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

Always at Your Service Joseph A. Widay Vice President 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 E Index ECA Index ES Index FIG Index FR Index A'T-5.0, Rev 6 AlT-17.0, Rev 16 FIG-2.0, Rev 4 FIG-14.0, Rev 2 E-0, Rev 35 ECA-0.0, Rev 27 ES-0. 1, Rev 22 FR-H. I, Rev 30 FR-H.2, Rev 6 FR-H.3, Rev 7 FR-S.I, Rev 16 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 E n t An Energy East Comnpany

NPSP0200 WRIGHTJ INPUT PARAMETERS: TYPE:

Pr PRE EMERGENCY PROCEDURE

(.

Ginna Nuclear Power Plant PROCEDURE INDEX STATUS VALUE(S):

EF Fri 10/10/2003 12:01:30 pm Page 1 of 1 5 YEARS ONLY:

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

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(7

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NPSP0200 WRIGHTJ INPUT PARAMETERS: TYPE:

PRECA PRECA EMERGENCY CONTiNGENCY ACTIONS PROC Ginna Nuclear Power Plant PROCEDURE INDEX Fri 10/10/2003 12:01:06 pm Page 1 of 1 5 YEARS ONLY:

STATUS VALUE(S):

EF 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 WRIGHTJ INPUT PARAMETERS: TYPE:

PRES XRES I

Ott, PRES EQUIPMENT SUB-PROCEDURE

(

Ginna Nuclear Power Plant PROCEDURE INDEX STATUSVALUE(S):

EF Fri 10110/2003 12:22:21 pm Page 1 of 1 S YEARS ONLY:

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r-r 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.

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NPSP0200 WRIGHTJ INPUT PARAMETERS: TYPE:

PRFR PRFR FUNCTIONAL RESTORATION GUIDELINE PROC PROCEDURE NUMBER PROCEDURE TITLE FR-C.1 RESPONSE TO INADEOUATE CORE COOLING FR-C.2 RESPONSE TO DEGRADED CORE COOLING FR-C.3 RESPONSE TO SATURATED CORE COOLING FR-It.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL FR-H.4 RESPONSE TO LOSS OF NORMAL STEAM RELEASE FR-H.5 RESPONSE TO STEAMI GENERATOR LOW LEVEL FR-1.1 RESPONSE TO HIGH PRESSURIZER LEVEL FR-12 RESPONSE TO LOW PRESSURIZER LEVEL FR-1.3 RESPONSE TO VOIDS IN REACTOR VESSEL FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL St FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL FR-S.1 RESPONSE TO REACTOR RESTARTIATWS FR-S.2 RESPONSE TO LOSS OF CORE SHUTDOWN FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE FR-Z.2 RESPONSE TO CONTAINMENT FLOODING FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVE Ginna Nuclear Power Plant PROCEDURE INDEX STATUSVALUE(S):

EF OU Fri 10/10/2003 12:21:45 pm Page 1 of 1 5 YEARS ONLY:

CAPABILITIES OCK CONDITION S OCK CONDITION L

EFFECT LAST REV DATE REVIEW 020 05130/2003 03/24/2003 017 05/30/2003 03/24/2003 009 05/30/2003 03/24/2003 030 10/10/2003 03/24/2003 006 10/10/2003 03/24/2003 007 10/10/2003 03/24/2003 005 05/30/2003 03/2412003 009 05/30/2003 03/2412003 016 05/30/2003 03/24/2003 011 05/30/2003 03/24/2003 018 05/30/2003 03/24/2003 026 05/30/2003 03/24/2003 008 05/30/2003 03/24/2003 016 10/10/2003 03/24/2003 009 05/3012003 03/24/2003 008 10/10/2003 03/24/2003 005 05/3012003 03124/2003 005 05/3012003 03/24/2003 NEXT REVIEW 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03/24/2008 03124/2008 03/24/2008 03/24/2008 03/24/2008 03/2412008 03/24/2008 03/24/2008 03/2412008 03/24/2008 0312412008 03/2412008 03124/2008 ST EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF PRFR TOTAL:

18 GRAND TOTAL 18

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Ginna Nuclear Power Plant PROCEDURE INDEX

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Fri 10/10/2003 12:05:05 pm Page 1 of 1 NPSP0200 WRIGHTJ 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 FIG-3.0 FIG-3.1 FIG-3.2 FIG-4.0 FIG-5.0 FIG-6.0 FIG-7.0 FIG-8.0 FIG-9.0 FIG-9.1 FIG-10.0 FIG-11.0 FIG-12.0 FIG-13.0 FIG-14.0 FIGURE SDM FIGURE NAT CIRC CID WITH SHROUD FANS FIGURE NAT CIRC C/ID WITHOUT SHROUD FANS FIGURE NC C/D WITH VOID IN UPPER HEAD FIGURE RCP SEAL LEAKOFF FIGURE RHR INECTlON FIGURE MIN RCS INJECTION FIGURE INTACT SIG PRESSURE FIGURE TSAT FIGURE TECH SPEC CfD FIGURE CfD LIMITS FIGURE UMIT A FIGURE SOAK LIMITS FIGURE CNMT HYDROGEN FIGURE BACK PRESSURE FIGURE IA ISOL 004 10/10/2003 03/27/2003 000 05/01/1998 03/27/2003 001 02/08/2001 03/27/2003 000 05/01/1998 03/27/2003 002 02/28/2001 03/27/2003 000 05/01/1998 03/27/2003 000 05/01/1998 03/27/2003 001 05/18/1998 03/27/2003 000 05/01/1998 03/27/2003 001 02/15/2001 03/27/2003 000 05/01/1998 03/27/2003 000 05/01/1998 03/27/2003 000 05/01/1998 03/27/2003 000 05/01/1998 03/27/2003 000 05/01/1998 03/27/2003 002 10/10/2003 03/27/2003 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 03/27/2008 EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF PRFIG TOTAL 17 GRAND TOTAL 17

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INPUT PARAMETERS: TYPE:

PRATT PRATT EOP ATTACHMENTS Ginna Nuclear Power Plant PROCEDURE INDEX Fri 10/10/2003 12:26:47 pm Page 1 of 2 e.....

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STATUSVALUE(S):

EF 5YEARS ONLY:

PROCEDURE NUMBER ATT-1.0 ATT-1.1 ATT-2.1 ATT-2.2 ATT-2.3 ATT-2.4 ATT-2.5 ATT-3.0 ATT-3.1 ATT-4.0 ATT-5.0 ATT-5.1 ATT-5.2 ATT-6.0 ATT-7.0 ATT-8.0 ATT-8.1 ATT-8.2 ATT-8.3 ATT-8.4 ATT-8.5 ATT-9.0 ATT-9.1 ATT-10.0 ATT-11.0 ATT-11.1 ATT-11.2 ATT-12.0.

ATT-13.0 ATT-14.0 PROCEDURE TITLE ATTACHMENT AT POWER CCW ALIGNMENT ATTACHMENT NORMAL CCW FLOW ATTACHMENT MIN SW ATTACHMENT SW ISOLATION ATTACHMENT SW LOADS IN CNMT ATTACHMENT NO SW PUMPS ATTACHMENT SPLIT SW HEADERS ATTACHMENTCVCVI ATTACHMENT CNMT CLOSURE ATTACHMENT CNMT RECIRC FANS ATTACHMENT COND TO SIG ATTACHMENT SAFW ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP ATTACHMENT COND VACUUM ATTACHMENT CR EVAC ATTACHMENT DC LOADS ATTACHMENT DIG STOP ATTACHMENT GEN DEGAS ATTACHMENT NONVITAL ATTACHMENT SWUV.

