ML19323C907

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Responds to NRC 800410 Ltr Re Clarification of Term Operable as Applicable to Single Failure Criterion for Safety Sys in Power Reactors.Units Operate in Accordance W/Sts.Util Review Concludes That Facility Is in Compliance
ML19323C907
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 05/12/1980
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NO-80-670, NUDOCS 8005190402
Download: ML19323C907 (1)


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80 0519 0 //f 2 j May 12, 1980 File: NC-3514(B) Serial No.: NO-80-670 Mr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SINGLE FAILURE CRITERIA FOR SAFETY SYSTEMS IN POWER REACTORS

Dear Mr. Eisenhut:

This letter is in response to your April 10, 1980 letter concerning clarification of the term "0PERABLE" as it applies to the single failure criterion for safety systems in power reactors.

The Brunswick units operate in accordance with Standard Technical Specifications, and our review has concluded that we are presently in compliance with your request. Therefore, no changes to our technical specifications are necessary.

If you have any questions, please contact us.

Yours very truly, 8

E. E. Utley Executive Vice President Power Supply and Engineering & Construction SHC/ JAM /jc (911887) koo!

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