ML20036C098

Provides Status of Effort in Response to IE Bulletin 79-02 at Plant

ML20036C098
Person / Time
Site:	Oyster Creek
Issue date:	06/04/1993
From:	Keaton R GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
5000-93-2093, C321-93-2093, IEB-79-02, IEB-79-2, NUDOCS 9306140066
Download: ML20036C098 (2)

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GPU Nuclear Conxpration Mgaye One Upper Pond Road -

wawMu Parsippany, New Jersey 07054 l

201-316-7000 l

TELEX 136-482 Writers Direct Dial Numbec June 4, 1993 5000-93-0040 C321-93-2093 t

U. S. Nuclear Regulatory Commission Att:

Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 Completion of IEB 79-02 Requirement

Reference:

(1) GPU Nuclear letter dated September 19, 1988, " Seismic Floor Response Spectra."

i (2) NRC letter dated September 15, 1989, " Upgrade of Pipe Supports and Anchorages to Meet IEB 79-02 and IEB 79-14 Using the New Floor Response Spectra - Oyster Creek Nuclear Generating Station."

In response to your recent request, this letter provides the status of GPUN's effort in response to IEB 79-02 at OCNGS.

Our letter of September 19, 1988 (Reference 1) transmitted a " pie-chart" showing the status of IEB 79-02 anchorage inspections as of September 9, 1988.

The chart indicated that 67 anchorage inspections had not been completed.

The letter also indicated that all remaining anchor-bolted base plates in the IEB 79-02 scope had previously been either inspected, qualified on the bases of high calculated factors of safety (>20), determined to have adequate QA documentation or upgraded.

During refueling outage 12R which ended in May 1989, GPUN completed the remaining 67 anchorages using the methodology discussed in the

.l September 19, 1988 letter.

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i Based on the anchor-bolt design criteria documents, wedge-type anchor-bolts with factors of safety between 4 and 20, and shell-type anchor-bolts with factors of safety between 5 and 20 were inspected and appropriate QA documentation was generated by recording the actual anchor-bolt installation.

i Factors of safety for the anchor bolts were determined from the piping-analysis performed using the original design basis Housner spectrum provided in the OCNGS FSAR consistent with th9 NRC letter dated September 15, 1989 l

(Reference 2).

j If you have any questions regarding the information provided in this letter,.

please call Mike Laggart, Manager, Corporate Nuclear Licensing, at (201) 316-7968.

Sincerely, R. W. Keaten Vice President and Director Technical Functions RWK\\YN\\plp cc: Administrator, Region I Oyster Creek NRC Project Manager Oyster Creek Senior Resident Inspector

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