ML20210H660

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Forwards Rev 1 to App D to NEDO-24195, GE Reload Fuel Application for Oyster Creek. Submitted W/Tech Spec Change Request 149 Re Cycle 11 Reload.App Summarizes Results of Cycle 11 Reload Core Design & Safety Analysis
ML20210H660
Person / Time
Site: Oyster Creek
Issue date: 09/17/1986
From: Fielder P
GENERAL PUBLIC UTILITIES CORP.
To: Zwolinski J
NRC
Shared Package
ML20210H663 List:
References
3859F, NUDOCS 8609260256
Download: ML20210H660 (1)


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100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number l

September 17, 1986 Mr. John A. Zwolinski, Chief Reactors Branch No. 5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

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Dear Mr. Zwolinski:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request (TSCR) No.149 Please find attached Revision 1 of Appendix D to NED0-24195, which was submitted with TSCR No. 149 on June 17, 1986.

The subject TSCR concerned Cycle 11 Reload.

Testing of the fuel following Cycle 10 operation necessitated the redesign of the Cycle 11 core from that which was presented in the June 17, 1986 submittal. The revised Appendix D is a summary of the results of the Cycle 11 Reload core design and safety analysis.

The previously requested technical specification changes are not altered by this revision of Appendix D.

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p r B. Fiedler Vice President and Director Oyster Creek PBF/JL/hef (3859f) cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

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