ML17311A040

Forwards Revised Emergency Operating Procedures for Plant

ML17311A040
Person / Time
Site:	Ginna
Issue date:	01/23/1997
From:	Widay J ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264A809	List: ML17264A808 ML17311A040
References
NUDOCS 9702030046
Download: ML17311A040 (14)

Text

CATEGORY 1 REGULAT(Q INFORMATION DISTRZBUTIONISTEM (RIDE)

AGCESSION NBR:9702030046 DOC.DATE: 97/01/23 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 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Forwards revised Emergency Operating Procedures'for plant.

DISTRIBUTION CODE: A002D TITLE: OR Submittal:Inadequate COPIES RECEIVED!LTR Core Cooling J ENCL g (Item II.F.2)

SIZE: &+25 D GL 82-28 I

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 >

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME 'LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 VISSINGFG. 1 1 INTERNA FILE CENTER 0 1 1 NRR/DRPM/PECB 1 1 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! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 II

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ROCHESTERGASANDELECTRICCORPORATION a 89EASTAVENUE, ROCHESTER, N.Y. 14649%001 JOSEPH A. WIDAY TELEPHONE Rant Managor AREAGODE 716 546-2700 Ginna Nuclear Rant January 23, 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, Q..

os ph A. Widay JAW/jdw XC: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s): Q3O 02 I E Index E-1, Rev. 14 ES-1.3, Rev. 20 ECA Index E-3, Rev. 19 FR-C.1, Rev. 13 ES Index ECA-2.1, Rev. 14 FR-C.2, Rev. 12 FR Index ECA-3.3, Rev. 15 FR-P.1, Rev. 14 9702030046 970i23 PDR ADOCK 05000244 r F PDR

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REPORT HO. 01 GINHA NUCLEAR POWER PLANT 01/10/97 PAGE: 3 REPORT: HPSP0200 PROCEDURES INDEX DOC TYPE: PRES EQUIPNENT SUB-PROCEDURE PARAMETERS: DOC TYPES - PRER PRES PRFR STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUNBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ES-O.D REDIAGNOSIS 009 04/07/94 04/07/94 04/07/99 EF ES-0.1 REACTOR TRIP RESPONSE 012 06/03/96 04/07/94 04/07/99 EF ES-0.2 HATURAL CIRCULATION COOLDOWN 009 06/03/96 04/20/95 04/20/00 EF ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAN VOID IN VESSEL 006 06/03/96 04/07/94 04/07/99 EF ES-1.1 Sl TERNINATION 012 06/03/96 04/20/95 04/20/00 EF ES-1.2 POST LOCA COOLDOWH AND DEPRESSURIZA'LION 014 06/03/96 04/20/95 04/20/00 EF ES-1.3 TRANSFER TO COLD LEG RECIRCULATION 019 01/10/97 03/26/93 03/26/ 8 EF ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 010 06/03/96 04/20/95 04/20/00 EF ES-3.2 POST-SGTR COOLDOWN USING BLSSOWN 011 06/03/96 04/20/95 04/20/00 EF ES-3.3 POST-SGTR COOLDOWN USING STEAN DUHP 011 06/03/96 4/20/95 04/20/00 EF TOTAL FOR PRES 10

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REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/25/95 08:54 PAGE 2 REPORT NAME: DOC-P001 PROCEDURES INDEX DOC TYPE: PRF CRITICAL SAFETY FUNCTION STATUS PROC PARAMETERS: DOC TYPES - PRES PRF PRFR PRPT PRPTT STATUS: 5 YEARS ONLY:

PROCEDURE PROCEDURE TITLE REV EFFECT LAST NEXT ST NUMBER DATE REVIEW REVIEW F-0.1 SUBCRITICALITY CSFST 001 07/21/89 07/13/94 01/13/97 EF F-0.2 CORE COOLING CSFST 003 07/21/89 07/13/94 01/13/97 EF F-0.3 HEAT SINK CSFST 002 01/12/90 07/13/94 01/13/97 EF F-0.4 INTEGRITY CSFST 001 07/21/89 07/13/94 01/13/97 EF F-0.5 CONTAIHHENI'SFST 002 01/12/90 07/13/94 01/13/97 EF F-0.6 IHVEN'IORY CSFST 003 01/12/90 07/13/94 01/13/97 EF TOTAL FOR PRF

