ML20195K020

Requests Addl Info Re Util 831114 & 851023 Submittals for Generic Ltr 83-28,Item 2.2 (Part 1) Re Equipment Classification Program (Programs for All Other safety- Related Components).Response Requested by 880229

ML20195K020
Person / Time
Site:	Oyster Creek
Issue date:	01/22/1988
From:	Dromerick A Office of Nuclear Reactor Regulation
To:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
References
GL-83-28, TAC-53698, NUDOCS 8801290119
Download: ML20195K020 (5)

Text

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UAN 2 2 1965

, Docket flo. 50-219 DISTRIBU110N ,

<? Docket File A. Dromerick NRC & Local PORs OGC-Peth.

PDI-4 Peading E. Jordan Mr. P. B. Fiedler S. Varga J. Partlow Vice President and Director B. Boger ACRS (10)

Cyster Creek Nuclear Generating Station S. florris Gray File Post Office Eox 388 Forked River, New Jersey 08731 Cear t'r. fiedler:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR 11EM 2.2 (PART 1) 0F GENERIC LETTER 83.28, FOR OYSlER CREEK huCLEAR GENERATING STATION (TAC h0. 53698)

The staff has reviewed the inforn.ation provided by GPU Nuclear Corporation in letters dated November 14, 1983 and October P3, 1985 concerning Item 2.2 (Part 1) "Equipment Classification Program (Programs for All Other Safety-Pelated Cortponents)" of Generic Letter 83-?8. Based on our review of this information, we find that additional infotniation is required. The information r.eeded by the staff to ccmplete the evaluation is described in the enclosure.

You are requested to respond to this tequest by February 29, 19P8 in order to meet the scheduled cen;pletion date.

The reporting and/or recordkeeping requirerrent contained in this letter affect fewer than ten respcndents; therefore, CMB clect once is r<ot required under P.L.97-511.

Sincerely, "e m?.a mi.F E 3 W Alexander H. Drorterick, Project l'anager Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Peactor Pegulation

Enclosure:

As stated cc w/ enclosure:

See next page ci, ck:bd '

01/M/88 01/q/88 01/g /88 8801290119 880122 DR ADOCK O y9

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l Mr. P. B. Fiedler Oyster Creek Nuclear t . Oyster Creek Nuclear Generating Station Generating Station ec:

Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridge e/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C. 20037 Forked River, New Jersey 08731 J.B. Libeman, Esquire Comissioner Bishop Libeman, Cook, et al . New Jersey Department of Energy 1155 Avenue of the Americas 101 Ccenerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineering U.S. Nuclear Regulatory Comission Department of Environmental Protection 631 Park Avenue .

CN 411 -

King of Prussia, Pennsy1Yania 19406 Trenton, New Jersey 08625

, BWR Licensing Manager GPU Nuclear Corporation

^i. 1 Upper Pond Road Parsippany, New Jersey 07054 Deputy Attorney General 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 Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg. '

P. O. Box 388 Forked River, New Jersey 08731

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ENCLOSURE OYSTER CREEK NUCLEAR GENERATIhG STATI0fl DOCKET ll0. 50-219 REQUEST FOR ADDITIONAL INFORitATION FOR GENER:C LETTER 83-28, ITEM 2.

2.1 INTRODUCTION

We have reviewed the respcnses to Generic Letter 83-26, Item 2.2.1 dated November 14, 1983 and October 23, 1985 provided by GPU Nuclear Company, the licensee for the Oyster Creek Nuclear Generating Station and find them generally acceptable with the following exceptions. The licensee is requested to provide additional information for these items as described below.

Evaluation and Specific Information Request:

1. Item 2.2.1 (Program):

Guidelinc:

Licensees / applicants should confirm that an equipment classification program exists which provides assurance that all safety-related components are designated as safety-related on plant documents such as drawings, procedures, system descriptions, test and maintenance instructions, operating procedures, and information handling systems so that personnel I who perform activities that affect such safety-related components are aware that they are working on safety-related components and are guided by safety-related procedures and constraints.

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l Evaluation:

The licensee failed to state that his equipment quality classificaticn list includes all safety-related components or that it forms a single, l consistent and unambiguous source of classification information as specifically requested by sub-item 2.2.1.2.

Conclusion:

The licensee's response is incomplete. They should complete their pregram l by revising their response to include all safety-related components and to describe how the information system is controlleo as requested in sub-item 2.2.1.2.

2. Item 2.2.1.2 (Information Handling System):

Guideline:

The licensee's response should confirm that the equipment classification program includes an information handling system that is used to identify safety-related equipment and components. Approved procedures which govern its development, maintenance, and validation should exist.

Evaluation:

The licensee's response identified their information handling system as a listing of safety-related components and described how it was originally prepared. The response did not describe how new safety-related items are entered on the list, how changes in the classification of listed items are made, how the listed items are verified, how unauthorized changes to the listing are prevented nor how the listing is maintained as a single, consistent, and unambiguous source of component classification information.

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Conclusion:

The licensee should supplement their response to describe precedures I which control how the list of components is revised, validated, how l unauthorized char:ges are prevented and hcw the listing is maintained as a single, consistent and unambiguous source of component classification information.

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