Text

Emergency Operating Procedures
	ML032950083
Person / Time
Site:	Ginna
Issue date:	10/10/2003
From:	Widay J; Rochester Gas & Electric Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML032950083 (171)
	v • d • e

Joseph A. Widay Vice President Always at Your Service and Plant Manager October 10, 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, 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):

ANT Index A'T-5.0, Rev 6 ES-0. 1, Rev 22 E Index AlT-17.0, Rev 16 FR-H. I, Rev 30 ECA Index FIG-2.0, Rev 4 FR-H.2, Rev 6 ES Index FIG-14.0, Rev 2 FR-H.3, Rev 7 FIG Index E-0, Rev 35 FR-S.I, Rev 16 FR Index ECA-0.0, Rev 27 FR-Z. 1, Rev 8 00?of-An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www. rge.com En t An Energy East Comnpany

(. (.

NPSP0200 Ginna Nuclear Power Plant Fri 10/10/2003 12:01:30 pm WRIGHTJ PROCEDURE INDEX Page 1 of 1 INPUT PARAMETERS: TYPE: Pr STATUS VALUE(S): EF 5 YEARS ONLY:

PRE EMERGENCY PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE ml DATE REVIEW REVIEW ST E-0 REACTOR TRI' OR SAFETY INJECTION 035 10110/2003 03/2412003 03/24/2008 EF E-1 LOSS OF REACTOR OR SECONDARY COOlANT 028 05/30/2003 0312412003 03/24/2008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 011 05/30/2003 03/24/2003 03/24/2008 EF E-3 STEAM GENERATOR TUBE RUPTURE 034 05/30/2003 03/24/2003 03/24/2008 EF PRE TOTAL: 4 GRAND TOTAL: 4

(. (7 (

NPSP0200 Ginna Nuclear Power Plant Fri 10/10/2003 12:01:06 pm WRIGHTJ PROCEDURE INDEX Page 1 of 1 INPUT PARAMETERS: TYPE: PRECA STATUS VALUE(S): EF 5 YEARS ONLY:

PRECA EMERGENCY CONTiNGENCY ACTIONS PROC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ECA-0.0 LOSS OF ALL AC POWER 027 10/1012003 03/24/2003 03/24/2008 EF ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REOUIRED 022 05/3012003 03/24/2003 03124/2008 EF ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED 015 05/30/2003 03/24/2003 03/24/2008 EF ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 022 05/30/2003 03/24/2003 03/24/2008 EF ECA-1.2 LOCA OUTSIDE CONTAINMENT 006 05/30/2003 03/2412003 03/24/2008 EF ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS 026 05/30/2003 03/24/2003 03/24/2008 EF ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED 026 05/30/2003 03/2412003 03/24/2008 EF ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED 027 05/30;2003 03/24/2003 03/24/2008 EF ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 029 05/30/2003 03/24/2003 03/24/2008 EF PRECA TOTAL: 9 GRAND TOTAL: 9

C ( (

NPSP0200 Ginna Nuclear Power Plant Fri 10110/2003 12:22:21 pm WRIGHTJ PROCEDURE INDEX Page 1 of 1 INPUT PARAMETERS: TYPE: PRES STATUSVALUE(S): EF S YEARS ONLY:

XRES

' . ... I Ott, .,- ,_ _..

. ._ ~_._.. . .. . ._......I..-..... r-r PRES EQUIPMENT SUB-PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ES-0.0 REDIAGNOSIS 010 05/01/1998 03124/2003 03/24/2008 EF ES-0.i REACTOR TRIP RESPONSE 022 10/10/2003 03/24/2003 03/24/2008 EF ES-0.2 NATURAL CIRCULATION COOLDOWN 013 05/30/2003 03/24/2003 03/24/2008 EF ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL 009 05/30/2003 03/24/2003 03/24/2008 EF ES-1.1 SI TERMINATION 025 05/30/2003 03/24/2003 03/24/2008 EF ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 026 05/30/2003 03/24/2003 03/24/2008 EF ES-1.3 TRANSFER TO COLD LEG RECIRCULATION 036 05;30/2003 03/24/2003 03/24/2008 m' ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 015 n5/30/2003 03/24/2003 03/24/2008 E ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN 016 05/30/2003 03/24/2003 03/24/2008 EF ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 016 05/30/2003 03/24/2003 03/24/2008 EF PRES TOTAL: 10 GRAND TOTAL 10

C, C. (

NPSP0200 Ginna Nuclear Power Plant Fri 10/10/2003 12:21:45 pm WRIGHTJ PROCEDURE INDEX Page 1 of 1 INPUT PARAMETERS: TYPE: PRFR STATUSVALUE(S): EF OU 5 YEARS ONLY:

PRFR FUNCTIONAL RESTORATION GUIDELINE PROC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST FR-C.1 RESPONSE TO INADEOUATE CORE COOLING 020 05130/2003 03/24/2003 03/24/2008 EF FR-C.2 RESPONSE TO DEGRADED CORE COOLING 017 05/30/2003 03/24/2003 03/24/2008 EF FR-C.3 RESPONSE TO SATURATED CORE COOLING 009 05/30/2003 03/24/2003 03/24/2008 EF FR-It.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 030 10/10/2003 03/24/2003 03/24/2008 EF FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE 006 10/10/2003 03/24/2003 03/24/2008 EF FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 007 10/10/2003 03/24/2003 03/24/2008 EF FR-H.4 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 005 05/30/2003 03/2412003 03124/2008 EF FR-H.5 RESPONSE TO STEAMI GENERATOR LOW LEVEL 009 05/30/2003 03/2412003 03/24/2008 EF FR-1.1 RESPONSE TO HIGH PRESSURIZER LEVEL 016 05/30/2003 03/24/2003 03/24/2008 EF FR-12 RESPONSE TO LOW PRESSURIZER LEVEL 011 05/30/2003 03/24/2003 03/24/2008 EF FR-1.3 RESPONSE TO VOIDS IN REACTOR VESSEL 018 05/30/2003 03/24/2003 03/2412008 EF FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL St OCK CONDITION 026 05/30/2003 03/24/2003 03/24/2008 EF FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL S OCK CONDITION 008 05/30/2003 03/24/2003 03/24/2008 EF FR-S.1 RESPONSE TO REACTOR RESTARTIATWS 016 10/10/2003 03/24/2003 03/2412008 EF FR-S.2 RESPONSE TO LOSS OF CORE SHUTDOWN 009 05/3012003 03/24/2003 03/24/2008 EF FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE 008 10/10/2003 03/24/2003 0312412008 EF FR-Z.2 RESPONSE TO CONTAINMENT FLOODING 005 05/3012003 03124/2003 03/2412008 EF FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVE L 005 05/3012003 03/24/2003 03124/2008 EF PRFR TOTAL: 18 GRAND TOTAL 18

( ( (

NPSP0200 Ginna Nuclear Power Plant Fri 10/10/2003 12:05:05 pm WRIGHTJ PROCEDURE INDEX Page 1 of 1 ma- -. vs 7 -

INPUT PARAMETERS: TYPE: PRFIG STATUSVALUE(S): EF.QU 5 YEARS ONLY:

PRFIG EOP FIGURE PROCEDURES PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST FIG-1.0 FIGURE MIN SUBCOOLING 000 0510111998 03/27/2003 03/27/2008 EF FIG-2.0 FIGURE SDM 004 10/10/2003 03/27/2003 03/27/2008 EF FIG-3.0 FIGURE NAT CIRC CID WITH SHROUD FANS 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-3.1 FIGURE NAT CIRC C/ID WITHOUT SHROUD FANS 001 02/08/2001 03/27/2003 03/27/2008 EF FIG-3.2 FIGURE NC C/D WITH VOID IN UPPER HEAD 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-4.0 FIGURE RCP SEAL LEAKOFF 002 02/28/2001 03/27/2003 03/27/2008 EF FIG-5.0 FIGURE RHR INECTlON 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-6.0 FIGURE MIN RCS INJECTION 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-7.0 FIGURE INTACT SIG PRESSURE 001 05/18/1998 03/27/2003 03/27/2008 EF FIG-8.0 FIGURE TSAT 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-9.0 FIGURE TECH SPEC CfD 001 02/15/2001 03/27/2003 03/27/2008 EF FIG-9.1 FIGURE CfD LIMITS 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-10.0 FIGURE UMIT A 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-11.0 FIGURE SOAK LIMITS 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-12.0 FIGURE CNMT HYDROGEN 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-13.0 FIGURE BACK PRESSURE 000 05/01/1998 03/27/2003 03/27/2008 EF FIG-14.0 FIGURE IA ISOL 002 10/10/2003 03/27/2003 03/27/2008 EF PRFIG TOTAL 17 GRAND TOTAL 17

('. (7 (:

NPSP0200 Ginna Nuclear Power Plant Fri 10/10/2003 12:26:47 pm WRIGHTJ PROCEDURE INDEX Page 1 of 2

~ ~ ~ ~ ~---~ ~ ~ .~ SA,_

s - - ~~~~1 1 - II-- e .....

-- 1 4_ ~ ~ w _ t M # ~ w 1 l> - s _ _ -w ~ e b INPUT PARAMETERS: TYPE: PRATT STATUSVALUE(S): EF 5YEARS ONLY:

PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 003 02/1212003 02/122003 02/1212008 ATT-1.1 ATTACHMENT NORMAL CCW FLOW 000 05/18/2000 05/18/2000 05/18/2005 ATT-2.1 ATTACHMENT MIN SW 005 0201/2001 0203/2003 02/03/2008 EF ATT-2.2 ATTACHMENT SW ISOLATION 008 03/06/2002 03/27/2003 03/27/2008 EF ATT-2.3 ATTACHMENT SW LOADS INCNMT 004 03/06/2002 12/31/1999 12/31/2004 ATT-2.4 ATTACHMENT NO SW PUMPS 002 05/30/2003 10/31/2001 10/31/2006 ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06i2612002 06t2612002 06/26/2007 EF ATT-3.0 ATTACHMENTCVCVI 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 SIG 006 10/10/2003 12/3111999 12/31/2004 EF ATT-5.1 ATTACHMENT SAFW 008 05/30/2002 1231/1999 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 02103/2003 02/03/2008 EF ATT-7.0 ATTACHMENT CR EVAC 006 03/06/2002 0203/2003 02/03/2008 E:

EF ATT-8.0 ATTACHMENT DC LOADS 006 03/2211999 01/14/1999 01/14/2004 E:

EF ATT-8.1 ATTACHMENT DIG STOP 005 03/06/2002 02/03/2003 02/03/2008 E:

ATT-8.2 ATTACHMENT GEN DEGAS 008 06/20/2002 08/17/1999 08/17/2004 E:

ATT-8.3 ATTACHMENT NONVITAL 004 03/06/2002 02103/2003 02/03/2008 B:

ATT-8.4 ATTACHMENT SWUV. 005 03/06/2002 02103/2003 02103/2008 E:

ATT-8.5 ATTACHMENT LOSSOFOFFSTEPOWER 001 08/26/2003 05/0212002 05/0212007 E:

ATT-9.0 ATTACHMENT LETDOWN 008 03/06/2002 03/06/2002 03/06/2007 E:

ATT-9.1 ATTACHMENT EXCESS LID 005 03/06/2002 10/31/2001 10/31/2006 E:

ATT-10.0 ATTACHMENT FAULTED SG 006 03/06/2002 03/27/2003 03/27/2008 E:

ATT-11.0 ATTACHMENT A CONCERNS 003 08/26/2003 03/27/2003 03/27/2008 E:

ATT-11.1 ATTACHMENT A SUPPLY 003 03/06/2002 03/27/2003 03/27/2008 E:

ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/2002 03/10/2003 03/10/2008 E:

ATT-12.0. ATTACHMENT N2 PORVS 005 02/12V2003 02/1212003 0211212008 E:

ATT-13.0 ATTACHMENT NC 003 02/1212003 02112/2003 0211212008 ATT-14.0 ATTACHMENT NORMAL RHR COOLING 003 03/06/2002 09/23/1999 09/23/2004

( ( f'. '. f -

NPSP0200 Ginna Nuclear Power Plant Fri 1011012003 12:26:48 pm WRIGHTJ PROCEDURE INDEX Page 2 of 2

.,_ .. . - -,. .. ,. ,t -

INPUT PARAMETERS: TYPE: PRATT STATUS VALUE(S): EF 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 04/3012003 01/08/2002 01/08/2007 E:

ATT-14.2 ATTACHMENT RHR ISOL 003 02/12/2003 02/12/2003 02/12/2008 ATT-14.3 ATTACHMENT RHR NPSH 003 03/06/2r)02 01/06/1999 01/06/2004 ATT- 14 .5 ATTACHMENT RHR SYSTEM 003 03/20/2003 02/03/2003 02/03/2008 E:

ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 002 03/06/2002 01/14/1999 01/14/2004 E:

ATT-15.0 ATTACHMENT RCP START 009 03/06/2002 03/17/2000 03/17/2005 E:

ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/1997 0203/2003 02/03/2008 E:

ATT-15.2 ATTACHMENT SEAL COOLING 005 03/06/2002 02103/2003 02/03!2008 E:

ATT-16.0 ATTACHMENT RUPTURED SIG 011 07/18/2001 01/11/2000 01/11/2005 E:

EF ATT-16.1 ATTACHMENT SGTL 002 03/06/2002 09/08/2000 09/08/2005 2:

EF ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 002 04/09/2002 09/08/2000 09/08/2005 E:

EF ATT- 17.0 ATTACHMENT SD-I 016 10/10/2003 02/29/2000 02/28/2005 2:

EF ATT-17.1 ATTACHMENT SD-2 006 03/06/2002 01/30/2001 01/30/2006 E:

ATT-18.0 ATTACHMENT SFP - RWST 005 03/06/2002 02/03/2003 02/03/2008 E:

ATT-20.0 ATTACHMENT VENT TIME 003 07/26/1994 02/03/2003 02/03/2008 2:

ATT-21.0 ATTACHMENT RCS ISOLATION 002 03/06/2002 02/03/2003 02/03/2008 2:

EF ATT-22.0 ATTACHMENT RESTORING FEED FLOW 003 05/02/2002 01/22/2002 01/22/2007 2:

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 GRAND TOTAL 50

EOP: TITLE:

REV: 6 ATT-5.0 ATTACHMENT COND TO S/G PAGE 1 of 1 Responsible Manager _ ____X_ Date /_ 0 3 FLOW THROUGH MFW PUMP B

1. Depress MANUAL pushbuttons for BOTH MFW flow control valves and BOTH bypass valve controllers AND ensure demand at ZERO.

2. Dispatch AO to MCC B.

3. At main control board place MFW Pump B discharge valve switch to open (MOV-3976).

4. WHEN MFW pump B discharge valve indicates open, THEN direct AO to open breaker for SG FWP DISCH VLV B, MCC B position 8G.

5. Ensure condensate trim valve controller demand at zero.

6. Ensure at least two condensate pumps running.

FLOW THROUGH MFW PUMP A

1. Depress MANUAL pushbuttons for BOTH MFW flow control valves and BOTH bypass valve controllers AND ensure demand at ZERO.

2. Dispatch AO to MCC A.

3. At main control board, place MFW Pump A discharge valve switch to OPEN (MOV-3977).

4. WHEN MFW pump A discharge valve indicates open, THEN direct AO to open breaker SG FWP DISCH VLV 1A, MCC A position 9J.

