ML20127A075

Forwards Rev 1 to Spent Fuel Storage Capacity Mod SAR & Safety Evaluation for Design & Installation of New High Density Spent Fuel Racks, Per Request for Approval of New Spent Fuel Storage Racks

ML20127A075
Person / Time
Site:	Peach Bottom
Issue date:	08/01/1985
From:	Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML20127A081	List: ML20127A075 ML20127A087 ML20127A091
References
NUDOCS 8508050392
Download: ML20127A075 (2)

Text

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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. DALTROFF ELacinic PR o c loN August 1, 1985 I Docket Nos. 50-277 50-278 Mr. Hugh L. Thompson, Jr., Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l l

SUBJECT:

Peach Bottom Atomic Power Station Unit 2 and 3- Installation of New Spent Fuel Storage Racks

REFERENCE:

Letter, S. L. Daltroff to Hugh L. Thompson, June 13, 1985 - Request for Approval of New Spent Fuel Storage Racks

Dear Mr. Thompson:

The " Spent Fuel Storage Capacity Modification Safety i Analysis Report", Revision 0, dated May, 1985 was submitted with '

the letter referenced above.

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Revision 0 of the Report discussed the methodology and acceptance criteria for the analyses of the new spent fuel racks.

The June 13 letter indicated that certain confirmatory analytical work to be included in the Report had not yet been completed.

However, due to schedule constraints described more fully in the letter, we requested that the NRC commence its review of the acceptability of the new racks based upon Revision O of the Report so as to permit completion of the review and approval of the racks by no later than January 1, 1986. All analyses have been completed and have been incorporated into Revision 1 of the attached Report. These additions are identified by a vertical bar in the margin of the Report.

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Mr. Hugh L. Thompson, Jr. August 1, 1985 Page 2 Further, we are also submitting a Safety Evaluation dated July 1985 which directly addresses the criteria of 10 CFR Section 50.59 and which concludes that there are no unreviewed safety questions concerning the new fuel racks. Copies of the Safety Evaluation, along with Revision 1 of the Spent Fuel Storage Capacity Modification Safety Analyses Report, dated July, 1985, are transmitted herewith.

Should you have any questions or need additional information, please do not hesitate to contact us.

Very truly yours,

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Attachments cc: Dr. T. E. Murley, Administrator, Region I, USNRC T. P. Johnson, Resident Site Inspector

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