ML20137H768

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Safety Evaluation Supporting Amends 50 & 31 to Licenses NPF-9 & NPF-17,respectively
ML20137H768
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 01/09/1986
From:
NRC
To:
Shared Package
ML20137H764 List:
References
NUDOCS 8601210662
Download: ML20137H768 (2)


Text

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o UNITED STATES 1*

NUCLEAR REGULATORY COMMISSION h

WASHINGTON, D. C. 20555 o

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SAFETY EVALUATION REPORT RELATED TO AMENDMENT N0. 50 TO FACILITY OPERATING LICENSE NPF-9 AND TO AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY DOCKET NOS. 50-369 AND 50-370 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 INTRODUCTION By letter dated April 2,1985, Duke Power Company (the licensee) requested a revision to the Technical Specification Surveillance Requirements (3/4.1.3.3) for the rod position indication system in Modes 3, 4 and 5 (Hot standby, Hot shutdown, and Cold shutdown). The proposed change is to add a statement to allow the closing of the Reactor Trip System (RTS) breakers in order to perform the required surveillance of Specification 4.1.3.3.

In the event of an inoper-able indicator, the RTS breakers are required to be opened which would,,in preventing rod motion, increase the, time and radiation exposure associated with the surveillance. Action on that part of the proposed amendments which would have added " Control Rod Drive System capable of rod withdrawal" has been de-ferred pending receipt of further information.

l EVALUATION Surveillance Specification 4.1.3.3 requires rod position indicator (s) to period-ically be detennined to be operable by perfomance of an analog channel opera-tional test.

If a rod position indicator has been declared inoperable, the required Action is to immediately open the RTS breakers.

In this situation, the rods cannot be moved.

To perform the surveillance without moving the rods l

requires six workers in the vessel head area for three days to make all required i

connections and perform the test. This change allows the RTS breakers to be closed, but only during the surveillance, to verify rod position indicator operability by rod motion.

If the surveillance results should indicate an inoperable rod position 1.dicator, the required Action (immediately open the i

RTS breakers) remains unchanged. After completion of repairs, the surveillance would be repeated to determine operability of the indicator (s). Again, the proposed change allows the RTS breakers to be closed during this surveillance.

This process would be repeated until the indicator (s) is declared operable.

In support of the proposed change, the licensee provided the. justification and safety analysis. Because the proposed change would not affect the required shutdown margin that must be maintained in'accordance with Technical Specifica-tion 3/4.1.1.1 and 3/4.1.1.2, it would have no impact upcn plant safety and is, therefore, acceptable.

8601210662 860109 PDR ADOCK 05000369 P

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ENVIRONMENTAL CONSIDERATION These amendments involve changes to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a surveillance requirement. We have determined that the amendments involve no significant increase in the amounts and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative radiation exposure. The NRC staff has made a proposed determination that the amendments involve no significant hazards consideration, and there has been no public canment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 61.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.

CONCLUSION The Commission made a proposed determination that the amendments involved no significant hazards consideration which was published in the Federal Register (50 FR 46212) on November 6,1985 and consulted with the state of North Carolina.

No public comments were received, and the State of North Carolina did not have any comments.

We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors:

D. Hood, PAD 4, Division of PWR Licensing-A N. Trehan, Instrumentation and Control Systems Branch, DSI J. Thompson, PAD 4, Division of PWR Licensing-A Dated: January 9, 1986 t

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