5. Ensure condensate trim valve controller demand at zero.

6. Ensure at least two condensate pumps running.

EOP: TITLE:

. ~~~~~~~~~~~~~~REV:

16 ATT-17.0 ATTACHMENT SD-i PAGE 1 of 3 Responsible Manager Date _ _16 ___

Perform the following local actons to complete normal secondary system shutdown:

o Close reheater 4th pass temperature control valves:

o V-2432 (SW corner 1A MSR) o V-2433 (SW corner B MSR) o V-2434 (SW corner 2A MSR) o V-2435 (SW corner 2B MSR) o Close reheater steam chain valves:

o V-3550 (SW of B MSR) o V-3551 (SW of B MSR) o V-3552 (NW of 1A MSR) o V-3553 (NW of 1A MSR) o Open Reheater steamline vents (SW corner of condenser, middle floor):

o V-8500 o V-8501 o V-8502 o V-8504 o V-8505 o Open Reheater steamline vents (SW corner of condenser, above walkway):

o V-8506 o V-8507 o V-8508 o V-8509 o Locally close flange heating isolation valves:

o MOV-3601A (TB Middle Lvl East of TURB Lube Oil Reservoir) o MOV-3602A NOTE: IF either S/G pressure is LESS THAN condensate header pressure, THEN manual isolation of the MFW regulating and bypass valves should be considered before aligning for cooldown recirculation.

o Open the following valves to align for condensate feed system cooldown RECIRC:

o V-3982B (at #5 heater outlet header) o V-3983B (at #5 heater outlet header) o V-4363 (at 5 heater outlet header) o V-4365 (by MFW regulating valves) o V-4361 (southwest corner of condenser, middle floor) o V-3976A MFP A discharge valve bypass valve o V-3977A MFP B discharge valve bypass valve o Secure all 5 secondary chemical addition pumps on TURB BLDG middle floor by #5 heaters.

o Secure all 3 ammonia pumps, TURB BLDG basement by MCC A.

o Secure the Ethanolamine (ETA) injection pump, TURB BLDG basement by turbine lube oil purifier.

o Isolate SW from the following coolers:

o MFW Pump Oil Coolers (MFW pump room) o V-4703 o V-4704 o Exciter Air Cooler:

o V-4679B (chain valve next to condensate transfer pump) o Bus Duct Air Cooler (TURB BLDG basement East of bus duct cooler) o V-4674 o V-4674C (mini bypass around V-4674) o Throttle SW as necessary from following coolers:

o Generator Seal Oil Unit Coolers (H2 side and air side):

o V-4676A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o V-4677A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o Main Lube Oil Coolers (SW corner of Turb Oil Reservoir) o V-4691 o V-4692 o IF HDT Pump A seal injection primary filter (FGSOIA) is in service, THEN perform the following to place the HDT Pump A seal injection bypass line (and filter FGS02A) in service and isolate the primary filter as follows (north side of HDT Pump A):

1. Ensure closed HDT Pump A bypass filter outlet valve, V-3709C.

2. Slowly open HDT Pump A bypass filter inlet isolation, V-3907F.

3. Slowly throttle open HDT Pump A bypass filter outlet valve, V-3709C WHILE concurrently closing HDT Pump A primary filter outlet valve, V-3709B to maintain approximately 5 - 8 gpm seal injection flow (FAL-3799A).

o IF HDT Pump B seal injection primary filter (FGSOlB) is in service, THEN perform the following to place the HDT Pump B seal injection bypass line (and filter FGS02B) in service and isolate the primary filter as follows (south side of HDT Pump B):

1. Ensure closed HDT Pump B bypass filter outlet valve, V-3710C.

2. Slowly open HDT Pump B bypass filter inlet isolation, V-3910F.

3. Slowly throttle open HDT Pump B bypass filter outlet valve, V-3710C WHILE concurrently closing HDT Pump B primary filter outlet valve, V-3710B to maintain approximately 5 - 8 gpm seal injection flow (FAL-3799B).

o WHEN the turbine shaft stops, THEN notify Control Room. Control Room personnel will determine if adequate power (36 KW) available to start turning gear.

o Transfer house heating steam to house heating boiler if necessary (refer to T-35H, NUCLEAR HOUSE HEATING STEAM TO BOILER STEAM SUPPLY CHANGE).

o Align S/G blowdowns as follows:

1. Secure blowdown to the condenser per T-14G, STEAM GENERATOR BLOWDOWN HEAT RECOVERY SYSTEM SHUTDOWN.

2. Verify S/G releases are in effect. IF NOT, THEN ensure releases are in effect before performing the next step.

3. Align Steam Generator Blowdown Flash Tank drains to the discharge canal per T-14F.1, SG BLOWDOWN ALIGNMENT TO DISCHARGE CANAL.

o Restore MAKEUP to CSTs as directed by Control Room.

Responsible Manager _ Date /0 -16 ,2 663 FIGURE SDM NOTE: o Curve includes allowance for one stuck rod. Add 100 ppm for each additional stuck rod.

o To obtain core burnup, use PPCS point ID BURNUP.

BORON CONCENTRATION (PPM) 1800 1600 -

1400 -

1200 -

EI 1000 -

800 -

600 -

400 -

200 -

I 0

I I I I l 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 .20000 CYCLE 31 BURNUP (MWD/MTU)

Responsible Manager - as_ _

____1__ Dae Date ____ 6_

TURBINE BUILE 7195A Dese Ar Crpi 5365 ABOVE INST AIR DRYER A H2 Cooler Inlet Valve (AOV-4230) 5316

_ Condensate Trim Valves 5317 VN I (AOV-9508D. 9508G) ABOVE COND AVT 6903 BOOSTER PUMP B Cond. Bypass Valve (AOV-3959) 7601 P Condensate Makeup 1/N (AOV4315) Screen House 14519(

ABOVE DIG FUEL STORAGE 7602 TANK LEVEL INDICATORS H 4_ MFW Reg &Bpass Valves (AOV-4269. 4270. 4271,4272) 7024 i _4~ Steam Dump Valves 1 /\l (AOV-3349. 3351. 3353. 3355) 6923 Z 5315 ABOVE DOOR 37 I\A AT COLUMN E-4 BY FIRE WATER STORAGE TANK STORAGE TANK H2 Cooler Bypass Valve (AOV.4229) 5397 I HOT SHOP I Steam Dump Valves (AOV-3350, 3352. 33 AUIBD

AUXILIARY BUILDING HOT AUX SHOP BLDG

- -I*

j 7350 7352

\

7352 CCW From EXCESS L/D Hx Z7I (AOV-745)(FC) 1 ~~7367

.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ .Letdown z 7037 IL&LUUW1I

.E Valve VdIVC 7370 _ (AOV-1 12A)

(AOV-371 )(FC)

Z14232H 7374 7 7375 Z 7376 (Fai! to VCT)

Charging Line _ T373 1 P (AOV-142)(FO) -

RHR Hx RHR Flow RHR Flow L1\y1_ VCT Makeup Bypass Valve Valve Valve (AOV-110A)(FO) (AOV-626) (AOV-625) (AOV-624) j 1731 (FC) (FO) (FO) 2 7002 VCT Makeup (AOV-11 OB, 1OC) -

(FC) 7004 Charging Pump Speed Control q

'1I VCT Makeup (Fails to Minimum)

(AOV-111) (FC) -N-7003 7009 Charging Pump Suction Z 7006 (AOV-1 12B)

(FC)

I Charging Pump Suction I (AOV-11 2C) !

(P0) ~~~~7005

( n I

Z7011 T

I NaOH Tank Outlet Valves Letdown Valve Letdown Valve (AOV-836A, 836B) (TCV-145) (PCV-135)

(FO) (Fails to VCT) (FO)

N4-ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER _

RESPONSIBL9 MANAGER 10 -/6-co3 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 2 of 29 A. PURPOSE - This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.

B. ENTRY CONDITIONS/SYMPTOMS

1. The following are symptoms that require a reactor trip, if one has not occurred:

o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-1, REACTOR CONTROL AND PROTECTTON SYSTEM.

o Operator discretion.

2. The following are symptoms of a reactor trip:

o Any First Out reactor trip annunciator lit.

o A rapid decrease in core neutron level as indicated by nuclear instrumentation.

o MRPI indicates all control and shutdown rods on bottom.

o Reactor trip breakers indicate open.

3. The following are symptoms that require a reactor trip and safety injection, if one has not occurred:

o Any plant parameter reaches the Safety Injection setpoint and logic listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

4. The following are symptoms of a reactor trip and safety injection:

o Any SI annunciator lit.

o Safeguards sequencing started.

[ EOP: TITE:

I ~~~~~~~~~~~~~~REV:

35 E-0 REACTOR TRIP OR SAFETY INJECTION l PAGE 3 of 29 STEP _ ACTION/EXPECTED RESPONSE 1 1 RESPONSE NOT OBTAINEDI 0 Verify Reactor Trip:

o At least one train of reactor Manually trip reactor.

IF reactor trip breakers NOT open.

trip breakers - OPEN THEN perform the following:

o Neutron flux - DECREASING a. Open Bus 13 and Bus 15 normal feed breakers.

o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM b. Verify rod drive MG sets tripped.

c. Close Bus 13 and Bus 15 normal feed breakers.

d. Reset lighting breakers.

IF the reactor will NOT trip OR IF power range NIS indicates greater than 5%. THEN go to FR-S.1.

RESPONSE TO REACTOR RESTART/ATWS.

Step 1 Verify Turbine Stop Valves - Manually trip turbine.

0 CLOSED IF turbine trip can NOT be verified. THEN close both MSIVs.

Verify Both Trains Of AC Attempt to start any failed 0 Emergency Busses Energized To emergency D/G to restore power to At Least 420 VOLTS: all AC emergency busses.

Bus 14 and Bus 18 IF Bus 14 AND Bus 16 are

Bus 16 and Bus 17 deenergized. THEN go to ECA-O.O, LOSS OF ALL AC POWER. Step 1.

EOP: TITLE: REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 29 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl

-0 Check if SI is Actuated:

a. Any SI Annunciator - LIT a. IF any of the following conditions are met. THEN manually actuate SI and CI:

o PRZR pressure less than 1750 psig

-OR-o Steamline pressure less than 514 psig

-OR-o CNMT pressure greater than 4 psig

-OR-o SI sequencing started

-OR-o Operator determines SI required IF SI is NOT required. THEN go to ES-0.1. REACTOR TRIP RESPONSE. Step 1.

b. SI sequencing - BOTH TRAINS b. Manually actuate SI and CI.

STARTED.

TIThE:

EOP:

E-0 REACTOR TRIP OR SAFETY INJECTION REV: 35 I

~~~~~~~~~~~~~PAGE 5 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDl NOTE: o FOLDOUT page should be open and monitored periodically.

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

5 Verify SI and RHR Pumps Running:

a. All SI pumps - RUNNING a. Perform the following:

1) Ensure SI pump suction supply open from RWST.

2) Manually start pumps.

b. Both RHR pumps - RUNNING b. Manually start pumps.

6 Verify CNMT RECIRC Fans Running:

a. All fans - RUNNING a. Manually start fans.

b. Charcoal filter dampers green b. Dispatch personnel to relay room status lights - EXTINGUISHED with relay rack key to locally open dampers by pushing in trip relay plungers.

AUX RELAY RACK RA-2 for fan A

AUX RELAY RACK RA-3 for fan C

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 29 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED

7 Verify CNMT Spray Not Verify CNMT spray initiated.

Required:

IF CNMT spray NOT initiated. THEN o Annunciator A-27. CNMT SPRAY - perform the following:

EXTINGUISHED

a. Depress manual CNMT spray o CNMT pressure - LESS THAN 28 PSIG pushbuttons (2 of 2).

b. Ensure CNMT spray pumps running.

IF no CNMT spray pump available.

THEN go to Step 8.

c. Ensure CNMT spray pump discharge valves open for operating pump(s).

o CNMT spray pump A:

MOV-860A

MOV-860B o CNMT spray pump B:

MOV-860C

MOV-860D

d. Verify NaOH flow (FI-930)

IF NaOH flow NOT indicated, THEN place switches for NaOH tank outlet valves to OPEN.

AOV-836A

AOV-836B

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 29 8 Check If Main Steamlines Should Be Isolated:

a. Any MSIV - OPEN a. Go to Step 9.

b. Check CNMT pressure - LESS THAN b. Ensure BOTH MSIVs closed and go 18 PSIG to Step 9.

c. Check if ANY main steamlines c. Go to Step 9.

should be isolated:

o Low Tavg (5450F) AND high steam flow (.4x10 6 lb/hr) from either S/G

-OR-o High-High steam flow (3.6x106 lb/hr) from either S/G

d. Verify MSIV closed on the d. Manually close valves.

affected SG(s) 9 Verify MFW Isolation:

a. MFW pumps - TRIPPED a. Perform the following:.

1) Manually close MFW pump discharge valves and trip MFW pumps.

2) Continue with Step 9c. WHEN both FPs are tripped. THEN perform Step 9b.

b. Depress MANUAL pushbuttons for A and B S/G MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

c. SG blowdown and sample valves - c. Place S/G blowdown and sample CLOSED valve isolation switch to CLOSE.

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 29 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 10 Verify Both MDAFW Pumps Manually start both MDAFW pumps.

Running IF less than 2 MDAFW pumps are running, THEN manually open TDAFW pump steam supply valves.

MOV-3505A

MOV-3504A 11 Verify At Least Two SW Pumps Perform the following:

- RUNNING

a. Ensure one SW pump running on each energized screenhouse AC emergency bus:

Bus 17

Bus 18

b. IF offsite power NOT available.

THEN ensure SW isolation.

c. IF NO SW pumps running. THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.

EOP: TITLE: REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 29 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 12 Verify CI And CVI:

a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.

Annunciator A-26. CNMT ISOLATION

. Annunciator A-25. CNMT VENTILATION ISOLATION

b. Verify CI and CVI valve status b. Manually close CI and CVI valves lights - BRIGHT as required.

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 for alternate isolation valves).

c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights - valves.

BRIGHT

FCV-4561

. FCV-4562

d. Letdown orifice valves - CLOSED d. Place affected valve switch to CLOSE. IF valves can NOT be

. AOV-200A verified closed by MCB

AOV-200B indication, THEN close alternate

AOV-202 isolations. (Refer to ATT-3.0.

ATTACHMENT CI/CVI)

EOP: TITLE: REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 10 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDl

* * . * * * * . * . * . * * * . . . * . . . . . * . *

4 * * . A .

CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY.

A * * * * . . . * * * * * *

a * * * * * * * * * * * * * * * * * * * * . . . 4 13 Check CCW System Status:

a. Verify CCW pump - AT LEAST ONE a. IF offsite power available. THEN RUNNING manually start one CCW pump.

b. Place switch for excess letdown AOV-310 to CLOSE

c. Place switch for CCW from excess letdown. AOV-745 to CLOSE 14 Verify SI And RHR Pump Flow:

a. SI flow indicators - CHECK FOR a. IF RCS pressure less than FLOW 1400 psig. THEN manually start pumps and align valves. IF NOT.

THEN go to Step 15.

b. RHR flow indicator - CHECK FOR b. IF RCS pressure less than FLOW 140 psig. THEN manually start pumps and align valves. IF NOT.

THEN go to Step 15.

15 Verify AFW Valve Alignment: Manually align valves as necessary.

a. AFW flow - INDICATED TO BOTH S/G(s)

b. AFW flow from each MDAFW pump -

LESS THAN 230 GPM

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 11 of 29 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED I

16 Monitor Heat Sink:

a. Check SIG narrow range level - a. Perform the following:

GREATER THAN 5% [25% adverse CNMT] in any S/G 1) Verify total AFW flow -

GREATER THAN 200 GPM IF total AFW is less than 200 gpm. THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow. IF AFW flow greater than 200 gpm can NOT be established. THEN go to FR-H.1. RESPONSE TO LOSS OF SECONDARY HEAT SINK.

Step 1.

2) Go to Step 17.

b. Check S/G narrow range level - b. Secure AFW flow to any S/G with BOTH SG LESS THAN 50% level above 50%.

c. Control feed flow to maintain S/G narrow range level between 5% [25% adverse CNMT] and 50%.

I

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.

deluge - OPEN

MOV-852A

. MOV-852B

b. Verify SI pump C - RUNNING b. Manually start pump on available bus.

c. Verify SI pump A - RUNNING c. Perform the following:

1) Ensure SI pumps B and C running. IF either pump NOT.

running. THEN go to Step 17e.

2) Ensure SI pump C aligned to discharge line A:

o MOV-871A open o MOV-871B closed

3) Go to Step 18.

d. Verify SI pump B - RUNNING d. Perform the following:

1) Ensure SI pumps A and C running. IF either pump NOT.

running. THEN go to Step 17e.

2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 18.

e. Verify SI pump C discharge e. Manually open valves as valves - OPEN necessary.

MOV-871A

MOV-871B

EOP: TITLE:

REV: 35 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 13 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED CAUTION IF OFESITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER) 18 Check CCW Flow to RCP Thermal IF CCW to a RCP is lost. THEN Barriers: perform the following:

o Annunciator A-7. RCP 1A CCW a. Stop affected RCPs.

RETURN HI TEMP OR LO FLOW -

EXTINGUISHED b. Reset SI.

o Annunciator A-15. RCP B CCW c. Verify adequate power available RETURN HI TEMP OR LO FLOW - to run one charging pump (75 kw).

EXTINGUISHED

d. Start one charging pump at minimum speed for seal injection.

e. Adjust HCV-142 to establish either of the following:

o Labyrinth seal DP to each RCP greater than 15 inches of water.

-OR-o RCP seal injection flow to each RCP greater than 6 gpm.

f. IF large imbalance in seal injection flow exists. THEN consider local adjustment of V-300A and V-300B.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 19 Check If TDAFW Pump Can Be Stopped:

a. Both MDAFW pumps - RUNNING a. Go to Step 20.

b. PULL STOP TDAFW pump steam supply valves

MOV-3504A

MOV-3505A

20 Monitor RCS Tavg - STABLE AT IF temperature less than 5470 F and OR TRENDING TO 5470 F decreasing. THEN perform the following:

a. Stop dumping steam.

b. Ensure reheater steam supply valves are closed.

c. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one S/G.

d. WHEN S/G level greater than 5%

[25% adverse CNMT] in one SG.

THEN limit feed flow to that required to maintain level in at least one SG.

e. Ii: cooldown continues. THEN close both MSIVs.

IF temperature greater than 5471F and increasing. THEN dump steam to stabilize and slowly decrease temperature to 5470F.

TITLE:

EOP:

E-0 REACTOR TRIP OR SAFETY INJECTION REV: 35 I

~~~~~~~~~~~~~~PAGE 15 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NO OBTAINEDP 21 Check PRZR PORVs And Spray Valves:

a. PORVs - CLOSED a. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any valve can NOT be closed.