ATTACHMENT LOSSOFOFFSTEPOWER ATTACHMENT LETDOWN ATTACHMENT EXCESS LID ATTACHMENT FAULTED SG ATTACHMENT A CONCERNS ATTACHMENT A SUPPLY ATTACHMENT DIESEL AIR COMPRESSOR ATTACHMENT N2 PORVS ATTACHMENT NC ATTACHMENT NORMAL RHR COOLING EFFECT LAST REV DATE REVIEW 003 02/1212003 02/122003 000 05/18/2000 05/18/2000 005 0201/2001 0203/2003 008 03/06/2002 03/27/2003 004 03/06/2002 12/31/1999 002 05/30/2003 10/31/2001 000 06i2612002 06t2612002 006 03/06/2002 01/06/1999 004 03/06/2002 01/25/1999 003 07/26/1994 03/27/2003 006 10/10/2003 12/3111999 008 05/30/2002 1231/1999 003 01/14/1999 01/14/1999 003 12/18/1996 02103/2003 006 03/06/2002 0203/2003 006 03/2211999 01/14/1999 005 03/06/2002 02/03/2003 008 06/20/2002 08/17/1999 004 03/06/2002 02103/2003 005 03/06/2002 02103/2003 001 08/26/2003 05/0212002 008 03/06/2002 03/06/2002 005 03/06/2002 10/31/2001 006 03/06/2002 03/27/2003 003 08/26/2003 03/27/2003 003 03/06/2002 03/27/2003 004 11/18/2002 03/10/2003 005 02/12V2003 02/1212003 003 02/1212003 02112/2003 003 03/06/2002 09/23/1999 NEXT REVIEW 02/1212008 05/18/2005 02/03/2008 03/27/2008 12/31/2004 10/31/2006 06/26/2007 01/06/2004 01/25/2004 03/27/2008 12/31/2004 12/31/2004 01/14/2004 02/03/2008 02/03/2008 01/14/2004 02/03/2008 08/17/2004 02/03/2008 02103/2008 05/0212007 03/06/2007 10/31/2006 03/27/2008 03/27/2008 03/27/2008 03/10/2008 0211212008 0211212008 09/23/2004 ST EF EF EF EF EF EF EF EF EF EF EF EF E:

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B:

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PRATT PRATT EOP ATTACHMENTS Ginna Nuclear Power Plant PROCEDURE INDEX

, t STATUS VALUE(S):

EF Fri 1011012003 12:26:48 pm Page 2 of 2 5 YEARS ONLY:

PROCEDURE NUMBER ATT-14.1 ATT-14.2 ATT-14.3 ATT-14.5 ATT-14.6 ATT-15.0 ATT-15.1 ATT-15.2 ATT-16.0 ATT-16.1 ATT-16.2 ATT-17.0 ATT-17.1 ATT-18.0 ATT-20.0 ATT-21.0 ATT-22.0 ATT-23.0 ATT-24.0 ATT-26.0 PRATT PROCEDURE TITLE ATTACHMENT RHR COOL ATTACHMENT RHR ISOL ATTACHMENT RHR NPSH ATTACHMENT RHR SYSTEM ATTACHMENT RHR PRESS REDUCTION ATTACHMENT RCP START ATTACHMENT RCP DIAGNOSTICS ATTACHMENT SEAL COOLING ATTACHMENT RUPTURED SIG ATTACHMENT SGTL ATTACHMENT RCS BORON FOR SGTL ATTACHMENT SD-I ATTACHMENT SD-2 ATTACHMENT SFP - RWST ATTACHMENT VENT TIME ATTACHMENT RCS ISOLATION ATTACHMENT RESTORING FEED FLOW ATTACHMENT TRANSFER 4160V LOADS ATTACHMENT TRANSFER BATTERY TO TSC ATTACHMENT RETURN TO NORMAL OPERATIONS EFFECT LAST REV DATE REVIEW 006 04/3012003 01/08/2002 003 02/12/2003 02/12/2003 003 03/06/2r)02 01/06/1999 003 03/20/2003 02/03/2003 002 03/06/2002 01/14/1999 009 03/06/2002 03/17/2000 003 04/24/1997 0203/2003 005 03/06/2002 02103/2003 011 07/18/2001 01/11/2000 002 03/06/2002 09/08/2000 002 04/09/2002 09/08/2000 016 10/10/2003 02/29/2000 006 03/06/2002 01/30/2001 005 03/06/2002 02/03/2003 003 07/26/1994 02/03/2003 002 03/06/2002 02/03/2003 003 05/02/2002 01/22/2002 000 02/26/1999 02/26/1999 000 09/08/2000 09/08/2000 000 10/31/2001 10/31/2001 NEXT REVIEW 01/08/2007 02/12/2008 01/06/2004 02/03/2008 01/14/2004 03/17/2005 02/03/2008 02/03!2008 01/11/2005 09/08/2005 09/08/2005 02/28/2005 01/30/2006 02/03/2008 02/03/2008 02/03/2008 01/22/2007 02/26/2004 09/08/2005 10/31/2006 ST E:

E:

2:

E:

2:

E:

2:

EF EF EF EF EF 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.

Date

/0 -16,2 663 Responsible Manager 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 -

1000 -

800 -

600 -

400 -

200 -

EI I

0 I

I I

0 2000 4000 6000 8000 10000 12000 CYCLE 31 BURNUP (MWD/MTU)

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14000 16000 18000

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Responsible Manager TURBINE BUILE as_

Date

____1__

Da e

6_

7195A Dese Ar Crpi 5365 ABOVE INST AIR DRYER A H2 Cooler Inlet Valve (AOV-4230) 5316 Condensate Trim Valves VN I (AOV-9508D. 9508G) 6903 ABOVE COND BOOSTER PUMP B 5317 AVT Cond. Bypass Valve (AOV-3959) 7601 P Condensate Makeup 1/N (AOV4315) 14519(

Screen House ABOVE DIG FUEL STORAGE TANK LEVEL INDICATORS 7602 H 4_

MFW Reg & Bpass Valves (AOV-4269. 4270. 4271,4272) 7024 i

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Steam Dump Valves 1

/\\l (AOV-3349. 3351. 3353. 3355) 6923 I\\A Z

5315 ABOVE DOOR 37 AT COLUMN E-4 BY FIRE WATER STORAGE TANK STORAGE TANK H2 Cooler Bypass Valve (AOV.4229)

I HOT SHOP I AUIBD 5397 Steam Dump Valves (AOV-3350, 3352. 33

AUXILIARY BUILDING HOT SHOP AUX BLDG 7350 7352

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

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7037 Z14232H L1\\y1_

VCT Makeup (AOV-110A)(FO) j 1 731 VCT Makeup (AOV-11 OB, 1 OC)

(FC)

'1I VCT Makeup (AOV-111) (FC)

I Z7

.Letdown Valve (AOV-1 12A)

(Fai! to VCT)

I

.E L&LUUW1I VdIVC (AOV-371 )(FC) 7370 T 373 1

Charging Line (AOV-142)(FO) 7374 P

RHR Hx Bypass Valve (AOV-626)

(FC) 7 7375 RHR Flow Valve (AOV-625)

(FO)

Z 7376 RHR Flow Valve (AOV-624)

(FO) 2 7002 7004

-N-7003 Charging Pump Speed Control q (Fails to Minimum) 7009 Charging Pump Suction (AOV-1 12B)

I (FC)

Z 7006 Charging Pump Suction I

(AOV-11 2C)

(P0)

~~~~7005 (n

I Z7011 T

I Letdown Valve (PCV-135)

(FO)

NaOH Tank Outlet Valves (AOV-836A, 836B)

(FO)

Letdown Valve (TCV-145)

(Fails to VCT)

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 trip breakers - OPEN o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.

IF reactor trip breakers NOT open.

THEN perform the following:

a. Open Bus 13 and Bus 15 normal feed breakers.

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 0

0 Verify Turbine Stop Valves -

CLOSED Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:

Bus 14 and Bus 18

Bus 16 and Bus 17 Manually trip turbine.

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

Attempt to start any failed emergency D/G to restore power to all AC emergency busses.

IF Bus 14 AND Bus 16 are deenergized. THEN go to ECA-O.O, LOSS OF ALL AC POWER. Step 1.

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 29 STEP ACTION/EXPECTED RESPONSE 1RESPONSE 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 4 psig greater than

-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 STARTED.

b. Manually actuate SI and CI.

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TIThE:

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

~~~~~~~~~~~~~PAGE 5 of 29 STEP ACTION/EXPECTED RESPONSE 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

b. Charcoal filter dampers green status lights - EXTINGUISHED

a. Manually start fans.

b. Dispatch personnel to relay room 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

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

7 Verify CNMT Spray Not Required:

o Annunciator A-27. CNMT SPRAY -

EXTINGUISHED o CNMT pressure - LESS THAN 28 PSIG Verify CNMT spray initiated.

IF CNMT spray NOT initiated. THEN perform the following:

a. Depress manual CNMT spray 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

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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

b. Check CNMT pressure - LESS THAN 18 PSIG

c. Check if ANY main steamlines should be isolated:

a. Go to Step 9.

b. Ensure BOTH MSIVs closed and go to Step 9.

c. Go to Step 9.

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 affected SG(s)

d. Manually close valves.

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 and B S/G MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

A

c. SG blowdown and sample valves CLOSED

c. Place S/G blowdown and sample valve isolation switch to CLOSE.

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 29 STEP ACTION/EXPECTED RESPONSE 1RESPONSE 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.

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 29 STP ACTION/EXPECTED RESPONSE llRESPONSE 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 lights - BRIGHT

b. Manually close CI and CVI valves 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 outlet valve status lights -

BRIGHT

c. Dispatch AO to locally fail open valves.

FCV-4561

. FCV-4562

d. Letdown orifice valves - CLOSED

. AOV-200A

AOV-200B

AOV-202

d. Place affected valve switch to CLOSE.

IF valves can NOT be verified closed by MCB indication, THEN close alternate isolations.

(Refer to ATT-3.0.

ATTACHMENT CI/CVI)

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 10 of 29 STEP ACTION/EXPECTED RESPONSE 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 RUNNING

a. IF offsite power available. THEN 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 FLOW

a. IF RCS pressure 1400 psig. THEN pumps and align THEN go to Step less than manually start valves.

IF NOT.

15.

b. RHR flow indicator - CHECK FOR FLOW 15 Verify AFW Valve Alignment:

b. IF RCS pressure less than 140 psig. THEN manually start pumps and align valves.

IF NOT.

THEN go to Step 15.

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

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

16 Monitor Heat Sink:

a. Check SIG narrow range level -

GREATER THAN 5% [25% adverse CNMT] in any S/G

a. Perform the following:

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 -

BOTH SG LESS THAN 50%

b. Secure AFW flow to any S/G with level above 50%.

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

I

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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 deluge - OPEN

MOV-852A

. MOV-852B

b. Verify SI pump C - RUNNING

c. Verify SI pump A - RUNNING

d. Verify SI pump B - RUNNING

e. Verify SI pump C discharge valves - OPEN

MOV-871A

MOV-871B

a. Ensure at least one valve open.

b. Manually start pump on available bus.

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. 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. Manually open valves as necessary.

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REV: 35 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 13 of 29 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED CAUTION IF OFESITE POWER IS LOST AFTER SI RESET.

TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5. ATTACHMENT LOSS OF 18 Check CCW Flow to RCP Thermal Barriers:

o Annunciator A-7. RCP 1A CCW RETURN HI TEMP OR LO FLOW -

EXTINGUISHED IF CCW to a RCP is lost. THEN perform the following:

a. Stop affected RCPs.

b. Reset SI.

o Annunciator A-15.

RETURN HI TEMP OR EXTINGUISHED RCP B CCW LO FLOW -

c. Verify adequate power available to run one charging pump (75 kw).

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.

STP ACTION/EXPECTED RESPONSE llRESPONSE 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 5470F 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.

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

- CLOSED

b. Manually close auxiliary spray 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 2260 PSIG

d. Normal PRZR spray valves - CLOSED

PCV-431A

PCV-431B

c. Continue with Step 22.

WHEN pressure less than 2260 psig.

THEN do Step 21d.

d. Place controllers in MANUAL at 0% demand.

IF valves can NOT be closed. THEN stop associated RCP(s).

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

a. RCP status - ANY RCP RUNNING

b. SI pumps - AT LEAST TWO RUNNING

c. RCS pressure minus maximum SIG pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs 23 Check If S/G Secondary Side Is Intact:

o Pressure in both S/Gs - STABLE OR INCREASING o Pressure in both S/Gs - GREATER THAN 110 PSIG 24 Check If S/G Tubes Are Intact:

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

a. Go to Step 23.

b. Go to Step 23.

c. Go to Step 23.

IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized. THEN go to E-2. FAULTED STEAM GENERATOR ISOLATION. Step 1.

Go to E-3. STEAM GENERATOR TUBE RUPTURE. Step 1.

'11-/

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 17 of 29 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED I 25 Check If RCS Is Intact:

a. CNMT area radiation monitors -

NORMAL Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.

. 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

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

a. RCS pressure:

o Pressure - GREATER THAN 1625 PSIG

a. Do NOT stop SI pumps.

Go to Step 27.

o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core exit T/Cs - GREATER THAN 0 0F USING FIG-1.0. FIGURE MIN SUBCOOLING

b. Do NOT stop Step 27.

SI pumps.

Go to

c. Secondary heat sink:

o Total feed flow to S/Gs -

GREATER THAN 200 GPM

c. IF neither condition met. THEN do NOT stop SI pumps.

Go to Step 27.

-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.

the following:

Perform

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.

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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 THAN 5%

b. Control feed flow to maintain narrow range level between 17%

and 50%

29 Check Secondary Radiation Levels -

NORMAL

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

b. IF narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.

Go to E-3. STEAM GENERATOR TUBE 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

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REV: 3 5

.E-O REACTOR TRIP OR SAFETY INJECTION PAGE 20 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

4 A

4 4

4 CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET.

TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5. ATTACHMENT LOSS OF 30 Reset SI 31 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A26. CNMT ISOLATION - EXTINGUISHED

b. Perform the following:

1) Reset SI.

2) Depress CI reset pushbutton.

K-)

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 21 of 29 STEP ACTION/EXPECTED RESPONSE 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)

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TITLE:RE

3

.d REV: 35l E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 29 STEP ACTION/EXPECTED RESPONSE 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.

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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 turbine building - OPEN

. MOV-4613 and MOV-4670

. MOV-4614 and MOV-4664

d. Verify adequate air compressor(s) - RUNNING

e. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR INCREASING

c. Perform the following:

1) Manually align valves.

2) Dispatch AO to locally reset compressors as necessary.

d. Manually start electric air 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. Perform the following:

1) Continue attempts to restore IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).

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

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REV: 35 l

E -0 l

REACTOR TRIP OR SAFETY INJECTION l

l PAGE 24 of 29 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED I 34 Check Auxiliary Building Radiation -

NORMAL

Plant vent iodine R-10B)

Plant vent particulate (R-13)

Plant vent gas (R-14)

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

CHG pump room (R-4) 35 Check PRT Conditions o PRT level (LI-442) - LESS THAN 84%

o PRT temperature (TI-439) - LESS THAN 120 0F o PRT pressure (PI-440A) - LESS THAN 3 PSIG Evaluate cause of abnormal conditions.

IF the cause is a loss of RCS inventory outside CNMT. THEN go to ECA-1.2. LOCA OUTSIDE CONTAINMENT.

Step 1.

Evaluate the following flowpaths for cause of abnormal conditions:

RCP seal return relief

PRZR PORVs

PRZR safeties

Letdown line relief IF excess letdown previously in service. THEN close AOV-310. excess letdown isolation valve from loop A cold.

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 29 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDI 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 250 PSIG

2) Pressure - STABLE OR INCREASING l) Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.

2) Go to Step 37.

b. Stop both RHR pumps and place in AUTO 37 Check Normal Power Available To Charging Pumps:

o Bus 14 normal feed breaker -

CLOSED o Bus 16 normal feed breaker -

CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).

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

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 29 STEP ACTION/EXPECTED RESPONSE 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:

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REV: 35 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 27 of 29 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 39 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

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

a. Verify AC emergency busses energized by offsite power:

o Emergency DG output breakers

- OPEN o AC emergency bus voltage -

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

a. Perform the following:

1) Verify non-safeguards bus tie breakers closed:

Bus 13 to Bus 14 tie

. Bus 15 to Bus 16 tie

2) Place the following pumps in PULL STOP:

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)

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REV: 3 5 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 29 of 29 TE ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 41 Return to Step 20

-END-

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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~:

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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

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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).

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REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 25 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION f 13 CONTROLLED COPY NUMBER 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.

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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

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:

o At least one train of reactor trip breakers - OPEN o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM O

Verify Turbine Stop Valves -

CLOSED Manually trip reactor.

IF reactor trip breakers NOT open.

THEN perform the following:

a. Open Bus 13 and Bus 15 normal feed breakers.

b. Verify rod drive MG sets tripped.

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

d. Reset lighting breakers.

Manually trip turbine.

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

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REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 4 of 25 STEP ACTION/EXPECTED RESPONSE 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)

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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.

