ML20059K509

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Discusses Weaknesses Described in Paragraph 2.1.3.1 of 930913 Operational Safeguards Response Evaluation Rept Re Protection Program for Certain safety-related Equipment.Nrc Believes That Reactor Bldg Issue Not Resolved
ML20059K509
Person / Time
Site: Oyster Creek
Issue date: 01/25/1994
From: Stolz J
Office of Nuclear Reactor Regulation
To: J. J. Barton
GENERAL PUBLIC UTILITIES CORP.
References
TAC-M84616, NUDOCS 9402020128
Download: ML20059K509 (3)


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January 25, 1994 Docket No. 50-219 Mr. John J.

Barton Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731

Dear Mr. Barton:

SUBJECT:

REACTOR BUILDING ACCESS CONTROL MODIFICATION (TAC NO. M84616)

The weaknesses described in paragraph 2.1.3.1 of the September 13, 1993 Operational Safeguards Response Evaluation (OSRE) report concern a long-standing open issue regarding your protection program for certain safety related equipment.

This issue was identified in a NRC Region I inspection report, 50-219/86-39, dated March 9, 1987, and in a Regulatory Effectiveness Review Report forwarded to GPU Nuclear (GPUN) on August 19, 1988.

In a meeting on January 3, 1990, GPUN described reactor building access control modifications and informed the NRC that the modifications would be completed by early 1992.

An April 1990 SALP report noted a licensee commitment to " include resolution of the boundary issue in its long-range plans and to correct vagueness in the plan revision."

However, a June 5, 1992 update to the Oyster Creek Integrated Schedule deferred the modification to 1997.

In a letter dated September 14, 1992, GPUN proposed canceling the modification based on a number of factors described as augmenting protection against the design basis threat.

In a letter dated November 18, 1992, we informed you that, to complete our review of your proposal, we would evaluate your contingency response capability for protecting related equipment as part of an OSRE.

Based on the findings of the team, we believed that the reactor building issue had not been resolved.

Your October 25, 1993 response to the OSRE report also did not resolve the issue.

At that time there was some untested and incomplete testing of the defensive strategy.

Further, it was not clear that the proposed strategy is sufficient.

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Mr. John J.

Barton Your response letter indicated that the Oyster Creek Nuclear Generating Station would have completed all corrections to weaknesses noted in the OSRE report by May 1994.

We will contact you soon to schedule a return visit of the OSRE team this summer to Oyster Creek to assess and test the modified protection strategy and other corrections to OSRE weaknesses.

Sincerely, Original signed by Michael Boyle John F.

Stolz, Director for Project Directorate I-4 Division of Reactor Projects - I/II i

Office of Nuclear Reactor Regulation i

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Oyster Creek Nuclear Mr. John J. Barton Generating Station Vice President and Director cc:

Resident Inspector Ernest L. Blake, Jr., Esquire c/o U.S. Nuclear Regulatory Commission Shaw, Pittman, Potts & Trowbridge Post Office Box 445 2300 N Street, NW.

Forked River, New Jersey 08731 Washington, DC 20037 Kent Tosch, Chief Regional Administrator, Region I New Jersey Department of U.S. Nuclear Regulatory Commission Environmental Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 CN 415 Trenton, New Jersey 08625 BWR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop:

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Post Office Box 388 Forked River, New Jersey 03731 i