ML17311A047

Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr

ML17311A047
Person / Time
Site:	Ginna
Issue date:	05/22/1997
From:	Widay J ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PROC-970522, NUDOCS 9706040174
Download: ML17311A047 (89)

Text

CATEGORY 1

-REGULATO INFORMATION DISTRIBUTION ,~TEM (RIDS)

ACCESSION NBR:9706040174 DOC.DATE: 97/05/22 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant,. Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION WIDAY,J.A. Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFII IATION PM . 5'/N/gI /

SUBJECT:

Revised EOPs,including procedures index,rev 5 to ATT-15.0, rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & rev 9 to ECA-0.2.W/970522 ltr.

DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:Inadequate Core Cooling (Item II.F.2) GL 82-28 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL .. ID CODE/NAME LTTR ENCL 0 PD1-1 PD 1 1 VISSINGFG. 1 1 INTERNAL. Ol 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SRXB 1 '1 RES DE 1 1 RES/DET/EIB 1 1 RES/DSIR/RPSB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10

Laat 0\laa Ilrw IIIlIII]Pl rZZrZ EF/ Il lrllIZild ROCHESTER GASAND ELECTRIC CORPORATION o 89EASTA VENUE, ROCHESTER, N.Y. 14649<001 JOSEPH A. WIDAY TELEPHONE Plant Manager AREA CODE 7t6 546-2700 Glnna Nuclear Pkrnt May 22, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate l-1 Washington, D.C. 20555

Subject:

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

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, se h A. Wid JAW/jdw XC: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector 9706040174 970522 PDR ADOCK 05000244 PDR enclosure(s):

@OD ATT Index AP-ELEC.3, Rev. -3 AP Index ECA-0.1, Rev. 13 ECA Index6 3 0 ~ ~ ECA-0.2, Rev. 9 ATT-15.0, Rev. 5 ATT-15.2, Rev. 3 llllllllllllllllllll[IIIIIII)llllll

0 REPORT NO. 01 REPORT: NPSP0200 GINNA NUCLEAR POWER PLANT PROCEDURES INDEX 03/24/97 PAGE: 30 DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PRAR PRATI'RFR 5 YEARS ONLY:

PROCEDURE EFFECT NEXT NUMBER PROCEDURE TITLE DATE RBVIEW ST ATT-1.0 ATTACHMENT AT POWER CCW ALIGNME 001 0 I/26/94 02/19/93 02/19/98 BF ATT-2.0 ATTACHMENT AUX BLDG SW 003 07/26/94 04/21/93 04/21/98 EF A -2.1 ATTACHMENT MIN SW 003 03/24/9I 03/26/93 03/26/98 EF ATT-2.2 ATTACHMENT SW ISOLATION 003 07/26/94 07/29/93 01/29/9 EF ATI'.3 ATTACHMENT SW LOADS IN CNMT 003 01/25/95 01/25/95 01 5/00 EF ATT-3.0 ATTA NT CI/CVI 003 '07/26/94 02/11/9 02/11/99 EF ATZ-3. 1 ATTACHMENT CLOSURB 002 07/26/94 0 11/94 02/11/99 EF ATT-4.0 ATTACHMENT CNNL'ECI FANS 003 07/26 4 06/17/93 06/17/98 EF ATT-5.0 ATTACHMENT COND TO S/G 004 /25/95 01/25/95 01/25/00 EF ATT-5.1 ATTACHMENT SAFW 09/26196 11/08/94 5 11/08/99 EF ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 002 10/26/95 03/04/94 03/04/99 EF ATT-6. 0 ATTACHMENT COND VACUUM 003 12/18/96 03/26/93 03/26/98'P ATT-7. 0 ATTACHMENT CR EVAC 002 12/18/96 03/26/93 03/26/98 EF ATT-8. 0 ATTACHMENT DC LOADS 003 07/26/94 01/26/94 01/26/99 EP ATT-8. 1 ATTACHMENT D/G STOP 11/03/95 02/19/93 02/19/98 EP ATT-8. 2 ATTACHMENT GEN DEGAS 005 02/11/94 07 94 02/11/99 EF ATT-8.3 ATTACHMENT NONVITAL 003 07/26/94 02 93 02/19/98 EF ATT-8. 4 ATTACHMENT SI/UV 003 07/26/94 02/19/93 0 98 EF ATT-9. 0 ATTACHMENT L WN 005 07/26/94 01/26/94 01/26/99 EF ATT-9. 1 ATTA EXCESS L/D 002 07/26/94 02/03/93 02/03/98 EP ATT 10.0 ACHMENT FAULTED S/G 005 10/03/96 06/11/93 06/11/98 EF ATT-11.0 ATTACHMENT IA CONCERNS 001 01/26/94 07/02/93 07/02/98 EP ATZ-11.1 ATTACHMENT IA SUPPLY 001 07/26/94 07/02/93 07/02/98 EF ATT-12,0 ATTACHMENT N2 PORVS 003 03/24/97 02/03/93 02/03/98 EF

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REPORT NO. 01 GINNA NUCLEAR POWER PLANT 03/24/97 PAGE: 31 REPORT:'NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT BOP ATTACHMENTS PARAMETERS: DOC TYPES - PRAR . PRATT PRFR 5 YEARS ONLY:

PROCEDURB EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-13.0 ATTACHMENT NC 002 07/26/94 02/03/93 02/03/98 EF ATT-14.0 ATTACHMENT NORMAL RHR COOLING 001. 07/26/94 10/19/94 10/19/99 Ef ATI'-14. 1 ATTACHMENT RHR COOL 003 07/26/94 03/06/93 03/06/98 EF ATI'-14.2 ATTACHMENT RHR ISOL 001 07/26/94 03/06/93 03/06/98 EP ATT-14.3 ATTACHMENT RHR NPSH 001 07/26/94 01/26/94 01/26/99 EP ATT-14.4 ATTACHMENT RHR SAMPLE 001 07/26/94 01/26/94 01/26/99 EF ATT 14.5 ATTACHMENT RHR SYSTEM 002 07/26/94 02/03/93 02/03/98 EF ATT-14. 6 ATTACHMENT RHR PRESS REDUCTION 000 04/07/94 04/07/94 04/07/99 EF ATT-15. 0 ATTACHMENT RCP START 004 04/20/95 04/20/95 04/20/00 EF ATT-15. 1 ATTACHMENT RCP DIAGNOSTICS 002 09/26/96 02/19/93 02/19/98 EF ATT-15. 2 ATTACHMENT SEAL COOLING 002 07/26/94 02/03/93 02/03/98 EF ATT-16. 0 AT1'ACHMENT RUPTURED S/G 006 10/03/96 11/08/94 11/08/99 EF ATT 17.0 ATTACHMENT SD-1 006 11/03/95 02/03/95 02/03/00 Ef ATT-17. 1 ATTACHMENT SD-2 005 09/26/96 01/26/94 01/26'/99 Ef ATT-18.0 ATTACHMENT SPP - RWST 003 07/26/94 02/19/93 02/19/98 Ef ATT-19.0 ATTACHMENT SI FLUSH 01/25/95 ATT-20.0 ATTACHMENT VENT TIME 003 07/26/94 02/19/93 02/19/98 EF ATT-21.0 ATTACHMENT RCS ISOLATION 001 07/26/94 02/03/93 02/03/98 EF ATT-22.0 ATTACHMENT RESTORING fEED PLOW. 000 03/24/97 03/24/97 03/24/02 EF TOTAL FOR PRATT 43

