ML20212M326

Forwards Safety Evaluation Re Mark I Containment Vacuum Breakers.Util 850814,0523 & 861203 Responses to Staff Re Acceptable Methodology for Breaker Qualification Insufficient for Delaying Mod to Vacuum Breakers

ML20212M326
Person / Time
Site:	Oyster Creek
Issue date:	03/03/1987
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20212C077	List: ML20212C072 ML20212M326 ML20212M356
References
GL-83-08, GL-83-8, TAC-57161, TAC-61969, NUDOCS 8703110369
Download: ML20212M326 (4)

Text

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O' i.g UNITED STATES NUCLEAR REGULATORY COMMISSION

, j 'W WASHINGTON, D C.20655

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k / March 3, 1987 ,

Docket No. 50-219 Mr. P. B. Fiedler Vice President and Director Cyster Creek fluclear Generating Station Fost Office Fox 388 Forked River, New Jersey 05731

SUBJECT:

MARK I CONTAINPENT TORUS-TO-DRYWELL VACUUY BREAKEP.S (FPA D-20, TAC 57161 AND 61969)

Re: Oyster Creek Nuclear Generating Station h

In the latter stages of the Mark I Centainment Long Term Program, a potential failure mode for the containment torus-to-drywell vacuum breakers was identified.

Because this issue was not part of the sc' ope of this program, the staff issued Generic letter (GL) 83-08, Modification of Vacuum Breakers on Mark I Containments, dated February 2, 1983. In this GL, the staff requested that you submit the results of calculations for Oyster Creek which either formed the basis for modifications to the vacuum breakers or provided the justification for the vacuum breakers acceptability.

In*your letter dated May 11, 1983, in response to GL P?-08, you identified that Oyster Creek has Atwood and Morrill swing check velves on piping lines external to the torus which are the vacuum breakers identified in the GL. You stated that the results of the preliminary analysis did not identify modifications were needed for the vacuum breakers; however, you stated that once the staff issued this review of the general methodology for defining loads on the valves, the final analysis of these valves would be made.

In its letter dated April 11, 1985, the staff issued acceptable methodology for use in the analyses and qualification of the vacuum breakers. This methodology was also contained in the staff's Safety Evaluation (SET to General Electric dated December 24, 1984. The staff requested that you finalize the evaluation of the vacuum breakers and submit the results to the staff. The results of this evaluation were submitted by letters dated August 14, 190,5, and May 23 and December 3, 1986.

In your three responses to the staff's letter dated April 11, 1985, you identified the counterweight arms, disc arms, disc arm keys, valve shaft, counterweight hubs and counterweicht arm hub keys need to be replaced.

You requested that this modification work be completed on 7 of the 14 vacuum breakers in the Cycle 12 Refueling (Cycle 120 outage and on the remaining 7 on the Cycle 13R outage. Your justification for this schedule was submitted in the December 3, 1986 letter.

8703110369 DR 870303 ADOCK 05000219 PDR

Mr. P. B. Fiedler March 3, 1987 The staff has reviewed your three responses to its letter dated April 11, 1985.

Our evaluation is contained in the attached SE. The staff has concluded that you have not previded sufficient justification for delaying the modification work on seven vacuum breakers for two refueling outages to the Cycle 13R outage.

The Cycle 1?P outage will be in 1988 and the Cycle I?P outage will be in 1990. You are, therefore, required to complete the modification work on all 14 vacuum breakers in the Cycle 19D outage. ,

Sincerely.

Ah iackN.Donohew,.1r..hro.iectManager

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l BWR Project Directorate A1 Division of BWR Licensing Enclesure:

Safety Evaluat'an w/ attached Technical Evaluation Report f cc w/ enclosure:

See neyt page

Mr. P. B. Fiedler Dyster Creek Nuclear Oyster Creek Nuclear. Generating Station Generating Station

, CC:

l Mr. Ernest L. Blake, Jr. Resident Inspector Shaw, Pittran, Potte and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C. ?0037 Corked River, New Jersey 087?!

J.B. Liberman, Escuire Commissioner Pishop, Liberman, Cook, et al. New Jersey Department of Enerqv 1155 Avenue of the Americas 101 Commerce Street Few York, New York 10016 Newark, New Jersey 07107 Fr. David M. Scott, Actina Chief Reainnal Adm{pistrator, RL uion I Bureau of Nuclear Engineering II.S. Nuclear Regulatory Commission Department of Environmental Protectior.

631 Park Avenue CN 411 Kir,p of Prussia, Pennsv1vania 19406 Trentor, New Jersey 09,625 BWR Licensing Nanager GPU Nuclear Corporation-1 Upper Pond Roed Parsippany, New Jersey 07054 Deputy Attorney Gener&1 State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Dyster Creek Nuclear Ger.erating Station Mail Stop: Site Emergency Blda.

P. O. Box 3P8 Forked River, New Jersey 08731

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y Mr. P. B. Fiedler -

-?- March 3, 1987 f f' The staff has reviewed your three responses to its letter dated April 11, 1985.

Our evaluation is contained in the attached SE. The staff has concluded that you h4ve not provided sufficient.iustification for delaying the modification work on seven vacucm breakers for two refueling outages to the Cycle 13R outage.

The Cycle 12R outage will be in 1988 and the Cycle 13R ourage will be in 1990. You are, therefore.. required to complete the modification work on all 14 vacuum breakers in the Cycle 12R outage. >

Sincerely, l- (, al l =

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, .( 1-ac N. Don hew, Jr. , Pro.iect Manager .  ? ,f BWR Pro,iect sirectorate M. ' 'l l Division of nWR Licensing'

Enclosure:

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f Safety Evaluation w/ attached '

Technical Evaluation Report o l/ .'- )

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cc w/ enclosure: l/

See next page 1 t.

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