ML17264A748

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Special Rept:On 961015,identified Problem W/Automatic Release Actuation of Sys Deluge Valve & Sys Declared Inoperable.Compensatory Actions Will Remain in Effect Until All Four Suppression Sys Restored to Operable Status
ML17264A748
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/27/1996
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9612060128
Download: ML17264A748 (6)


Text

CATEGORY j REGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9612060128 DOC.DATE: 96/11/27 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSINGiG.S.

SUBJECT:

Special rept:on 961015,identified problem w/automatic release actuation of sys deluge valve

& sys declared inoperable. Compensatory actions will remain in effect util all four suppression sys restored to operable status.

DISTRIBUTION CODE:

IE22D COPIES RECEIVED:LTR L ENCL 0 SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

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

05000244 G

RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD B+

LE CE R

DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1 FILE 01 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR COPIES LTTR ENCL 1

1 1

1 1

RECIPIENT ID CODE/NAME VISSING P G.

AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCO BRYCEPJ H

NOAC POORE,W.

NUDOCS FULL TXT COPIES LTTR ENCL D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LIST'R REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROI DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 25 ENCL

1 g'

AHD November 27, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Guy S. Vissing Project Directorate I-l Washington, D.C. 20555

Subject:

Thirty (30) Day Special Report Inoperable Fire Suppression Systems in the Transformer Yard R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

In accordance with the Ginna Station Technical Requirements Manual (TRM), Required Action TR 3.7.2.C, which requires a special report outlining the cause of system inoperability and plans for restoring the system to operable status, this thirty (30) day special report is being submitted.

On October 15, 1996, the suppression system which protects the station ¹12B transformer (system S23) was tested in accordance with the requirements of Surveillance Test Procedure PT-13.4.10B.

The results of the testing activities identified a problem with the automatic release actuation of the system deluge valve and the system was declared inoperable at approximately 1435 EDST on October 15, 1996.

Compensatory actions were immediately taken as per TRM Required Actions TR 3.7.2.B.1 and 3.7.2.B.2.

Hourly fire watch tours were initiated and backup fire suppression equipment (hose lines with a deck gun, connected to a yard hydrant) was placed in the area of the station ¹12B transformer.

ACTION Report 96-0938 was initiated to address the inoperability of the system.

Work activities were initiated the next day (10/16/96) with a local fire protection factory-trained company to identify what repairs were required to restore system S23 to operation.

Trouble shooting activities were scheduled to be initiated on 10/18/96.

However, due to an unexpected increase in combustible gas levels in the main ¹1 transformer, all work in this area of the plant was deferred until the condition of the main transformer could be determined.

(i goO$ $

96i2060128 96ii27 PDR ADOCK 05000244 S

PDR

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Page 2 On 10/23/96, Rochester Gas and Electric (RGAE) decided to replace the main transformer, since the cause of the combustible gas increase could not be identified.

On 10/24/96, the main ¹1 transformer suppression system (system S20) was removed from service in order to minimize the potential for an inadvertent discharge of the system while working on the main transformer.

Hourly fire watch tours were initiated and backup fire suppression equipment (existing hose lines with the deck gun) was available as the backup equipment.

These compensatory actions will remain in effect until all four suppression systems (as discussed below) are restored to operable status.

In order to remove the main transformer equipment, four fire suppression systems were removed from service: for the main ¹1 transformer (system S20), for the auxiliary transformer ¹11 (system S21), for the auxiliary transformer ¹12A (system S22), and for the auxiliary transformer

¹12B (system S23).

Prior to removing system S21 and system S22 from service on 10/25/96, hourly fire watch tours were modified to include all four suppression systems in the transformer yard.

Backup fire suppression equipment continued to be available via the utilization of hose lines with a deck gun which were connected to a yard hydrant.

The sprinkler piping systems have all been reinstalled for each of the affected systems (S20, S21, S22, and S23) with manual actuation capability.

The installation of the detection portion of each system, which willprovide full system operability, is under construction and scheduled for completion in December, 1996.

Very truly yours, Robert C. Mecredy xc:

Mr. Guy S. Vissing (Mail Stop 14C7)

PWR Project Directorate I-1 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector