ML20059M508

Requests Sims Be Updated to Reflect Implementation Re Generic Safety Issue 40 & Generic Ltr 86-01 on Pipe Breaks in BWR Scram Sys

ML20059M508
Person / Time
Site:	Browns Ferry
Issue date:	10/01/1990
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-040, REF-GTECI-NI, TASK-040, TASK-40, TASK-OR GL-86-01, GL-86-1, NUDOCS 9010040316
Download: ML20059M508 (3)

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-. TENNESSEE VALLEY. AUTHORITY

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CHATTANOOGA. TENNESSEE 374ol -

SN 157B Lookout Place 00T 011980- ,

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk-Washington, D.C.-'20555-Gentlemen In the Matter of.' -) Docket Mo. 50-260-Tennessee' Valley ~ Authority )

BROWNS FERRY NUCLEAR PLANT (BFN) - SAFETY CONCERNS ASSOCIATED WITH PIPE. BREAKS'

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IN THE BOILING WATER REACTOR (BWR) SCRAM SYSTEM (GSI 40 AND GENERIC' LETTER 86-01)- l The purpose of this letter is'to request the Safety Issues Management System j (SIMS) be updated to reflect the implementation of the subject Generic Safety Issue (GSI) as of the; date of this letter. Background information and basis for the closure of this issue is provided in the enclosure to this letter.. ,

There are no commitments contained in this le Ler. If_you have any questions, I please contact Patrick P. Carter, Manager of- Site Licensing, at -(205) 729-3570.

Very truly yours, ~f TENNESSEE VALLEY AUTHORITY l r E. G. Wallace, Manager Nuclear Licensing and; Regulatory Affairs' ,

i-Enclosure )

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9010040316 901001 PDR ADOCK 05000260 ,

P- PDC s ,

An Equal Opportunity Employer )COl

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U.S. Nuclear Regulatory. Commission 00T 011990 cc (Enclosure): .

t Ms. S. C. Black, Deputy Director.

Project Directorate II-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike,  !

Rockville, Maryland;J20852 NRC Resident Inspector .

Browns Ferry Nuclear Plant -

Route.12 Bcx 657  ;

Athens, Alabama 35609-2000 Thierry M. Ross, Project Managers

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U. S.' Nuclear. Regulatory Commission ,

One White Flint, North

-11555 Rockville Pike Rockville, Maryland 20852, 1 Mr. B. A. Wilson, Project Chief  ;

l U.S. Nuclear Regulatory Commission i Region II l

101 Marietta Street, NW, Suite 2900-l Atlanta, Ceorgia 30323 t

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ENCLOSURE BROWNS FERRY NUCLEAR PLANT SAFETY CONCERNS ASSOCIATED WITH PIPE BREAKS IN THE BOILING WATER: REACTOR SCRAM SYSTEM BACKGROUND:

During the preparation of BFN's. response to Generic Letter 90-04, Request for Information on the Status of Licensee Implementation of Generic Safety Issues '

Resolved With Impositions of' Requirements or Corrective Actions, TVA- .

identified a discrepancy'between TVA's programs.and the NRC assumptions-which were the basis for the closure of GSI 40, Safety Concerns-Associated with' Pipe Breaks in the Boiling Water Reactor (BWR) Scram System. The basis for the closure of this GSI was documented in Generic Letter 86-01 . Safety Concerns Associated with Pipe Breaks in the BWR Scram System..'Page.17 of the enclosure to this Generic Letter states that a post-scram reset walkdown recommended by-the Boiling. Water Reactor.0wners' Group _(BWROG)'was part of the basis for NRC's conclusion that the design of the scram discharge-volume (SDV) piping satisfied the-applicable criteria of-Standard Review Plan Sections 3.6.1 and 3.6.2, and was-therefore cceeptable. Since GenericiLetter ,

86-01 did not request.any action of licensees nor did separate NRC I correspondence request implementation of this BWROG suggested periodic inspection, TVA did not interpret this NRC assumption as being a regulatory requirement. Therefore, BFN's Fmy 30, 1990 response to Generic Letter 90 stated that the implementation of the visual verification assumption contained in the Generic Letter was never requested by NRC and was not currently required by the ASME code.

In response to a verbal request from.NRC's Project' Manager, TVA agreed to review this-NRC assumption and either incorporate-the BWROG recommended visual inspection of the scram discharge volume piping or provide further- +

justifi- ' ion for not implementing this recommendation. (BFh has previously addresseo se issue of scram discharge volume piping integrity by TVA letter,.

dated January 20, 1982. 'No NRC response has been. identified.)

BASIS FOR CLOSURE:

In order to resolve this issue. TVA has revised Abnormal Operating Instruction (AOI) 2-A0i-100-1, Reactor Scram, to require the scram discharge '

volume be visually inspected for leaks within 30 minutes of the first reactor scram, following a refueling outage, from rated temperature and; pressure.

Any identified leaks will be' brought to the Shift Operations Supervisor's immediate attention. This action incorporates the BWROG suggested inspection and frequency.

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