ML20045H714
| ML20045H714 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/12/1993 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20045H715 | List: |
| References | |
| C321-93-2150, NUDOCS 9307210172 | |
| Download: ML20045H714 (2) | |
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i GPU Nuclear Corporation Nuclear
= e = 388 Forked River, New Jersey 08731-0388.-
609 971-4000 Wnter's Direct Dial Number:
July 12,1993 1
C321-93-2150 8
U. S. Nuclear Regulatory Commission
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Att:
Document Control Desk Washington, DC 20555 q
Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station (0CNGS) j
~
Docket No. 50-219 Facility Operating License No. DPR-16 Technical Specification Change Request No.198, Rev.1 Drywell Pressure / Temperature Change
References:
(1) GPUN Letter C321-91-2197, " Provisional Operating License Technical Specification Change Request No.198 -
Drywell Pressure Change," July 22. 1991.
i (2) GPUN Letter C321-92-2040, ' Reactor Vessel Blowdown Multipliers," February 14, 1992.
Pursuant to 10 CFR 50.90, GPU Nuclear Corporation, operator of the Oyster Creek Nuclear Generating Statien (OCNGS), Facility Operating License No. DPR-16, requests a change to Appendix A of that license via a revision to the request made by Reference 1.
This revision is in response to a verbal NRC request made as part of the NRC review of _the Reference 1 change request and the Reference 2-additional supporting basis. This revision to Technical Specification Change Request (TSCR) No.198 changes the drywell temperature to be consistent with the saturation temperature for the proposed revised drywell. pressure ~ of 44 psig.
This temperature is 292 F as determined by the supporting evaluations' detailed in the Reference 1 submittal. This revision to TSCR No. 198 also adds a Basis section for the TSCR and provides_a revised TSCR page 3.4-8 (previously 3.4-7)' which reflects those TS Amendments approved subsequent 'to the Reference I submittal.
This revised change request has been reviewed in accordance with Section 6.5 of the OCNGS Technical Specifications, and using the standards in 10 CFR 50.92 we have concluded that these proposed changes do not constitute a significant hazards consideration.
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