REPORT NO. 01 GINHA NUCLEAR POWER PLANT 05/31/96 PAGE: 1 REPORT: HPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORNAL PROCEDURE PARANETERS: DOC TYPES - PRAP STATUS: 5 YEARS OHLY.:

PROCEDURE EFFECT LASI'EXT HUHBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCM.1 LEAKAGE INTO THE COHPONEHT COOLING LOOP 011 02/24/96 04/20/95 04/20/00 EF AP-CCW.2 LOSS OF CCM DURING POWER OPERATION 012 02/24/96 08/30/94 08/30/99 EF AP-CCM.3 LOSS OF CCM - PLANI'HUTDOWN 010 03/29/96 08/30/94 08/30/99 EF AP-CR.1 CONTROL ROON INACCESSIBILITY 013 11/17/94 11/17/94 11/17/99 EF AP-CVCS.1 CVCS LEAK 010 02/24/96 04/20/95 04/20/00 EF AP-CVCS.2 DELETED XX 04/21/93 DE AP-CM.'I LOSS OF A CIRC WATER PUHP 005 03/13/96 04/21/93 04/21/98 QU AP-ELEC.1 LOSS OF 12A AHD/OR 12B BUSSES 012 02/24/96 03/21/95 03/21/00 EF AP-ELEC.2 SAFEGUARD BUSSES LOM VOLTAGE OR SYSTEH LOM FREQUEHCY 007 02/11/94 02/11/94 02/11/99 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRAHSFORNER (BELOW 350 F) 002 02/24/96 ~ 03/06/93 03/06/98 EF AP-FM.1 PARTIAL OR COHPLETE LOSS OF IIAIH FEEDMATER 009 04/21/93 04/21/93 04/21/98 EF AP- IA.1 LOSS OF INSTRUNEHT AIR 011 10/26/95 09/09/94 09/09/99 EF AP-PRZR.1 ABNORNAL PRESSURIZER PRESSURE 008 02/24/96 09/29/94 09/29/99 EF AP-RCC.1 CONTINUOUS CONTROL ROD MITNDRA'WAL/INSERTION 006 02/24/96 06/04/93 06/04/98 EF AP-RCC.2 RCC/RPI HALFUHCTION 006 02/24/96 04/23/93 04/23/98 EF AP-RCC.3 DROPPED ROO RECOVERY 001 02/24/96 04/23/93 04/23/98 EF AP-RCP.1 RCP SEAI. IIALFUNCTION 010 05/31/96 04/20/95 04/20/00 EF AP-RCS.1 REACTOR COOLANT LEAK 010 02/24/96 04/20/95 04/20/00 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 007 06/09/94 10/08/93 10/08/98 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 006 04/23/93 04/23/93 04/23/98 EF AP-RCS.4 SHUTDOWN LOCA 004 04/20/95 04/20/95 04/20/00 EF AP-RNR.1 LOSS OF RHR 010 03/29/96 03/06/93 03/06/98 EF AP-RHR.2 LOSS OF RNR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 006 03/21/95 03/21/95 03/21/00 EF AP-SW.1- SERVICE MATER LEAK 010 02/24/96 07/29/93 07/29/98 EF

1 REPORT NO. 01 GINNA NUCLEAR POWER PLANT 05/31/96 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARANETERS: DOC TYPES - PRAP STATUS: 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUHBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 007 05/07/93 05/07/93 05/07/98 EF AP-TURB.2 TURBINE LOAD REJECTIOH 014 02/24/96 06/04/93 06/04/98 EF AP-TURB.3 TURB I HE V I BRAT ION 006 03/26/93 03/26/93 03/26/98 EF AP-TURB.4 LOSS OF CONDEHSER VACUUII 010 04/27/95 03/26/93 03/26/98 EF AP-TURB.S RAPID LOAD REDUCTION 001 09/14/95 07/10/95 07/10/00 EF TOTAL FOR PRAP 29

REPORT NO. 01 GIHNA NUCLEAR POWER PLANT 01/25/95 08:50 PAGE 3 REPORT NAME: DOC P001 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PRAP PRATT PRE PRECA PRER STATUS: 5 YEARS ONLY:

PROCEDURE PROCEDURE TITLE REV EFFECT LAST NEXT ST NUMBER DATE REVIE'W REVIEW ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 001 07/26/94 02/19/93 08/19/95 EF ATT-2.0 ATTACHMENT AUX BLDG SW 003 07/26/94 04/21/93 10/21/95 EF ATT-2.1 ATTACHMENT MIN SW 001 07/26/94 03/26/93 09/26/95 EF ATT-2.2 ATTACHMENT SW ISOLATION 003 07/26/94 07/29/93 01/29/96 EF ATT-2.3 ATTACHMENT SW LOADS IN CNMT 003 01/25/95 01/25/95 07/25/97 EF ATT-3.0 ATTACHMENT CI/CVI 003 07/26/94 02/11/94 08/11/96 EF ATT-3.'I ATTACHMENT CHMT CLOSURE 002 07/26/94 02/11/94 08/11/96 EF ATT-4.0 ATTACHMENT CHMT RECIRC FANS 003 07/26/94 06/17/93 12/17/95 EF ATT-5.0 ATTACHMENT COHO TO S/G 004 01/25/95 01/25/95 07/25/97 EF ATT-5.1 ATTACHMENT SAFW 004 11/08/94 11/08/94 05/08/97 EF ATT-5.2 ATTACHMENI'IRE WATER COOLING TO TDAFW PUHP 001 07/26/94 03/04/94 09/04/96 EF ATT-6.0 ATTACHMENT COHD VACUUM 001 07/26/94 03/26/93 09/26/95 EF ATT-7.0 ATTACHMENT CR EVAC 001 07/26/94 03/26/93 09/26/95 EF ATT-8.0 All'ACKMENT DC LOADS 003 07/26/94 01/26/94 07/26/96 EF ATT-8.1 ATTACHMENT 0/G STOP 003 07/26/94 02/19/93 08/19/95 EF ATT-8.2 ATTACHMENT GEN DEGAS 005 07/26/94 02/11/94 08/11/96 EF ATT-8.3 ATTACHMENT NONVITAL 003 07/26/94 02/19/93 08/19/95 EF ATT-8.4 ATTACHMENT SI/UV 003 07/26/94 02/19/93 08/19/95 EF ATT-9.0 ATTACHMENT LETDOWN 005 07/26/94 01/26/94 07/26/96 EF ATT-9.1 ATTACHMENT EXCESS L/D 002 07/26/94 02/03/93 08/03/95 EF ATT-10.0 ATTACHMENT FAULTED S/G 004 07/26/94 06/11/93 12/11/95 EF ATT-11.0 ATTACHMENT IA CONCERNS 001 07/26/94 07/02/93 01/02/96 EF ATT-11.1 ATTACHMENT IA SUPPLY 00'I 07/26/94 07/02/93 01/02/96 EF ATT-12.0 ATTACHMENT N2 PORVS 002 07/26/94 02/03/93 08/03/95 EF ATT 13.0 ATTACHMENT NC 002 07/26/94 02/03/93 08/03/95 EF

