ML020440541

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Rochester Gas and Electric Corporation Emergency Operating Procedures
ML020440541
Person / Time
Site: Ginna Constellation icon.png
Issue date: 01/08/2002
From: Widay J
Rochester Gas & Electric Corp
To: Clark R
Document Control Desk, Office of Nuclear Security and Incident Response
References
Download: ML020440541 (11)
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Text

R§f A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECTRIC CORPORATION 0 89 EASTAVENUE, ROCHESTER, N.Y 14649-0001 - 716-771-3250 www.rge.com JOSEPH A. WIDAY VICE PRESIDENT & PLANT MANAGER GINNA STATION January 8, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Robert Clark Project Directorate I Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Clark:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, Le; A.

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):

ATT Index ATT-2.4, Rev 1 ATT- 14.1, Rev 5

~Q 11

Xt GINNA NUCLEAR POWER PLANT 01/08/02 PAGE: 1 REPORT NO. 01 PROCEDURES INDEX I REPORT: NPSP0200 DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PRATT PRER PRPT PRPTT STATUS: EF QU 5 YEARS ONLY:

EFFECT LAST NEXT PROCEDURE REV DATE REVIEW REVIEW ST NUMBER PROCEDURE TITLE 001 07/26/94 02/10/98 02/10/03 EF ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 000 05/18/00 05/18/00 05/18/05 EF ATT-1 .1 ATTACHMENT NORMAL CCW FLOW 005 02/01/01 02/10/98 02/10/03 EF ATT-2.1 ATTACHMENT MIN SW 007 10/31/01 08/11/98 08/11/03 EF ATT-2.2 ATTACHMENT SW ISOLATION 003 01/25/95 12/31/99 12/31/04 EF ATT-2. 3 ATTACHMENT SW LOADS IN CNMT 001 01/08/02 10/31/01 10/31/06 EF ATT-2.4 ATTACHMENT NO SW PUMPS 005 01/25/99 01/06/99 01/06/04 EF ATT-3.0 ATTACHMENT CI/CVI 003 01/25/99 01/25/99 01/25/04 EF ATT- 3.1 ATTACHMENT CNMT CLOSURE 003 07/26/94 05/13/98 05/13/03 EF ATT-4 .0 ATTACHMENT CNMT RECIRC FANS 004 01/25/95 12/31/99 12/31/04 EF ATT-5.0 ATTACHMENT COND TO S/G 007 09/20/01 12/31/99 12/31/04 EF ATT-5.1 ATTACHMENT SAFW 003 01/14/99 01/14/99 01/14/04 EF ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 12/18/96 02/10/98 02/10/03 EF ATT-6.0 ATTACHMENT COND VACUUM 005 02/11/00 02/10/98 02/10/03 EF ATT-7.0 ATTACHMENT CR EVAC 006 03/22/99 01/14/99 01/14/04 EF ATT-8.0 ATTACHMENT DC LOADS 004 11/03/95 02/10/98 02/10/03 EF ATT-8.1 ATTACHMENT D/G STOP 006 08/17/99 08/17/99 08/17/04 EF ATT-8.2 ATTACHMENT GEN DEGAS 003 07/26/94 02/10/98 02/10/03 EF ATT- 8.3 ATTACHMENT NONVITAL 004 04/24/97 02/10/98 02/10/03 EF ATT- 8.4 ATTACHMENT SI/UV 007 06/09/00 01/06/99 01/06/04 EF ATT -9.0 ATTACHMENT LETDOWN 004 10/31/01 10/31/01 10/31/06 EF ATT-9.1 ATTACHMENT EXCESS L/D 005 10/03/96 05/13/98 05/13/03 EF ATT- 10.0 ATTACHMENT FAULTED S/G 002 04/07/97 08/11/98 08/11/03 EF ATT-11.0 ATTACHMENT IA CONCERNS 002 04/07/97 08/11/98 08/11/03 EF ATT-11.1 ATTACHMENT IA SUPPLY

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I I I GINNA NUCLEAR POWER PLANT 01/08/02 PAGE: 2 REPORT NO. 01 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PRATT PRER PRPT PRPTT STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT PROCEDURE TITLE REV DATE REVIEW REVIEW ST NUMBER ATTACHMENT DIESEL AIR COMPRESSOR 002 05/11/01 04/03/98 04/03/03 EF ATT-11.2 ATTACHMENT N2 PORVS 003 03/24/97 02/10/98 02/10/03 EF ATT-12.0 ATTACHMENT NC 002 07/26/94 02/10/98 02/10/03 EF ATT-13.0 002 04/07/97 09/23/99 09/23/04 EF ATT-14.0 ATTACHMENT NORMAL RHR COOLING ATTACHMENT RHR COOL 005 01/08/02 05/01/98 05/01/03 EF ATT-14.1 ISOL 001 07/26/94 02/10/98 02/10/03 EF ATT- 14.2 ATTACHMENT RHR ATTACHMENT RHR NPSH 002 08/01/97 01/06/99 01/06/04 EF ATT -14 . 3 ATTACHMENT RHR SAMPLE 001 07/26/94 01/06/99 01/06/04 EF ATT- 14 .4 ATTACHMENT RHR SYSTEM 002 07/26/94 02/10/98 02/10/03 EF ATT- 14.5 ATTACHMENT RHR PRESS REDUCTION 001 01/14/99 01/14/99 01/14/04 EF ATT - 14 . 6 ATTACHMENT RCP START 008 09/14/01 03/17/00 03/17/05 EF ATT-15 .0 ATTACHMENT RCP DIAGNOSTICS 003 04/24/97 02/10/98 02/10/03 EF ATT- 15.1 ATTACHMENT SEAL COOLING 004 08/30/01 02/10/98 02/10/03 EF ATT- 15.2 011 07/18/01 01/11/00 01/11/o5 EF ATT-16.0 ATTACHMENT RUPTURED S/G ATTACHMENT SGTL 001 07/18/01 09/08/00 09/08/05 EF ATT- 16 .1 ATTACHMENT RCS BORON FOR SGTL 001 10/13/00 09/08/00 09/08/05 EF ATT-16.2 ATTACHMENT SD-I 011 01/09/01 02/29/00 02/28/05 EF ATT- 17.0 ATTACHMENT SD-2 005 09/26/96 01/30/01 01/30/06 EF ATT- 17. 1 ATTACHMENT SFP - RWST 004 10/08/97 02/10/98 02/10/03 EF ATT-18. 0 003 07/26/94 02/10/98 02/10/03 EF ATT- 20.0 ATTACHMENT VENT TIME ATT- 21 1.0 ATTACHMENT RCS ISOLATION 001 07/26/94 02/10/98 02/10/03 EF ATTACHMENT RESTORINC FEED FLOW 002 09/20/01 03/24/97 03/24/02 EF ATT-22 . 0 ATTACHMENT TRANSFER 4160V IOADS 000 02/26/99 02/26/99 02/26/04 EF ATT -23 . 0 000 09/08/00 09/08/00 09/08/05 EF ATT-24 . 0 ATTACHMENT TRANSFER BATTERY TO TSC

