ML20064N392
| ML20064N392 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/31/1982 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20064N395 | List: |
| References | |
| NUDOCS 8209080339 | |
| Download: ML20064N392 (2) | |
Text
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GPU Nuclear r
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August 31, 1982 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Subj ec t : Oyster Creek Nuclear Generating Station Docket No. 50-219 Request for Amendment to Provisional Operating License No. DPR-16 i
Technical Specification Change Request No. 96 i
Amendment No. 79 of the Facility Description and Safety Analysis Report Pursuant to Title 10, Code of Federal Regulations, Section 50.59 and 50.90, GPU Nuclear, operator of the Oyster Creek Nuclear Generating Station, requests for amendment to the Facility Description and Safety Analysis Report (FDSAR) and amendment to Appendix A to Provisional Operating License No. DPR-16, Technical Specifications and Bases for Oyster Creek Nuclear Generating Station.
We have previously submitted NEDO-24195, General Electric Reload Fuel Application for Oyster Creek by our letter of April 21, 1980.
This report describes General Electric (GE) supplied reload fuel mechanical design, nuclear evaluation methods, steady-state hydraulic models, and reactor limits determination information, which are identical to NEDO-240ll-P-A, GE Generic Reload Fuel Application Licensing To pical Re por t,
except those features and considerations unique to the Oyster Creek application. We also submitted by our letter of March 9, 1981, Appendix A to NEDO-24195, Oyster Creek Reference Cycle Supplement, which presents a core loading pattern, core composition, and all core design parameters and safety analysis results similar to Appendix A to NEDO-240ll-P-A.
The purpose of this submittal is to incorporate (1) GE supplied reload fuel and core design features of NEDO-24195 into the Oyster Creek FDSAR, and (2) those limits for operation of Cycle 10 and future cycles determined by methods described in NEDO-24195 and current FDSAR including all applicable amendments into Appendix A, Technical Specifications and Bases to Provisional Operating License No. DPR-16, Oyster Creek Nuclear Generating Station.
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PDR GPU Nuclear is a part of the General Public Utilities System
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2 The subject Technical Specification Change Request involves Sections 1,
2.1, 2.2, 2.3, 3.1, 3.2, 3.4, 3.5, 3.10, 4.2 and 4.10.
Plant transient analysis by GE's ODYN computer code and part of ECCS-LOCA analysis are not included in this submittal and will be submitted at a later date.
We anticipate these analyses will be submitted by December 31, 1982.
These proposed Technical Specification changes and our previous submittals of April 21, 1980 and March 9, 1981 provide the bases for the Oyster Creek Cycle 10 reload.
The FDSAR Amendment No. 79 and Technical Specification Change Request No.
96 have been reviewed and approved by the Plant Operations Review Committee and and Independent Safety Review Group in accordance with Section 6.5 of the Oyster Creek Technical Specifications.
previously determined that this change request was Class IV per 10 It was CFR 170.22.
Therefore, pursuant to that section a check was enclosed for
$ 12,300 and was included in the April 21, 1980 submittal.
Since this submittal furnishes information which is a continuation of the previous submittals, no additional fee is being submitted at this time.
Very truly yours, d
iedler Vice President and Director - Oyster Creek Ir