THEN manually close its block valve.

MOV-516 for PCV-430

MOV-515 for PCV-431C IF block valve can NOT be closed. THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

Step 1.

b. Auxiliary spray valve (AOV-296) b. Manually close auxiliary spray

- CLOSED valve. IF valve can NOT be closed. THEN perform the following:

1) Decrease charging pump flow to minimum.

2) Ensure charging valve to loop B cold leg open (AOV-294).

c. Check PRZR pressure - LESS THAN c. Continue with Step 22. WHEN 2260 PSIG pressure less than 2260 psig.

THEN do Step 21d.

d. Normal PRZR spray valves - CLOSED d. Place controllers in MANUAL at 0% demand. IF valves can NOT be

PCV-431A closed. THEN stop associated

PCV-431B RCP(s).

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 16 of 29 ACTION/EXPECTED RESPONSE STE RESPONSE NOT OBTAINED 22 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING a. Go to Step 23.

b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 23.

c. RCS pressure minus maximum SIG c. Go to Step 23.

pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs 23 Check If S/G Secondary Side IF any S/G pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized. THEN go o Pressure in both S/Gs - STABLE to E-2. FAULTED STEAM GENERATOR OR INCREASING ISOLATION. Step 1.

o Pressure in both S/Gs - GREATER THAN 110 PSIG 24 Check If S/G Tubes Are Intact: Go to E-3. STEAM GENERATOR TUBE RUPTURE. Step 1.

o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL

'11-/

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 17 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED I 25 Check If RCS Is Intact: Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.

a. CNMT area radiation monitors -

NORMAL

. R-2

R-7

R-29

R-30

b. CNMT pressure - LESS THAN 0.5 PSIG

c. CNMT sump B level - LESS THAN 8 INCHES

d. CNMT sump A level o Level - STABLE o Annunciator C-19. CONTAINMENT SUMP A HI LEVEL - EXTINGUISHED

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 18 of 29 26 Check If SI Should Be Terminated:

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 27.

o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN 0 0F Step 27.

USING FIG-1.0. FIGURE MIN SUBCOOLING

c. Secondary heat sink: c. IF neither condition met. THEN do NOT stop SI pumps. Go to o Total feed flow to S/Gs - Step 27.

GREATER THAN 200 GPM

-OR-o Narrow range level in at least one S/G - GREATER THAN 5%

d. PRZR level - GREATER THAN 5% d. Do NOT stop SI pumps. Perform the following:

1) IF normal PRZR spray available. THEN try to stabilize RCS pressure with PRZR spray.

2) Go to Step 27.

e. Go to ES-1.1. SI TERMINATION.

Step 1.

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 19 of 29 NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o The Critical Safety Function Red Path Summary is available in APPENDIX 1.

27 Initiate Monitoring of Critical Safety Function Status Trees

28 Monitor S/G Levels:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% than 200 gpm until narrow range level greater than 5% in at least one SG.

b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an and 50% uncontrolled manner, THEN go to E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.

29 Check Secondary Radiation Go to E-3. STEAM GENERATOR TUBE Levels - NORMAL RUPTURE. Step 1.

o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity

EOP: TITLE:

REV: 35

.E-O REACTOR TRIP OR SAFETY INJECTION PAGE 20 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4 4

A 4 4 4

4

4 4 * * * * *

4 4 4 * * * * *

CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER) 30 Reset SI 31 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A26. CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.

2) Depress CI reset pushbutton.

K-)

lop: TITLE: REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 21 of 29 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 32 Verify Adequate SW Flow:

a. At least three SW pumps - RUNNING a. Manually start SW pumps as power supply permits (257 kw each).

IF less than three pumps running. THEN ensure SW isolation.

IF NO SW pumps running. THEN perform the following:

1) Pull stop any DG that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.

IF only one SW pump running.

THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0. ATTACHMENT SD-1)

rEOP:

.d TITLE:RE REV::3 35l E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 33 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

Bus 13 to Bus 14 tie

Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressor(s) (75 kw each).

IF NOT. THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR

-OR-o Evaluate if CNMT RECIRC fans should be stopped.

(Refer to ATT-4.0.

ATTACHMENT CMT RECIRC FANS

3) WHEN bus 15 is restored, THEN reset control room lighting.

b. Check SW Pumps - AT LEAST TWO b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)

2) Go to step 33d.

This Step continued on the next page.

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 23 of 29 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 33 continued from previous page)

c. Verify SW isolation valves to c. Perform the following:

turbine building - OPEN

1) Manually align valves.

. MOV-4613 and MOV-4670

. MOV-4614 and MOV-4664 2) Dispatch AO to locally reset compressors as necessary.

d. Verify adequate air d. Manually start electric air compressor(s) - RUNNING compressor(s) as power supply permits (75 kw each).

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

e. Check IA supply: e. 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 34. WHEN IA restored. THEN do Steps 33f and g.

f. Reset both trains of XY relays for IA to CMT AOV-5392

g. Verify IA to CNMT AOV-5392 - OPEN

. EOP: TITLE: REV: 35 l E -0 l REACTOR TRIP OR SAFETY INJECTION l l PAGE 24 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED I 34 Check Auxiliary Building Evaluate cause of abnormal Radiation - NORMAL conditions.

Plant vent iodine R-10B) IF the cause is a loss of RCS

Plant vent particulate (R-13) inventory outside CNMT. THEN go to

Plant vent gas (R-14) ECA-1.2. LOCA OUTSIDE CONTAINMENT.

Step 1.

CCW liquid monitor (R-17) e LTD line monitor (R-9)

CHG pump room (R-4) 35 Check PRT Conditions Evaluate the following flowpaths for cause of abnormal conditions:

o PRT level (LI-442) - LESS THAN 84%

RCP seal return relief

PRZR PORVs o PRT temperature (TI-439) - LESS

PRZR safeties THAN 120 0F

Letdown line relief o PRT pressure (PI-440A) - LESS IF excess letdown previously in THAN 3 PSIG service. THEN close AOV-310. excess letdown isolation valve from loop A cold.

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 29 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINEDI

* * *

4 4 4 .4 * * .* * * * * * * * * *

4 *

CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

36 Monitor If RHR Pumps Should Be Stopped:

a. Check RCS pressure:

1) Pressure - GREATER THAN l) Go to E-1. LOSS OF REACTOR OR 250 PSIG SECONDARY COOLANT. Step 1.

2) Pressure - STABLE OR 2) Go to Step 37.

INCREASING

b. Stop both RHR pumps and place in AUTO 37 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker -

CLOSED IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker - to ATT-4.0. ATTACHMENT CNMT RECIRC CLOSED FANS).

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 38 Check If Charging Flow Has Been Established:

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

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO to close seal injection needle valve(s) to affected RCP:

V-300A for RCP A

V-300B for RCP B

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

b. Charging pump suction aligned to b. Manually align valves.

RWST:

IF LCV-112B can NOT be opened.

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

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 as necessary and adjust charging flow to restore PRZR level

. EG: TITLE: REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION

. PAGE 27 of 29 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 39 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 28 of 29 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 40 Check If Emergency DGs Should Be Stopped:

a. Verify AC emergency busses a. Perform the following:

energized by offsite power:

1) Verify non-safeguards bus tie o Emergency DG output breakers breakers closed:

- OPEN

Bus 13 to Bus 14 tie o AC emergency bus voltage - . Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS

2) Place the following pumps in o AC emergency bus normal feed PULL STOP:

breakers - CLOSED

EH pumps

. Turning gear oil pump

. HP seal oil backup pump

3) Ensure condenser steam dump mode control in MANUAL.

4) Restore power to MCCs:

A from Bus 13

B from Bus 15

E from Bus 15

F from Bus 15

5) Start HP seal oil backup pump.

6) Ensure DG load within limits.

7) Refer to ATT-8.4. ATTACHMENT SI/UV for other equipment lost with loss of offsite power.

8) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

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

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 29 of 29 ACTION/EXPECTED RESPONSE TE lRESPONSE NOT OBTAINEDl 41 Return to Step 20

-END-

EOP: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION

, 44: PAGE 1 of 1 E-0 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MN SUBCOOLING (FIG-l.0)

3) ATTACHMENT CI/CVI (AT-3.0)

4) ATTACHMENT SD-1 (ATT-17.0)

5) ATTACHMENT CNMT RECIRC FANS (AIT-4.0)

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

7) ATTACHMENT SI/UV (ATT-8.4)

8) ATTACHMENT NO SW PUMPS (ATT-2.4)

9) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)

10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

11) FOLDOUT

EDP~: TITLE:

REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 700°F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] ND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold eg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE: REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE

1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:

a. SI pumps - AT LEAST TWO RUNNING

b. RCS pressure minus maximum S/G pressure - LESS THAN 175 PSIG

[400 psig adverse CNMT]

2. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a. Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

3. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

EOP: TITLE: REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 25 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER f13 RESPONSIBLp MANAGER

/F -/d - 0E EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 27 ECA-O.O LOSS OF ALL AC POWER PAGE 2 of 25 A. PURPOSE - This procedure provides actions to respond to a loss of all AC power.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure may be entered directly or from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, on the indication that both Bus 14 and Bus 16 are deenergized.

2. SYMPTOMS - Which indicate a loss of all AC power are:

a. Neither 480 volt AC emergency bus 14 nor 16 available.

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 3 of 25 STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl

. . . * . . . . . . 4 .

4 .

4 . .

4 . * . . . .. * . . . * . . . . . .4

CAUTION DUE TO POTENTIALLY EXTREME ENVIRONMENTAL CONDITIONS, CAUTION SHOULD BE USED WHEN ENTERING THE INTERMEDIATE BLDG FOR LOCAL ACTIONS.

. . - - * * - - - - *4 * *

4* 4 4 * - - - - 4

4 * * * . . 4 . . .

4 NOTE: o CSFSTs should be monitored for information only. FR procedures should not be implemented.

o Local actions may require portable lighting and communication devices.

o Verify Reactor Trip: Manually trip reactor.

o At least one train of reactor IF reactor trip breakers NOT open.

trip breakers - OPEN THEN perform the following:

o Neutron flux - DECREASING a. Open Bus 13 and Bus 15 normal feed breakers.

o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM b. Verify rod drive MG sets tripped.

c. Close Bus 13 and Bus 15 normal feed breakers.

d. Reset lighting breakers.

O Verify Turbine Stop Valves -

CLOSED Manually trip turbine.

IF turbine trip can NOT be verified. THEN close both MSIVs.

EWP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 4 of 25 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: FOLDOUT page should be open and monitored periodically.

3 Adjust S/G ARVs To Control Tavg At Approximately 547'.F 4 Stop Both RCPs NOTE: Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

5 Check If RCS Is Isolated:

a. PRZR PORVs - CLOSED a. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

b. Verify RCS isolation valves closed:

1) Place letdown orifice valve switches to CLOSE

AOV-200A

AOV-200B

AOV-202

2) Place letdown isolation valve switches to CLOSE

AOV-371

AOV-427

3) Place excess letdown isolation valve switch to CLOSE (AOV-310)

EOP: TITLE: REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 5 of 25 6 Verify Adequate TDAFW Flow:

a. Verify TDAFW pump - RUNNING a. Perform the following:

1) Verify governor valve, V-3652. latched.

IF governor valve tripped.

THEN dispatch AO to locally reset valve.

2) Manually or locally open at least one TDAFW pump steam supply valve.

MOV-3505A

MOV-3504A

b. Verify TDAFW pump flow - GREATER b. Verify proper TDAFW valve THAN 200 GPM alignment:

1) TDAFW pump discharge valve (MOV-3996) open.

2) Intact S/G TDAFW pump flow control valves open.

IF NOT, THEN manually align valves as necessary.

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER

. . PAGE 6 of 25 AC IO /E PE TE R SP NS RED

_E ATON/EXPECTED RESPONSFIREPNE NO BA NOTE: Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o AO should increase surveillance of TDAFW pump until AC power is restored.

7 Try To Restore Power to Any Train Of AC Emergency Busses:

a. Verify emergency DG aligned for a. Manually align switches on rear unit operation of MCB.

o Mode switch in UNIT o Voltage control selector in AUTO

b. Check emergency D/Gs - BOTH D/G b. WHEN non-running DG available RUNNING for starting. THEN perform the following:

1) Depress DG FIELD RESET pushbutton

2) Depress DG RESET pushbutton

3) Start D/G

4) IF D/G starts. THEN go to Step 7c.

5) IF DG will NOT start. THEN dispatch.AO to locally start emergency D/Gs.

IF no emergency D/G available. THEN perform the following:

a) Direct AO to attempt to restore emergency D/G (Refer to ER-D/G.1.

RESTORING D/G) b) Go to Step 8.

This Step continued on the next page.

EOe: TITLE:RE Ed: ~~~~~~~~~~~~~REV: :2 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 7 of 25 ACTION/EXPECTED RES:PONSEEPOSENO (Step 7 continued from previous page)

c. Check DG voltage and frequency

1) Voltage - APPROXIMATELY 480v 1) Adjust voltage control to restore voltage to approximately 480v

2) Frequency - APPROXIMATELY 60 2) Adjust governor to restore Hz frequency to approximately 60 Hz

d. Verify adequate DG cooling d. Manually energize busses and start SW Pumps.

o Bus 17 and/or Bus 18 -

ENERGIZED IF adequate cooling can NOT be supplied to a running D/G, THEN o One SW Pump running for each perform the following:

running D/G

1) Pull stop the D/G AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

2) Align alternate cooling (Refer to ER-D/G.2. ALTERNATE COOLING FOR EMERGENCY D/Gs).

e. Verify at least one train of AC e. Manually energize AC emergency emergency busses - ENERGIZED busses.

Bus 14 and Bus 18 IF Bus 14 AND Bus 16 are

Bus 16 and Bus 17 deenergized, THEN go to Step 8.

f. Return to procedure and step in effect

IEOfP: TITLE:. Ed: ~~~~~~~~~~~~REV: R V 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 8 of 25 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 * * * * - 4 * * * *

a* * - 4 * * * * - * * - - * * -4

4

4 4 *

4 -

CAUTION o WHEN POWER IS RESTORED TO BUS 14 AND/OR BUS 16. RECOVERY ACTIONS SHOULD CONTINUE STARTING WITH STEP 27.

o IF AN SI SIGNAL EXISTS OR IF AN SI SIGNAL IS ACTUATED DURING THIS PROCEDURE, IT SHOULD BE RESET TO PERMIT MANUAL LOADING OF EQUIPMENT ON AN AC EMERGENCY BUS.

4* * . .

4 4

. 4

. * . 4 * . 4

4

. . . . . 4 * . * . 4 4 . . . . . 4 4 4 8 Establish The Following Equipment Alignment:

a. Pull stop AC emergency bus loads

RHR pumps

CNMT RECIRC fans

. CNMT spray pumps

SI pumps

. CCW pumps

. Charging pumps

. MDAFW pumps

b. Evaluate non-vital loads (Refer to ATT-8.3. ATTACHMENT NONVITAL)

c. Place non-running SW pump switches to STOP. then return to AUTO

d. Place switch for MOV-313. RCP seal return isolation valve, to CLOSE

e. Momentarily place to CLOSE RCP CCW return valves

MOV-759A

. MOV-759B

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 9 of 25 ACTIO/EXPCTEDRESPOSE l[RESONSENOT OBTAINED 1 NOTE: Temporary power may be provided to Bus 16 by performing procedure ER-ELEC.4 and to Bus 13 by performing procedure ER-ELEC.5 at the Shift Supervisor's discretion.

9 Try To Restore Offsite Power:

a. Consult Power Control to a. IF normal offsite power supply determine if either normal NOT readily available. THEN offsite power supply - AVAILABLE perform the following:

o 12B transformer via breaker 1) Restore IA system using the 76702 Diesel Air Compressor (Refer to ATT-11.2, ATTACHMENT

-OR- DIESEL AIR COMPRESSOR).

o 12A transformer via breaker 2) Evaluate Main transformer 75112 backfeed for long term concerns (Refer to ER-ELEC.3.

EMERGENCY OFFSITE BACKFEED VIA MAIN & UNIT TRANSFORMER).

3) Go to Step 10.

b. Reset SI. if necessary

c. Restore offsite power (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER)

[EDP:

ECA-0.0 TITIE:SEW:

l

~~~~~~~~~~~~~REV:

LOSS OF ALL AC POWER RV 27l 2

~~~~~~~~~~~~~~PAGE 10 of 25 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 10 Initiate Local Actions To Isolate RCS And To Provide Cooling To Vital Areas And Equipment

a. Open all Reactor Protection and Control System rack doors in the Control Room.

b. Direct Security personnel to open the following vital rea doors to increase cooling:

Control Room Door S51

. Intermediate Bldg Door S37 (AFW pump area)

. Intermediate Bldg Door F36 (Automatic fire door. Rod Drive MG set area)

Intermediate Bldg Door S44 (Steam Header area)

c. Dispatch AO To Locally Isolate RCP Seals and BASTs (Refer to ATT-21.0, ATTACHMENT RCS ISOLATION)

d. Dispatch AO to align backup cooling water to TDAFW Pump (Refer to ATT-5.2. ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP)

ACTION/EXPECTED RESPONSE l[RESPONSE STP NOT OBTAINED I 11 Isolate Makeup And Reject IF valves can NOT be manually From Hotwell To CST By closed, THEN dispatch AO to locally Placing Hotwell Level isolate makeup and reject lines.

