ML20247K098
| ML20247K098 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/15/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| References | |
| IEB-79-02, IEB-79-14, IEB-79-2, TAC-68217, NUDOCS 8909210071 | |
| Download: ML20247K098 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION l
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WASHINGTON, D. C. 20555
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e e er 15, G 89 Docket io. 50-219 Mr. E. E. Fitzpatrick Vice President and Director Oyster Creek Nuclear Generating Station i
Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
SUBJECT:
UPGRADE OF PIPE SUPPORTS AND ANCHORAGES TO MEET IEB 79-02 AND IEB 79-14 USING THE NEW FLOOR RESPONSE SPECTRA-0YSTER CREEK NUCLEAR' j
GENERATINGSTATION(TACNO.68217)
References:
1.
Letter from A. Dromerick (NRC) to E. Fitzpatrick (GPUN),
dated October 17,-1988.
2.
Letter from GPUN to NRC on the subject of Seismic Floor Response Spectra dated Sept. 19, 1988.
During the Systematic Evaluation Program (SEP) implementation, major safety related structures and components were evaluated to ensure compliance with the updated seismic requirements. However, all pipe supports and their anchorages were not evaluated to ensure compliance with IE Bulletins (IEB) 79-02 and 79-14. To assure NRC that the existing pipe support and enchorage designs (as built) would satisfy the requirements of the Bulletins, the lic6:nsee initiated a seismic reevaluation program that would reduce the floor response spectra compared to the ones developed during SEP reviews. The new reduced floor spectra are based on the expected staff adoption of a relaxed position regarding the location of input ground motion and the corresponding position requiring detailed soil-structure interaction analysis. The program was initiated by the licensee in July.1987.
A number of meetings and information exchanges occurred between July 1987 and June 1988. During the last meeting with the licensee on May 28, 1988, the licensee had committed to resolve these issues he' ore the 12th refueling Cycle of the plant so that the recuired modifications could be performed during the refueling outage.
Instead, the licensee sent a letter (reference 2) summarizing the stttus of vcrious supports and anchorages and describing the plans to l
resc1ve the issues by the end of Cycle 12 outage. The staff accepted the l
licensee's plans (reference 1) in order to expedite resolution of the Bulletins. However, resolution has not progressed at the timely rate which had been anticipated. Therefore, we require that GPU Nuclear Corporation take the following actions:
- All the pipe supports must meet the provisions of IEB 79-14 using the loads from the original FSAR criteria. Reference 2 indicates approximately 14% of the pipe supports are in this category.
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Mr. E. E. Fitzpatrick -
- All the support anchorages must meet the provisions of IEB 79-02 using the loads from the original FSAR criteria. Approximately 15% of the support anchorages would be in this category.
Your analysis results and implementation of any raodifications required should be completed prior to restart from the 13R refueling outage.
The staff will perform an aucit of the calculations related to the appropriateness of seismic spectra damping values, loads, load combinations and extent of compliance with the Bulletin criteria.
We request that you respond within 30 days of receipt of this letter indicating your intent to comply with these requirements.
Sincerely, e
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Jo n F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page
Mr. E. E. Fitzpatrick l
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All the support anchorages must meet the provisions l
of IEB 79-02 using the loads from the original FSAR criteria. Approximately 15% of the support anchorages would be in this category.
Your analysis results and implementation of any modifications required should be completed prior to restart from the 13R refueling outage.
The staff will perform an audit of the calculations related to the appropriateness of seismic spectra damping values, loads, load combinations and extent of compliance with the Bulletin criteria.
We request that you respond within 30 days of receipt of this letter indicating your intent to comply with these requirements.
Sincerely, signed by Peter Tam for John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION
. Docket File =
NRC & Local PDRs Plant File S. Varga (14E4)
B. Boger (14A2)
S. Norris A. Dromerick OGC E. Jordan (tiriBB3302)
B. Grimes (9A2)
ACRS (10)
[ TAC 68217]
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09/lS/89 09
/89 09//178
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i Mr. E. E. Fitzpatrick Oyster Creek Nuclear y
Oyster Creek Nuclear Generating Station Generating Station cc:
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Ernest L. Blake, Jr.
Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 l
Washington, D.C.
20037 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 101 Comerce Street New York, New York 10036 Newark, New Jersey 07102 Jennifer Moon, Acting Chief Regional Administrator, Region I New Jersey Department of Environmental U.S. Nuclear Regulatory Commission Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 CN 415 Trenton, New Jersey 08625 BWR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Departir.ent 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
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Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey C8731
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