ML18039A202

Forwards LER 97-008-00,which Provides Details Re Main Steam Safety/Relief Valves That Exceeded TS Setpoint Limit During Surveillance Tests

ML18039A202
Person / Time
Site:	Browns Ferry
Issue date:	12/03/1997
From:	Crane C TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18039A203	List: ML18039A202 ML18039A204
References
NUDOCS 9712110181
Download: ML18039A202 (6)

Text

REGULATO INFORMATION DZSTRIBUTION YSTEM (RIDS)

ACCESSION NBR:9712110181 DOC.DATE: 97/12/03 NOTARIZED: NO 'DOCKET FACIL:50-260 Browns Ferry Nuclear Power 'Station, Unit 2, Tennessee 05000260 AUTH;NAMS AUTHOR AFFILIATION CRANE,C.M. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards LER 97-008-00,which provides details re main steam safety/relief valves that exceeded TS setpoint limit during surveillance tests.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ) ENCL Q SIZE:

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

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3-PD 1 1 DEAGAZIO,A 1 1 INTERNAL: ACRS 1 1 AEOD RAB 2 2 AEOD/SPD/RRAB 1 1 FILE E 1 1 NRR/DE/ECGB 1 1 D EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE, J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL ERZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION LZS'1 OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTRC DESK (DCD) ON EXTENSION 415-2083

'FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25

I+I f

Tennessee Yal!ey Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Christopher M. (Chris) Crane Vice President, Browns Ferry Nucfear Plant December 3, 1997 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.,20555

Dear Sir:

BROGANS FERRY NUCLEAR PLANT'BFN) UNIT 2 DOCKET NO. 50-260 FACILITY OPERATING LICENSE DPR-52 LICENSEE EVENT REPORT 50-260/97008 The enclosed report provides details concerning Unit 2'ain steam safety/relief valves that: exceeded their technical specifications setpoint limit during surveillance tests,.

This report is submitt:ed in accordance with 10 CFR,50.73(a).(2)(i)(B) as a condition prohibited by the plant's technical specifications.

Sincerely, C. M. rane nclo ure cc: S page 2 t

w~QA i 97i2iiOi8i F7i20S ADOCK 05000260 PDR 8 PDR

4~

4~ i

U.S. Nuclear Regulatory Commission Page 2 December 3, 1997 Enclosure cc (Enclosure):

'Mr. Albert W. De Agaz'io, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.W.

Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611

Qi i