Controller (LC-107) In Manual AT 50% v Makeup isolation V-4058

Reject isolation V-4055 12 Isolate S/G: IF valves can NOT be manually closed. THEN dispatch AO to locally

a. Manually close both MSIVs isolate the affected flow path.

b. Depress MANUAL pushbuttons AND manually close MFW flow control valves

MFW regulating valves

. MFW bypass valves

c. Place MCB master switch for S/G blowdown and sample valves to CLOSE

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

, . . . , 4 . , 4 . * . . 4 4 . . , , * .4 4

. . . , , . *4 * . . . . . . .

CAUTION A FAULTED OR RUPTURED SIG THAT IS ISOLATED SHOULD REMAIN ISOLATED. STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM AT LEAST ONE SG.

. , . . , . . , 4 4 , , 4 , . . 4 , * , 4 4 . , . . . 4 . 4 4 . . , 4 4 4 4 . , ,

13 Check If SG Secondary Side Perform the following:

Is Intact:

a. IF any SG pressure decreasing o Pressure in both SGs - STABLE in an uncontrolled manner OR OR INCREASING completely depressurized. THEN isolate faulted SIG unless o Pressure in both SGs - GREATER needed for RCS cooldown:

THAN 110 PSIG

1) Close faulted S/G MDAFW pump discharge valve.

SIG A. MOV-4007

S/G B. MOV-4008

2) Close faulted S/G TDAFW flow control valve.

S/G A. AOV-4297

S/G B. AOV-4298

3) Verify faulted S/G ARV controller in MANUAL with output at 0%.

S/G A. AOV-3411

S/G B. AOV-3410

4) Pull stop faulted S/G TDAFW pump steam supply valve.

S/G A. MOV-3505A

S/G B. MOV-3504A IF valve(s) can NOT be closed manually. THEN dispatch AO to locally close valve(s) to isolate flow.

b. Dispatch AO to complete faulted S/G isolation (Refer to ATT-10.0. ATTACHMENT FAULTED S/G).

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 14 Check If S/G Tubes Are Intact: Try to identify ruptured SG.

Continue with Step 15. WHEN o Dispatch RP tech or AO to ruptured SG identified. THEN locally check steamline perform the following:

radiation - NORMAL

a. Isolate ruptured SIG unless needed for RCS cooldown:

1) Close ruptured SG MDAFW pump discharge valve.

SG A. MOV-4007

SG B. MOV-"008

2) Pull stop ruptured SIG MDAFW pump.

3) Close ruptured SG TDAFW flow control valve.

SG A. AOV-4297

SG B. AOV-4298

4) Adjust ruptured SG ARV controller to 1050 psig in AUTO. WHEN S/G pressure less than 1050 psig. THEN ensure ruptured S/G ARV closed.

SG A. AOV-3411

. SG B. AOV-3410

5) Pull stop ruptured S/G TDAFW pump steam supply valve.

SIG A. MOV-3505A

S/G B. MOV-3504A IF valve(s) can NOT be closed manually. THEN dispatch AO to locally close valve(s) to isolate flow.

b. Dispatch AO to complete ruptured S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G).

EOP: TIRE:

REV: 27 ECA-O.O LOSS OF ALL AC POWER PAGE 14 of 25 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED

* . * . * * . . . . . * . * . . . . * . * . . * . . * * * . . . . 4

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS. USING FIRE OR CITY WATER. WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

. * . * . . . . * . * * . * * . , . . . . . . . . * . * . * * . * . . . * .4 4 NOTE: TDAFW pump AOV flow control AOVs may drift open on loss of IA.

15 Monitor Intact S/G Levels:

a. Narrow range level - GREATER a. Maintain maximum AFW flow until THAN 5% [25% adverse CNMT] narrow range level greater than 5% [25% adverse CNMT] in at least one SG.

b. Control AFW flow by thiattling b. Control AW flow by throttling TDAFW flow control valves TDAFP discharge MOV-3996.

. S/G A. AOV-4297 IF MOV-3996 can NOT be

. S/G B. AOV-4298 controlled. THEN dispatch AO to locally control AFW flow by throttling TDAFW flow control valves.

SG A. AOV-4297

S/G B. AOV-4298 IF valves can NOT be throttled, THEN control AFW flow by starting and stopping TDAFW pump.

c. Control AFW flow to maintain c. IF narrow range level in any narrow range level between 17% intact S/G continues to increase

[25% adverse CNMT] and 50% in an uncontrolled manner. THEN return to Step 14.

EDP: TITLE:

REV: 27 ECA-O.O LOSS OF ALL AC POWER PAGE 15 of 25 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED NOTE: IF the loss of power is expected to continue beyond 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . THEN degassing of main generator should commence as soon as personnel become available (Refer to ATT-8.2. ATTACHMENT GEN DEGAS).

16 Check DC Bus Loads:

a. Place control switches for MFW pump AC oil pumps to OFF (allows timer to stop DC oil pumps)

b. Stop all large non-essential DC loads

1) Evaluate DC loads (Refer to ATT-8.0. ATTACHMENT DC LOADS).

2) WHEN turbine is stopped. THEN perform the following:

a) Locally close Turbine backup seal oil reg outlet valve V-5475J.

b) Stop Turbine DC lube oil pump (within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).

c. Check DC bus voltage - GREATER c. IF either DC bus less than THAN 105 VOLTS DC 105 volts DC. THEN refer to ER-ELEC.2. RECOVERY FROM LOSS OF

Bus A A or B DC BUS.

. Bus B

d. Direct electricians to locally monitor DC power supply

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 16 of 25 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 17 Verify Source Range Dispatch personnel with relay rack Detector(s) - ENERGIZED key to turn off 125 VDC power switches in REACTOR PROTECTION

N-31 racks RLTR-1 and RLTR-2 to

N-32 deenergize source range block relays.

* * * * * * * * * *

4

4 4 4 .4

4 4

4 4 &

4 4

4 4 4 CAUTION WHEN POWER IS RESTORED TO BUS 14 AND/OR BUS 16. RECOVERY ACTIONS SHOULD CONTINUE STARTING WITH STEP 27.

18 Check CST Level - GREATER Initiate makeup to CSTs using fire THAN 5 FEET or city water as a source. (Refer to ER-AFW.l. ALTERNATE WATER SUPPLY TO AFW PUMPS).

EOP: TITLE: REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 17 of 25 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED

* * . . * * * * . * * . * * . * * * * * . * * . * * * * * *

4 * * *

4 4

CAUTION o S/G PRESSURES SHOULD BE MAINTAINED GREATER THAN 200 PSIG TO PREVENT INJECTION OF SI ACCUM NITROGEN INTO THE RCS.

o S/G NARROW RANGE LEVEL SHOULD BE MAINTAINED GREATER THAN 5% [25% ADVERSE CNMT] IN AT LEAST ONE INTACT S/G. IF LEVEL CANNOT BE MAINTAINED. S/G DEPRESSURIZATION SHOULD BE STOPPED UNTIL LEVEL IS RESTORED IN AT LEAST ONE SIG.

,* * * * *

4 4 4 4

4. * *

4 4 *

4*. * * . . *

4

4 *

4 *

4 4 * *

NOTE: o The SIGs should be depressurized at maximum rate to minimize RCS inventory loss.

o PRZR level may be lost and reactor vessel upper head voiding may occur due to depressurization of SGs. Depressurization should not be stopped to prevent these occurrences.

o S/G ARV nitrogen pressure should be monitored and nitrogen supply bottles changed as necessary.

19 Initiate Depressurization Of Intact S/Gs To 300 PSIG:

a. Check S/G narrow range levels - a. Perform the following:

GREATER THAN 17% [25% adverse CNMT] IN AT LEAST ONE S/G 1) Maintain maximum AFW flow until narrow range level greater than 17% [25% adverse CNMT] in at least one S/G.

2) Continue with Step 20. WHEN narrow range level greater than 17% [25% adverse CNMT]

in at least one S/G. THEN do Steps 19b and 20.

b. Manually dump steam from intact b. Locally dump steam from intact S/Gs at maximum rate using S/G S/Gs at maximum rate using S/G ARVs ARV.

_ ACTION/EXPECTED RESPONSEIREPNE OTBANDI NOTE: o Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

o IF Instrument Bus D deenergized. THEN NIS SUR meters will NOT be available.

20 Monitor Reactor For Subcriticality:

a. Verify Subcriticality using the a. IF unable to verify following indications: subcriticality using NIS. THEN perform the following:

1) Check source range(s). N-31 AND N-32 o Control SG ARVs to stop SIG depressurization and allow o Indicator - ON SCALE RCS to heat up.

o Power - STABLE OR o Direct RP to sample RCS and DECREASING PRZR for boron concentration.

2) Check intermediate range. N-35 o Request plant staff assistance in evaluating core o Indicator - ON SCALE reactivity status o Power - STABLE OR DECREASING

3) Check power range. N-41 and N-43 o Indicators - LESS THAN 5%

o Power - STABLE OR DECREASING

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 19 of 25 NOTE: Depressurization of SIGs will result in a SI actuation. SI should be reset to permit manual loading o equipment on emergency usses.

21 Check SI Signal Status:

a. Any SI annunciator - LIT a. Go to Step 25. WHEN SI actuated. THEN do Steps 21b. 22.

23 and 24.

b. Reset SI 22 Verify CI And CVI:

a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.

Annunciator A-26. CNMT ISOLATION

. Annunciator A-25. CONTAINMENT VENTILATION ISOLATION

b. Verify CI and CVI valve status b. Manually close CI and CVI lights - BRIGHT 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. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights - valves.

BRIGHT

AOV-4561

AOV-4562

d. Verify RHR Pump Suction from d. IF sump recirculation NOT in CNMT Sump B valves - CLOSED progress, THEN manually close valves.

MOV-850A

MOV-850B IF valves can NOT be verified closed by MCB indication. THEN dispatch AO to locally close valves.

K>

EOP: TITLE: REV: 27 ECA-0.0 LOSS OF ALL AC POWER I PAGE 20 of 25 STEP ACTION/EXPECTED RESPONSEREPNE OT BAI D 23 Check If S/G Depressurization Should Be Stopped:

a. Check RCS cold leg temperatures a. Perform the following:

- GREATER THAN 315 0F

1) Control S/G ARVs to stop S/G depressurization.

2) Go to Step 24.

b. Check SIG pressures - LESS THAN b. Continue with Step 24. WHEN SIG 300 PSIG pressure decreases to less than 300 psig. THEN do Step 23c and d.

c. Check IA supply: c. Control S/G ARVs in manual to maintain S/G pressures at o Pressure - GREATER THAN 300 psig 60 PSIG IF manual control is NOT o Pressure - STABLE OR available. THEN locally control INCREASING S/G ARVs to maintain S/G pressures at 300 psig.

d. Control SIG ARVs to maintain S/G d. Control S/G ARVs in manual to pressures at 300 psig IN AUTO maintain S/G pressures at 300 psig IF manual control is NOT available. THEN locally control S/G ARVs to maintain S/G pressures at 300 psig.

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 21 of 25 ACTION/EXPECTED RESPONSEl STEP RESPONSE NOT OBTAINED 24 Check CNMT Pressure - HAS IF CNMT pressure is less than 28 REMAINED LESS THAN 28 PSIG psi.THEN perform the following:

o Annunciator A-27. CNMT SPRAY - a. Reset CNMT spray.

EXTINGUISHED

b. Place CNMT spray pump discharge o CNMT pressure indicators - LESS valve switches to CLOSE to THAN 28 PSIG deenergize open contactor.

IF NOT. THEN continue with step 25.

WHEN CNMT pressure less than 28 psig. THEN reset CNMT spray and place CNMT spray pump discharge valve switches to CLOSE.

25 Check Core Exit T/Cs - LESS IF core exit temperatures greater THAN 12000F than 1200'F and increasing, THEN go to SACRG-1. SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.

step 1.

26 Check If AC Emergency Power Continue to control RCS conditions Is Restored - BUSSES 14 and monitor plant status:

AND/OR 16 ENERGIZED

a. Check status of desired actions:

o AC power restoration o ARV nitrogen pressure o Diesel air compressor to IA system o RCP seal isolation o DC power supply

b. Return to Step 13.

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 22 of 25 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STP 27 Manually Control S/G ARVs To Locally control S/G ARVs.

Stabilize S/G Pressures

EOP': TITIE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 23 of 25 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: SW isolation may occur when power is restored to AC emergency busses.

28 Verify SW System Operation:

a. Check Bus 17 and Bus 18 - AT a. Perform the following:

LEAST ONE ENERGIZED

1) Pull stop any DG that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.

3) Go to Step 29.

b. Verify two SW pumps - RUNNING b. IF normal power available. THEN establish two SW pumps running.

IF normal power NOT available.

THEN establish one SW pump running for each operating D/G.

IF NO SW pumps running. THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.

IF only one SW pump running.

THEN perform the following:

1) Manually perform SW isolation.

2) Refer to AP-SW.2. LOSS OF SERVICE WATER.

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 24 of 25 STEP ACTION/EXPECTED RESPONSE IRESPONSE NOT OBTAINED I

* * * * *

4 * * *. * .

4 * *

4 4 *4 4 .4 *

CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.

* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

4 * * *

29 Verify Following Equipment Manually load equipment as power Loaded On Available AC supply permits.

Emergency Busses:

o 480 volt MCCs - ENERGIZED

MCC C from Bus 14

MCC D from Bus 16 o Verify instrument busses -

ENERGIZED

Bus A from MCC C (A battery)

Bus B from MCC C

Bus C from MCC D (B battery) o Dispatch personnel to verify proper operation of battery chargers

30 Select Recovery Procedure:

a. Check RCS subcooling based on a. Go to ECA-0.2. LOSS OF ALL AC core exit T/Cs - GREATER THAN POWER RECOVERY WITH SI REQUIRED.

00 F USING FIG-1.0. FIGURE MIN Step 1.

SUBCOOLING

b. Check PRZR level - GREATER THAN b. Go to ECA-0.2, LOSS OF ALL AC 5% [30% adverse CNMT] POWER RECOVERY WITH SI REQUIRED.

Step 1.

c. Check SI and RHR Pumps - NONE c. Go to ECA-0.2. LOSS OF ALL AC RUNNING POWER RECOVERY WITH SI REQUIRED.

Step 1.

d. Go to ECA-0.1. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED. Step 1

-END-

EOP: TITLE: REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 1 ECA-0.0 APPENDIX LIST TITLE

1) FIGURE MIN SUBCOOLING (FIG-1.0)

2) ATTACHMENT DC LOADS (ATT-8.0)

3) ATTACHMENT FAULTED S/G (ATT-10.0)

4) ATTACHMENT RUPTURED S/G (ATT-16.0)

5) ATTACHMENT CI/CVI (ATT-3.0)

6) ATTACHMENT NONVITAL (ATT-8.3)

7) ATTACHMENT GEN DEGAS (ATT-8.2)

8) ATTACHMENT RCS ISOLATION (ATT-21.0)

9) ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP (ATT-5.2)

10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

11) ATTACHMENT NO SW PUMPS (ATT-2.4)

12) FOLDOUT

EOP: TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 1 FOLDOUT PAGE

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

EOP: TILE:

ES-0.1 REACTOR TRIP RESPONSE REV: 22 PAGE 1 of 20 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __

RESPONSI MANAGER o-E-TI ba EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP~: TITLE: R~:2 ES-0.1 REACTOR TRIP RESPONSE PAGE 2 of 20 A. PURPOSE - This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when SI is neither actuated nor required.

EP: TITLE: REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 3 of 20 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl

* * * * * * * *

4 * * * * * * * * *

4 * * * * * * * * * *

4

4 * * * *

CAUTION IF SI ACTUATION OCCURS DURING THIS PROCEDURE, THEN E-0. REACTOR TRIP OR SAFETY INJECTION. SHOULD BE PERFORMED.

4 4 4 4 4 4 4

4

4 4 4 * *

4

4 4 4 4 4 4 4

4 4 4 * * *

4 4 4 * *

NOTE: o FOLDOUT page should be open and monitored periodically.

o Critical Safety Function Status Trees should be monitored. (Refer to Appendix 1 for Red Path Summary.)

o Refer to AP(s) that were in effect prior to the reactor trip.

1 Monitor RCS Tavg - STABLE AT IF temperature less than 5471F and OR TRENDING TO 5470 F decreasing. THEN perform the following:

a. Stop dumping steam.

b. Ensure S/G blowdown and sample valves closed.

c. Ensure reheater steam supply valves are closed.

d. IF MDAFW pumps supplying greater than 200 gpm, THEN ensure TDAFW pump steam supply valves in PULL STOP.

e. IF cooldown continues. THEN control total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one SG. WHEN S/G level greater than 5% in one SG, THEN limit feed flow to that required to maintain SIG level.

f. IF cooldokn continues below 540 0F. THEN close both MSIVs.

