ML20024B748
| ML20024B748 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/07/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| JPN-83-65, NUDOCS 8307110309 | |
| Download: ML20024B748 (2) | |
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123 Main Street White Plains, New York 10601 914 681 6240 1
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July 7, 1983 3m-83-65 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Domenic B.
Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Potential Pipe Support Design Nonconformance
Dear Sir:
The Power Authority has been informed by one of our technical consultants of a potential nonconformance in the reanalysis of 348 pipe supports installed in the FitzPatrick plant.
The potential nonconformance involves only the design of the supports for normal loads.
The design of the supports for seismic loads was completed in accordance with the applicable codes, standards and methodology approved by the NRC.
Therefore, the seismic design of the pipe supports is not in question.
The consultant has also identified approximately 20 additional supports which may be affected.
The Authority is taking immediate action to evaluate the potential nonconformance.
A visual inspection of the twenty potentially affected pipe supports is in progress.
The Authority will employ another consultant, not previously involved in pipe support analysis for the FitzPatrick plant, to review and evaluate the potential nonconformance.
The Authority's preliminary determination, which is based on the information now available and therefore which is subject to change, is that evaluation of this potential nonconformance is unlikely to show a condition whicn is reportable under 10 CFR 21.
i Y
8307110309 830707 PDR ADOCK 05000333 IO S
PDR I
The FitzPatrick plant is currently in the cold condition for a refueling outage.
Most of the potentially affected pipe supports are not subject to the loads for whicn their design has been questioned.
Therefore, the health and safety of the public are not affected.
Tne Power Authority will complete the evaluation of the potential nonconformance prior to startup from the current refueling outage, and inform the NRC of the results.
If you have any further questions, please contact Mr. J.A. Gray, Jr.,
of my staff.
Very truly yours,
- ("^
J s
xecutive Vice President Nuclear Generation cc:
Mr. Harry B.
Kister United States Nuclear Regulatory Commission Region I 6 3L Park Avenue King of Prussia, Pa.,
19406 Mr. J.
Linville Resident Inspector U.S.
Nuclear Regulatory Commission P.O.
Box 135 Lycoming, NY 1309 3