ML20065U412
| ML20065U412 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/26/1990 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-90-2038, GL-89-10, NUDOCS 9101020306 | |
| Download: ML20065U412 (2) | |
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GPU Nuclear Cor;x> ration 3 ~ 9 tuclear
= 3 r 388 Forked River, New Jersey 08731-0388 609 971 4000 Writer's Direct Dial Nurnber; Dec ember 26, 1990 C321-90-2038 U.S.
Nuclear Regulatory Commission Attn Document Control Desk Washington, D.C.
20555 Dear Sir
Subject:
Oyster-Creek Nuclear Generating Station Docket No. 50-219 Generic Letter 89-10, Supplement No. 3 Cn October 25, 1990, the USNRC issued Generic Letter 89-10, Supplement 3,
" Consideration
'f the Results of NRC Sponsored Tests of Motor Operated valves." Thi document contained a required response within 30 days of receipt of the supplement. This letter is being written to request an extension of that 30 day interval to February 15, 199f.
The basic intent of GL 89-10, Supplement 3, was to assign priority within the previously determined scope of work described in the original Generic Letter.
The priority which had been selected by GPU Nuclear due to'on-going inspection programs to ensure the integrity of the reactor pressure boundary did not closely reflect the priority selected by the NRC.
Accordingly, a majority of the efforts expended by GPU Nuclear to date were not a significant contribution to the effort now requested by the USNRC.
In addition, the engineering resources which had been dedicated to supporting the NRC Diagnostic Evaluation Team Inspection were not available to assist in the Generic Letter response until recently.
A preliminary evaluation of the systems designated by the NRC in GL 89-10 Supplement 3 has determined that there are no immediate safety concerns associated with these systems.
Additionally, a preliminary review of other motor operated valves has disclosed no deficiencies of greater safety significance than that noted in Supplement 3.
A complete safety assessment is in progress and is presently projected for completion by February 15, 1990.
A full response as required by GL 89-10 Supplement 3-will be provided by that date.
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If any further information is required, please contact Mr. John Rogers, Oyster Creek Licensing Engineer-at 609-971-4893.
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Very truly yours,
',t e
- E. E'.. F spatrick Vice President and Director
-Oyster Creek EEF/JJR/jc cc Mr. Thomas Martin, Administratori Region i U.S. Nuclear. Regulatory Commission 475 Allendale' Road j
King of Prussia, PA--19406 I
NRC Resident Inspector oyster Creek Nuclear' Generating Statior 1
Mr. Alexander Dromerick.
U.S. Nuclear Regulatory Commission-j Mail Station P1-137 Washington, DC 20555-
~ (C3212038)'
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