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TITLE:

REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 6 of 25

_E

AC IO /E PE TE R SP NS RED 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 unit operation

a. Manually align switches on rear of MCB.

o Mode switch in UNIT o Voltage control selector in AUTO

b. Check emergency D/Gs - BOTH D/G RUNNING

b. WHEN non-running DG available 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

2 Ed:

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

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

2) Frequency - APPROXIMATELY 60 Hz

d. Verify adequate DG cooling o Bus 17 and/or Bus 18 -

ENERGIZED o One SW Pump running for each running D/G

1) Adjust voltage control to restore voltage to approximately 480v

2) Adjust governor to restore frequency to approximately 60 Hz

d. Manually energize busses and start SW Pumps.

IF adequate cooling can NOT be supplied to a running D/G, THEN perform the following:

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 emergency busses - ENERGIZED

Bus 14 and Bus 18

Bus 16 and Bus 17

e. Manually energize AC emergency busses.

IF Bus 14 AND Bus 16 are deenergized, THEN go to Step 8.

f. Return to procedure and step in effect

IEOfP:

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

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

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

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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 determine if either normal offsite power supply - AVAILABLE o 12B transformer via breaker 76702

-OR-o 12A transformer via breaker 75112

a. IF normal offsite power supply NOT readily available. THEN perform the following:

1) Restore IA system using the Diesel Air Compressor (Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR).

2) Evaluate Main transformer 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:

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

27l ECA-0.0 LOSS OF ALL AC POWER 2

l

~~~~~~~~~~~~~~PAGE 10 of 25 STP ACTION/EXPECTED RESPONSE llRESPONSE 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)

STP ACTION/EXPECTED RESPONSE l[RESPONSE NOT OBTAINED I 11 Isolate Makeup And Reject From Hotwell To CST By Placing Hotwell Level Controller (LC-107) In Manual AT 50%

12 Isolate S/G:

a. Manually close both MSIVs IF valves can NOT be manually closed, THEN dispatch AO to locally isolate makeup and reject lines.

v Makeup isolation V-4058

Reject isolation V-4055 IF valves can NOT be manually closed. THEN dispatch AO to locally 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 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 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).

STP ACTION/EXPECTED RESPONSE llRESPONSE 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).

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REV: 27 ECA-O.O LOSS OF ALL AC POWER PAGE 14 of 25 STEP ACTION/EXPECTED RESPONSE 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 THAN 5% [25% adverse CNMT]

b. Control AFW flow by thiattling TDAFW flow control valves

. S/G A. AOV-4297

. S/G B. AOV-4298

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

b. Control AW flow by throttling TDAFP discharge MOV-3996.

IF MOV-3996 can NOT be 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 narrow range level between 17%

[25% adverse CNMT] and 50%

c. IF narrow range level in any intact S/G continues to increase in an uncontrolled manner. THEN return to Step 14.

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TITLE:

REV: 27 ECA-O.O LOSS OF ALL AC POWER PAGE 15 of 25 STP ACTION/EXPECTED RESPONSE llRESPONSE 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

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REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 16 of 25 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 17 Verify Source Range Detector(s) -

ENERGIZED

N-31

N-32 Dispatch personnel with relay rack key to turn off 125 VDC power switches in REACTOR PROTECTION racks RLTR-1 and RLTR-2 to deenergize source range block relays.

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

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REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 17 of 25 STP ACTION/EXPECTED RESPONSE llRESPONSE 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.

NOTE:

_ ACTION/EXPECTED RESPONSEIREPNE OTBANDI 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 following indications:

1) Check source range(s). N-31 AND N-32 o Indicator - ON SCALE o Power - STABLE OR DECREASING

2) Check intermediate range. N-35 o Indicator - ON SCALE o Power - STABLE OR DECREASING

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

o Power - STABLE OR DECREASING

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

o Control SG ARVs to stop SIG depressurization and allow RCS to heat up.

o Direct RP to sample RCS and PRZR for boron concentration.

o Request plant staff assistance in evaluating core reactivity status

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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.

actuated. THEN 23 and 24.

WHEN SI do Steps 21b. 22.

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 lights - BRIGHT

c. CNMT RECIRC fan coolers SW outlet valve status lights -

BRIGHT

b. Manually close CI and CVI valves.

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

c. Dispatch AO to locally fail open valves.

AOV-4561

AOV-4562

d. Verify RHR Pump Suction from CNMT Sump B valves - CLOSED

MOV-850A

MOV-850B

d. IF sump recirculation NOT in progress, THEN manually close valves.

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

K>

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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

- GREATER THAN 315 0F

a. Perform the following:

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

2) Go to Step 24.

b. Check SIG pressures - LESS THAN 300 PSIG

c. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR INCREASING

d. Control SIG ARVs to maintain S/G pressures at 300 psig IN AUTO

b. Continue with Step 24.

WHEN SIG pressure decreases to less than 300 psig. THEN do Step 23c and d.

c. Control S/G ARVs in manual to 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.

d. Control S/G ARVs in manual to 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.

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REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 21 of 25 STEP ACTION/EXPECTED RESPONSEl RESPONSE NOT OBTAINED 24 Check CNMT Pressure -

HAS REMAINED LESS THAN 28 PSIG o Annunciator A-27. CNMT SPRAY -

EXTINGUISHED o CNMT pressure indicators - LESS THAN 28 PSIG IF CNMT pressure is less than 28 psi.THEN perform the following:

a. Reset CNMT spray.

b. Place CNMT spray pump discharge valve switches to CLOSE to 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 THAN 12000F 26 Check If AC Emergency Power Is Restored -

BUSSES 14 AND/OR 16 ENERGIZED IF core exit temperatures greater than 1200'F and increasing, THEN go to SACRG-1. SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.

step 1.

Continue to control RCS conditions and monitor plant status:

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.

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

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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.

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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 CAPACITY OF THE POWER SOURCE.

EMERGENCY BUS SHOULD NOT EXCEED THE 4

29 Verify Following Equipment Loaded On Available AC Emergency Busses:

Manually load equipment as power supply permits.

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 core exit T/Cs - GREATER THAN 00F USING FIG-1.0. FIGURE MIN SUBCOOLING

a. Go to ECA-0.2. LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED.

Step 1.

b. Check PRZR level - GREATER THAN 5% [30% adverse CNMT]

b. Go to ECA-0.2, POWER RECOVERY Step 1.

LOSS OF ALL AC WITH SI REQUIRED.

c. Check SI and RHR Pumps - NONE RUNNING

c. Go to ECA-0.2. LOSS OF ALL AC 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-

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REV: 27 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 1 ECA-0.0 APPENDIX LIST 1) 2)

3) 4)

5) 6)

7) 8)

9) 10) 11) 12)

TITLE FIGURE MIN ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT SUBCOOLING (FIG-1.0)

DC LOADS (ATT-8.0)

FAULTED S/G (ATT-10.0)

RUPTURED S/G (ATT-16.0)

CI/CVI (ATT-3.0)

NONVITAL (ATT-8.3)

GEN DEGAS (ATT-8.2)

RCS ISOLATION (ATT-21.0)

FIRE WATER COOLING TO TDAFW PUMP (ATT-5.2)

DIESEL AIR COMPRESSOR (ATT-11.2)

NO SW PUMPS (ATT-2.4)

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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.

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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:

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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:

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REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 3 of 20 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 4 * * * * * * * * *

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4

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

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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.

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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

b. Verify MFW flow control valves -

CLOSED a MFW regulating valves

MFW bypass valves

c. Verify total AFW flow - GREATER THAN 200 GPM

a. Continue with Step 3. WHEN temperature less than 5540F.

THEN do Steps 2b through f.

b. Depress MANUAL pushbuttons for A and B MW regulating valve and bypass valve controllers AND adjust to 0 demand.

c. Manually start both MDAFW pumps.

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.

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

3 Monitor S/G Levels:

a. Narrow range level - GREATER THAN 5%

b. Control feed flow to maintain narrow range level between 17%

and 52%.

4 Verify MRPI Indicates -

ALL CONTROL AND SHUTDOWN RODS ON BOTTOM

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

b. IF narrow range level in any S/G continues to increase. THEN stop feed to that SG.

IF one or more control rods NOT fully inserted. THEN perform the 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.

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

ENERG IZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses - CLOSED o 480 volt bus voltage - GREATER THAN 420 VOLTS o Emergency DG output breakers -

OPEN Perform the following:

a. IF any AC emergency bus normal feed breaker open. THEN ensure associated DG breaker closed.

b. Perform the following as necessary:

1) Ensure one CCW pump running.

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).

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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.

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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:

o Adequate air compressor(s) -

RUNNING o

IA pressure - GREATER THAN 60 PSIG Dispatch AO to locally reset and start adequate air compressors.

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

THEN use diesel air compressor.

(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 RUNNING

b. PRZR level - GREATER THAN 13%

c. Verify letdown - IN SERVICE

d. PRZR level - TRENDING TO 35%

e. Check PRZR heaters - ENERGIZED o PRZR proportional heaters o PRZR heater backup group

a. Perform the following:

1) Close letdown isolation.

AOV-427.

2) Manually start one charging pump.

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 excess letdown in service.

IF NOT. THEN manually place letdown in service (Refer to ATT-9.O. ATTACHMENT LETDOWN).

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

e. Reset PRZR heaters and energize to restore PRZR pressure.

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22 ES-0.1 REACTOR TRIP RESPONSE PAGE 10 of 20 9 Check PRZR Pressure Control:

a. PRZR pressure - GREATER THAN 1750 PSIG

a. Perform the following:

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 2210 PSIG

b. IF pressure less than 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.

STEP ACTION/EXPECTED RESPONSE 1RESPONSE 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.

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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

b. PULL STOP TDAFW pump steam supply valves

. MOV-3504A

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

a. Go to Step 11.

a. Verify condenser available:

o Any MSIV - OPEN o Annunciator G-15, STEAM DUMP ARMED -

LIT

a. Perform the following:

1) Place S/G ARV controller in AUTO at 1005 psig and verify proper operation.

IF S/G ARV 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 TRENDING TO 5470F

d. Adjust steam dump to restore Tavg.

IF steam dumps not available, THEN use ARVs.

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REV: 22 ES-0.1 REACTOR TRIP RESPONSE PAGE 13 of'20 STEP ACTION/EXPECTED RESPONSE 1RESPONSE 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.

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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 -

DEENERGIZED

b. Check intermediate range flux -

EITHER CHANNEL LESS THAN 10-10 AMPS

a. Go to Step 13e.

b. Perform the following:

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:

o Both intermediate range channels - LESS THAN 10-10 AMPS

c. Continue with Step 14.

When either condition met. THEN do Steps 13d and e.

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors -

ENERGIZED

d. Manually energize source range 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

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

a. Check condenser - AVAILABLE

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 rod shroud fan - RUNNING

2) Verify one Rx compartment cooling fan - RUNNING

d. Dispatch AO to perform ATT-17.0.

ATTACHMENT SD-i

a. Dispatch AO to perform ATT-17.1.

ATTACHMENT SD-2.

1) Manually start one fan as power supply permits (45 kw).

2) Manually start one fan as power supply permits (23 kw).

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

a. PRZR pressure - BETWEEN 1800 PSIG AND 2260 PSIG

b. PRZR level - BETWEEN 35% AND 40%

c. SIG narrow range levels -

BETWEEN 17% AND 52%

d. RCS Tavg - GREATER THAN 5401F 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 o Level - GREATER THAN 20%

-OR-o Level - STABLE OR INCREASING

a. Control PRZR heaters and spray as necessary.

b. Control charging as necessary.

c. Control S/G feed flow as necessary.

d. Close both SIVs.

b. Manually increase VCT makeup flow as follows:

1) Ensure BA transfer pumps and RMW pumps running.

2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.

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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.

VCT level greater than THEN do Step 17b.

WHEN 40%.

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

CLOSED

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

a. Any MDAFW pump - AVAILABLE

b. Verify AMSAC TRIPPED status light - EXTINGUISHED

a. Verify TDAFW pump operating to maintain required SIG level and go to Step 20.

b. Reset AMSAC.

c. Verify both SG levels THAN 17%

- GREATER

c. Continue with Step 20.

level greater than 17%.

Steps 18d. e and 19.

WHEN S/G THEN do

d. Verify Bus 11A and Bus B - AT LEAST ONE ENERGIZED

d. Perform the following:

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 switches in AUTO

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

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

3) Open TDAFW flow control valves.

AOV-4297

AOV-4298

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

a. Verify the following:

o Both S/G levels - GREATER 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

a. Continue with Step 20.

WHEN conditions met. THEN do Steps 19b through f.

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REV: 22 ES-0.1 REACTOR TRIP RESPONSE n 3.

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

a. Consult Plant Staff - COOLDOWN REQUIRED

b. At least one RCP - RUNNING

a. Go to 0-3. HOT SHUTDOWN WITH XENON PRESENT.

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-

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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

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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

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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 200F 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).

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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 FFEIV A E 3

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.

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

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a

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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.

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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 NON-FAULTED SG PRESSURE

a. IF RWST level greater than 28%.

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.

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30 FR-H.1

RESPONSE

O LOSS OF SECONDARY HEAT SINK PAGE 4 of 31 STEP ACTION/EXPECTED RESPONSE 1RESPONSE 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:

o Verify either SIG level - WIDE RANGE GREATER THAN 50 inches

[100 inches adverse CNMT]

o Verify PRZR pressure - LESS THAN 2335 PSIG IF a loss of heat sink is indicated. THEN perform the following:

a. Trip both RCPs.

b. Go to Step 13 to initiate bleed and feed cooling.

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

