ML20137Q725
| ML20137Q725 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/22/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20137Q727 | List: |
| References | |
| LSO5-85-11-031, LSO5-85-11-31, NUDOCS 8512050344 | |
| Download: ML20137Q725 (4) | |
Text
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4' UNITED STATES NUCLEAR REGULATORY COMMISSION e
o WASHINGTON, D. C. 20555 November 22, 1985 Docket No. 50-219 LS05-85-il-031 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
MAXIMUM DRYWELL TEMPERATURE Re: Oyster Creek Nuclear Generating Station Enclosed is the staff's evaluation of your letter of August 1,1985, on the drywell temperature analysis for the design basis loss-of-coolant accident (LOCA).
In that lutter, you stated that GPU Nuclear (the licensee) has re-considered the maximum allouable drywell bulk temperature prior to the LOCA and for two other events (Main Steam Line Break and Loss of Drywell Cooling) and has determined that 150 F for these events poses an insignificant reduc-tion in safety margin for the primary containment in withstanding these events. You concluded that it is safe to permit nonnal plant operations up to this maximum temperature.
Based on the enclosed safety evaluation, the staff has concluded that a maximum drywell bulk temperature of 150 F for Oyster Creek is acceptable.
As you stated in your letter, the Updated Final Safety Analysis Report (FSAR) will be revised to reflect this change to the design basis for Oyster Creek. This should be done at the next scheduled revision of the FSAR.
The Appendix A Technical Specifications (TS) for Oyster Creek do not have limiting conditions for operation or surveillance requirements on the maximum allowable drywell temperature. Such TS are in the General Electric Boiling Water Reactor Standard Technical Specifications (BWR-STS),
NUREG-0123 Revision 4, and should be in the Oyster Creek TS because this temperature is an important part of the design basis of the plant and is subject to the manner in which the plant is operated. Such TS would provide assurance that the drywell temperature does not exceed the safety analysis. You are requested to propose appropriate limiting conditions for operation and surveillance requirements for the maximum allowable drywell bulk temperature for Oyster Creek or a justification for not needing these TS before the restart from the Cycle 11 refueling (Cycle 11R) outage. We request that you also provide the algorithm for determining the drywell bulk temperature and a justification for the algorithm or propose a TS for the drywell peak temperature.
0512050344 851122 PDR ADOCK 05000219 l
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Mr. P. B. Fiedler November 22, 1985 You stated that an evaluation was being made on the aging effect of the 150*F drywell temperature on environmentally qualified equipment inside the drywell. Please provide the date when this will be submitted to the staff and what effect, if any, this 150*F would have on electrical equipment environmentally qualified under 10 CFR Part 50.49.
Sincerely.
John Zwolinski, Chief 4
Operat'ng Reactors Branch No. 5 Division of Licensing
Enclosure:
Safety Evaluation cc w/ enclosure:
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NOV 2 21985 Mr. P. B. Fiedler You stated that an evaluation was being made on the aging effect of the 150 F drywell temperature on environmentally qualified equipment inside the drywell. Please provide the date when this will be submitted to the staff and what effect, if any, this 150'F would have on electrical equipment environmentally qualified under 10 CFR Part 50.49, i
Sincerely, estslant sLW by John A Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION 1 Docket File NRC PDR Local PDR OR8#5 Rdg HThompson OELD EJordan BGrimes JPartlow JDonohew CJamerson JZwolinski ACRS (10)
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Mr. P. B. Fiedler Oyster Creek Nuclear Oyster Creek. Nuclear Generating Station Generating Station cc:
G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W.
Post Office Box 445 Washington, D.C.
20036 Forked River, New Jersey.08731 J.B. Liberman, Esquire Comissioner Bishop, Libeman, 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 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Comission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 I
BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township
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818 West Lacey Road ti Forked River, New Jersey 08731 D. G. Holland l
Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 W
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