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/25/95 08:50 PAGE 4 REPORT NAME: DOC-P001 PROCEDURES INDEX OOC TYPE: PRAT'I EOP ATTACHMENTS PARAMETERS: OOC TYPES - PRAP PRATT PRE PRECA PRER STATUS: 5 YEARS ONLY:

PROCEDURE PROCEDURE TITLE REV EFFECT LAST NEXT ST NUMBER DATE REVIEW REVIEW ATT-14.0 ATTACHMENT NORMAL RHR COOLING 001 07/26/94 10/19/94 04/19/96 EF ATT-14.1 ATTACHHENT RHR COOL 003 07/26/94 03/06/93 09/06/95 EF ATI'-14.2 ATTACHMENT RHR ISOL 00'I 07/26/94 03/06/93 09/06/95 EF ATT-14.3 ATTACHMENT RHR HPSH 001 07/26/94 01/26/94 07/26/96 EF ATT-14.4 ATTACHMENT RHR SAMPLE 001 07/26/94 01/26/94 07/26/96 EF ATT-14.5 ATTACHMENT RHR SYSTEM 002 07/26/94 02/03/93 08/03/95 EF ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 000 04/07/94 04/07/94 10/07/96 EF ATT-15.0 ATTACKHENT RCP START 003 07/26/94 02/19/93 08/19/95 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 001 07/26/94 02/19/93 08/19/95 EF ATT-15.2 ATTACHMENT SEAL COOLING 002 07/26/94 02/03/93 08/03/95 EF ATT-16.0 ATTACHMENT RUPTURED S/G 005 11/08/94 11/08/94 05/08/97 EF ATT-17.0 ATTACHMENT SD-1 004 07/26/94 02/19/93 08/19/95 EF ATT-17.1 ATTACHMENT SD-2 004 07/26/94 01/26/94 07/26/96 EF ATT-18.0 ATTACHMENT SFP - RWST 003 07/26/94 02/19/93 08/19/95 EF ATT-19.0 ATTACHMENT SI FLUSH XX 01/25/95 DE ATT-20.0 ATTACHMENT VENT TIME 003 07/26/94 02/19/93 08/19/95 EF ATT-21.0 ATTACHMENT RCS ISOLATION 001 07/26/94 02/03/93 08/03/95 EF TOTAL FOR PRATT 42

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REPORT NO. 01 GINNA NUCLEAR POWER PLANT 05/31/96 PAGE: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRECA EMERGENCY CONTINGENCY ACTIONS PROC PARAMETERS: DOC TYPES - PRECA PRFR STATUS: 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ECA-O.O LOSS OF ALL AC POWER 017 04/20/95 04/20/95 04/20/00 EF ECA.0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT Sl REQUIRED 012 05/31/96 04/20/95 04/20/00 EF ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED 008 04/07/94 04/07/94 04/07/99 EF ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 010 04/20/95 04/20/95 04/20/00 EF ECA-1.2 LOCA OUTSIDE CONTAINMENT 003 02/09/95 02/09/95 02/09/00 EF ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS 012 05/31/96 04/2D/95 04/20/00 EF ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANI'-SUBCOOLED RECOVERY DESIRED 011 04/20/95 04/20/95 04/20/00 EF ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED 014 04/20/95 04/20/95 '04/20/00 EF ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 012 04/20/95 04/20/95 04/20/00 EF TOTAL FOR PRFR

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EOP: TITLE:

REV: 3 ATT-15.0 ATTACHMENT RCP START PAGE 1 of 1 Superintendent Date ) The following are prerequisites for starting an RCP:

A) o o

RCP RCP oil oil lift lift pump running (-2 minutes) pressure white light LIT B) In addition, the following conditions should be met prior to starting an RCP:

o Both PRZR spray valves closed DEMAND AT 04 o CCW in service to selected RCP(s) with flow and temperature alarms (A-7, A-15) extinguished.

o Selected RCP(s) seal inlet temperature LESS THAN 135'Z o Selected RCP(s) motor bearing temperatures LESS THAN 200'F (PPCS address is GD RCPS or use recorder, if selected) o Selected RCP(s) seal injection in service o Seal injection flow. GREATER THAN 6 GPM o Labyrinth seal D/P - GREATER THAN 15 INCHES OF WATER o Selected RCP(s) Nl seal D/P GREATER THAN 220 PSID o Selected RCP(s) oil levels:

o Level alarms (A-24, A-32) EXTINGUISHED o Level indicators ON SCALE o Selected RCP(s) seal return alignment:

a) RCP Nl seal outlet valve(s) open:

o AOV-270A for RCPA o AOV-270B for RCP B b) IF'OV-313, seal return isolation, open, THEN verify the following:

o VCT pressure GREATER THAN 15 PSIG o Selected RCP(s) Nl seal leakoff flow BETWEEN 0.25 GPM AND 5.5 GPM o Selected RCP(s) standpipe low level alarm (B-ll, B-12) EXTINGUISHED c) IF MOV-313 closed, THEN verify other RCP Nl seal parameters normal for selected RCP(s):

o RCP Nl seal inlet temperature LESS THAN 135'F o RCP gl seal D/P - GREATER THAN 220 PSID NOTE: RCP oil lift pump should be stopped after RCP is running.

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EOP: TI 'ALE:

REV 2 ATT-15.2 ATTACHMENT SEAL COOLING PAGE 1 of 2 Superintendent ~ Date 7 IF all RCP seal cooling has been lost, THEN CCW cooling should be restored before establishing seal injection.

A. Perform the following to restore CCW flow to RCPs:

1) IF RCP seal injection NOT in service, THEN verify RCP CCW return valves closed.

o MOV-759A, for RCP A o MOV-759B, for RCP B

2) Verify adequate power available to run one CCW pump (124 kw each pump). IF power available, THEN start one CCW pump.

3) Ensure MOV-817, CCW to CNMT OPEN

4) Open RCP CCW supply valves and thermal barrier return valves for affected RCP:

o MOV-749A and AOV-754A for RCP A o MOV-749B and AOV-754B for RCP B

5) Restore CCW flow to RCP(s) as follows:

a) IF RCP seal injection in service, THEN ensure RCP CCW return valve(s) open:

o MOV-759A for RCP A o MOV-759B for RCP B b) IF RCP seal injection NOT established, THEN perform the following:

1) Dispatch AO to locally crack open affected RCP CCW return valve(s):

o MOV-759A for RCP A o MOV-759B for RCP B

2) WHEN affected RCP Nl seal outlet temperature is LESS THAN 235'F, THEN manually open affected RCP CCW. Return MOV from control board.

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EOP: LITLE:

REV' ATT-15.2 ATTACHMENT SEAL COOLING PAGE 2 of 2 B. Perform the following to restore RCP seal injection:

1) Verify RCP 51 seal outlet temperatures LESS THAN 235'F.