~~~~~~~~~~~~~~O OBAINEPCED IEPNE 4

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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

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

a. Check S/G blowdown and samples valves - CLOSED

a. Place S/G blowdown and sample valve isolation switch to CLOSE.

b. Check MCB indications for cause of AFW failure:

1) Verify CST level - GREATER THAN 5 FEET

2) Verify busses supplying power to MDAFW pumps - ENERGIZED

1) Refer to ER-AFW.1. ALTERNATE WATER SUPPLY TO AFW PUMPS.

2) Continue attempts to restore 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.

STEP ACTION/EXPECTED RESPONSE 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 -

GREATER THAN 200 GPM

e. Continue attempts to restore AFW 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

b. Check condensate system:

o Condensate pump - ANY RUNNING o MFW pump suction pressure -

GREATER THAN 185 PSIG

c. Establish MFW flow:

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.

a. Go to Step 7.

b. IF offsite power available. THEN try to place condensate system in service.

IF NOT. THEN go to Step 7.

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

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3 0 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:

1) Align SAFW system for 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

a. IF greater than 200 gpm total SAFW flow can NOT be established. THEN go to Step 8.

EOP~:

TITL.E:RE:

3 W

EN:

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

3 0 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 10 of 31 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 4

4 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

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 THAN 1950 PSIG

b. Depressurize RCS to less than 1950 psig:

a. Go to Step 10c.

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 spray valve (AOV-296)

2) Use one PRZR PORV.

IF IA to 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 maximum rate to depressurize at least one SIG to less than 380 psig

h. Verify condensate flow to S/Gs

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

h. Go to Step 12.

11 Check S/G Levels:

a. Narrow range level in at least one S/G - GREATER THAN 5% [25%

adverse CNMT]

a. IF feed flow verified and level increasing in at least one SG.

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:

o Either S/G level - WIDE RANGE GREATER THAN 50 inches

[100 inches adverse CNMT]

o PRZR pressure - LESS THAN 2335 PSIG

a. IF loss of heat sink is indicated. THEN perform the following:

1) Go to Step 13 to initiate bleed and feed cooling.

b. Return to Step 1 A

a A

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:

a. Check SI pumps - AT LEAST ONE RUNNING

b. Check valve alignment for operating SI pumps - PROPER EMERGENCY ALIGNMENT Manually start pumps and align valves as necessary to establish RCS feed path.

IF a feed path can NOT be established. THEN continue attempts to establish feed flow. Return to 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, TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5. ATTACHMENT LOSS OF 4

4 4

16 Check If SI Can Be Reset:

a. Check SI blocked status light -

EXTINGUISHED

b. Check the following:

o PRZR pressure - LESS THAN 1750 PSIG

-OR-o Either steamline pressure -

LESS THAN 514 PSIG

a. Place SI block switches to UNBLOCK

b. IF PRZR pressure stable or increasing. THEN reset SI and go to Step 17.

IF PRZR pressure decreasing.

