ML18026B098

Provides Addl Info Re Containment Leak Rate Testing,Per 840420 request.Twenty-seven Instrumentation Valves & Piping Leak Tested at Accident Pressure & Found within Limits.Lines & Valves Will Be Type a Tested in Future Procedures

ML18026B098
Person / Time
Site:	Browns Ferry
Issue date:	07/12/1984
From:	Kammer D TENNESSEE VALLEY AUTHORITY
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8407170361
Download: ML18026B098 (6)

Text

REGULATORY NFORMATION DISTRIBUTION SYv EM (RIDS) 05000259 05000260 05000296 ACCESSION NBR:8407170361 DOC DATE.: 8<i/07/12 NOTARIZED! YES DOCKET FACIL:50-259 Browns Fer ry Nuclear.Power Stations Uni t 1~ Tennessee 05 0

9 5000259 50 260 Br ns Ferry Nuclear power Stationi Unit 2i Tennessee 05000260 50-296 Browns Ferry Nuclear Power Stationi Unit 3i,Tennessee 050 6

ow 0029 AUTH~ NAME

AUTHOR AFFILIATION KAMYERiD AS<

Tennessee Valley Authority RECIP ~ NAME RECIPIENT AFFILIATION, DENTONiH ~ RE Office of Nuclear Reactor Regulationr Director 1

SUBJECT; Provides addi info re containment leak rate testinggper 840420 requests Twenty-seven instrumentation valves 8.piping leak tested at accident pre'ssure 8 found within limits.Lines L valves will be Type A tested in future procedures.

DI'STRIBUTION CODE:

A017S COPIES RECEIVED:LTR ENCL SIZE:

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P TITLE:

OR Submittal:

Append J Containment. Leak Rate Testing NOTES:NMSS/FCAF 1cy, icy NMSS/FCAF/PM, OL:06/26/73 NMSS/FCAF icy, icy NMSS/FCAF/PM, OL:06/28/74 NMSS/FCAF icy, icy NMSS/FCAF/PM'L:07/02/76 RECIPIENT ID CODE/NAME NRR ORB2 BC 01 INTERNAL: ELD/HDSQ 08 NRR/DSI/CSB 06 RGN2 COPIES LTTR ENCL RECIPIENT ID CODE/NAME RE FILE 00

'COPIES LTTR ENCL EXTERNAL; ACRS NRC PDR NTIS NOTES:

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02 1

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LPDR NSIC 03 05 TOTAL NUMBER OF COPIES'EQUIRED:

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TENNESSEE VALLEYAUTHORITY CIPTTQNOfGg. TE$NFSSEE $

7401 July 12, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 By letter from D. B. Vassallo to H. G. Parris dated April 20,

1984, we received a request for additional information regarding containment leak rate testing at the Browns Ferry Nuclear Plant.

Specifically requested were technical specifications requiring that certain instrument lines and valves be Type A tested or an alternative means to ensure that the testing will be accomplished.

As part of the corrective action following the test failure on Browns Ferry unit 2, 27 instrumentation valves and their associated piping which form part of the reactor protection system were locally leak tested at accident pressure and exhibited leakage within acceptable limits.

These instrument lines were subsequently included in the containment integrated leak rate test (CILRT) procedure and will be Type A tested during all future CILRTs.

It is our position not to include the valves to be Type A tested in the technical specifications because of the extensive number of the tested components. 'he 27 instrument valves and associated piping have been included in the CILRT surveillance instructions for future tests.

We consider this an adequate means of ensuring that the instrument, lines and valves are included in the Type A tests.

Very truly yours, TENNESSEE VALLEY AUTHORITY os'.

S.

Kammer Nuclear Engineer

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-.Sworn ~to.gnd subsc be before me

'his ~~ day of 1984 Notary Public My Commission Expires 8407170361 840712 cc:

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/o 1983-TVA 50TH ANNIVERSARY An Equal Opportunity Employer

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Mr. Harold R. Denton, Director July, 12, 1984 cc:

U.S. Nuclear Regulatory Commission Region II ATTN:

James P. O'Reilly, Regional Administrator 101 Marietta Street, NM, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Prospect Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue

Bethesda, Maryland 20814

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