IF temperature greater than 5470F and increasing. THEN dump steam to stabilize and slowly decrease temperature to 5471F.

IEOP: TITLE:

llEOP lT~~~~~~tE . ~~~

I REV: 22l ES-0.1 REACTOR TRIP RESPONSE PAGE 4 of 20 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check S/G Feed Flow Status:

a. Check RCS Tavg - LESS THAN 5541F a. Continue with Step 3. WHEN temperature less than 554 0 F.

THEN do Steps 2b through f.

b. Verify MFW flow control valves - b. Depress MANUAL pushbuttons for CLOSED A and B MW regulating valve and bypass valve controllers AND a MFW regulating valves adjust to 0 demand.

MFW bypass valves

c. Verify total AFW flow - GREATER c. Manually start both MDAFW pumps.

THAN 200 GPM IF total AFW flow greater than 200 gpm can NOT be established.

THEN perform the following:

o Manually start TDAFW pump.

-OR-o Perform the following:

1) Establish MFW on bypass valves.

2) Go to step 3.

d. Close MFW pump discharge valves

. MOV-3977. A MFW pump

MOV-3976, B MFW pump

e. Stop MFW pumps and place in PULL STOP

f. WHEN both MFP pumps are stopped..

THEN depress MANUAL pushbuttons for A and B MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

EOP: TITLE:

.- ~~REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 5 of 20 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl

3 Monitor S/G Levels:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% than 200 gpm until narrow range level greater than 5% in at least one SG.

b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase. THEN stop and 52%. feed to that SG.

4 Verify MRPI Indicates - ALL IF one or more control rods NOT CONTROL AND SHUTDOWN RODS ON fully inserted. THEN perform the BOTTOM following:

a. Place RMW mode selector switch to BORATE.

b. Adjust boric acid flow control valve. FCV-11OA. for desired flowrate.

c. Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).

d. Place RMW control to start and verify flow. IF flow can NOT be established. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION.

EOP: TIRE:

ES-0.1 REACTOR TRIP RESPONSE PAGE 6 of 20 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 5 Verify All AC Busses - Perform the following:

ENERG IZED BY OFFSITE POWER

a. IF any AC emergency bus normal o Normal feed breakers to all 480 feed breaker open. THEN ensure volt busses - CLOSED associated DG breaker closed.

o 480 volt bus voltage - GREATER b. Perform the following as THAN 420 VOLTS necessary:

o Emergency DG output breakers - 1) Ensure one CCW pump running.

OPEN

2) Close non-safeguards bus tie breakers:

Bus 13 to Bus 14 tie

Bus 15 to Bus 16 tie

3) Reset Bus 13 and Bus 15 lighting breakers.

4) Dispatch AO to locally reset and start adequate air compressors.

5) Place the following pumps in PULL STOP:

EH pumps

Turning gear oil pump

. HP seal oil backup pump

6) Restore power to MCCs.

A from Bus 13

B from Bus 15

E from Bus 15

F from Bus 15

7) Start HP seal oil backup pump

8) Establish 2 CNMT RECIRC fans in service (205 kw each).

9) Ensure DG load within limits.

c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).

EOP: TITLE: REV 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 7 of 20 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 6 Verify At Least Two SW Pumps Manually start SW pumps as

- RUNNING necessary.

IF NO SW pumps running, THEN perform the following:

a. Pull stop DG that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4. ATTACHMENT NO SW PUMPS IF only one SW pump running. THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

EOP: TITLE:

ES-0.1 REACTOR TRIP RESPONSE REV: 22 PAGE 8 of 20 STE P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED l 7 Verify IA Available: Dispatch AO to locally reset and start adequate air compressors.

o Adequate air compressor(s) -

RUNNING IF adequate electric air compressor(s) can NOT be operated.

o IA pressure - GREATER THAN THEN use diesel air compressor.

60 PSIG (Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

IF IA pressure can NOT be maintained. THEN perform the following:

a. Refer to AP-IA.1. LOSS OF INSTRUMENT AIR.

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

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

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

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check PRZR Level Control:

a. Verify charging pumps - ANY a. Perform the following:

RUNNING

1) Close letdown isolation.

AOV-427.

2) Manually start one charging pump.

b. PRZR level - GREATER THAN 13% b. Perform the following:

1) Place letdown isolation AOV-427 switch to close.

2) Verify excess letdown isolation valve AOV-310 closed.

3) Ensure PRZR heaters off.

4) Control charging to restore PRZR level greater than 13%.

5) Continue with Step 9. WHEN PRZR level greater than 13%.

THEN do Steps 8c through e.

c. Verify letdown - IN SERVICE c. Verify excess letdown in service. IF NOT. THEN manually place letdown in service (Refer to ATT-9.O. ATTACHMENT LETDOWN).

d. PRZR level - TRENDING TO 35% d. Control charging and letdown to maintain PRZR level at 35%.

e. Check PRZR heaters - ENERGIZED e. Reset PRZR heaters and energize to restore PRZR pressure.

o PRZR proportional heaters o PRZR heater backup group

EOP~: TITLE:. Ed: ~~~~~~~~~~~~REV: R V 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 10 of 20 9 Check PRZR Pressure Control:

a. PRZR pressure - GREATER THAN a. Perform the following:

1750 PSIG

1) Verify SI actuation. IF NOT.

THEN manually actuate SI and CI.

2) G to E-0. REACTOR TRIP OR SAFETY INJECTION. Step 1.

b. PRZR pressure - GREATER THAN b. IF pressure less than 2210 PSIG 2210 PSIG and decreasing, THEN perform the following:

1) Ensure PRZR PORVs closed.

IF any valve can NOT be closed, THEN manually close its block valve.

PCV-430, MOV-516

PCV-431C, MOV-515

2) Ensure normal PRZR spray valves closed.

PCV-431A

. PCV-431B IF valves can NOT be closed, THEN stop associated RCP(s).

3) Ensure PRZR heaters energized.

This Step continued on the next page.

ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED (Step 9 continued from previous page)

c. PRZR pressure - LESS THAN c. IF pressure greater than 2260 PSIG 2260 psig and increasing. THEN perform the following:

1) Verify demand on PRZR pressure controller 431K greater than 50%. IF NOT.

THEN place controller in MANUAL and adjust to restore PRZR pressure to approximately 2235 psig.

2) Ensure PRZR heaters off.

3) Control pressure using normal PRZR spray.

IF normal PRZR spray NOT available and letdown is in service. THEN perform the following:

a) Verify spray line fluid to PRZR AT less than 3200F.

IF NOT. THEN use one PORV.

b) Use auxiliary spray.

IF PRZR spray NOT available, THEN use one PRZR PORV.

EOP: TITLE: REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 12 of 20 10 Check If TDAFW Pump Can Be Stopped:

a. Both MDAFW pumps - RUNNING a. Go to Step 11.

b. PULL STOP TDAFW pump steam supply valves

. MOV-3504A

MOV-3505A 11 Establish Condenser Steam Dump Pressure Control:

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

o Any MSIV - OPEN 1) Place S/G ARV controller in AUTO at 1005 psig and verify o Annunciator G-15, STEAM DUMP proper operation. IF S/G ARV ARMED - LIT NOT controlling in AUTO. THEN control S/G ARV manually.

2) Go to Step lld.

b. Adjust condenser steam dump controller HC-484 to 1005 psig in AUTO

c. Place steam dump mode selector switch to MANUAL

d. Verify RCS Tavg - STABLE AT OR d. Adjust steam dump to restore TRENDING TO 5470F Tavg. IF steam dumps not available, THEN use ARVs.

r EOP: TITLE: REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 13 of'20 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 12 Check RCP Status - AT LEAST Perform the following:

ONE RUNNING

a. Establish conditions for starting an RCP:

o Ensure bus 11A or lB 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.

EOP: TITLE:

REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 14 of 20 NOTE: Loss of forced air cooling may result in failure of NIS detectors.

13 Check If Source Range Detectors Should Be Energized:

a. Source range channels - a. Go to Step 13e.

DEENERGIZED

b. Check intermediate range flux - b. Perform the following:

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing THEN initiate boration.

2) Continue with Step 14. WHEN flux is less than 10-10 amps on any operable channel, THEN do Steps 13c. d and e.

c. Check the following: c. Continue with Step 14. When either condition met. THEN do o Both intermediate range Steps 13d and e.

channels - LESS THAN 10-10 AMPS

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors - d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.1. SR MALFUNCTION, and go to Step 14.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

EOP: TITLE:

REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 15 of 20 ACTION/EXPECTED RESPONSE STEP RESPONSECNOT OBTAINED 14 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1.

ATTACHMENT SD-2.

b. Perform the following:

o Open generator disconnects

lG13A71

9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump (Refer to T-5F.

STARTING OR STOPPING THE CONDENSATE PUMPS)

c. Verify adequate Rx head cooling:

1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw).

2) Verify one Rx compartment 2) Manually start one fan as cooling fan - RUNNING power supply permits (23 kw).

d. Dispatch AO to perform ATT-17.0.

ATTACHMENT SD-i

EOP: TITLE:

REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 16 of 20 ACTION/EXPECTED RESPONSE STE RESPONSE NOT OBTAINED 15 Maintain Stable Plant Conditions:

a. PRZR pressure - BETWEEN a. Control PRZR heaters and spray 1800 PSIG AND 2260 PSIG as necessary.

b. PRZR level - BETWEEN 35% AND 40% b. Control charging as necessary.

c. SIG narrow range levels - c. Control S/G feed flow as BETWEEN 17% AND 52% necessary.

d. RCS Tavg - GREATER THAN 5401F d. Close both SIVs.

16 Check VCT Makeup System:

a. Verify the following:

1) Adjust boric acid flow control valve to 9.5 gpm

2) Adjust RMW flow control valve to 40 gpm

3) RMW mode selector switch in AUTO

4) RMW control armed - RED LIGHT LIT

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

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- RMW pumps running.

o Level - STABLE OR INCREASING 2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.

EP: TITLE:

REV: 2 2 ES-0.1 REACTOR TRIP RESPONSE PAGE 17 of 20 ACTION/EXPECTED RESPONSEREPSENTOANE 17 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 18. WHEN VCT level greater than 40%.

THEN do Step 17b.

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

EOP: TITLE: REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 18 of 20 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 18 Verify TDAFW Pump Aligned For AUTO Start:

a. Any MDAFW pump - AVAILABLE a. Verify TDAFW pump operating to maintain required SIG level and go to Step 20.

b. Verify AMSAC TRIPPED status b. Reset AMSAC.

light - EXTINGUISHED

c. Verify both SG levels - GREATER c. Continue with Step 20. WHEN S/G THAN 17% level greater than 17%. THEN do Steps 18d. e and 19.

d. Verify Bus 11A and Bus B - AT d. Perform the following:

LEAST ONE ENERGIZED

1) IF TDAFW pump NOT required to maintain SG level. THEN pull stop TDAFW pump steam supply valves:

MOV-3504A

MOV-3505A

2) Go to Step 19.

e. Verify the following:

1) TDAFW pump - OFF 1) Perform the following:

a) IF TDAFW pump required to maintain S/G level. THEN go to Step 20.

b) Stop TDAFW pump.

2) TDAFW pump steam supply valve 2) Place TDAFW pump steam supply switches in AUTO valve switches in AUTO.

3) Verify TDAFW flow control 3) Open TDAFW flow control valves - OPEN, DEMAND AT 0 valves.

AOV-4297

AOV-4298

EOP: TITLE: REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 19 of 20 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 19 Establish Normal AFW Pump Shutdown Alignment:

a. Verify the following: a. Continue with Step 20. WHEN conditions met. THEN do Steps o Both S/G levels - GREATER 19b through f.

THAN 17% AND STABLE OR INCREASING o Total AFW flow - LESS THAN 200 GPM

b. Close MDAFW pump discharge valves

MOV-4007

MOV-4008

c. Place AFW bypass switches to DEF

d. Stop all but one MDAFW pump

e. Open AFW discharge crossover valves

MOV-4000A

MOV-4000B

f. Adjust AFW bypass valves to control S/G levels

AOV-4480

AOV-4481

. EOP: TITLE:

REV: 22 ES-0.1 REACTOR TRIP RESPONSE

. . .. n 3. 20, of 20

PAGE ACTION/EXPECTED RESPONSE l[RESPONSE STP NOT OBTAINED 20 Determine If Cooldown Is Required:

a. Consult Plant Staff - COOLDOWN a. Go to 0-3. HOT SHUTDOWN WITH REQUIRED XENON PRESENT.

b. At least one RCP - RUNNING b. Perform the following:

1) Ensure 2 control rod shroud fans running.

2) Go to ES-0.2. NATURAL CIRCULATION COOLDOWN. Step 1.

c. Go to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN

-END-

EOP: TITLE:

REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 ES-O.1 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)

3) ATTACHMENT LETDOWN (ATT-9.o)

4) ATTACHMENT RCP START (ATT-15.0)

5) ATTACHMENT NC (ATT-13.0)

6) ATTACHMENT SD-1 (ATT-17.0)

7) ATTACHMENT SD-2 (ATT-17.1)

8) ATTACHMENT NO SW PUMPS (ATT-2.4)

9) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

10) FOLDOUT

EOP: TITLE: REV: 2 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% 55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000 F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT - CNMT pressure greater than 60 psig

MOP: TIThE:

REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 FOLDOUT PAGE

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2. SI ACTUATION CRITERIA IF ANY condition listed below occurs, THEN actuate SI and CI and go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

o RCS subcooling based on core exit T/Cs - LESS THAN F USING FIG-1.0, FIGURE MIN SUBCOOLING

- OR -

o PRZR level - LESS THAN 5% [30% adverse CNMT]

AND RCS subcooling based on core exit T/Cs - LESS THAN 200 F USING FIG-1.0, FIGURE MIN SUBCOOLING

- OR -

o Any automatic SI setpoint is reached

3. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

EOP: TITLE: REV: 3 0 FR-H.1 RESPONSE O LOSS OF SECONDARY HEAT SINK PAGE 1 of 31 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 0

RESPONSIBL e AGER

- A 3E FFEIV EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions for responding to a loss of secondary heat sink in both S/Gs.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when minimum AFW flow is not verified AND normal range level in both SGs is less than 5% [25% adverse CNMT]

b. F-0.3, HEAT SINK Critical Safety Function Status Tree on a RED condition.

EOP: TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 3 of 31

* * * * * * * * . * *

a * * * * * * * * * * * * * * * *4 * * *

4 * * * *

CAUTION o IF TOTAL FEED FLOW IS LESS THAN 200 GPM DUE TO OPERATOR ACTION, THIS PROCEDURE SHOULD NOT BE PERFORMED.

o FEED FLOW SHOULD NOT BE REESTABLISHED TO A FAULTED SG IF A NON-FAULTED S/G IS AVAILABLE.

*

4 4 4 A *

4 4 * *

4

4

4 4 4 *

4 * *

i4 4 4 * * * * *

NOTE: o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 Rhr.

o Foldout Page should be open and monitored periodically.

1 Check If Secondary Heat Sink Is Required:

a. RCS pressure - GREATER THAN ANY a. IF RWST level greater than 28%.

NON-FAULTED SG PRESSURE THEN return to procedure and step in effect.

IF RWST level less than 28%.

THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.

This Step continued on the next page.

EOP: TITLE:, Ed: ~~~~~~~~~~~~~REV: R V 30 FR-H.1 RESPONSE O LOSS OF SECONDARY HEAT SINK PAGE 4 of 31 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED (Step 1 continued from previous page)

b. Check RCS cold leg temperature - b. IF RCS pressure less than GREATER THAN 3500F 400 psig [300 psig adverse CNMT]. THEN try to place RHR System in service while continuing with this procedure:

1) Reset SI.

2) Place letdown pressure controller in MANUAL CLOSED.

3) Open the following valves (reset xy relays):

AOV-371. letdown isolation valve

AOV-427. loop B cold leg to REGEN Hx

. At least one letdown orifice valve (AOV-200A.

AOV-200B. or AOV-202)

4) IF pressure on PI-135 less than 400 psig, THEN establish RHR normal cooling (Refer to ATT-14.1, ATTACHMENT RHR COOL).

5) IF adequate cooling with RHR system established, THEN return to procedure and step in effect.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2 Monitor Secondary Heat Sink: IF a loss of heat sink is indicated. THEN perform the o Verify either SIG level - WIDE following:

RANGE GREATER THAN 50 inches

[100 inches adverse CNMT] a. Trip both RCPs.

o Verify PRZR pressure - LESS THAN b. Go to Step 13 to initiate bleed 2335 PSIG and feed cooling.