THEN perform the following:

1) WHEN PRZR pressure less than 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.

CONTAINMENT ISOLATION -

EXTINGUISHED

b. Perform the following:

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 RUNNING two SW pumps -

a. Manually start pumps as power 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 valves - AT LEAST ONE SET OPEN

b. Manually align valves.

MOV-4615 and MOV-4734

. MOV-4616 and MOV-4735

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TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 17 of 31 STP ACTION/EXPECTED RESPONSE llRESPONSE 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.

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

c. Verify turbine building SW isolation valves - OPEN

MOV-4613 and MOV-4670

MOV-4614 and MOV-4664

d. Verify adequate air compressor(s) - RUNNING

e. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR INCREASING

c. Perform the following:

1) Manually align valves.

2) Dispatch A to locally reset compressors as necessary.

d. Manually start electric air 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. Perform the following:

1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).

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 Path:

o Core exit TCs -

STABLE OR DECREASING o RVLIS Level (no RCPs) - GREATER THAN 77% [82% adverse CNMT]

Perform the following:

a. Open Rx head vent valves.

SOV-590

SOV-591

SOV-592

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 CAUTION THE RCS BLEED PATH MUST BE MAINTAINED EVEN THAN SI PUMP SHUTOFF HEAD.

IF RCS PRESSURE REMAINS GREATER 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 To Charging Pumps:

o Bus 14 normal feed breaker -

CLOSED o Bus 16 normal feed breaker -

CLOSED Verify adequate capacity to run (75 kw each).

emergency D/G charging pumps IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS).

STEP ACTION/EXPECTED RESPONSE 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 STE ACTION/EXPECTED RESPONSE 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 EXCHANGERS.

1 HOUR WITHOUT CCW TO THE RHR HEAT 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

b. Check the following:

o CNMT pressure -.LESS THAN 4 PSIG

a. Go to Step 27.

b. Continue with Step 27. WHEN BOTH conditions satisfied. THEN do Steps 26c through 26f.

o Sodium hydroxide tank level -

LESS than 55%

c. Reset CNMT spray

d. Check NaOH flow (FI-930) - NO FLOW

d. Place NaOH tank outlet valve 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

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:

RESPONSE NOT OBTAINED

a. Check narrow range level in at least one S/G - GREATER THAN 5%

[25% adverse CNMT]

a. Return to Step 27.

b. Adjust S/G ARV controllers to existing S/G pressure 4

4 a

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:

o Core exit T/Cs - DECREASING o RCS hot leg temperatures -

DECREASING Perform the following:

a. Control steam dump and feed flow to establish natural circulation and stabilize RCS temperature.

b. Return to Step 27.

EOP:

TITLE:

REV: 30 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 25 of 31 STEP ACTION/EXPECTED RESPONSE 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 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*.

32 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps - RUNNING

b. RCS subcooling based on core exit T/Cs - GREATER THAN 351F

[900F adverse CNMT] USING FIG-1.0. FIGURE MIN SUBCOOLING

a. Go to Step 33.

b. Check the following:

o RCS pressure greater than 1625 psig [1825 psig adverse CNMT]

o RCS subcooling based on core exit T/Cs greater than 00F using FIG-l.0. FIGURE MIN SUBCOOLING IF NOT. THEN go to Step 35.

c. Check PRZR level - GREATER THAN 13% [40% adverse CNMT]

c. Do NOT stop SI pump.

Go to 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

b. Determine required RCS subcooling from table:

a. Go to Step 34.

Charging Pump RCS Subcouling Criteria Availability NONE 120OF [2000F adverse CNMT]

ONE 115OF [1901F adverse CNMT]

TWO 105OF [180'F adverse CNMT]

THREE 1000F [1750F adverse CNMT]

c. RCS subcooling based on core exit T/Cs - GREATER THAN VALUE FROM TABLE ABOVE USING FIG-1.0.

FIGURE MIN SUBCOOLING

c. Check the following:

o RCS pressure greater than 1625 psig [1825 psig adverse CNMT]

o RCS subcooling based on core exit T/Cs greater than 00F using FIG-1.0. FIGURE MIN SUBCOOLING IF NOT. THEN go to Step 35.

d. PRZR level - GREATER THAN 13%

[40% adverse CNMT]

d. Do NOT stop SI pump.

Step 35.

Go to

e. Stop one SI pump

ACTIN/EPECTED RESPONSEIREPNEOTBAND 34 Check If Last SI Pump Should Be Stopped:

a. One SI pump - RUNNING

b. Check the following:

a. Go to Step 37.

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%

[40% adverse CNMT]

c. Do NOT stop SI pump.

Step 35.

Go to

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 Associated Block Valves -

ANY BLEED PATH OPEN 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.

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.

STP ACTION/EXPECTED RESPONSE llRESPONSE 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 INJECTION MODE

b. Check RCS pressure:

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

2) Pressure - STABLE OR INCREASING

a. Go to Step 39.

b. Go to appropriate plant procedure:

o IF RWST level greater than 28%. THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

Step 1.

-OR-o IF RWST THEN go TO COLD Step 1.

level less than 28%.

to ES-1.3. TRANSFER LEG RECIRCULATION.

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: 3 0 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)

3) 4)

5) 6)

7) 8)

9) 10) 11)

ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT CNMT RECIRC FANS (ATT-4.0)

COND TO S/G (Arr-5.o)

N2 PORVS (ATT-12.0)

RHR COOL (ATT-14.1)

SAFW (ATT-5.1)

RESTORING FEED FLOW (ATT-22.0)

NO SW PUMPS (ATT-2.4)

LOSS OF OFFSITE POWER (ATT-8.5)

DIESEL AIR COMPRESSOR (ATT-11.2)

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 D

A 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 1140 PSIG 2 Verify FW Isolation To Affected S/G(s):

a. MFW pumps - TRIPPED

b. MEW flow control valve(s) -

CLOSED

. MFW regulating valve(s)

MFW bypass valve(s)

c. MFW pump discharge valve(s) -

CLOSED 3 Check Affected SG(s) Narrow Range Level -

LESS THAN 90%

[80% adverse CNMT]

a. Return to procedure and step in effect.

a. Trip MFW pumps.

b. Depress MANUAL pushbutton(s) AND l manually close valves.

I

c. Manually close valves.

Go to FR-H.3. RESPONSE TO STEAM GENERATOR HIGH LEVEL. Step 1.

STP ACTION/EXPECTED RESPONSE l

RESPONSE NOT OBTAINEDl 4

4 4

i a

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 Try To Dump Steam From The Affected S/G(s):

Go to Step 6.

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

b. Pressure - LESS THAN 1140 PSIG

a. Go to Step 6.

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 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 Stop pumps feeding affected S/G(s).

7 Check RCS Hot Leg Temperatures -

LESS THAN 5300F Cool down RCS to less than 5301F 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 43 CONTROLLED COPY NUMBER 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 Range Level -

GREATER THAN 80%

IF less than 80% in all S/Gs. THEN return to procedure and step in effect.

2 Verify FW Isolation To Affected S/G(s):

a. MFW pumps - TRIPPED

b. MFW flow control valve(s) -

CLOSED

a. Trip MFW pumps.

b. Depress MANUAL pushbutton(s) AND manually close valves.

I

. MFW regulating valve(s)

MFW bypass valve(s)

c. Verify both S/G pressures -

GREATER THAN CONDENSATE HEADER PRESSURE

c. Stop any running condensate pumps.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 3 Close AFW And SAFW Flow Control Valves To Affected S/G(s):

Stop pumps feeding 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'

RESPONSE TO STEAM GENERATOR HIGH L REV: 7 VEL PAGE 5 of 7

--4 STEP ACTION/EXPECTED RESPONSE RESPONSE NO 4 Check Affected SIG(s) Level:

' OBTAINED I

a. Narrow range level - LESS THAN 90% [80% adverse CNMT]

b. Narrow range level - DECREASING

c. Control AFW flow to maintain narrow range level between 17%

[25% adverse CNMT] and 52%

d. Return to procedure and step in effect

a. Go to Stel

b. IF affect(

to increa.

following:

1) Dispatc isolatc o For regt vali valA o For' regt val%

valA

2) Go to 5.

d SG level continues

e. THEN perform the h AO to locally affected S/G:

S/G A. close MFW lating and bypass e outlet isolation es. V-3987 and V-3991

-OR-S/G B. close MFW lating and bypass e outlet isolation es. V-3986 and V-3990 tep 5.

