

1) Place in OP PAN, IMP OUT

2) Place load rate thumbwheel to 10%/hour

3) Match setter and reference

c. Verify annunciator G-15, STEAM c. WHEN Tavg within 51F of Tref, DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed.

2) Reset steam dump.

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

e. Verify Rods in AUTO e. Place rods AUTO. if desired.

f. Verify 431K in AUTO f. Place 431K in AUTO. if desired.

g. Verify PRZR spray valves in AUTO g. Place PRZR spray valves in AUTO.

if desired.

This Step continued on the next page.

.6 EOP:TITLE:

REV: 17 kAP-TURB.4 LOSS OF CONDENSER VACUUM PAGE 10 o 1 l1l PAGE 10 of 11l 8 o (StepT i e RoESPrNSEvious (Step 8 continued from previous page)

h. Verify PRZR heaters restored: h. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO

i. Verify MFW regulating valves in i. Place MFW regulating valves in AUTO AUTO, if desired.

j. Dispatch AO to remove priming ejector from service if desired

k. Verify S/G blowdown and sample k. Perform the following:

valve master isolation switch in REMOTE 1) Dispatch AO to locally isolate blowdown.

2) WHEN blowdown locally isolated, THEN place blowdown and sample valve master switch to REMOTE.

3) Direct AO to restore blowdown flow (Refer to T-14N, BLOWDOWN SYSTEM FLOW CHANGES).

9 Evaluate MCB Annunciator Status (Refer to AR Procedures)

EOP: TITLE: REV: 17 AP-TURB.4 LOSS OF CONDENSER VACUUM PAGE 11 of 11 10 Perform Notifications:

a. Notify higher supervision

b. Request Turbine System Engineer evaluate effect of back pressure transient on the turbine.

11 Return To Procedure Or Guidance In Effect

-END-

4; t -- , -, ,

-- I . 1, AP-TURB.4 APPENDIX LIST TITLE

1) FIGURE BACK PRESSURE (FIG-13.0)

2) ATTACHMENT COND VACUUM (ATT-6.0)