EOP: TITLE:

. ~~~~~~~~~REV:

30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 6 of 31

~~~~~~~~~~~~~~O OBAINEPCED IEPNE

* *

4 * *

4 *

4 * * * * * * * * * * * * *

4 * * * * * * * * * * * *

4 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).

4 A * *

0 4 4

4 4 4 4 4 4 4 4 4 * * * * *

4 4 4 4

4 4

4

. 4. 4 3 Try to Establish AFW Flow To At Least One S/G:

a. Check S/G blowdown and samples a. Place S/G blowdown and sample valves - CLOSED valve isolation switch to CLOSE.

b. Check MCB indications for cause of AFW failure:

1) Verify CST level - GREATER 1) Refer to ER-AFW.1. ALTERNATE THAN 5 FEET WATER SUPPLY TO AFW PUMPS.

2) Verify busses supplying power 2) Continue attempts to restore to MDAFW pumps - ENERGIZED power to MDAFW pumps.

. Bus 14

Bus 16

3) Determine AFW flow requirements per ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

4) Check AFW valve alignment 4) Dispatch AO to locally align valves.

o AFW pump discharge valves

- OPEN

MOV-4007

MOV-4008

MOV-3996 o TDAFW pump flow control valves - OPEN

AOV-4297

AOV-4298 This Step continued on the next page.

ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED (Step 3 continued from previous page)

c. Check AFW pumps - ALL RUNNING c. Perform the following:

1) Manually start MDAFW pumps.

2) Check TDAFW pump steam supply valves OPEN.

MOV-3504A

MOV-3505A

3) If necessary dispatch AO to locally reset TDAFW pump governor valve.

4) IF NO AFW pumps operable.

THEN go to Step 4.

d. Control AFW flow per requirements of ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

e. Check total flow to S/Gs - e. Continue attempts to restore AFW GREATER THAN 200 GPM flow and go to Step 4.

f. Return to procedure and step in effect 4 Stop Both RCPs

* * . . . * . . . * . * . * . . . * . . . . . * * . * . . * * * * . * . . .

0 CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER) 5 Reset SI If Actuated

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Try To Establish MFW Flow To At Least One S/G:

a. Check any MFW pump - AVAILABLE a. Go to Step 7.

b. Check condensate system: b. IF offsite power available. THEN try to place condensate system o Condensate pump - ANY RUNNING in service.

o MFW pump suction pressure - IF NOT. THEN go to Step 7.

GREATER THAN 185 PSIG

c. Establish MFW flow: c. IF MFW flow can NOT be established. THEN go to Step 7.

1) Check MFW pump discharge valves - CLOSED

2) Verify MFW regulating or bypass valves - OPERABLE

3) Depress MANUAL pushbuttons for A and B MFW regulating valve and bypass valve controllers AND adjust to 0%

demand.

4) Dispatch AO to restore MFW pump SW cooling

5) Verify S/G blowdown key switches in NORMAL

6) Ensure Annunciator H-4.MAIN FEED PUMP OIL SYSTEM -

EXTINGUISHED

7) Close Condensate Bypass valve. AOV-3959.

8) Ensure Annunciator H-li. FEED PUMP SEAL WATER LO DIFF PRESS 15 PSI - EXTINGUISHED

9) Ensure one MFW pump recirc valve - OPEN This Step continued on the next page.

[EOP: TITLE:RE:

E: TI~~~~~~~~~~~~~~~REV: 3 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK

. PAGE 9 of 31 STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 6 continued from previous page)

10) Start selected MFW pump

11) Open MFW pump discharge valve

12) Adjust MFW regulating or bypass valves to control MFW flow per requirements of ATT-22.0. ATTACHMENT RESTORING FEED FLOW

d. Go to Step 11 7 Establish SAFW Flow:

a. Perform the following: a. IF greater than 200 gpm total SAFW flow can NOT be

1) Align SAFW system for established. THEN go to Step 8.

operation (Refer to ATT-5.1, ATTACHMENT SAFW)

2) Determine SAFW flow requirements per ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

3) Start both SAFW pumps

4) Control SAFW flow per requirements of ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

5) Verify SAFW total flow -

GREATER THAN 200 GPM

b. Go to Step 11

EOP~: W TITL.E:RE: EN: ~~~~~~~~~~~~~~~REV: 33 0 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 10 of 31 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED

4 44 4 4 ~ * * *. . * * * . * . * . . *. * - - * - *4 4 CAUTION IF WIDE RANGE LEVEL IN BOTH SGS DECREASES TO LESS THAN 50 INCHES [100 INCHES ADVERSE CNMT] OR IF PRZR PRESSURE INCREASES TO GREATER THAN 2335 PSIG DUE TO LOSS OF HEAT SINK, THEN STEPS 13 THROUGH 15 SHOULD BE IMMEDIATELY INITIATED FOR BLEED AND FEED.

. . . . * . . . * * * * . . . . 4 * - - * * . . *

4* * . * * - - - - . . 4 8 Establish Conditions to Feed S/G(s) From Condensate System:

a. Check condensate pumps - ANY a. IF offsite power available. THEN RUNNING manually start at least one condensate pump. IF a condensate pump can NOT be started. THEN go to Step 12.

b. Establish condensate flowpath (Refer to ATT-5.0. ATTACHMENT COND TO SG)

c. De-energize PRZR heaters 9 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Place S/G ARV controllers in AUTO at desired pressure and go o Any MSIV - OPEN to Step 10.

o Annunciator G-15. STEAM DUMP ARMED - LIT

b. Adjust condenser steam dump controller HC-484 to highest S/G pressure

c. Verify condenser steam dump controller HC-484 in AUTO

d. Place steam dump mode selector switch to MANUAL

~~~~~~~~~~~~~~O OBAINEPCED IEPNE

* * * * * * * * -* * * * * * * * * * * * * * * . * * * * *

4 ** * * *

CAUTION FOLLOWING BLOCK OF AUTOMATIC SI ACTUATION, MANUAL SI ACTUATION MAY BE REQUIRED IF CONDITIONS DEGRADE.

* * *

4 * * * *

4 4 4

4 4

4

4

4

4 4 * * ** * * * * *

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

10 Establish Condensate Flow to S/G:

a. Check RCS pressure - GREATER a. Go to Step 10c.

THAN 1950 PSIG

b. Depressurize RCS to less than 1950 psig:

1) Check letdown - IN SERVICE 1) Use one PRZR PORV. IF IA to CNMT. AOV-5392. NOT open.

THEN refer to ATT-12.0, ATTACHMENT N2 PORVS.

a) IF PORV NOT available.

THEN use auxiliary spray valve, AOV-296 and go to step lOc.

2) Depressurize using auxiliary 2) Use one PRZR PORV. IF IA to spray valve (AOV-296) CNMT. AOV-5392. NOT open.

THEN refer to ATT-12.0.

ATTACHMENT N2 PORVS.

c. WHEN PRZR pressure less than 1950 psig, THEN place SI block switches to BLOCK

Train A

Train B

d. Verify SAFETY INJECTION BLOCKED status light - LIT This Step continued on the next page.

(Step 10 continued from previous page)

e. Stop depressurizing RCS and maintain RCS pressure less than 1950 psig

f. Depress MANUAL pushbuttons AND manually adjust MFW regulating or bypass valves to control feed flow per requirements of ATT-22.0. ATTACHMENT RESTORING FEED FLOW

g. Dump steam to condenser at g. Manually or locally dump steam maximum rate to depressurize at using intact SG ARV at maximum least one SIG to less than rate to depressurize at least 380 psig one SIG to less than 380 psig.

h. Verify condensate flow to S/Gs h. Go to Step 12.

11 Check S/G Levels:

a. Narrow range level in at least a. IF feed flow verified and level one S/G - GREATER THAN 5% [25% increasing in at least one SG.

adverse CNMT] THEN maintain flow to restore narrow range level greater than 5% [25% adverse CNMT]. IF NOT verified. THEN go to Step 12.

b. Return to procedure and step in effect

12 Verify Secondary Heat Sink:

a. Check the following: a. IF loss of heat sink is indicated. THEN perform the o Either S/G level - WIDE RANGE following:

GREATER THAN 50 inches

[100 inches adverse CNMT] 1) Go to Step 13 to initiate bleed and feed cooling.

o PRZR pressure - LESS THAN 2335 PSIG

b. Return to Step 1

* * * * * * * * *

A aA*

a

*

a a

*

a

CAUTION STEPS 13 THROUGH 15 MUST BE PERFORMED QUICKLY IN ORDER TO ESTABLISH RCS HEAT REMOVAL BY RCS BLEED AND FEED.

13 Actuate SI and CI 14 Verify RCS Feed Path: Manually start pumps and align valves as necessary to establish

a. Check SI pumps - AT LEAST ONE RCS feed path.

RUNNING IF a feed path can NOT be

b. Check valve alignment for established. THEN continue attempts operating SI pumps - PROPER to establish feed flow. Return to EMERGENCY ALIGNMENT Step 3.

STEstACTION/EXPECTED RESPONSES EO 15 Establish RCS Bleed Path:

a. Open both PRZR PORV block valves a. Ensure power to MCCs supplying block valves.

MCC D for MOV-515

MCC C for MOV-516 IF any block valve can NOT be opened. THEN dispatch AO to locally check breaker:

. MOV-515. MCC D position 6C

MOV-516. MCC C position 6C

b. Place both PRZR PORV switches to OPEN

c. Align RCS overpressure protection system to open both PRZR PORVs (Refer to ATT-12.0.

ATTACHMENT N2 PORVS)

d. Verify PORVs - BOTH OPEN d. IF BOTH PRZR PORVs can NOT be opened, THEN ensure both PORV switches in OPEN.

* . - . * * * * . * - * . -* * * * * * * * * - . 4 * * *

CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER)

*

4 * * * * * * * *

4 4 4 4 * * *

4 **

4 * * * * * *

16 Check If SI Can Be Reset:

a. Check SI blocked status light - a. Place SI block switches to EXTINGUISHED UNBLOCK

b. Check the following: b. IF PRZR pressure stable or increasing. THEN reset SI and go o PRZR pressure - LESS THAN to Step 17.

1750 PSIG IF PRZR pressure decreasing.

-OR- THEN perform the following:

o Either steamline pressure - 1) WHEN PRZR pressure less than LESS THAN 514 PSIG 1750 psig. THEN reset SI.

2) Go to Step 17.

c. Reset SI 17 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A-26. b. Perform the following:

CONTAINMENT ISOLATION -

EXTINGUISHED 1) Reset SI.

2) Depress CI reset pushbutton

PEO: TITLE: - -

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 16 of 31 18 Verify Adequate SW Flow:

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

IF less than two SW pumps can be operated. THEN perform the following:

1) F NO SW pumps running. THEN perform the following:

a) Pull stop any DG that is NOT supplied by alternate cooling, AND immediately depress associated.VOLTAGE SHUTDOWN pushbutton.

b) Refer to ATT-2.4.

ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running.

THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

3) Go to Step 19.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves - AT LEAST ONE SET OPEN

MOV-4615 and MOV-4734

. MOV-4616 and MOV-4735

EOP: TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 17 of 31 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 19 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

Bus 13 to Bus 14 tie

Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT. THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR).

-OR-o Evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0.

ATTACHMENT CNMT RECIRC FANS).

3) Start HP seal oil backup pump.

4) WHEN bus 15 restored, THEN reset control room lighting.

b. Check SW pumps - AT LEAST TWO b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR).

2) Go to Step 19d.

This Step continued on the next page.

ACTION/EXPECTED RESPONSE STE RESPONSE NOT OBTAINED (Step 19 continued from previous page)

c. Verify turbine building SW c. Perform the following:

isolation valves - OPEN

1) Manually align valves.

MOV-4613 and MOV-4670

MOV-4614 and MOV-4664 2) Dispatch A to locally reset compressors as necessary.

d. Verify adequate air d. Manually start electric air compressor(s) - RUNNING compressors as power supply permits (75 kw each). IF electric air compressors can NOT be started. THEN start diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR).

e. Check IA supply: e. 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 21. WHEN IA restored, THEN do Steps 19f. g and 20.

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

g. Verify IA to CNMT AOV-5392 - OPEN g. Continue with Step 21. WHEN IA restored to CNMT. THEN do Step 20.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: PRZR PORVs may close temporarily until adequate IA pressure is restored in CNMT.

20 Restore RCS Overpressure Protection System To Standby:

a. Verify instrument bus D - a. Perform the following:

ENERGIZED

1) Ensure steam dump mode control in MANUAL.

2) Restore power to instrument bus D from MCC B or MCC A (maintenance supply).

b. Place PORV PCV-430 and PCV-431C N2 arming switches to BLOCK

SOV-8619A

. SOV-8619B

c. Close PORV PCV-430 and PCV-431C N2 SURGE TK VLVs

SOV-8616A

SOV-8616B

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Verify Adequate RCS Bleed Perform the following:

Path:

a. Open Rx head vent valves.

o Core exit TCs - STABLE OR DECREASING

SOV-590

SOV-591 o RVLIS Level (no RCPs) - GREATER

SOV-592 THAN 77% [82% adverse CNMT]

SOV-593

b. Align any available low pressure water source to intact SGs.

IF no low pressure water source can be aligned. THEN go to Step 22.

c. Depressurize at least one intact S/G to atmospheric pressure using SG ARV.

* . * * * * * * * . * * * * * * * * . * * . * . * . * *

4 *

S

4 * . S *

CAUTION ACTIONS TAKEN TO INITIATE RCS BLEED AND FEED SHALL NOT BE REVERSED WHEN PERFORMING STEPS 1 THROUGH 12 OF E-0. REACTOR TRIP OR SAFETY INJECTION.

* *

S * * ,

4 * * * * *

S S * *

4 * * . S

S

4 5

S * * * * * *

4 22 Complete Steps 1 through 12 Of E-0, REACTOR TRIP OR SAFETY INJECTION, While Continuing With This Procedure

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAI

A . * * *

4 4

4 *

4 4 4 4 4 * . . 4 .

4 . .

4 * * * *

4 CAUTION THE RCS BLEED PATH MUST BE MAINTAINED EVEN IF RCS PRESSURE REMAINS GREATER THAN SI PUMP SHUTOFF HEAD.

. - 4 . . . . 4

4 - - - 4 .

4 * - 4 - - - - - 4 * - - - 4 * - 4 4 - -

23 Maintain RCS Heat Removal:

o Maintain SI flow o Maintain both PRZR PORVs and block valves - OPEN 24 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker -

CLOSED IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker - to ATT-4.0, ATTACHMENT CNMT RECIRC CLOSED FANS).

ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 25 Check If Charging Flow Has Been Established:

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

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.

THEN dispatch AO to locally close seal injection needle valve(s) 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 as necessary to establish maximum charging flow

EOP: TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 23 of 31 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED

4

4 * -

4 *

4

4

4 * * *

4 4 * * - - *

4* - 4 * - - 4 * *-

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

TRANSFER TO COLD LEG RECIRCULATION.

o IF CONTAINMENT PRESSURE INCREASES TO GREATER THAN 28 PSIG. CONTAINMENT SPRAY SHOULD BE VERIFIED.

o RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

4 4

4 * *

4

4 4 4

4 4 * * * *

4 4 4

4 4 4 4 *

4 *

4

4 4 4 4

26 Monitor If CNMT Spray Should Be Stopped:

a. CNMT spray pumps - RUNNING a. Go to Step 27.

b. Check the following: b. Continue with Step 27. WHEN BOTH conditions satisfied. THEN do o CNMT pressure - .LESS THAN Steps 26c through 26f.

4 PSIG o Sodium hydroxide tank level -

LESS than 55%

c. Reset CNMT spray

d. Check NaOH flow (FI-930) - NO d. Place NaOH tank outlet valve FLOW switches to CLOSE.

. AOV-836A

AOV-836B

e. Stop CNMT spray pumps and place in AUTO

f. Close CNMT spray pump discharge valves

MOV-860A

MOV-860B

MOV-860C

MOV-860D

RESPONSE NOT OBTAINED 27 Continue Attempts To Establish Secondary Heat Sink In At Least One S/G:

a. Attempt to restore one or more of the following:

AFW flow

Main FW flow

Standby AFW flow

Condensate flow

b. WHEN a feed source is available.

THEN control feed flow per requirements of ATT-22.0.

ATTACHMENT RESTORING FEED FLOW 28 Check For Adequate Secondary Heat Sink:

a. Check narrow range level in at a. Return to Step 27.

least one S/G - GREATER THAN 5%

[25% adverse CNMT]

b. Adjust S/G ARV controllers to existing S/G pressure

4 *

4 a *

4 * * * * * *

4 4

4 4 4 4 4 4 4 4 4 4 4 4 4 4

4

4 *

4 CAUTION IF THE RCS IS WATER SOLID. THEN ANY INCREASE IN RCS TEMPERATURE MAY RESULT IN A SIGNIFICANT RCS PRESSURE INCREASE. RCS HEATUP SHOULD BE PREVENTED.

29 Monitor RCS Temperatures: Perform the following:

o Core exit T/Cs - DECREASING a. Control steam dump and feed flow to establish natural circulation o RCS hot leg temperatures - and stabilize RCS temperature.

DECREASING

b. Return to Step 27.

EOP: TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 25 of 31 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 30 Check CCW Pumps - ANY RUNNING Perform the following:

a. IF any RCP #1 seal outlet temperature offscale high. THEN isolate CCW to thermal barrier of affected RCP(s).