4

VEL REV: 7 RESPONSE TO STEAM GENERATOR HIGH LIL PAGE 6 of 7 STEP _ ACTION/EXPECTED RESPONSE RESP NOI 5 Adjust Affected SIG(s) ARV.

Setpoint To 1050 PSIG a

a *

a *

a *

a * * * *

CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED F SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G OBTAINED a

T H aN a

a a

SOW. THEN STEAM a * * * * * * * * * * * * * *

al*

6 Close Affected S/G Steam Supply Valve In PULL STOP TDAFW Pump And Place

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)

Radiation Levels -

NORMAL

SIG blowdown, R-19

SIG A. R-31

SIG B. R-32 IF an E-3 or is in effect.

procedure and NOT. THEN go GENERATOR TUB

CA-3 series procedure THEN return to step in effect.

IF

o E-3, STEAM

RUPTURE. Step 1.

I REV: 7 RESPONSE TO STEAM GENERATOR HIGH L' PAGE 7 of 7 STEP ACTION/EXPECTED RESPONSE 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 cooling, AND immediately depress assoc.

SHUTDCWN pushbutton.

by alternate ated VOLTAGE

b. Refer to ATT-2.4, ATTACHMENT NO SW PUM S.

EOP:

lTITLE:

lREV: 1 6 FR-S.1 RESPONSE TO REACTOR RESTART/ATIS PAGE 1 of 13 ROCHESTER GAS AND ELECTRIC CORPO GINNA STATION CONTROLLED COPY NUMBER RESPONSIB8 MANAGER 10 -it-)OD ATION 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 reactivity to a core which is observed to when expected to be shut down.

B. ENTRY CONDITIONS/SYMPTOMS o add negative e critical

1. ENTRY CONDITIONS -

This procedure is e tered from:

a. E-0, REACTOR TRIP OR SAFETY INJECT' when reactor trip is not verified trip is not effective.

b. F-0.1, SUBCRITICALITY, Critical Sai Status Tree on either a RED or ORAl ON, nd manual ety Function GE condition.

RESPONSE TO REACTOR RESTART/AT qS REV: 16 PAGE 3 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NO NOTE:

Adverse CNMT values should be used whenever CNMT than 4 psig or CNMT radiation is greater than 10+

OBTAINEDl 0

0 0

Verify Reactor Trip:

o At least one train of reactor trip breakers - OPEN o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Verify Turbine Stop Valves -

CLOSED Check AFW Pumps Running:

a. MDAFW pumps - RUNNING

b. TDAFW pump - RUNNING IF NECESSARY Manually tri]

IF reactor ti THEN manuall' Manually tril IF turbine ti verified. THI

a. Manually

b. Manually valves.

. MOV-350'

. MOV-350 ressure is greater 5 R/hr.

reactor.

ip breakers NOT open.

insert control rods.

turbine.

ip can NOT be N close both MSIVs.

tart MDAFW pumps.

pen steam supply A

A K>

4,

I

-l-- -- -- -

RESPONSE TO REACTOR RESTART/A WS I

1 REV: 16 PAGE 4 of 13 0

0 CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE RE STEPS 1 THROUGH 12 OF E-0. REACTOR TRIP OR SAFETY INJE 0.

.0

.0 NOTE:

o If offsite power is lost coincident with SI.

lockout relays must be reset to restore BA an o Foldout page should be open and monitored per FT OBTAINED A

ERSED TION.

WHEN PERFORMING 0

0 4 Initiate Emergency Boration Of RCS:

a. Check SI status:

o All SI annunciators -

EXTINGUISHED o All SI pumps -

OFF IN AUTO

b. Verify at least one charging pump - RUNNING

c. Align boration path:

1) Start two BA transfer pumps

2) Open MOV-350

3) Verify BA flow

d. Verify charging flow path:

o Charging valve to loop B cold leg (AOV-294) - OPEN o Charging flow control valve (HCV-142) - DEMAND AT 0%

a. Perform

1) Compl of E-SAFET conti:

2) IF SI to St to St

b. Perform

1) Reset

2) Start

c. Initiate maximum acid flo FCV-110A establis ER-CVCS.

CONTROL

d. Manually flow.

hen MCC C and MCC D

RMW pumps.

odically.

he following:

te steps 1 through 12 REACTOR TRIP OR INJECTION, while uing with this procedure flow indicated. THEN go p 5. IF NOT, THEN go p 4b.

he following:

SI if necessary.

one charging pump.

normal boration at

'ate using the boric control valve.

IF flow can NOT be ed. THEN refer to

. REACTOR MAKEUP ALFUNCTION.

align valves and verify I.

I EOP:

TITLE:

FR-S.1 RESPONSE TO REACTOR RESTART/

REV: 16 PAGE 5 of 13 5 Check PRZR PORV Status:

a. RCS pressure - LESS THAN 2335 PSIG

b. Check PORVs - BOTH CLOSED I.

I -

RESPONSET Ifj

a. Verify P valves o PRZR POR necessar less tha

b. IF PRZR 2335 psi PORVs.

IF any Pi THEN man valve.

be close locally ZR PORVs and block en.

IF NOT. THEN open s and block valves as until PRZR pressure 2335 psig.

ressure less than

, THEN manually close RV can NOT be closed.

ally close its block F block valve can NOT

, THEN dispatch AO to heck breaker.

. MOV-511, MCC D position 6C

MOV-51*. MCC C position 6C 6 Verify CNMT Ventilation Isolation

a. CVI annunciator - LIT

Annunciator A-25. CNMT VENTILATION ISOLATION

b. Verify CVI valve status lights -

BRIGHT

a. Momentar particul actuate

b. Manually required IF valve closed b, dispatch valves (

ATTACHME isolatio ly deenergize CNMT te monitor. R-l1. to VI.

close CVI valves as can NOT be verified MCB indication. THEN AO to locally close efer to ATT-3.0.

IT CI/CVI for alternate valves).

or,

i RESPONSE TO REACTOR RESTART/AkWS REV: 16 PAGE 6 of 13

+/-

STEP ACTION/EXPECTED

RESPONSE

RESPONSE INOT OBTAINEDI 7 Check If The Following Trips Have Occurred:

a. Reactor trip

a. Dispatch reactor:

o Trip]

13 an AO to locally trip

[G set breakers at bus

bus 15.

-OR-eactor trip breakers

-Y.

AO to locally trip sing manual trip lever nd of HP turbine.

o Open local

b. Dispatch turbine on west

b. Turbine trip

8 Check If Reactor Is Subcritical:

a. Energize MCC A AND B

b. Check power range channels -

LESS THAN 5%

c. Check Intermediate range channels o Startup rate - NEGATIVE

-OR-o Intermediate range channels -

DECREASING

d. Go to Step 18.

b. Go to Sp 9.

c. Go to Sttp 9.

K>1-

EOP:

TITLE:l E:1l REV: 1 6 FR-S.1 RESPONSE TO REACTOR RESTART/A WS PAGE 7 of 13 a*-

a * *

a * -

a a -a

-a a

a CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTER]

AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNj PUMPS).

)T OBTAINED a

a a

ATE WATER SOURCES FOR TE WATER SUPPLY TO AFW i

A * * * *

A a a a

ala a a a

9 Monitor S/G Level:

a. Narrow range level in at least one SIG - GREATER THAN 5% [25%

adverse CNMT]

a. Perform lhe following:

1) Verif total feed flow great r than 400 gpm.

IF NO' pumps necesi IF AF1 estabJ SAFW ATTACI

2) Maint, great(

narroi than at le,

. THEN manually start and align valves as ary.

can NOT be ished, THEN establish (Refer to ATT-5.1.

KENT SAFW) in total feed flow r than 400 gpm until range level greater

% [25% adverse CNMT] in st one SG.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

4

I RESPONSE TO REACTOR RESTART/AWS REV: 16 PAGE 8 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE N I

)T OBTAINED 10 Verify Dilution Paths -

ISOLATED

a. Place RMW mode switch to BORATE

b. Stop RMW pumps 11 Stabilize RCS Temperature:

a. Control steam dump as necessary

b. Verify the following:

o Core exit T/Cs - STABLE OR 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

b. Perform 1

1) Close

2) Direci pump I

RMW

RMW

b. IF RCS cc controll MSIVs an(

he following:

RMW to blender (AOV-1:

AO to locally open RI reaker Pump A. MCC C Pos 13B Pump B. MCC D Pos 1B 11) qW oldown can NOT be

d. THEN close both go to Step 12.

