ML17254A516

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Forwards Safety Evaluation Conditionally Accepting Licensee 831104 & 850319 Responses to Generic Ltr 83-28,Item 4.3 Re Reactor Trip Breaker Automatic Shunt Trip.Addl Responses Re Testing & Bypass Breaker Interlocks Requested
ML17254A516
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/19/1985
From: Zwolinski J
Office of Nuclear Reactor Regulation
To: Kober R
ROCHESTER GAS & ELECTRIC CORP.
Shared Package
ML17254A517 List:
References
GL-83-28, LSO5-85-08-021, LSO5-85-8-21, NUDOCS 8508200357
Download: ML17254A516 (4)


Text

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UNITED STATES NUCL AR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 19, 1985 Docket No 50-244 LS05-85-05-021 Mr. Roger W. Kober, Vice President Electric and Steam Production Rochester Gas

& Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Mr. Kober:

SUBJECT:

REVIEW OF DESIGN FOR AUTOMATIC SHUNT TRIP FOR REACTOR TRIP BREAKERS (Generic Letter 83-28, Item 4.3)

Re:

R. E. Ginna Nuclear Power Plant By letters dated November 4, 1983, and March 19, 1985, Rochester Gas and Electric Corporation provided responses to Generic Letter 83-28 including Item 4.3, Reactor Trip Reliability (Automatic Actuation of the Shunt Trip Attachment for Westinghouse plants).

Included also was a response to plant specific questions identified in the NRC evaluation of the Generic Westinghouse design which was submitted by the Westinghouse Owner's Group on June 14, 1983.

Enclosed is the staff's safety evaluation (SE) which addresses your response to Item 4.3 of Generic Letter 83-28, and the staff position on Reactor Trip Bypass Breaker Position Indication.

We find that the design modifications are acceptable, except as noted in the SE.

You should provide responses to the staff positions regarding on-line

testing, the provision of the test features used for on-line testing, the provision of bypass breaker position indication, and bypass breaker interlocks.

Also, you should provide a response to the confirmatory items that are summarized in the Conclusion section of the SE.

This information is necessary in order to permit the completion of this review and should be s'upplied within 90 days of the receipt of this letter.

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Roger W. Kober August 19, 1985 In addition, you should submit proposed technical specifications which are responsive to the staff requirements noted in the enclosed SE.

Since the submittal of a proposed technical specification is not a prerequisite for implementation of this modification, any proposed technical speci-fication change will be reviewed as a separate item covered by Generic Letter 83-28.

This request for information was approved by the Office of Management and Budget under clearance number 3150-0011.

Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D. C. 20503.

Sincerely,

Enclosures:

1.

Safety Evaluation 2.

Staff Position gj'intel Signeh by:

John A. Zwolinski, Chief Operating Reactors Branch ¹5 Division of Licensing cc: w/enclosures:

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Mr. Poger W. Kober Pochester Gas and Electric Corporation P,.

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Ginna Nuclear Power Plant CC:

Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire
Avenue, N.W.

Suite 1100 Washington, D.C.

20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 l!orld Trade Center New York, New York 10047 Resident Inspector R.E.

Ginna Plant c/o U.S.

NRC 1503 Lake Road

Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Pa>k Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
Ontario, New York 14519 ilay Dunkleberger Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza
Albany, New York 12223