IF NOT, THEN consult TSC prior to restoring seal injection.

2) Verify any charging pump running.

NOTE: RCP seal cooldown rate should not exceed 1'F/min.

3) Dispatch AO with an RWST area key to locally restore seal injection flow as follows:

a) Verify seal injection valves, V-300A and V-300B, closed.

b) Notify control room to monitor RCP gl seal outlet temperatures.

c) Crack open RCP seal injection needle valves, V-300A and V-300B, until minimum flow i.s established.

d) Adjust seal injection flow as directed by control room to maintain cooldown rate less than 1'F/min until normal seal injection flow is established.

EOP: TITLE:

REV 1 P-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'F) PAGE 1 of 20 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 2 of 20 A. PURPOSE This procedure provides actions to respond to a loss

'of 12A or 12B SS Transformer when RCS temperature is less than 350'F.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure may be entered from:

a. AP-ELEC.l, when busses 12A and/or 12B are found to be deenergized and RCS temperature is less than 350'F.

2. SYMPTOMS The symptoms of loss of 512A or 12B SS Transformer are:

a. Annunciator L-20, 12A XFMR OR 12A BUS TROUBLE, lit, or

b. Annunciator L-28, 12B XFMR OR 12B BUS TROUBLE, lit.

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EOP: TITLE:

REV 1 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW P-ELEC.3 350'F) PAGE 3 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o 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.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR, 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.

o ANYTIME EMERGENCY D/GS ARE THE ONLY SOURCE OF AC POWER TO THE PLANT, PERSONNEL SHOULD BE ASSIGNED TO MAINTAIN SURVEILLANCE OF THE D/GS.

o IF ANY RADIOACTIVE RELEASE IN PROGRESS, THEN IT SHOULD BE TERMINATED UNTIL SUPPORT CONDITIONS ARE EVALUATED.

• • • • • • • • • • 'x 0 0 *x x 4

4 x x %.** 0' x x  % **x x**********

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

1 Verify Emergency D/G IF appropriate emergency D/G(s) NOT Associated With Dead Bus running, THEN attempt to start RUNNING manually. (Refer to ER-D/G.l, RESTORATION OF A FAILED D/G.)

o Bus 12A - D/G A o Bus 12B - D/G B 2 Verify Both Trains Of AC Try to restore power to all AC Emergency Busses Energized To emergency busses. IF power can NOT At Least-420 VOLTS: be restored to at least one train, THEN refer to ECA-O.O, LOSS OF ALL o Bus 14 and bus 18 AC POWER.

o Bus 16 and bus 17

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EOP: TITLE:

LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 4 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: When restarting equipment for recovery, it is preferable to start equipment on busses being supplied from offsite power, if possible.

3 Verify Service Water System Operation:

a. SW pumps - AT LEAST ONE RUNNING a. Verify selected start SW pumps IN EACH LOOP on a timer (40 sec) after D/G start. IF NOT, THEN manually start pumps as conditions permit (258 kw each).

b. SW header pressure - GREATER b. Manually align valves as THAN 40 PSIG IN EACH LOOP necessary.

4 Check CCW Pump Status:

a. At least one CCW pump - RUNNING a. Start one CCW pump (124 kw).

b. Annunciator A-22, CCW PUMP b. Start second CCW pump (124 kw).

DISCHARGE LO PRESS 60 PSIG EXTINGUISHED

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EOP: TITLE:

LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 5 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check RCS Temper'atua'e STABLE IF RCS temperature increasing, THEN stabilize temperature using available method.

~ RHR normal cooling

~ Dump steam and feed

~ Blowdown and feed IF RCS temperature decreasing, THEN perform the following:

a. Stop dumping steam or control RHR normal cooling.

b. IF cooldown continues, THEN perform the following:

l) IF either MDAFW pump operable, THEN ensure TDAFW pump steam supply valves in PULL STOP.

2) WHEN S/G level greater than 5% in one S/G, THEN limit feed flow to that required to maintain S/G level.

14,) w ~ g E

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 6 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• • • • • • • x**x%'**x x% *x x**x********x*******

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

• • • • • • • • • • • • • • x x ** x **x ***x x **************

6 Restore Non-Safeguards Busses As Follows:

a. Verify non-safeguards busses a. Close non-safeguards bus tie ENERGIZED breaker for affected bus(ses) possible:

if

~ Bus 13

~ Bus 15 ~ Bus 13 to bus 14 tie

~ Bus 15 to bus 16 tie

b. Verify MCC A - ENERGIZED b. Perform the following:

1) Ensure the following pumps in PULL STOP:

~ EH pump A

~ Turning gear oil pump

~ HP seal oil backup pump

2) Close MCC A supply breaker from bus 13.

c. Verify MCC B - ENERGIZED c. Perform the following:

1) Ensure EH pump B in PULL STOP.

2) Close MCC B supply breaker from bus 15.

d. Check CNMT vent sample pump ~" d. IF CNMT purge or mini-purge in RUNNING progress, THEN secure purging.

e. Verify annunciator J-8, 480V MCC e. Restore power to other MCCs as SUPPLY BREAKER TRIP D/G loading permits.

EXTINGUISHED

~ MCC E

~ MCC F

~ MCC G

f. Reset control room necessary lighting if

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC.3 350'F) PAGE 7 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED t

7 Check IA System:

a. Verify 2 IA compressors - RUNNING a. Manually start IA compressors as necessary (75'w each).

b. Check IA supply b. Dispatch an AO to locally reset and start IA compressors (75 kw o Pressure - GREATER THAN each).

60 PSIG IF IA can NOT be established, o Pressure - STABLE OR THEN refer to AP-IA.1, LOSS OF INCREASING INSTRUMENT AIR.

8 Check RCS Cooling:

a. RHR system - PREVIOUSLY ALIGNED a. Go to Step 18.

FOR RHR NORMAL COOLING

b. Check RHR pumps - ANY RUNNING b. IF RHR normal cooling previously in service, THEN go to Step 9.

IF RHR normal cooling NOT required, THEN go to Step 18.

c. Go to Step 11

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC.3 350'F) PAGE 8 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish Conditions To Start RHR Pump:

a. Any RHR pump - AVAILABLE a. IF RCS level greater than 64 inches, THEN go -to AP-RHR.1, LOSS OF RHR. IF NOT, THEN go to AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.

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

in service

1) Ensure at least one CCW pump o CCW pumps - AT LEAST ONE running.

RUNNING

2) Open MOV-738A and MOV-738B as o CCW to RHR Hxs, MOV-738A AND necessary.

MOV-738B - OPEN AS NECESSARY IF CCW can NOT be restored, THEN

.continue attempts to restore CCW (Refer to AP-CCW.3, LOSS OF CCW PLANT SHUTDOWN).

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

K'ic V(

I

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REV' LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW P-ELEC.3 350'F) PAGE 9 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• • • • • • • x ***x ** x

• P x ***

CAUTION 0 0 x x *************** A o STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL OR PRESSURE DECREASE DUE TO SHRINK OR VOID COLLAPSE.