4.

RESPONSE TO REACTOR RESTART/AlIWS REV: 16 PAGE 9 of 13 12 Verify MFW Isolation:

3T OBTAINED

a. MFW pumps - TRIPPED

a. Manually discharg pumps.

close MFW pump valves and trip MFW

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:

o Any S/G Pressure - DECREASING IN AN UNCONTROLLED MANNER

-OR-o Any S/G Pressure - LESS THAN 110 PSIG Go to Step 16.

.4

I EOP:

BIlLE:

FR-S.1 RESPONSE TO REACTOR RESTART/A REV: 16 PAGE 10 of 13 STEP ACTION/EXPETEDRESPNSERESPONSE N 4

4 4

CAUTION

)T OBTAINED

4 4

4 0

4 4

0

4 0

o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR CS COOLDOWN.

o IF BOTH S/GS ARE FAULTED. AT LEAST 50 TO EACH SG.

GPM FEED FLOW ISHOULD BE MAINTAINED 4

a 14 Isolate Feed Flow S/G:

o Close faulted S/G discharge valve To Faulted MDAFW pump Manually cl se valves.

IF valves c4 dispatch AO flowpaths a, n NOT be closed. THEN to locally isolate necessary.

S/G A. MOV-4007

S/G B. MOV-4008 o Pull stop faulted S/G MDAFW pump o Close faulted S/G control valve TDAFW flow

. 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

RESPONSE TO REACTOR RESTART/

REV: 16 PAGE 11 of 13 STEP ACTION/EXPECTED RESPONSE

RESPONSE

I4 NOT OBTAINED 4

4 4

T CAUTION 4

4 IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW.

SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S G.

THEN STEAM 4

4 4

i

14 4

4 15 Isolate Steam Flow From Faulted S/G:

o Verify faulted SG ARV -

CLOSED

S/G A. AOV-3411

S/G B. AOV-3410 Manually cl se valves.

IF valves c dispatch AO flowpaths a in NOT be closed. THEN to locally isolate necessary.

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)

RESPONSE TO REACTOR RESTART/ATWS REV: 16 PAGE 12 of 13 STEP ACTION/EXPECTEDCRESPONSE RESPONSE 1 I.

OT OBTAINED 16 Check Core Exit T/Cs -

LESS IF core exi THAN 12000 F than 1200°F to SACRG-1.

ROOM GUIDEL step 1.

NOTE: Adverse CNMT conditions or loss of forced air co failure of NIS detectors.

17 Verify Reactor Subcritical:

o Power range channels - LESS THAN 5%

o Intermediate range channels -

STABLE OR DECREASING o Intermediate range channels startup rate - NEGATIVE o Core exit T/Cs - STABLE Perform the

a. Stabiliz

b. Continue

c. Perform procedur NOT cool positive

d. Direct R for boro

e. Verify b greater IF adequate verified, T IF NOT. THE

a. Allow RC

b. Perform procedur NOT cool positive

c. Return t t temperatures greater and increasing. THEN go SEVERE ACCIDENT CONTROL

[NE INITIAL RESPONSE.

ling may result in following:

RCS temperature.

to inject boric acid.

ctions of other FR s in effect which do own or otherwise add reactivity to the core.

to sample RCS and PRZR concentration.

ron concentration han FIG-2.0. FIGURE SDM.

shutdown margin EN go to Step 18.

perform the following:

to heat up.

ctions of other FR s in effect which do own or otherwise add reactivity to the core.

Step 4.

1

EOP:

TITLE:

REV: 1 6 FR-S.1 RESPONSE TO REACTOR RESTART/Arws PAGE 13 of 13 iL i-BORATION ACTIONS.

ACTION/EXPECTED RESPONSE

RESPONSE

/EXOBTED

A

A a

CAUTION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN K

*Ga aUaIa a a a a a RGIN DURING SUBSEQUENT 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

a.

Pull stop any D/G that is NOT suppliec cooling, AND immediately depress assoc SHUTDOWN pushbutton.

the following:

by alternate iated VOLTAGE

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 high CNMT pressure.

B. ENTRY CONDITIONS/SYMPTOMS

1.

ENTRY CONDITIONS -

This procedure is

a. F-0.5, CONTAINMENT Critical Safet, Tree, on a RED or ORANGE conditio to respond to a ntered from:

Function Status

RESPONSE TO HIGH CONTAINMENT PRE REV: 8 PAGE 3 of 7 OTE:

ACTION/EXPECTEDs e oRESPONSE id NOTE: FOLDOUT Page should be open and monitored period

)T OBTAINED 1 Verify All CI And CVI Valve Status Lights -

BRIGHT IF flow pat manually cl IF valves c closed by M dispatch AO valves. (Re ATTACHMENT cally.

NOT required. THEN ise CI and CVI valves.

in NOT be verified B indication. THEN to locally close er to ATT-3.0.

I/CVI).

REV: 8 RESPONSE TO HIGH CONTAINMENT PRESURE PAGE 4 of 7 4 *

4

4 * *

CAUTION

)T OBTAINED 4

4,

4.

4 4

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 CNMT spray pumps - OPEN

a. IF in RH]

THEN per

MOV-896A

MOV-896B

1) Opera spray ES-1.:

RECIR recirculation mode.

orm the following:

e SI pumps and one CNMT pump as directed. in

. TRANSFER TO COLD LEG ULATION. Step 14.

2) Go toiStep 3.

b. Verify CNMT spray pumps - RUNNING

c. Verify NaOH flow (FI-930)

d. Verify CNMT spray pump discharge valves - OPEN

b. Manuallyistart pumps.

c. IF NaOH place sw outlet v4

AOV-83

AOV-83 low NOT indicated. THEN tches for NaOH tank lves to OPEN.

A B

d. Ensure at least one in each set open.

MOV-860A

MOV-860B

MOV-860C

MOV-860D

MOV-86 A or MOV-860B

MOV-86 C or MOV-860D d.

I RESPONSE TO HIGH CONTAINMENT PRE REV: 8 PAGE 5 of 7 3 Verify CNMT RECIRC Fans Running:

)T OBTAINED

a. All fans - RUNNING

b. Charcoal filter dampers green status lights - EXTINGUISHED

a. Manually Istart fans.

b. Dispatch with rel open daml relay pl personnel to relay room y rack key to locally ers by pushing in trip 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 RESPONSE TO HIGH CONTAINMENT PRE REV: 8 PAGE 6 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE l'

4.

)T OBTAINEDI

.~~~~~~~~~~~~

4 CAU' o AT LEAST ONE SIG SHALL BE MAINTAIN o IF BOTH SGS ARE FAULTED. THEN AT MAINTAINED TO EACH SG.

5 Check If S/G Secondary Side Is Intact:

o Pressure in both S/Gs - STABLE OR INCREASING o Pressure in both SGs - GREATER THAN 110 PSIG TION ED AVAILABLE FOR LEAST 50 GPM FEED

'CS COOLDOWN.

FLOW SHOULD BE a

a

1*

Isolate fee

a. Ensure f discharg

S/G A.

SG B.

b. Ensure f control

SG A.

SG B.

c. Depress faulted and bypa valves c

SG A.

SG B.

d. Ensure M closed.

IF valves c dispatch AO as necessar I flow to faulted SG:

ulted S/G MDAFW pump valve closed.

MOV-4007 MOV-4008 ulted SG TDAFW flow alve closed.

AOV-4297 AOV-4298 IANUAL pushbuttons for

/G MFW regulating valve

's valve AND ensure osed.

HCV-466 and HCV-480 HCV-476 and HCV-481 W pump discharge valves n NOT be closed. THEN.

to locally close valves to isolate flow.

.4

6 Return To Procedure And Step In Effect

-END-

RESPONSE TO HIGH CONTAINMENT PRESSURE REV: 8 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 l

REV: 8 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

a.

Pull stop any DG that is NOT supplied cooling, AND immediately depress assoc SHUTDOWN pushbutton.

b.

Refer to ATT-2.4, ATTACHMENT NO SW PUN the following:

by alternate jated VOLTAGE

?S.

ML032950083

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