ML19341C009

Safety Evaluation Supporting Amend 1 to License NPF-9

ML19341C009
Person / Time
Site:	McGuire
Issue date:	01/28/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19341C005	List: ML19341C004 ML19341C007 ML19341C009
References
TAC-46812, NUDOCS 8102280389
Download: ML19341C009 (2)

Text

O s^rerv evatu^110" av 1"e OFFICE OF NUCLEAP REACTOR REGULATION RELATED TO AMENDMENT N0. 1 TO LICENSE HPF-9 DUKE POWER COMPANY Introduction The status of the staff review of the McGuire engineered safety feature actuation system is presented in section 7.0, subsecticn 7.3 of Supplement No. 4 to the Safety Evaluation Report (NUREG-0422), January,1981. Our evaluation shows that although we have not completed our review, the staff concludes that plant operation below 5 percent during completion of confirmatory testing of the system is acceptable and that this testing would be completed prior to fuel loading.

This safety evaluation report docunents the basis for modification (perform confirmatory testing prior to initial criticality) of operating license section 2.C.(12) which reflects this conclusion.

Evaluation The design of the McGuire engineered safety feature actuation system provides that upon reset of an engineered safety feature actuation signal all safety-related equipment remains in its emergency mode. Confirmatory testing will provide

-additional assurance of this design feature. The requested change for performance of this testing for the period prior to initial criticality of the reactor core is acceptable since no heat is generated by the reactor core and there is no fission product inventory in the core.

In the event of an engineered safety feature actuation and reset during this time period, the failure of any safety-related equipment to remain in its emergency mode would not result in the release of any radiation.

Environmental' Consideration We hav) determined that the'~ amendment does not authorize a change. in effluent types or total amounts nor an iiicrease in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Section 51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.

Conclusion We have concluded, based on the considerations discussed abcve, that:

.(1) because the amendment does not involve a significant increase in the probability of consequences of accidents previously considered and does not 8102280 @ %

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2-involve a significant decrease in a safety rargin, the anendrent does not involve a significant hazards consideration, (2) there is reasonable assur-ance that the health and safety of the public will not be endangered by operation in the proposed canner, and (3) such activitier will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

DATE: JAN 2 81931 G

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