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

• • x ***x ** x x x x

• x x x

• x

• x '* x x x ********x ****x **

10 Restore RHR Flow:

a. Start one RHR pump

b. At least one RHR pump - RUNNING b. Go to Step 10d.

c. Establish RHR flow - WITHIN c. Manually adjust RHR flow as LIMITS OF TABLE BELOW necessary.

RCS STATUS MAXIMUM RHR FLOW RCS LEVEL - ANY 3000 gpm LEVEL ABOVE 18" RCS LEVEL < 18" 1000 GPM RCS LEVEL < 10" 800 GPM RCS LEVEL < 6" 500 GPM

d. RHR flow - RESTORED d. IF RCS level greater than 64 inches, THEN go to AP-RHR.1, LOSS OF RHR. IF NOT, THEN go to AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.

e. Place RHR Hx bypass valve, HCV-626, controller in AUTO at desired flowrate

f. Open RHR pump flow control valves as necessary to stabilize RCS temperature

~ HCV-624

~ HCV-625

g. Check core exit T/Cs - STABLE OR g. Start another RHR pump or DECREASING increase RHR flow to establish required RCS cooling. DO NOT exceed RHR flow limits from table above.

V I W U

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 10 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll Check AFW Pump Status:

a. AFW pumps - ANY RUNNING a. Go to Step 12.

I

b. Both S/G levels - AT DESIRED b. Continue with Step 12. WHEN LEVEL desired S/G levels established, THEN do Step llc.

c. Stop running AFW pumps and place switches in PULL STOP 12 Evaluate RCS Conditions:

a. Check RCS status: a. IF RCS is open to atmosphere, THEN go to Step 17.

o RCS - CLOSED o RCS pressure - GREATER THAN ATMOSPHERIC

b. Verify RCP ¹1 seal D/Ps b. IF any RCP running with ¹1 seal GREATER THAN 220 PSID D/P less than 220 psid, THEN stop affected RCP.

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC.3 350'F) PAGE 11 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 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 14. WHEN VCT level greater than 20%,

THEN do Step 13b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C open o LCV-112B closed 14 Check Charging Pumps ANY IF charging pumps required, THEN CHARGING PUMP RUNNING perform the following:

a. Verify charging to loop B cold leg, AOV-294, open.

b. Verify charging flow control valve, HCV-142, open as necessary.

c. IF desired, THEN place letdown pressure controller, PCV-135, in MANUAL.

d. Start one charging pump (75 kw each pump).

e. Increase charging pump speed and control PCV-135 as necessary to control PRZR pressure or level.

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC.3 350'F) PAGE 12 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Monitor RCS Pressure:

a. Pressure - LESS THAN 390 PSIG a. IF RCS is solid, THEN control charging and letdown pressure control valve (PCV-135) as necessary to stabilize RCS pressure.

IF PRZR bubble established, THEN operate normal or auxiliary spray to decrease pressure.

b. Pressure - STABLE b. Stabilize RCS pressure using appropriate means.

~ Charging

~ Letdown

~ PCV-135 (solid)

~ Normal spray

~ Auxiliary spray

~ PRZR heaters 16 Check PRZR Level:

a. Narrow range level - ON SCALE a. IF RCS is solid, THEN go to Step 17.

b. Level - TRENDING TO PROGRAM b. Adjust charging pump speed as necessary to control PRZR level.

17 Monitor RCS Temperature

a. Core exit T/Cs - STABLE OR a. Adjust RCS cooling as necessary DECREASING and return. to Step 3.

~ S/G steaming

~ S/G feeding

~ RHR cooling

b. Go to Step 26

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REV 1 P-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'F) PAGE 13 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check AFW System Status:

a. Verify TDAFW pump steam supply a. IF S/Gs providing heat sink, valves in PULL STOP THEN perform the following:

1) Verify adequate MDAFW flow.

2) Pull stop TDAFW pump.

3) Adjust AFW flow as necessary to stabilize S/G level and RCS temperature.

b. Verify MDAFW valves closed

pump crosstie b. Ensure at least one off. IF two pumps MDAFW pump required, THEN close both MDAFW pump crosstie valves.

17'tart

~ MOV-4000A

~ MOV-4000B 19 Check Any S/G Level GREATER MDAFW pumps as necessary to THAN restore S/G level.

20 Check RCS Pressure GREATER Increase RCS pressure to greater THAN 300 PSIG than 300 psig. IF RCP ¹1 seal D/P can NOT be maintained greater than 220 psid, THEN trip any running RCP.

21 Check RCP Status ANY RCP Verify natural circulation (Refer RUNNING to Attachment NC). IF natural circulation NOT verified, THEN increase dumping steam.

+11,

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC.3 350'F) PAGE 14 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Monitor RCS Temperature Control S/G ARVs to stabilize RCS STABLE OR DECREASING temperature. IF S/G ARVs do NOT provide adequate cooling, THEN perform the following:

a. Initiate S/G blowdown from both S/Gs.

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

23 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE a. Perform the following:

RUNNING

1) Start charging pumps as necessary.

2) Establish greater than 20 gpm charging line flow.

b. Check letdown indications: b. Perform the following:

o Check PRZR level - GREATER 1) Close loop B cold leg to THAN 13% REGEN Hx, AOV-427.

o Letdown flow - APPROXIMATELY 2) Close letdown orifice valves 40 GPM (AOV-200A, AOV-200B, and AOV-202) o Letdown flow - STABLE

3) IF PRZR level greater than 13%, THEN go to Step 24. IF NOT, THEN continue with Step 26. WHEN PRZR level greater than 13%, THEN do Steps 24 and 25.

c. Adjust charging pump speed and HCV-142 as necessary to level and labyrinth seal D/P restore'RZR

d. Go to Step 25

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REV: 1 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW P-ELEC.3 350'F) PAGE 15 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Steps 24 and 25 may be performed concurrently.

24 Establish Normal Letdown: Perform the following steps in sequence to establish excess

a. Establish charging line flow to letdown:

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert

b. Verify the following switches in valve, AOV-312, to NORMAL CLOSE:

o Ensure CCW from excess letdown

~ Letdown orifice valve open, AOV-745 (AOV-200A, AOV-200B, and AOV-202) o Ensure RCP seal return isolation

~ Loop B cold leg to REGEN Hx valve open, MOV-313 AOV-427 o Open excess letdown isolation

c. Place letdown controllers in valve, AOV-310 MANUAL at 40% open o Slowly open HCV-123 to maintain

~ TCV-130 excess letdown temperature less

~ PCV-135 than 195 'F and pressure less than 100 psig

d. Open AOV-427

e. Open letdown orifice valves as necessary

f. Place TCV-130 in AUTO at 105'F

g. Place PCV-135 in AUTO at 250 psig

h. Adjust charging pump speed and HCV-142 as necessary

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW= REV: 1 P-ELEC.3 350'F) PAGE 16 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Verify PRZR Heaters Restored: IF PRZR heaters required, THEN perform the following:

o PRZR proportional heater breaker CLOSED a. Verify adequate D/G capacity available for PRZR heaters (400 o PRZR backup heater breaker kw each bank).

