ML17262A433

Followup Rept of 910403 Event Re Removal of RHR Sys & Component Cooling Water Sys from Svc Due to Packing Leak from MOV-738B.Valve Manually Placed on Backseat & Leak Terminated

ML17262A433
Person / Time
Site:	Ginna
Issue date:	04/03/1991
From:	SPECTOR S M ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9104090259
Download: ML17262A433 (6)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9104090259 DOC.DATE: 91/04/03 NOTARIZED:

NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION SPECTOR,S.M.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Followup rept of 910403 event re removal of RHR sys&component cooling water sys from svc due to packing leak from MOV-738B.Valve manually placed on backseat&leak-terminated.

DISTRIB'STION CODE: IE22D COPIES RECEIVED:LTR 4 ENCL L SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 A RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DS P/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D N PLB8D1 REG FIL 02 FILE 01 EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MAYS,G NUDOCS FULL'TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2, 2 1 1 1 1 1 1 1 1 1 D D R D NOTE TO ALL"RIDS" RECIPIENTS:

A D D PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 n f pa+

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/Pgt"'"""I ROCHESTER GAS AND ELECTRIC i i<<<<t+g~<<~%~A Q.104K, j~,!STATIC r CORPORATION

~89 EAST AVENUE, ROCHESTER, N.Y.14649.0001

'C L E P<0<<<<f, A<<<<KA cooE 7lc 546 2700 April 3, 1991 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Follow-up Summary Of Close-Out Of April 3, 1991 Unusual Event.R.E.Ginna Nuclear Power Plant Docket No.50-244 In accordance with NUREG 0654, FEMA-REP-1, Rev.1 reporting requirements which requires a written summary of"close-out or class reduction conditions", the attached close-out summary for'the April 3, 1991 Unusual Event is hereby submitted.

This event has in no way affected the public's health and safety.Very truly yours, xc'tanley.Spector Plant Manager U.S.Nuclear Regulatory Commission Region I 475 Allendale Road.King of Prussia, PA 19406 Ginna USNRC Senior Resident, Inspector Richard Beldue Robert C.Mecredy 9104090259 910403 PDR ADOCK 05000244 F'DR ATTACHMENT FOR CLOSE-OUT OF APRIL 3 1991 UNUSUAL EVENT On April 2, 1991 at 2335 EST the reactor was in the refueling mode with refueling in progress.The Reactor Coolant System (RCS)temperature and pressure were approximately 60 F and 0 psig respectively.

Maintenance personnel were in the process of repacking motor operated valve (MOV)-738B (CCW Inlet MOV to RHR HX B)which they believed to be isolated, but was not.At this time the Control Room was notified of a packing leak from MOV-738B.Subsequent investigation of plant piping and instrument drawings revealed that the leak was non-isolatable.

An attempt was made to open MOV-738B electrically to place the valve on the backseat and stop the packing leak.This attempt caused the leak rate to increase to approximately 25 gallons per minute and Mov-738B was closed electrically.

At approximately 2341 EST, April 2, 1991 a plant announcement was made to inform personnel of the Component Cooling Water (CCW)spill in the Auxiliary Building Mezzanine Level.At approximately 0003 EST, April 3, 1991, refueling operations were terminated and the Residual Heat Removal (RHR)system and CCW system were removed from service to manually.place MOV-738B on the back seat to stop the packing leak.Also at approximately 0003 EST, April 3, 1991, the Operations Shift Supervisor declared an Unusual Event in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification", EAL: Cold Shutdown Activities; Potential Loss of Core Cooling Due To Inability To Maintain Residual Heat Removal System While In Cold Shutdown.These activities may include loss of cooling to the RHR system such as a CCW or service water systems.All off-site notifications were made per EPIP 1-5 (Notifications).

Ginna Technical Specifications specifically allow for the removal of both RHR pumps for up to one (1)hour provided core outlet temperature is maintained at least 10 F below saturation and no operations are permitted that would cause dilution'f the reactor coolant system boron concentration.

It is noted that although compliance to the Ginna Technical Specifications was being maintained, the Operations Shift Supervisor conservatively declared the Unusual Event.This conservative approach activated the response team to provide support should conditions further degrade.The RHR system was then run for two minutes every five minutes during the.isolation of CCW.

At 0027 EST, April 3, 1991, MOV-738B was manually placed on its backseat and the leak was terminated.

The"A" CCW pump was then started and the"A" RHR pump was restarted.

RHR discharge temperature was not'ed to be approximately 8 F higher than prior to the event.-At approximately 0122 EST, April 3, 1991, after the plant was returned to pre-event conditions and all concerns resolved, the Operations Shift Supervisor, with approval and concurrence from the Plant Manager, the Superintendent

-Ginna Production, and the Operations Manager declared the Unusual Event terminated in accordance with EPIP 3-4 (Emergency Declassification and Recovery).

All off-site agencies were notified of the termination of the Unusual Event.