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/10/97 PAGE: 4 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRFR FUNCTIONAL RESTORATION GUIDELINE PROC PARAMETERS: DOC TYPES; PRER PRES PRFR STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEM REVIEN ST FR-C.1 RESPONSE TO IHADEQUATE CORE COOLING 012 01/10/97. 04/07/94 04/07/99 EF FR-C.2 RESPONSE TO DEGRADED CORE COOLING 011 01/10/97 04/07/94 04/07/99 EF FR-C.3 RESPOHSE TO SATURATED CORE COOLING 007 01/10/97 03/02/95 03/02/00 EF FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 015 11/08/96 04/20/95 04/20/00 EF FR-H.2 RESPONSE TO STEAM GEHERATOR OVERPRESSURE 003 05/31/96 02/22/95 02/22/00 EF FR-H.3 RESPONSE TO STEAM GEHERATOR HIGH LEVEL 004 05/31/96 02/22/95 02/22/00 EF

'R-H.4 RESPONSE TO LOSS OF NORMAL STEAH RELEASE CAPABILITIES 003 05/31/96 04/21/93 04/21/98 EF FR-H.S RESPONSE TO STEAM GENERATOR LOtl LEVEL 003 09/26/96 02/22/95 02/22/00 EF FR-I.1 RESPONSE TO HIGH PRESSURIZER LEVEL 007 05/31/96 04/20/95 04/20/00 EF:

FR-I.2 RESPONSE TO LOI PRESSURIZER LEVEL 004 05/03/91 07/28/93 07/28/98 EF FR-I.3 RESPONSE TO VOIDS IN REACTOR VESSEL 008 06/05/96 10/19/94 10/19/99. EF FR-P.1 RESPONSE TO IMHINEHT PRESSURIZED THERHAL SHOCK CONDITION 013 11/08/96 04/20/95 04/20/00 EF FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION 005 06/05/96. 11/08/94 11/08/99 EF FR-S.1 RESPONSE TO REACTOR RESTART/ATNS 010 05/31/96 04/20/95 04/20/00 EF FR-S.2 RESPONSE TO LOSS OF CORE SHUTDOWN 006 05/31/96 04/20/95 04/20/00 EF FR-Z.1 RESPONSE TO HIGH CONTAINHENT PRESSURE 003 10/16/92 02/22/95 02/22/00 EF FR-Z.2'R-2 RESPONSE TO COHTAINMENT FLOODING 002 04/09/90 02/22/95 02/22/00 EF

' RESPONSE TO NIGH CON'IAINHEN'I RADIATION LEVEL 003 09/30/92 02/22/95 02/22/00 EF TOTAL FOR PRF 18

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REPORT HO. 01 GINHA NUCLEAR POWER PLANT 01/25/95 08:50 PAGE 5 REPORT HAME: DOC.P001 PROCEDURES INDEX DOC TYPE: PRE EMERGENCY PROCEDURE PARAMETERS: DOC TYPES - PRAP PRATT PRE PRECA PRER STATUS 5 YEARS ONLY:

PROCEDURE PROCEDURE TITLE REV EFFECT LAST NEXT ST NUMBER DATE REVIEW REVIEW E-0 REACTOR TRIP OR SAFETY INJECTION 019 04/07/94 04/07/94 10/07/96 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 011 03/26/93 03/26/93 09/26/95 EF E-2 FAULTED STEAM GENERATOR ISOLATION 006 07/08/93 07/08/93 01/08/96 EF E-3 STEAM GENERATOR TUBE RUPTURE 015 06/09/94 04/07/94 10/07/96 EF TOTAL FOR PRE

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/25/95 08:50 PAGE 6 REPORT NAME: DOC-P001 PROCEDURES INDEX DOC T'YPE: PRECA EMERGENCY CONTINGENCY ACTIONS PROC PARAMETERS- DOC TYPES - PRAP PRATT PRE PRECA PRER STATUS: 5 YEARS ONLY:

PROCEDURE PROCEDURE TITLE REV EFFECT LAST NEXT ST NUHBER DATE REVIEW REVIEW ECA-0.0 LOSS OF ALL AC POWER 016 11/08/94 SS ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT Sl REQUIRED 010 06/09/94 04/07/94 10/07/96 EF ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH Sl REQUIRED 008 04/07/94 04/07/94 10/07/96 EF ECA-1.1 LOSS OF EMERGENC'Y COOLANT RECIRCULATION 009 04/07/94 04/07/94 10/07/96 EF ECA-1.2 LOCA OUTSIDE CONTAINMENT 002 04/09/90 09/23/92 03/23/95 EF ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS 010 06/09/94 04/07/94 10/07/96 EF ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANI'-SUBCOOLED RECOVERY DESIRED 010 04/07/94 04/07/94 10/07/96 EF ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED 013 04/07/94 04/07/94 04/07/96 EF ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 011 06/09/94 04/07/94 10/07/96 EF TOTAL FOR PRECA