RESET/IN AUTO

b. Reset and close PRZR proportional heater breaker if necessary.

c. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF on natural circulation and at least 100 kw of PRZR heaters can NOT be restored within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, THEN be on RHR within an additional 6 hours. (Refer to Technical Specification 3.1.1.5)

NOTE: Check Tech Spec section 3.7 for limiting conditions for operation.

26 Restore Normal Electric System Alignment:

a. Verify circuit 767 and/or 751 a. Continue with Step 28. WHEN AVAILABLE offsite power available, THEN do Steps 26b, c, d and 27.

b. Restore. power to 12A and/or 12B bus (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER)

c. Verify all emergency AC bus c. Restore emergency AC busses to normal feed breakers - CLOSED normal power supply (Refer to ER-ELEC.1, RESTORATION OF

~ Bus 14 OFFSITE POWER)

~ Bus 16

~ Bus 17

~ Bus 18

d. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)

~ ~

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC. 3 350'F) PAGE 17 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check Started:

lf An RCP Should Be

a. Check the following: a. Go to Step 28.

o Both RCPs - OFF o RCP operation - DESIRED

b. RCS pressure - APPROXIMATELY b. Control PRZR heaters and/or 325 PSIG charging pump speed as necessary to restore RCS pressure.

c. Check PRZR level - LESS THAN 38% c. Verify S/G temperature (obtained locally in CNMT at S/G handhole) less than RCS cold leg temperature. IF NOT, THEN go to Step 28.

d. Try to start an RCP d. IF an RCP can NOT be started, THEN continue to monitor natural

1) Establish conditions for circulation conditions (Refer to starting an RCP Attachment NC).

a) Bus 11A or 11B energized b) Refer to Attachment RCP START

2) Start one RCP 28 Check RCS Temperature Adjust RCS cooling as necessary.

STABLE OR DECREASING

~ S/G steaming

~ S/G feeding

~ RHR cooling

~ % ~

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV 1 P-ELEC.3 350'F) PAGE 18 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Establish Normal Shutdown Alignment:

a. Verify turning gear oil pump a. IF turbine oil system operation RUNNING required, THEN perform the following:

1) Manually start turning gear oil pump (42 kw).

2) Dispatch AO to place turbine on turning gear if desired.

b. Verify main generator b. Perform the following:

DEPRESSURIZED

1) Manually start the HP seal oil backup pump

2) Dispatch AO to locally perform the following:

o Verify proper operation of the seal oil system (Refer to T-34B, GENERATOR SEAL OIL SYSTEM NORMAL OPERATION).

o Ensure bearing drain vapor extractor running.

o Ensure main lube oil reservoir vapor extractor running.

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

THAN 135'F

1) Ensure one Rx compartment cooling fan running (23 kw) .

2) Ensure one control rod shroud fan running (45 kw).

d. Dispatch AO to start waste gas compressor as necessary

kit< I 7t C

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 19 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Restore Equipment Alignment:

a. Verify at least 1 CNMT recirc a. Start CNMT recirc fans as fan - RUNNING necessary'(240 kw each).

b. Check radiation monitoring, b. Perform the following:

systems:

1) Restore sample pumps and o CNMT vent sample pump radiation monitors as RUNNING necessary.

o Plant vent sample 2) Restart or ifpurge pump CNMT RUNNING mini-purge desired.

o All area and process monitors operating as required

c. Verify annunciator L-l, AUX BLDG c. IF bus 11A or 11B energized, VENT SYSTEM CONTROL PANEL THEN dispatch AO to restore AUX EXTINGUISHED BLDG ventillation (Refer to T-35A, AUX AND INTERMEDIATE BUILDING VENTILLATION STARTUP AND SHUTDOWN)

d. Verify service air compressor .- d. Dispatch AO to locally start RUNNING service desired.

air compressor if

e. Verify motor fire pump breaker e. Close motor fire pump breaker.

CLOSED

f. Check control board annunciator f. Perform alarm response panels - ALARM STATUS VALID FOR procedures for unexpected alarms.

PLANT CONDITIONS

g. Verify control board valve g. Manually align valves as alignment - NORMAL (Refer to necessary.

0-6.13, DAILY SURVEILLANCE LOG)

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 20 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check Status Of DC System Loads:

a. Verify emergency DC lube oil a. Manually stop emergency DC lube pump - OFF oil pump.

b. Verify TDAFW pump DG oil pump b. Perform the following:

OFF

1) Ensure TDAFW AC oil pump running.

2) Stop TDAFW pump DC oil pump.

c. Verify both MFW pump DC oil c. Stop MFW pump DC oil pumps.

pumps - OFF 32 Verify Offsite Power Continue attempts to restore RESTORED offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

33 Notify Higher Supervision NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

34 Return To Procedure Or Guidance In Effect

-END-

/

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV: 1 P-ELEC.3 350'F) PAGE 1 of 1 AP-ELEC.3 APPENDIX LIST TITLE PAGES

1) FIGURE MIN SUBCOOLING

2) ATTACHMENT RCP START

3) ATTACHMENT NC

4) ATTACHMENT D/G STOP

<<Y

~ vari Ef

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LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW REV' P-ELECT 3 350'F) PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 2300 RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADE(UATE SUBCOOLING 600 REGION ADVERS E CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE 100 INCREMENTS 10'F n

0 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

i' EOP: TITLE:

REV 12 ECA-0 1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED PAGE 1 of 20 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER G

RESP NSIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: '!TLE: REV: 12 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED of 20 PAGE 2 A. PURPOSE - This procedure provides actions to use normal operational systems to stabilize plant conditions following restoration of AC emergency power.

B. ENTRY CONDITIONS/SYMPTOMS

l. ENTRY CONDITIONS This procedure is entered from:

a. ECA-O.O, LOSS OF ALL AC POWER, when AC emergency power is restored and SI is not required.

EOP: T1TLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0.1 REQUIRED PAGE 3 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF AN SI SIGNAL IS ACTUATED PRIOR TO PERFORMING STEP 10 OF THIS PROCEDURE, THEN SI SHOULD BE RESET TO PERMIT MANUAL LOADING OF EQUIPMENT ON AN AC EMERGENCY BUS.

NOTE: o CSFSTs should be monitored for information only. FR procedures should not be implemented prior to completion of Step 10.

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

1 Check RCP Seal Isolation Status:

a. RCP seal injection needle valves a. Dispatch AO with key to RWST CLOSED gate to locally close valves before starting charging pump.

~ V-300A

~ V-300B b, RCP CCW return valves - CLOSED b. IF valves open or position not known, THEN check CCW pump

~ MOV-759A status:

~ MOV-759B

1) IF pump running, THEN go to Step 2 ~

2) IF pump NOT running, THEN manually close valves.

IF valve(s) can NOT be closed, THEN place switches for RCP thermal barrier valves to CLOSE. CCW'utlet

~ AOV-754A

~ AOV-754B

I EOP: TITLE SI REV: 12 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT REQUIRED PAGE 4 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check CI Annunciator A-26, Per form the following:

CONTAINMENT ISOLATION EXTINGUISHED a. Depress CI reset pushbutton

b. Verify annunciator A-26, CONTAINMENT ISOLATION, extinguished.

EOP: TITLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0 ' REQUIRED PAGE 5 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 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

b. Check at least two SW pumps b. Manually start SW pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps running, THEN go to Step 4.