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REPORT NO. 01 GINNA NUCLEAR POWER PL ANT 01/08/02 PAGE: 3 REPORT: NPSP0200 PROCEDURES INDEX i DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PRATT PRER PRPT PRPTT STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDUR]E TITLE REV DATE REVIEW REVIEW ST ATT-26.0 ATTACHMEJNT RETURN TO NORMAL OPERATIONS 000 10/31/01 10/31/01 10/31/06 EF TOTAL FOR PRATT 49

IIO TITLE: RV SREV: 1 I ATT-2.4 ATTACHMENT NO SW PUMPS PAGE 1 of 1 Responsible Manager r __ Date This attachment provides additional guidance if no service water pumps are available.

CAUTION RHR SYSTEM WILL NOT BE AVAILABLE FOR NORMAL SHUTDOWN COOLING OR SUMP RECIRCULATION. RCS COOLING MUST BE MAINTAINED USING THE SG AS THE HEAT SINK.

1. Trip both RCPs.
2. IF any D/G is running without adequate cooling, THEN perform the following:

a) Trip the affected D/G b) Imemdiately depress voltage shutdown pushbutton.

3. Isolate letdown.
4. Direct an AO to align alternate cooling to both D/Gs using ER-D/G.2.
5. Direct an AO to align fire water cooling to the TDAFW pump using ATT-5.2, ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP.
6. Refer to ER-AFW.I for options for maintaining a source of feed flow to the SGs (consult Plant Staff if necessary).
7. IF the plant fire water header is required to supply TDAFW pump cooling or CST makeup, THEN consider crosstie of city water hydrant to the plant fire water header (refer to SC-3.16.4.1).
8. Secure CRFCs until SW can be restored for motor cooling.
9. Consider securing the following equipment until service water can be restored:
  • MDAFW Pumps (TDAFW pump is preferred, if available)
  • Condensate Pumps (Refer to T-5F)
  • CCW Pumps (impact on thermal barrier)

IEOP: TITLE:

REV: 5 ATT-14.* ATTACHMENT RHR COOL PAGE 1 of 6 Responsible Manager Date NOTE: Maintain operating RCP #1 seal DP greater than 220 psid.

1. Maintain RCS Temp < 350'F 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 0 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.

IIEOP: TITLE:

REV: 5 ATT-14.1 ATTACHMENT RHR COOL PAGE 2 of 6 NOTE: WHEN the next step is performed, THEN Annunciator A-20 will extinguish.

10. Stop the running RHR PUMP.

II. 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).

IIEOP: TITLE:

REV: 5 ATT-14.1 ATTACHMENT RHR COOL 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.

24.2 IF NO RCP running, THEN stabilize RCS pressure between 350 and 360 psig.

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.

IEOP: TITLE: R V 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. Ensure CVCS letdown aligned up to PCV-135.
33. SLOWLY open RHR LETDOWN TO CVCS HCV-133 to 100% to fill AND pressurize the RHR system.
34. Verify RHR pressure (PIC-629) is within 200 psig of RCS pressure (P-420 or P-420A).
35. Remove AND reinsert control power fuses for RHR PUMP SUCTION FROM LOOP A HOT LEG MOV-700. (MCC C Pos 7F)
36. Close MOV-700 breaker (MCC C Pos 7F).
37. Remove AND reinsert control power fuses for RHR PUMP SUCTION FROM LOOP A HOT LEG MOV-701. (MCC D Pos 7F)
38. Close MOV-701 breaker (MCC D Pos 7F).
39. Open RHR PUMP SUCTION FROM LOOP A HOT LEG MOVs.
  • MOV-701
  • MOV-700
40. Verify closed RHR HX flow control valves.
  • HCV-626
  • HCV-625 0 HCV-624

NOTE: 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: PI-135 may read 100 psi greater than PI-420 due to RHR Pump shutoff head.

NOTE: Annunciator A-20 will light.

41. Start one RHR PUMP.

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

42. 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.

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

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

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

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

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

EOP: TITLE:

REV: 5 ATT-14.1 ATTACHMENT RHR COOL PAGE 6 of 6 44.5 Open RHR PUMP DISCHARGE TO LOOP B COLD LEG.

0 MOV-720

  • MOV-721 44.6 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.

44.7 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.

44.8 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.

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

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

44.11 Open RHR LETDOWN TO CVCS HCV-133.

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