IR 05000259/1996004

Provides Suppl Info for Resolution of Unresolved Item 260/ 96-04-03,shutdown Cooling Low Level Isolation Bypassed Prior to Cavity Floodup.Nrc Insp Repts 50-259/96-04,50-260/96-04 & 50-296/96-04 Discussed

ML18038B777
Person / Time
Site:	Browns Ferry
Issue date:	10/22/1996
From:	Abney T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9610290175
Download: ML18038B777 (10)

Text

CATEGORY j.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9610290175 DOC.DATE: 96/10/22 NOTARIZED:

NO FACZL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION ABNEY,T'.E.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFIZ ZATION Document Control Branch (Document Control Desk)DOCKET 05000259 05000260 05000296!SUBJECT: Provides suppl info for resolution of Unresolved Item 260/96-04-03,shutdown cooling low level isolation bypassed prior to cabity floodup.NRC insp repts 50-259/96-04,50-260/96-04

&50.-296/96-04 discussed'.

DISTRIBUTION CODE: ZE01D COPIES RECEIVED:LTR ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response t NOTES: RECIPIENT ID CODE/NAME PD2-3-PD INTERNAL: ACRS AEOD/TTC TENRR/DRPM/PERB OE'IR , RGN2 FILE 01 EXTERNAL: LITCO BRYCE,J H NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME WILLIAMS,J.

AEOD/SPD/RAB DEDRO'NRR/DISP/PIPB NRR/DRPM/PECB NUDOCS-ABSTRACT OGC/HDS3 NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D 0, U E N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE'WASTE.

TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR'REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19 0 0 Tennessee Valtey Authority.

Post Ollice Box 2000.Decatur, Atacama 35609 October 22, 1996 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:

In the Matter of)Tennessee Valley Authority)Docket Nos.50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)-SHUTDOWN COOLZNG LOW REACTOR LEVEL ZSOLATZON BYPASSED PRZOR TO CAVZTY FLOODUP This letter provides supplemental information for the resolution of Unresolved Item 260/96-04-03, Shutdown Cooling Low Level Isolation Bypassed Prior to Cavity Floodup.NRC Inspection Report No.96-04 discusses concerns with the practice of bypassing the low reactor water level isolation of shutdown cooling (SDC)prior to floodup of the reactor cavity.TVA has reviewed the following.

concerns raised in this report and the related references:

NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management, section 4,.2.3, guideline number one, states that the automatic isolation function of the Decay Heat Removal system (on low RPV level)should be maintained functional during shutdown cooling periods.NRC Inspection Report No.95-64, section 2.5;discusses the failure of a residual heat removal (RHR)valve to fully shut causing an unexpected reactor water level decrease.Actions taken to prevent recurrence included revision of electrical maintenance procedures to electrically stroke limitorque motor operated valves and manually verify torque seated following maintenance, 96i0290i75 9hi022 PDR ADQCK 0500025ttt PDR iCttl r Cl U.S.Nuclear Regulatory Commission Page 2 October 22, 1996 adding steps to ensure torque switch settings are returned to the as found setting on non GL 89-10 valves following maintenance, review of this matter with plant maintenance personnel, and a review of as-left torque switch settings on safety-related non GL 89-10 valves to verify same as as-found settings.~NRC Examination Report No.96-300, lists questions on interlocks associated with SDC suction valves as a generic weakness area on the examination.

RHR valve interlocks were reviewed with all examinees who missed the related questions.

Although the low level isolation function is not required by current Technical Specifications during conditions when primary containment is not required, based on review of the above, TVA will no longer allow bypass of the low level SDC isolation interlock.

TVA will revise affected Unit 2 and Unit 3 procedures

'to remove the ability to bypass the SDC low level isolation signal prior to the next scheduled refueling outage.TVA:also will supplement the September 6, 1996, Improved Standard Technical Specifications submittal (TS 362)to reflect ISTS requirements for the SDC low level isolation.

A summary of the commitments contained in this letter is enclosed.If you have any questions, please contact me at (205)729-2636erely, E.ney Manager of Lice in and Industry ffa rs Enclosure cc: See page 3 Ck U.S.Nuclear Regulatory Commission Page 3 OCtober 22, 1996 Enclosure cc (Enclosure):

Mr.Mark S.Lesser, Section Chief U.S.Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr.Joseph F.Williams, Project Manager U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 II{0 ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWHS PERRY HUCLEAR PLANT (BFN)UNITS Xq 2g AND 3 SHUTDONM COOLING LOW REACTOR LEVEL ZSOLATZOH BYPASSED PRZOR TO CAVZTY PLOODUP LZST OP COMMZTMENTS 1~2~TVA will revise affected Unit 2 and Unit 3 procedures to remove the ability to bypass the SDC low level isolation signal prior to the next scheduled refueling outage.TVA will supplement the September 6, 1996, Improved Standard Technical Specifications submittal (TS 362)to reflect ISTS requirements for the SDC low level isolatio t" 0 ik