. RCP A. MOV-749A and MOV-759A

RCP B. MOV-749B and MOV-759B

b. Manually start one CCW pump (122 kw).

- - 4 * - 4 - - - -4

4 - - - - - - *4 * * * * * -

4 * * - 4 - - - * -

CAUTION IF RCS IS SOLID. CLOSURE OF HEAD VENTS MAY RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

. . - - - 4 - - - -* * * -4 -4 4 4 4 4 4 -4 -4 4 -4 . * . . . .4 .

31 Verify Reactor Head Vent Manually close valves.

Valves - CLOSED

SOV-590

SOV-591

. SOV-592

SOV-593

ACTI~~~~~~~~~~~~O/XETE RESPONE I X * * * * * * ** * * * * * * * ** * * * * * * *

A *

CAUTION IF RCS IS SOLID. THEN TERMINATION OF BLEED AND FEED MAY RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

4 * * * *

4 * * * * * * * *

4 * * * * * * * * *

4 * * * * *

4*. * * *

32 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps - RUNNING a. Go to Step 33.

b. RCS subcooling based on core b. Check the following:

exit T/Cs - GREATER THAN 351F

[900F adverse CNMT] USING o RCS pressure greater than FIG-1.0. FIGURE MIN SUBCOOLING 1625 psig [1825 psig adverse CNMT]

o RCS subcooling based on core exit T/Cs greater than 00 F using FIG-l.0. FIGURE MIN SUBCOOLING IF NOT. THEN go to Step 35.

c. Check PRZR level - GREATER THAN c. Do NOT stop SI pump. Go to 13% [40% adverse CNMT] Step 35.

d. Stop one SI pump

STEP ACTION/EXPECTED RESPONSERSPNEOTBAID 33 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 34.

b. Determine required RCS subcooling from table:

Charging Pump RCS Subcouling Criteria Availability NONE 120OF [2000F adverse CNMT]

ONE 115OF [1901F adverse CNMT]

TWO 105OF [180'F adverse CNMT]

THREE 1000 F [1750F adverse CNMT]

c. RCS subcooling based on core c. Check the following:

exit T/Cs - GREATER THAN VALUE FROM TABLE ABOVE USING FIG-1.0. o RCS pressure greater than FIGURE MIN SUBCOOLING 1625 psig [1825 psig adverse CNMT]

o RCS subcooling based on core exit T/Cs greater than 00 F using FIG-1.0. FIGURE MIN SUBCOOLING IF NOT. THEN go to Step 35.

d. PRZR level - GREATER THAN 13% d. Do NOT stop SI pump. Go to

[40% adverse CNMT] Step 35.

e. Stop one SI pump

ACTIN/EPECTED RESPONSEIREPNEOTBAND 34 Check If Last SI Pump Should Be Stopped:

a. One SI pump - RUNNING a. Go to Step 37.

b. Check the following: b. Go to Step 35.

o RCS subcooling based on core exit T/Cs greater than 00F using FIG-1.0. FIGURE MIN SUBCOOLING o RCS pressure greater than 1625 psig [1825 psig adverse CNMT]

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

[40% adverse CNMT] Step 35.

d. Stop running SI pump

e. Go to Step 37 NOTE: After closing a PORV. it may be necessary to wait for RCS pressure to increase to permit stopping SI pumps in SI reduction steps.

35 Check PRZR PORVs And Go to appropriate plant procedure:

Associated Block Valves - ANY BLEED PATH OPEN o IF RWST level greater than 28%.

THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

-OR-o IF RWST level less than 28%.

THEN go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED i . *

4 *

4 * * * *

4 * * * * * * * * *

4 * * * * * * *

4 *

4

4

4 CAUTION IF RCS IS SOLID, CLOSURE OF PORVS WILL RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

36 Isolate PRZR Bleed Paths:

a. PRZR PORVs - BOTH OPEN a. Perform the following:

1) Stop all but one charging pump.

2) Control charging flow as necessary to maintain RCS pressure and PRZR level.

3) Establish excess letdown as follows:

a) Place AOV-312 to NORMAL.

b) Ensure CCW pump running.

c) Manually open CCW from excess letdown Hx open (AOV-745).

d) Ensure excess letdown flow control valve. HCV-123 is closed. demand at 0.

e) Reset both trains of XY relays for MOV-313.

f) Open MOV-313.

g) Open excess letdown isolation valve AOV-310.

h) Slowly open HCV-123.

This Step continued on the next page.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED (Step 36 continued from previous page)

b. Close one open PRZR PORV b. Close PORV block valve. IF block valve can NOT be closed.

THEN go to appropriate plant procedure:

o IF RWST level greater than 28%. THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

-OR-o IF RWST level less than 28%.

THEN go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION.

c. Return to Step 32 37 Check PRZR PORVs - BOTH CLOSED Close both PRZR PORVs. IF any PRZR PORV can NOT be closed. THEN manually close its block valve.

38 Check If RHR Pumps Should Be Stopped:

a. RHR pumps - ANY RUNNING IN a. Go to Step 39.

INJECTION MODE

b. Check RCS pressure: b. Go to appropriate plant procedure:

1) Pressure - GREATER THAN 250 psig [465 psig adverse o IF RWST level greater than CNMT] 28%. THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

2) Pressure - STABLE OR Step 1.

INCREASING

-OR-o IF RWST level less than 28%.

THEN go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION.

Step 1.

c. Stop RHR pumps and place in AUTO L

. EOP: TITLE: REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK

. [

..1- PAGE 31 of 31 STEP~ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl 39 Start Charging Pumps As Necessary And Control Charging Flow To Maintain PRZR Level 40 Go To ES-1.1, SI TERMINATION, Step 8

-END-

EOP: TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 1 of 1 FR-H.1 APPENDIX LIST TITLE

1) FIGURE MIN SUBCOOLING (FIG-1.0)

2) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)

3) ATTACHMENT COND TO S/G (Arr-5.o)

4) ATTACHMENT N2 PORVS (ATT-12.0)

5) ATTACHMENT RHR COOL (ATT-14.1)

6) ATTACHMENT SAFW (ATT-5.1)

7) ATTACHMENT RESTORING FEED FLOW (ATT-22.0)

8) ATTACHMENT NO SW PUMPS (ATT-2.4)

9) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)

10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

11) FOLDOUT

FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-H series procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a. Pull stop any DG that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __

I _

M., A 1-%'

RESPONSIBLE MANAGER

/ -ETIV DA EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions for an overpressure condition affecting any SG where pressure has increased above the highest steamline safety valve setpoint.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. F-0.3, HEAT SINK Critical Safety Function Status Tree on a YELLOW condition.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDI NOTE: o Throughout this procedure. "affected" refers to any S/G in which pressure is greater than 1140 psig.

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

o Foldout Page should be open and monitored periodically.

1 Identify Affected S/G(s):

a. Any S/G pressure - GREATER THAN a. Return to procedure and step in 1140 PSIG effect.

2 Verify FW Isolation To Affected S/G(s):

a. MFW pumps - TRIPPED a. Trip MFW pumps.

b. MEW flow control valve(s) - b. Depress MANUAL pushbutton(s) AND l CLOSED manually close valves. I

. MFW regulating valve(s)

MFW bypass valve(s)

c. MFW pump discharge valve(s) - c. Manually close valves.

CLOSED 3 Check Affected SG(s) Narrow Go to FR-H.3. RESPONSE TO STEAM Range Level - LESS THAN 90% GENERATOR HIGH LEVEL. Step 1.

[80% adverse CNMT]

STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl

* * * * * *

4 * * -

4 *

4 * * * *

i a 4

4 4 4 4 4 CAUTION IF AFFECTED S/G NARROW RANGE LEVEL INCREASES TO GREATER THAN 90% [80% ADVERSE CNMT]. THEN AN EVALUATION SHOULD BE MADE FOR S/G OVERFILL CONSIDERATIONS.

STEAM SHOULD NOT BE RELEASED FROM ANY SIG WITH LEVEL GREATER THAN 90% [80%

ADVERSE CNMT) PRIOR TO OVERFILL EVALUATION.

4 4 4

4 4 4 *

4 4 4 4 4 4 4

4 * * * * *

4 *

4

4 4 *

4 4

4

4 *

4 Try To Dump Steam From The Go to Step 6.

Affected S/G(s):

o Open SG ARVs

-OR-o Open MSIV bypass valves

-OR-o Open steam supply valves to TDAFW pump 5 Check Affected S/G(s)

Pressure:

a. Pressure - DECREASING a. Go to Step 6.

b. Pressure - LESS THAN 1140 PSIG b. Return to Step 3.

c. Control steam release to maintain S/G pressure less than 1140 psig

d. Return to procedure and step in effect

STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED a * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

CAUTION AFW FLOW SHOULD REMAIN ISOLATED TO AFFECTED SIG(S) UNTIL A STEAM RELEASE PATH IS ESTABLISHED.

* * * .

a * . . * * * * . . * . *

6 Close AFW And SAFW Flow Stop pumps feeding affected S/G(s).

Control Valves To Affected SIG(s) o S/G A

MOV-4007 and AOV-4480. MDAFW pump

AOV-4297. TDAFW pump

MOV-9701A, SAFW pump o S/G B

. MOV-4008 and AOV-4481. MDAFW pump

AOV-4298. TDAFW pump

MOV-9701B. SAFW pump 7 Check RCS Hot Leg Cool down RCS to less than 5301F Temperatures - LESS THAN 5300F by dumping steam from the unaffected SG.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAI 8 Continue Attempts To Manually Or Locally Dump Steam From Affected S/G(s):

o Open SG ARVs

-OR-o Open steam supply valves to TDAFW pump

-OR-o Dispatch AO to perform the following:

a. Open affected SIG MSIV bypass valve

b. Open both priming air ejector steam isolation valves

V-3580

V-3581 9 Return To Procedure And Step In Effect

-END-

FR-H.2 APPENDIX LIST

1) ATTACHMENT NO SW PUMPS (ATT-2.4)

2) FOLDOUT

FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-H series procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a. Pull stop any DG that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

EOP: TITLE: REV: 7 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL PAGE 1 of 7 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 43 RESPONSIBT4E NAGER i/o -/O- ,26c 3 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE: REV: 7 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL i PAGE 2 of 7 A. PURPOSE - This procedure provides actions to respond to a S/G high level condition and to address the S/G overfill concern.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. F-0.3, HEAT SINK Critical Safety Function Status Tree on a YELLOW condition, and

b. FR-H.2, RESPONSE TO STEAM GENERATOR OVERPRESSURE, if the affected S/G narrow range level is high.

EOP: TITLE: REV: 7 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL PAGE 3 of 7 ACTION/EXPECTED RESPOOTOANSE I 4 * * * * * * * * * * * * * * * * * * * *

4 . * * * * * * * * *

CAUTION o IF SIG NARROW RANGE LEVEL HAS INCREASED TO GREATER THAN 90% [80% ADVERSE CNMT]. THEN AN EVALUATION SHOULD BE MADE FOR SG OVERFILL CONSIDERATIONS.

STEAM SHOULD NOT BE RELEASED FROM ANY S/G WITH LEVEL GREATER THAN 90% [80%

ADVERSE CNMT] PRIOR TO OVERFILL EVALUATION.

o IF S/G OVERFILL IS EXPECTED AN ATTEMPT SHOULD BE MADE TO DISPATCH PERSONNEL TO PIN MAIN STEAMLINES.

* *

4

4

4 * *

4 * * * * * * * * * * * * * * * * * * * * * * * * * * *

NOTE: o Throughout this procedure. "affected" refers to any S/G in which narrow range level is greater than 80%.

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

o Foldout Page should be open and monitored periodically.

1 Check Affected SG(s) Narrow IF less than 80% in all S/Gs. THEN Range Level - GREATER THAN 80% return to procedure and step in effect.

2 Verify FW Isolation To Affected S/G(s):

a. MFW pumps - TRIPPED a. Trip MFW pumps.

b. MFW flow control valve(s) - b. Depress MANUAL pushbutton(s) AND CLOSED manually close valves. I

. MFW regulating valve(s)

MFW bypass valve(s)

c. Verify both S/G pressures - c. Stop any running condensate GREATER THAN CONDENSATE HEADER pumps.

PRESSURE

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 3 Close AFW And SAFW Flow Stop pumps feeding affected S/G(s).

Control Valves To Affected S/G(s):

o S/G A

MOV-4007 and AOV-4480. MDAFW pump

AOV-4297. TDAFW pump

MOV-9701A. SAFW pump o S/G B

MOV-4008 and AOV-4481. MDAFW pump

AOV-4298. TDAFW pump

MOV-9701B. SAFW pump

.1'

REV: 7 RESPONSE TO STEAM GENERATOR HIGH L VEL PAGE 5 of 7

--4 ACTION/EXPECTED RESPONSE STEP RESPONSE NO ' OBTAINED I 4 Check Affected SIG(s) Level:

a. Narrow range level - LESS THAN a. Go to Stel 5.

90% [80% adverse CNMT]

b. Narrow range level - DECREASING b. IF affect( d SG level continues to increa. e. THEN perform the following:

1) Dispatc h AO to locally isolatc affected S/G:

o For S/G A. close MFW regt lating and bypass vali e outlet isolation valA es. V-3987 and V-3991

-OR-o For' S/G B. close MFW regt lating and bypass val% e outlet isolation valA es. V-3986 and V-3990

2) Go to tep 5.

c. Control AFW flow to maintain narrow range level between 17%

[25% adverse CNMT] and 52%

d. Return to procedure and step in effect 4

REV: 7 RESPONSE TO STEAM GENERATOR HIGH LIL ;VEL PAGE 6 of 7 STEP _ ACTION/EXPECTED RESPONSE RESP NOI OBTAINED 5 Adjust Affected SIG(s) ARV.

Setpoint To 1050 PSIG a * * * * * * * *

a *

a *

a *

a * * * * *

a T H aN a a a a a a a CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED F SOW. THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G

* * * * * * * * * *

a * * * * * * * * * * * * * *

al* * * * * * * * * * *

6 Close Affected S/G TDAFW Pump Steam Supply Valve And Place In PULL STOP

S/G A. MOV-3505A

S/G B. MOV-3504A 7 Close Affected S/G(s) MSIV And Bypass Valves 8 Check Affected S/G(s) IF an E-3 or :CA-3 series procedure Radiation Levels - NORMAL is in effect. THEN return to procedure and step in effect. IF

SIG blowdown, R-19 NOT. THEN go :o E-3, STEAM

SIG A. R-31 GENERATOR TUB : RUPTURE. Step 1.

SIG B. R-32

I REV: 7 RESPONSE TO STEAM GENERATOR HIGH L' PAGE 7 of 7 ACTION/EXPECTED RESPONSE STEP RESPONSE NOBTAINEDE 9 Establish Blowdown From Affected S/G(s):

a. Reset SI and CI

b. Reset XY relays for affected S/G blowdown valves

c. Place blowdown key switch for affected SIG to defeat

d. Verify SG blowdown valves - OPEN

e. Dispatch AO to establish blowdown to condenser or flash tank, as desired (Refer to T-14F. STEAM GENERATOR BLOWDOWN SYSTEM STARTUP) 10 Return To Procedure And Step In Effect

-END-

EOP: TITLE: I REV: 7 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL PAGE 1 of 1 FR-H.3 APPENDIX LIST

1) ATTACHMENT NO SW PUMPS (ATT-2.4)

2) FOLDOUT

EOP: TITLE: ~~~~~~~~~REV:

7 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL PAGE of 1 FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-H eries procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform Ithe following:

a. Pull stop any DG that is NOT supplied by alternate cooling, AND immediately depress assoc. ated VOLTAGE SHUTDCWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUM S.

EOP: lTITLE: lREV: 16

. FR-S.1 RESPONSE TO REACTOR RESTART/ATIS PAGE 1 of 13 ROCHESTER GAS AND ELECTRIC CORPO ATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB8 MANAGER 10 -it-)OD EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:RE:1 REV: 16 FR-S.1 RESPONSE TO REACTOR RESTART/ATJS PAGE 2 of 13 A. PURPOSE - This procedure provides actions t o add negative reactivity to a core which is observed to e critical when expected to be shut down.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is e tered from:

a. E-0, REACTOR TRIP OR SAFETY INJECT' ON, when reactor trip is not verified nd manual trip is not effective.

b. F-0.1, SUBCRITICALITY, Critical Sai ety Function Status Tree on either a RED or ORAl GE condition.

REV: 16 RESPONSE TO REACTOR RESTART/AT qS PAGE 3 of 13 ACTION/EXPECTED RESPONSE STEP RESPONSE NO OBTAINEDl NOTE: Adverse CNMT values should be used whenever CNMT ressure is greater than 4 psig or CNMT radiation is greater than 10+ 5 R/hr.

0 Verify Reactor Trip:

o At least one train of reactor Manually tri] reactor.

IF reactor ti ip breakers NOT open.

trip breakers - OPEN THEN manuall' insert control rods.

o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM 0 Verify Turbine Stop Valves -

CLOSED Manually tril turbine.

