ML20101L792

Forwards Rev 0 to Rept 42112-R-001, Oyster Creek Nuclear Generating Station USI A-46 Seismic Evaluation Rept, Per GL 87-02

ML20101L792
Person / Time
Site:	Oyster Creek
Issue date:	03/29/1996
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20101L795	List: ML20101L792 ML20101L804
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR 6730-96-2085, GL-87-02, GL-87-2, NUDOCS 9604040218
Download: ML20101L792 (2)

Text

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8 GPU Nuclear Corporation N ', g Post Office Box 388 Route 9 South Forked River, New Jersey 00731-0388 609 971-4000 Writer's Direct Dial Number:

March 29, 1996 6730- % 2085 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 i

l Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Operating License No. DPR-16 Docket No. 50-219 USI A-46 Seismic Evaluation Report  ;

l On February 9,1987 the NRC issued Generic Letter (GL) 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety )

Issue (USI) A-46". This Generic letter encouraged utilities to participate in a generic <

program to resolve the seismic verification issues associated with USI A-46. As a result, the ,

Seismic Qualification Utility Group (SQUG) developed the " Generic implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment." l 1

l On May 22,1992, the NRC staff issued Generic Letter 87-02, supplement I which required i that all addressees provide either (1) a commitment to use both the SQUG commitments and the implementation guidance described in the GIP, Revision 2, as corrected on February 14, 1992, and as supplemented by the staff's Supplemental Safety Evaluation Report No.2 (SSER- 1

2) or (2) an alternative method for responding to GL 87-02. The supplement also required that those addressees committing to implement GIP-2 provide an implementation schedule as well as detailed information including the procedures and criteria used to generate the histructure response spectra to be used for USI A-46.

By letter dated September 14,1992 GPU Nuclear provided its response to Supplement I to GL  ;

87-02 for Oyster Creek Nuclear Generating Station. In the letter GPU Nuclear committed to j follow the SQUG commitments set forth in the GIP, including the clarifications and exceptions identified in SSER-2. Our letter dated June 30,1995 stated that GPU Nuclear would submit the summary report by March 29,1996.

9604040218 960329 PDR ADOCK 05000219 F PDR i uy000 1 0

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GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation

I 6730-96-2085 Page 2 On December 23,1993 GPU Nuclear submitted information concerning the method and criteria for developing in-structure response (IRS) spectra to be used for the resolution of USI l A-46. The NRC staff in their letter dated February 23,1995 concluded that the approach j proposed for generation of IRS is consistent with the provisions of the Standard Review Plan l and is therefore acceptable for the resolution of USI A-46 as well as for future designs and evaluations.

. The attached summary report, " Oyster Creek Nuclear Generating Station, USI A-46 Seismic l

Evaluation Report" (Report No. 42112-R-001) documents the results of the safe shutdown equipment identification, the screening verification and walkdown of equipment including certain Regulatory Guide 1.97 components , the relay evaluation, the tank and heat exchanger review, the cable and conduit raceway review and the outlier identification and resolution.

The report also provides the modification schedule for resolving outliers.

l Of all the work performed for the Oyster Creek's USI A-46 program including the 390 Safe l

Shutdown Equipment List (SSEL) component evaluations, the relay reviews, and the cable tray and conduit evaluations, approximately 64 modifications remain to be completed to resolve outliers identified during the effort. All of these modifications are expected to be completed by the end of the seventeenth refueling outage (17R) which is currently scheduled to commence on September 12,1998. All outliers identified during the program will be resolved by further analysis or by modification. No outliers will remain unresolved beyond the eighteenth refueling outage (18R). Outliers identified during the walkdown were evaluated l for operability concerns and as a result some items (13 ) were either repaired immediately or justified analytically for continued plant operation. Additional modifications were completed during or subsequent to the walkdown.

i If you have any questions concerning the information provided in the summary report, please contact Y. Nagai, Corporate Regulatory Affairs, at (201) 316-7974.

1 Very truly yours,

b l Michael B. Roche Vice President & Director Oyster Creek MBR/YN/gl Attachment cc

Administrator, Region I (w/o Attachment)

NRC Project Manager (w/o Attachment)

NRC Resident inspector (w/o Attachment)