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

isolation valves - OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

d. Start at least two air d. IF air compressors can NOT be compressors (75 kw each) started, THEN dispatch AO to locally reset compressors as necessary.

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

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

o Pressure - STABLE OR INCREASING 2) Continue with Step 6. WHEN IA restored, THEN do Steps 3f through 5.

f. Reset both trains of XY relays for IA to CNMT (AOV-5392) if necessary

g. Verify IA to CNMT AOV-5392 - OPEN

EOP: , TlTLK:

REV 12 ECA-F 1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED PAGE 6 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.

4 Manually Load Following Equipment On AC Emergency Busses:

a. Start one CCW pump (124 kw) b..Energize MCCs as power supply permits

~ MCC A from Bus 13

~ MCC B from Bus 15

~ MCC E from Bus 15

~ MCC F from Bus 15

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

d. WHEN bus 15 restored, THEN reset control room lighting

e. Start at least one CNMT RECIRC fan

f. Restore Rx head cooling as power supply permits:

1) Start one Rx compartment '1) Perform the following:

cooling fan (23 kw each) o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits.

(23 kw)

2) Start both control rod shroud 2) Manually start at least one fans (45 kw each) fan (45 kw)

g. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)

EOP $ TITLE$

SI REV: 12 ECA-0 ' LOSS OF ALL AC POWER RECOVERY WITHOUT REQUIRED PAGE 7 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If Charging Flow Has Been Established:

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

1) Ensure seal injection needle valves to both RCPs isolated:

~ RCP A, V-300A

~ RCP B, V-300B

2) Ensure HCV-142 open, demand at Oa.

b. Charging pump suction aligned to b. Manually align valves as RWST' necessary.

o LCV-112B - OPEN IF LCV-112B can NOT be opened, THEN perform the following:

o LCV-112C - CLOSED

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

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

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

c. Start charging pumps (75 kw each) as necessary and adjust charging flow to restore PRZR level

EOP TITLE$

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0.1 REQUIRED PAGE 8 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• 6 Monitor SI Initiation Criteria:

a. RCS subcooling based on core a. Go to ECA-0.2, LOSS OF ALL AC exit T/Cs - GREATER THAN O' POWER RECOVERY WITH SI REQUIRED, USING FIGURE MIN SUBCOOLING Step l.

b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained, THEN go to ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step l.

7 Check PRZR Level GREATER Control charging flow as necessary.

THAN 134'404 FOR ADVERSE CONTAINMENT]

EOP: TITLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0.1 REQUIRED PAGE 9 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o 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).

o IF S/G NR LEVEL DECREASES TO LESS THAN 5% [25% ADVERSE CNMT] AND FEED FLOW IS LESS THAN 200 GPM, THEN THE MDAFW PUMPS SHOULD BE MANUALLY LOADED ON AC EMERGENCY BUS TO SUPPLY WATER TO THE S/G(S).

NOTE: o If MDAFW pump operation is not required, pump switches should be maintained in PULL-STOP to prevent automatic start.

o TDAFW pump flow control valves fail open on loss of IA.

• 8 Monitor Intact S/G Levels:

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

adverse CNMT] in at least one S/G.

IF feed flow less than 200 gpm, THEN perform the following:

1) Verify MDAFW pump discharge valves open.

~ MOV-4007

~ MOV-4008

2) Manually start MDAFW pumps as necessary (228 KW each)..

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

[25$ adverse CNMT] and 52%

EOP: T1TLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0. 1 REQUIRED PAGE 10 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish S/G Pressure Control:

a. Adjust S/G ARV controllers to maintain existing S/G pressure

b. Verify S/G ARV controllers in AUTO

c. Dispatch AO to perform Attachment SD-2 CAUTION IF AN SI SIGNAL IS ACTUATED AFTER THE SI PUMP SWITCHES ARE PLACED IN AUTO, THEN ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, SHOULD BE PERFORMED.

NOTE: Safeguards pump switches should be placed in AUTO only if associated bus is energized.

10 Place Following Pump Switches In AUTO:

~ SI pumps

~ RHR pumps

~ CNMT spray pumps

EOP: T1TLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0. 1 REQUIRED PAGE 11 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: FR procedures may now be implemented as necessary.

ll Verify CCW Hx:

Adequate SW Flow To

a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps can be operated, THEN go to Step 19.

b. Verify AUX BLDG SW isolation b. Establish SW to AUX BLDG (Refer valves - OPEN to Attachment AUX BLDG SW).

~ MOV-4615 and MOV-4734 Continue with Step 19. WHEN SW

~ MOV-4616 and MOV-4735 restored to AUX BLDG, THEN do Steps. 11c through 18.

c, Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE AIARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.

12 Check Operation If Normal Can Be CVCS Established

a. Verify IA restored: a. Continue with Step 19. WHEN IA restored, THEN do Steps 12 o IA to CNMT (AOV-5392) - OPEN through 18.

o IA pressure - GREATER THAN 60 PSIG

b. Charging pump - ANY RUNNING b. Continue with Step 19. WHEN any charging pump running, THEN do Steps 13 through 18.

EOP: TITLE 0 SI REV: 12 ECA-F 1 LOSS OF ALL AC POWER RECOVERY WITHOUT REQUIRED PAGE 12 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o RCP THERMAL BARRIER COOLING SHOULD BE ESTABLISHED SLOWLY TO MINIMIZE POTENTIAL INTRODUCTION OF STEAM INTO THE CCW SYSTEM AND THERMAL SHOCK TO RCP.

o RCP SEAL INJECTION SHOULD BE ESTABLISHED SLOWLY TO MINIMIZE RCP THERMAL STRESSES AND POTENTIAL SEAL FAILURES.

o AS PART OF SUBSEQUENT RECOVERY ACTIONS, RCP(S) SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION UNLESS REQUIRED BY AN INADEQUATE CORE COOLING SITUATION.

I NOTE: SW should be aligned to CCW Hxs before restoring RCP seal cooling.

13 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs:

o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection:

o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER

-OR-o RCP seal injection flov to each RCP - GREATER THAN 6 GPM

EOP; T!TLE:

SI REV: 12 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT REQUIRED PAGE 13 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If Seal Return Flow Should Be Established:

a. Verify RCP ¹1 seal outlet a. Go to Step 15.

temperature - LESS THAN 235'F

b. Verify RCP seal outlet valves- b. Manually open valves as OPEN necessary.

~ AOV-270A

~ AOV-270B

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

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

valve MOV-313

1) Place MOV-313 switch to OPEN.

'. 2) Dispatch AO with key to RWST gate to locally open MOV-313.

e. Verify RCP ¹1 seal leakoff flow Close the affected RCP seal LESS THAN 6.0 GPM discharge valve:

~ RCP A, AOV-270A

~ RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 15.

f. Verify RCP ¹1 seal leakoff flow. f. Refer to AP-RCP.1, RCP SEAL

-. GREATER THAN 0.8 GPM MALFUNCTION.