IF turbine tiip can NOT be verified. THI N close both MSIVs.

0 Check AFW Pumps Running:

a. MDAFW pumps - RUNNING a. Manually tart MDAFW pumps.

b. TDAFW pump - RUNNING IF b. Manually pen steam supply NECESSARY valves.

. MOV-350' A

. MOV-350 A K>

4,

I

-l--

REV: 16 RESPONSE TO REACTOR RESTART/A WS

, I -.. 1 PAGE 4 of 13 OBTAINED FT

*

0 * - - 0 * * - - - - - * - - - * - - - . . * * -

A *- - *

CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE RE ERSED WHEN PERFORMING STEPS 1 THROUGH 12 OF E-0. REACTOR TRIP OR SAFETY INJE TION.

. . . . . . . . * . . 0 . . . . . . * .

0 . . .

0 . . *-- * * * * *

0

0

NOTE: o If offsite power is lost coincident with SI. hen MCC C and MCC D lockout relays must be reset to restore BA an

RMW pumps.

o Foldout page should be open and monitored per odically.

4 Initiate Emergency Boration Of RCS:

a. Check SI status: a. Perform he following:

o All SI annunciators - 1) Compl te steps 1 through 12 EXTINGUISHED of E- REACTOR TRIP OR SAFET INJECTION, while o All SI pumps - OFF IN AUTO conti: uing with this procedure

2) IF SI flow indicated. THEN go to St p 5. IF NOT, THEN go to St p 4b.

b. Verify at least one charging b. Perform he following:

pump - RUNNING

1) Reset SI if necessary.

2) Start one charging pump.

c. Align boration path: c. Initiate normal boration at maximum 'ate using the boric

1) Start two BA transfer pumps acid flo control valve.

FCV-110A IF flow can NOT be

2) Open MOV-350 establis ed. THEN refer to ER-CVCS. . REACTOR MAKEUP

3) Verify BA flow CONTROL ALFUNCTION.

d. Verify charging flow path: d. Manually align valves and verify flow.

o Charging valve to loop B cold leg (AOV-294) - OPEN o Charging flow control valve (HCV-142) - DEMAND AT 0%

I.

I EOP: TITLE:

REV: 16 FR-S.1 RESPONSE TO REACTOR RESTART/

PAGE 5 of 13 I.

I - RESPONSET Ifj 5 Check PRZR PORV Status:

a. RCS pressure - LESS THAN a. Verify P ZR PORVs and block 2335 PSIG valves o en. IF NOT. THEN open PRZR POR s and block valves as necessar until PRZR pressure less tha 2335 psig.

b. Check PORVs - BOTH CLOSED b. IF PRZR ressure less than 2335 psi , THEN manually close PORVs.

IF any PiRV can NOT be closed.

THEN man ally close its block valve. F block valve can NOT be close , THEN dispatch AO to locally heck breaker.

. MOV-511, MCC D position 6C

MOV-51*. MCC C position 6C 6 Verify CNMT Ventilation Isolation

a. CVI annunciator - LIT a. Momentar ly deenergize CNMT particul te monitor. R-l1. to

Annunciator A-25. CNMT actuate VI.

VENTILATION ISOLATION

b. Verify CVI valve status lights - b. Manually close CVI valves as BRIGHT required IF valve can NOT be verified closed b, MCB indication. THEN dispatch AO to locally close valves ( efer to ATT-3.0.

ATTACHME IT CI/CVI for alternate isolatio valves).

or, , --. i REV: 16 RESPONSE TO REACTOR RESTART/AkWS PAGE 6 of 13

+/-

ACTION/EXPECTED STEP RESPONSE RESPONSE IN OT OBTAINEDI 7 Check If The Following Trips Have Occurred:

a. Reactor trip a. Dispatch AO to locally trip reactor:

o Trip] [G set breakers at bus 13 an

bus 15.

-OR-o Open eactor trip breakers local -Y.

b. Turbine trip b. Dispatch AO to locally trip turbine sing manual trip lever on west nd of HP turbine.

8 Check If Reactor Is Subcritical:

a. Energize MCC A AND B

b. Check power range channels - b. Go to Sp 9.

LESS THAN 5%

c. Check Intermediate range channels c. Go to Sttp 9.

o Startup rate - NEGATIVE

-OR-o Intermediate range channels -

DECREASING

d. Go to Step 18.

K>1-

EOP: TITLE:l E:1l REV: 16 FR-S.1 RESPONSE TO REACTOR RESTART/A WS PAGE 7 of 13

)T OBTAINED

a*-

a * *

a * - - - a a -a * * - -a a

- *

a * - *

- a

a a .

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTER] ATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNjTE WATER SUPPLY TO AFW PUMPS).

i A * * * * * * * *

A a

a * * *

- *a

ala * * *

a

a a * *

9 Monitor S/G Level:

a. Narrow range level in at least a. Perform lhe following:

one SIG - GREATER THAN 5% [25%

adverse CNMT] 1) Verif total feed flow great r than 400 gpm.

IF NO' . THEN manually start pumps and align valves as necesi ary.

IF AF1 can NOT be estabJ ished, THEN establish SAFW (Refer to ATT-5.1.

ATTACI KENT SAFW)

2) Maint, in total feed flow great( r than 400 gpm until narroi range level greater than % [25% adverse CNMT] in at le, st one SG.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

4

I REV: 16 RESPONSE TO REACTOR RESTART/AWS PAGE 8 of 13 I

STEP ACTION/EXPECTED RESPONSE RESPONSE N )T OBTAINED 10 Verify Dilution Paths -

ISOLATED

a. Place RMW mode switch to BORATE

b. Stop RMW pumps b. Perform 1 he following:

1) Close RMW to blender (AOV-1:11)

2) Direci AO to locally open RIqW pump I reaker

RMW Pump A. MCC C Pos 13B

RMW Pump B. MCC D Pos 1B 11 Stabilize RCS Temperature:

a. Control steam dump as necessary

b. Verify the following: b. IF RCS ccoldown can NOT be controll d. THEN close both o Core exit T/Cs - STABLE OR MSIVs an( go to Step 12.

INCREASING o Pressure in both S/Gs -

STABLE OR INCREASING o Pressure in both S/Gs -

GREATER THAN 110 PSIG

c. Go to Step 16 4.

REV: 16 RESPONSE TO REACTOR RESTART/AlIWS PAGE 9 of 13 3T OBTAINED 12 Verify MFW Isolation:

a. MFW pumps - TRIPPED a. Manually close MFW pump discharg valves and trip MFW pumps.

b. Depress MANUAL pushbutton for A and B S/G MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

13 Identify Faulted SG: Go to Step 16.

o Any S/G Pressure - DECREASING IN AN UNCONTROLLED MANNER

-OR-o Any S/G Pressure - LESS THAN 110 PSIG

.4

I EOP: BIlLE:

REV: 16 FR-S.1 RESPONSE TO REACTOR RESTART/A PAGE 10 of 13 STEP ACTION/EXPETEDRESPNSERESPONSE N )T OBTAINED

* * ** * * * *

4 *

4 4 * * * * *

4 4 4 0 4 4 0 *

4 0 CAUTION o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR CS COOLDOWN.

o IF BOTH S/GS ARE FAULTED. AT LEAST 50 GPM FEED FLOW ISHOULD BE MAINTAINED TO EACH SG.

4 a * *

14 Isolate Feed Flow To Faulted Manually cl se valves.

S/G:

IF valves c4n NOT be closed. THEN o Close faulted S/G MDAFW pump dispatch AO to locally isolate discharge valve flowpaths a, necessary.

S/G A. MOV-4007

S/G B. MOV-4008 o Pull stop faulted S/G MDAFW pump o Close faulted S/G TDAFW flow control valve

. S/G A. AOV-4297

S/G B. AOV-4298 o Verify faulted S/G MFW regulating valve and bypass valve - CLOSED

S/G A. HCV-466 and HCV-480

S/G B. HCV-476 and HCV-481 o Verify MDAFW pump crosstie valves - BOTH CLOSED

MOV-4000A

MOV-4000B o Close faulted S/G SAFW pump discharge valve

S/G A. MOV-9701A

. S/G B. MOV-9701B

REV: 16 RESPONSE TO REACTOR RESTART/

PAGE 11 of 13 I4 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4

4 * * * * * * * * *

4 4 *

T

4 * * * *

4 * * *

4 * *

CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW. THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S G.

* * * * * * *

4 4

4

4 4 *

4 4 * * *14 * * *

4i

4 . *

15 Isolate Steam Flow From Manually cl se valves.

Faulted S/G:

IF valves c in NOT be closed. THEN o Verify faulted SG ARV - CLOSED dispatch AO to locally isolate flowpaths a necessary.

S/G A. AOV-3411

S/G B. AOV-3410 o Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP

S/G A. MOV-3505A

SG B. MOV-3504A o Verify faulted S/G blowdown and sample valves - CLOSED

S/G A. AOV-5738 and AOV-5735

S/G B. AOV-5737 and AOV-5736 o Dispatch AO to complete faulted S/G isolation (Refer to ATT-10.0. ATTACHMENT FAULTED S/G)

REV: 16 RESPONSE TO REACTOR RESTART/ATWS PAGE 12 of 13 I.

ACTION/EXPECTEDCRESPONSE STEP RESPONSE 1OT OBTAINED 16 Check Core Exit T/Cs - LESS IF core exi t temperatures greater THAN 12000 F than 1200°F and increasing. THEN go to SACRG-1. SEVERE ACCIDENT CONTROL ROOM GUIDEL [NE INITIAL RESPONSE.

step 1.

NOTE: Adverse CNMT conditions or loss of forced air co ling may result in failure of NIS detectors.

17 Verify Reactor Subcritical: Perform the following:

o Power range channels - LESS THAN a. Stabiliz RCS temperature.

5%

b. Continue to inject boric acid.

o Intermediate range channels -

STABLE OR DECREASING c. Perform ctions of other FR procedur s in effect which do o Intermediate range channels NOT cool own or otherwise add startup rate - NEGATIVE positive reactivity to the core.

o Core exit T/Cs - STABLE d. Direct R to sample RCS and PRZR for boro concentration.

e. Verify b ron concentration greater han FIG-2.0. FIGURE SDM.

IF adequate shutdown margin verified, T EN go to Step 18.

IF NOT. THE perform the following:

a. Allow RC to heat up.

b. Perform ctions of other FR procedur s in effect which do NOT cool own or otherwise add positive reactivity to the core.

c. Return t Step 4.

1

EOP: TITLE:

REV: 1 6 FR-S.1 RESPONSE TO REACTOR RESTART/Arws PAGE 13 of 13 iLi-ACTION/EXPECTED RESPONSE /EXOBTED RESPONSE

. . * *

A * * * * * * * * *

A *

a * * * * *Ga aUaIa a a *a a a

CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN K RGIN DURING SUBSEQUENT ACTIONS.

* * * * * * * * * * * * * * * * * * * * * *

a a a a a a a a a a a 18 Return to Procedure And Step In Effect

-END-4.

I-l REV: 16 RESPONSE TO REACTOR RESTART/A WS PAGE 1 of 1 FR-S.1 APPENDIX LI.T TITLE

1) FIGURE SDM (FIG-2.0)

2) ATTACHMENT FAULTED S/G (ATT-1o.o)

3) ATTACHMENT CI/CVI (ATT-3.0)

4) ATTACHMENT SAFW (ATT-5.1)

5) ATTACHMENT NO SW PUMPS IArr-2.4)

6) FOLDOUT

REV: 16 FR-S.1 RESPONSE TO REACTOR RESTART/A]WS PAGE 1 of 1 FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-S iseries procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perforn the following:

a. Pull stop any D/G that is NOT suppliec by alternate cooling, AND immediately depress assoc iated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUIIPS.

IEOP: TITLE:RV REV: 8 FR-Z.1 RESPONSE TO HIGH CONTAINMENT PREISURE

... . PAGE 1 of 7 ROCHESTER GAS AND ELECTRIC CORPdRATION GINNA STATION CONTROLLED COPY NUMBER - C3 RESPONSIBTI MANAGER

/0 -/D -o ; LI EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

REV: 8 FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRE{SURE PAGE 2 of 7 A. PURPOSE - This procedure provides actions to respond to a high CNMT pressure.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is ntered from:

a. F-0.5, CONTAINMENT Critical Safet, Function Status Tree, on a RED or ORANGE conditio

REV: 8 RESPONSE TO HIGH CONTAINMENT PRE PAGE 3 of 7 OTE: ACTION/EXPECTEDs e oRESPONSE id )T OBTAINED -

NOTE: FOLDOUT Page should be open and monitored period cally.

1 Verify All CI And CVI Valve IF flow pat NOT required. THEN Status Lights - BRIGHT manually cl ise CI and CVI valves.

IF valves c inNOT be verified closed by M B indication. THEN dispatch AO to locally close valves. (Re er to ATT-3.0.

ATTACHMENT I/CVI).

REV: 8 RESPONSE TO HIGH CONTAINMENT PRESURE PAGE 4 of 7

)T OBTAINED -

* * * * * * *

4 * *

4 ** *

4 * *

4 * *

4 , 4 . 4 *

4

CAUTION IF ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION. I IN EFFECT, THEN CNMT SPRAY SHOULD BE OPERATED AS DIRECTED IN ECA-1.1. RATHEa THAN STEP 2 BELOW.

* * * * * * * * * * * * * * * * * *1*

* *

4 * * * * *

2 Verify CNMT Spray Actuated:

a. Verify RWST outlet to SI and a. IF in RH] recirculation mode.

CNMT spray pumps - OPEN THEN per orm the following:

MOV-896A 1) Opera e SI pumps and one CNMT

MOV-896B spray pump as directed. in ES-1.: . TRANSFER TO COLD LEG RECIR ULATION. Step 14.

2) Go toiStep 3.

b. Verify CNMT spray pumps - RUNNING b. Manuallyistart pumps.

c. Verify NaOH flow (FI-930) c. IF NaOH low NOT indicated. THEN place sw tches for NaOH tank outlet v4 lves to OPEN.

AOV-83 A

AOV-83 B

d. Verify CNMT spray pump discharge d. Ensure at least one in each set valves - OPEN open.

MOV-860A

MOV-86 A or MOV-860B

MOV-860B

MOV-86 C or MOV-860D

MOV-860C

MOV-860D d.

I REV: 8 RESPONSE TO HIGH CONTAINMENT PRE PAGE 5 of 7

)T OBTAINED 3 Verify CNMT RECIRC Fans Running:

a. All fans - RUNNING a. Manually Istart fans.

b. Charcoal filter dampers green b. Dispatch personnel to relay room status lights - EXTINGUISHED with rel y rack key to locally open daml ers by pushing in trip relay pl ngers.

. AUX REqAY RACK RA-2 for fan A

AUX REIIAY RACK RA-3 for fan C 4 Verify MSIVs - CLOSED Manually cl se valves.

I REV: 8 RESPONSE TO HIGH CONTAINMENT PRE PAGE 6 of 7 4.

STEP ACTION/EXPECTED RESPONSE RESPONSE l')T .OBTAINEDI.~~~~~~~~~~~~

* *. * * *. *. * * *. * *. *. *. *. *

4 * * * * * * * * * * * *

CAU'TION o AT LEAST ONE SIG SHALL BE MAINTAIN ED AVAILABLE FOR 'CS COOLDOWN.

o IF BOTH SGS ARE FAULTED. THEN AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH SG.

. *. *. *. * * * . *. *. * * *. *. * , * *.

a * * *

a * * *1* * * * * * * * * * * *

5 Check If S/G Secondary Side Isolate fee I flow to faulted SG:

Is Intact:

a. Ensure f ulted S/G MDAFW pump o Pressure in both S/Gs - STABLE discharg valve closed.

OR INCREASING

S/G A. MOV-4007 o Pressure in both SGs - GREATER

SG B. MOV-4008 THAN 110 PSIG

b. Ensure f ulted SG TDAFW flow control alve closed.

SG A. AOV-4297

SG B. AOV-4298

c. Depress IANUAL pushbuttons for faulted :/G MFW regulating valve and bypa 'svalve AND ensure valves c osed.

SG A. HCV-466 and HCV-480

SG B. HCV-476 and HCV-481

d. Ensure M W pump discharge valves closed.

IF valves c n NOT be closed. THEN.

dispatch AO to locally close valves as necessar to isolate flow.

.4

6 Return To Procedure And Step In Effect

-END-

REV: 8 RESPONSE TO HIGH CONTAINMENT PRESSURE PAGE 1 of 1

___________________________________ I. _______________________

FR-Z.1 APPENDIX LST TITLE

1) ATTACHMENT CI/CVI (ATT-3.0)

2) ATTACHMENT NO SW PUMPS (ATT-2.4)

3) FOLDOUT

lEOPl TITLE: lR V REV: 8 l FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE PAGE 1 of 1 FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-Z keries procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perforn the following:

a. Pull stop any DG that is NOT supplied by alternate cooling, AND immediately depress assoc jated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUN ?S.

ML032950083

Contents

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML032950083

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search