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 COPIES RECEIVED!LTR J ENCL g SIZE: &+25D TITLE: OR Submittal:Inadequate Core Cooling (Item II.F.2)

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05000244 >

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ROCHESTERGASANDELECTRICCORPORATION a 89EASTAVENUE, ROCHESTER, N.Y. 14649%001 JOSEPH A. WIDAY Rant Managor Ginna Nuclear Rant January 23, 1997 TELEPHONE AREAGODE 716 546-2700 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):

Q 3 O 0 2 I E Index ECA Index ES Index FR Index E-1, Rev. 14 E-3, Rev. 19 ECA-2.1, Rev. 14 ECA-3.3, Rev. 15 ES-1.3, Rev. 20 FR-C.1, Rev. 13 FR-C.2, Rev. 12 FR-P.1, Rev. 14 r

9702030046 970i23 PDR ADOCK 05000244 F

PDR

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REPORT HO.

01 REPORT:

HPSP0200 DOC TYPE:

PRES GINHA NUCLEAR POWER PLANT PROCEDURES INDEX EQUIPNENT SUB-PROCEDURE 01/10/97 PAGE:

3 PARAMETERS:

DOC TYPES - PRER PRES PRFR STATUS:

EF QU 5 YEARS ONLY:

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

r t

YP

REPORT NO. 01 REPORT NAME: DOC-P001 DOC TYPE:

PRF GINNA NUCLEAR POWER PLANT PROCEDURES INDEX CRITICAL SAFETY FUNCTION STATUS PROC 01/25/95 08:54 PAGE 2

PARAMETERS:

DOC TYPES -

PRES PROCEDURE NUMBER F-0.1 F-0.2 SUBCRITICALITY CSFST CORE COOLING CSFST HEAT SINK CSFST INTEGRITY CSFST CONTAIHHENI'SFST IHVEN'IORY CSFST F-0.3 F-0.4 F-0.5 F-0.6 PRF PRFR PRPT PRPTT STATUS:

PROCEDURE TITLE 5 YEARS ONLY:

REV EFFECT DATE LAST NEXT ST REVIEW REVIEW 001 07/21/89 07/13/94 01/13/97 EF 003 07/21/89 07/13/94 01/13/97 EF 002 01/12/90 07/13/94 01/13/97 EF 001 07/21/89 07/13/94 01/13/97 EF 002 01/12/90 07/13/94 01/13/97 EF 003 01/12/90 07/13/94 01/13/97 EF TOTAL FOR PRF

REPORT NO.

01 REPORT:

NPSP0200 DOC TYPE:

PRFR GINNA NUCLEAR POWER PLANT PROCEDURES INDEX FUNCTIONAL RESTORATION GUIDELINE PROC 01/10/97 PAGE:

4 PARAMETERS:

DOC TYPES; PRER PRES PRFR STATUS:

EF QU 5 YEARS ONLY:

PROCEDURE NUMBER FR-C.1 FR-C.2 FR-C.3 FR-H.1 FR-H.2 FR-H.3

'R-H.4 FR-H.S FR-I.1 FR-I.2 FR-I.3 FR-P.1 FR-P.2 FR-S.1 FR-S.2 FR-Z.1 FR-Z.2'R-2

RESPONSE

TO

RESPONSE

TO

RESPONSE

TO IMHINEHT PRESSURIZED THERHAL SHOCK CONDITION ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION REACTOR RESTART/ATNS

RESPONSE

TO LOSS OF CORE SHUTDOWN

RESPONSE

TO

RESPONSE

TO HIGH CONTAINHENT PRESSURE COHTAINMENT FLOODING

RESPONSE

TO NIGH CON'IAINHEN'I RADIATION LEVEL PROCEDURE TITLE

RESPONSE

TO IHADEQUATE CORE COOLING

RESPONSE

TO DEGRADED CORE COOLING RESPOHSE TO SATURATED CORE COOLING

RESPONSE

TO LOSS OF SECONDARY HEAT SINK

RESPONSE

TO STEAM GEHERATOR OVERPRESSURE

RESPONSE

TO STEAM GEHERATOR HIGH LEVEL

RESPONSE

TO LOSS OF NORMAL STEAH RELEASE CAPABILITIES

RESPONSE

TO STEAM GENERATOR LOtl LEVEL

RESPONSE

TO HIGH PRESSURIZER LEVEL

RESPONSE

TO LOI PRESSURIZER LEVEL

RESPONSE

TO VOIDS IN REACTOR VESSEL EFFECT REV DATE LAST REVIEM NEXT REVIEN ST 012 01/10/97. 04/07/94 04/07/99 EF 011 01/10/97 04/07/94 04/07/99 EF 007 01/10/97 03/02/95 03/02/00 EF 015 11/08/96 04/20/95 04/20/00 EF 003 05/31/96 02/22/95 02/22/00 EF 004 05/31/96 02/22/95 02/22/00 EF 003 05/31/96 04/21/93 04/21/98 EF 003 09/26/96 02/22/95 02/22/00 EF 007 05/31/96 04/20/95 04/20/00 EF:

004 05/03/91 07/28/93 07/28/98 EF 008 06/05/96 10/19/94 10/19/99.

EF 013 11/08/96 04/20/95 04/20/00 EF 005 06/05/96.

11/08/94 11/08/99 EF 010 05/31/96 04/20/95 04/20/00 EF 006 05/31/96 04/20/95 04/20/00 EF 003 10/16/92 02/22/95 02/22/00 EF 002 04/09/90 02/22/95 02/22/00 EF 003 09/30/92 02/22/95 02/22/00 EF TOTAL FOR PRF 18

f l

F'

REPORT HO.

01 REPORT HAME: DOC.P001 DOC TYPE:

PRE GINHA NUCLEAR POWER PLANT PROCEDURES INDEX EMERGENCY PROCEDURE 01/25/95 08:50 PAGE 5

PARAMETERS:

DOC TYPES - PRAP PROCEDURE NUMBER PRATT PRE PRECA PRER PROCEDURE TITLE STATUS 5

YEARS ONLY:

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

REPORT NO.

01 REPORT NAME: DOC-P001 DOC T'YPE:

PRECA GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EMERGENCY CONTINGENCY ACTIONS PROC 01/25/95 08:50 PAGE 6

PARAMETERS-DOC TYPES - PRAP PROCEDURE NUHBER ECA-0.0 ECA-0.1 ECA-0.2 ECA-1.1 ECA-1.2 ECA-2.1 ECA-3.1 ECA-3.2 ECA-3.3 PRATT PRE PRECA PRER STATUS:

PROCEDURE TITLE LOSS OF ALL AC POWER LOSS OF ALL AC POWER RECOVERY WITHOUT Sl REQUIRED LOSS OF ALL AC POWER RECOVERY WITH Sl REQUIRED LOSS OF EMERGENC'Y COOLANT RECIRCULATION LOCA OUTSIDE CONTAINMENT UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS SGTR WITH LOSS OF REACTOR COOLANI'-SUBCOOLED RECOVERY DESIRED SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 5 YEARS ONLY:

REV EFFECT DATE LAST REVIEW NEXT ST REVIEW 016 11/08/94 SS 010 06/09/94 04/07/94 10/07/96 EF 008 04/07/94 04/07/94 10/07/96 EF 009 04/07/94 04/07/94 10/07/96 EF 002 04/09/90 09/23/92 03/23/95 EF 010 06/09/94 04/07/94 10/07/96 EF 010 04/07/94 04/07/94 10/07/96 EF 013 04/07/94 04/07/94 04/07/96 EF 011 06/09/94 04/07/94 10/07/96 EF TOTAL FOR PRECA