EOP! TlTLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0.1 REQUIRED PAGE 14 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Verify PRZR Level GREATER Continue with Step 19. WHEN PRZR THAN 134 [404 adverse CNMT] level increases to greater than 13%

[40% adverse CNMT], THEN do Steps 16 through 18.

16 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess

a. Establish charging line flow to letdown as follows:

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert

b. Pl'ace the following switches to valve, AOV-312, to NORMAL.

CLOSE' o Ensure CCW from excess letdown Letdown orifice valves open, (AOV-745).

(AOV-200A, AOV-200B, and AOV-202) o Open excess letdown isolation

~ AOV-371, letdown isolation valve AOV-310, valve

~ AOV-427, loop B cold leg to o Slowly open HCV-123 to maintain REGEN Hx excess letdown temperature less than 195'F and pressure less

c. Place letdown controllers in than 100 psig.

MANUAL at 40% open o Adjust charging pump speed as

~ TCV-130 necessary.

~ PCV-135 IF RCP seal return NOT established,

d. Reset both trains of XY relays THEN consult TSC to determine if for AOV-371 and AOV-427 if excess letdown should be placed service.

in necessary

e. Open AOV-371 and AOV-427

f. Open letdown orifice valves as necessary

g. Place TCV-130 in AUTO at 105'F

h. Place PCV-135 in AUTO at 250 psig

i. Adjust charging pump speed and HCV-142 as necessary

EOP: TITLE:

SI REV:

LOSS OF ALL AC POWER RECOVERY WITHOUT ECA-0. 1 REQUIRED 12"'AGE 15 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check VCT Makeup System:

a. Verify the following'. a. IF VCT auto makeup can NOT be established, THEN manually

1) Boric acid and RMW flow control VCT level, (Refer to control valves - SET FOR ER-CVCS.1, REACTOR MAKEUP REQUIRED CSD CONCENTRATION CONTROL MALFUNCTION).

(Refer to Figure SDM)

2) At least one BA and RMW pump in AUTO

3) RMW mode selector switch in AUTO

4) RMW control armed - RED LIGHT LIT

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

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- EHN pumps running. IF NOT, THEN dispetch AO tc reset o Level - STABLE OR INCREASING MCC C and MCC D UV lockouts as necessary.

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

3) Increase boric acid flow as necessary.

IF VCT level can NOT be restored, THEN go to Step 19.

EOP: TITLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0. 1 REQUIRED PAGE 16 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 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 19. WHEN VCT level greater than 40%,

THEN do Step 18b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C - OPEN o LCV-112B - CLOSED 19 Control PRZR Level:

a. Check letdown - IN SERVICE a. Stop and start charging pumps as necessary to control PRZR level.

b. Maintain PRZR level between 13%

[40% adverse CNMTj and 50%

EOP: TlTLF.:

REV 12 LOSS OP ALL AC POWER RECOVERY WITHOUT SI ECA-0. 1 REQUIRED PAGE 17 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If auxiliary spray is in use, spray flow may be increased by valves.

closing normal charging valve AOV-294 and normal PRZR spray o When using a PRZR PORV select one with an operable block valve.

20 Establish PRZR Pressure Control:

a. Check letdown - IN SERVICE a. Perform the following:

1) Use PRZR heaters and one PRZR PORV to maintain RCS pressure.

IF IA NOT available, THEN Refer to Attachment N2 PORVS to operate PORV.

2) Go to Step 21.

b. Use PRZR heaters and auxiliary spray valve (AOV-296) to maintain RCS pressure 21 Verify Natural Circulation: Increase dumping steam from intact S/Gs.

o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o S/G pressures - STABLE OR DECREASING o RCS hot leg temperatures STABLE OR DECREASING o Core exit T/Cs - STABLE OR DECREASING o RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR S/G PRESSURE

EOP,: TLTLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0 1 REQUIRED PAGE 18 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

'OTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

22 Check If Source Detectors Should Range Be Energized:

a. Source range channels  ; a. Go to Step 22e.

DEENERGIZED

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

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

2) Continue with Step 23. WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 22c through e.

c. Check the following: c. Continue with Step 23. WHEN either condition met, THEN do o Both intermediate range Steps 22d and e.

channels - LESS THAN 10 10 AMPS

-OR-o Greater than 20 minutes since reactor trip

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

IF source ranges can NOT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 23.

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

EOP: TITLE:

SI REV: 12 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT REQUIRED PAGE 19 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Verify Adequate Shutdown Margin:

a, Direct RP to sample RCS and PRZR liquid for boron concentration

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

'REATER THAN REQUIREMENTS OF FIGURE SDM 24 Maintain Stable Plant Conditions

a. RCS pressure - STABLE a. Control PRZR heaters and auxiliary spray if available.

b. RCS temperature - STABLE b. Control dumping steam as

. necessary.

c. PRZR level - BETWEEN 13% [40% c. Control charging as necessary.

adverse CNMT] and 50%

d. Intact S/G level - BETWEEN 17% d. Control S/G feed flow as

[25% adverse CNMT] and 52%  !

necessary.

• 25 Monitor SI Initiation Criteria:

a. RCS subcooling based on core a. Go to ECA-0.2, LOSS OF ALL AC exit T/Cs - GREATER THAN O' POWER RECOVERY WITH SI REQUIRED, USING FIGURE MIN SUBCOOLING Step l.

b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30$ adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained, THEN go to ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step l.

EOP: TITLE:

REV: 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0.1 REQUIRED PAGE 20 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Try To Restore Offsite Power Maintain. plant condition stable To All AC Busses (Refer to using AC emergency power.

ER-ELEC.1, RESTORATION OF OFFSITE POWER) 27 Determine Circulation IfCooldown Natural Is Required:

a. Consult plant staff to determine a. IF cooldown NOT required, THEN if RCS cooldown is necessary go to 0-3, HOT SHUTDOWN WITH XENON PRESENT.

b. At least one RCP - OPERABLE b. Go to ES-0.2, NATURAL CIRCULATION COOLDOWN ~

c. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN

-END-

EOP: TITLE:

SI REV: 12 ECA-0. 1 LOSS OF ALL AC POWER RECOVERY WITHOUT REQUIRED PAGE 1 of 1 ECA-0. 1 APPENDIX LIST TITLE PAGES

1) FIGURE MIN SUBCOOLING,

2) FIGURE SDM

3) ATTACHMENT SD-1

4) ATTACHMENT SD-2

5) ATTACHMENT N2 PORVS

6) ATTACHMENT SEAL COOLING

7) ATTACHMENT AUX BLDG SW

EOP: T1TLE:

REV: 12 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: .Subcooling Margin = Saturation Temperature From Figure Below t-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 ADVERSE CNMT REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ( F)

EOP: TlTLE:

REV 12 LOSS OF ALL AC POWER RECOVERY WITHOUT SI ECA-0.1 REQUIRED PAGE 1 of 1 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 (PPH) 1800 BORON INCREHENTS 20 PPH 1600 1400 ADEQUATE SDH 1200 100 PPH CONS ERVATISH INCLUDED 1000 800 600 400 BORATE BURNUP 200 INCREHENTS 200 HWD/HTU 2000 4000 6000 8000 '0000 12000 14000 16000 18000 CYCLE 26 BURNUP (HWD/HTU)