ML19095A070

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Supplemental Information to Amendment to Operating License Technical Specifications Change No. 47, to Include LOCA-ECCS Reanalysis
ML19095A070
Person / Time
Site: Surry  Dominion icon.png
Issue date: 10/29/1976
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Reid R, Rusche B
Office of Nuclear Reactor Regulation
References
Serial No. 219/082776
Download: ML19095A070 (1)


Text

R1c11MOND,V1uo1NIA 23261 October 29, 1976 Mr *. Benard C. Rusche, Director Office of Nuclear Reactor Regulation Attn:

Mr. Robert W. Reid, Chief Operating Reactors Branch Division of Operating Reactors U. S. Nuclear Regulatory Corrunission Washington, D. C.

20555

Dear Mr. Rusche:

Serial No. ;?..19/ogz.7 76 FR/MLB/EJL/RWC:crl Dockets No.

50-280 50-281 License Nos. DPR-32 DPR-37 SUPPLEMENTAL INFORMATION TO AMENDMENT TO THE OPERATING LICENSE TECHNICAL SPECIFICATIONS CHANGE NO. 47 SURRY POWER STATION UNITS 1 AND 2 Pursuant to 10CFR50.90, the Virginia Electric and Power Company, in our letter of September 27, 1976 (Serial No. 256), requested an amendment to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 and 2.

The amendment requested was a change to the Technical Speci-fications, designated as Change No. 47, which resulted from the reload core design for Surry 1, Cycle 4.

However, the amendment did not include the LOCA-ECCS rean~lysis required by the August 27, 1976 Order for Modification of License.

This reanalysis has now been completed> and the results are trans-mitted herewith as Attachment 1.

Also, the additional changes to the Techni-cal Specifications resulting from the reanalysis are transmitted herewith as.

Please note that for completeness, the changes to the Technical Specifications previously transmitted in the September 27, 1976 amendment are also included in Attachment 2.

All changes have been reviewed by both the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Corrunittee.

Further, it has been detennined that these changes do not involve an un-reviewed safety question as defined in 10CFR50.59.

Presently, Unit 1 is shut down for refueling.

We expect to complete the refueling in early December, 1976.

Should you have any questions or comments, we would be most happy to meet with you at your earliest convenience.

40 copie.s

, Attachments cc:

Mr. Normnn c. Moseley Very. truly yours,.

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C. M. Stallings Vice President-Power Supply and Production Ope~ations

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