ML17251B049

Discusses Proposed Mod to Existing Steam Generator Upper Lateral Configuration & Analysis to Demonstrate Acceptability of Resulting Loads from Postulated Seismic & Other Design Bases Events

ML17251B049
Person / Time
Site:	Ginna
Issue date:	04/13/1988
From:	Stahle C Office of Nuclear Reactor Regulation
To:	Kober R ROCHESTER GAS & ELECTRIC CORP.
References
NUDOCS 8804180285
Download: ML17251B049 (3)

Text

April 13, 1988 Docket No. 50-244 Mr. Roger M. Kober, Vice President Electric 5,Steam Production Rochester Gas

& Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

SNUBBER REPLACEMENT PROGRAM AT GINNA 0

On November 20,

1987, a summary report of the Steam Generator Snubber Replacement Program was provided to the staff for review.

This report described a proposed modification to the existing SG upper lateral support configuration and an analysis to demonstrate the acceptability of resulting loads from postulated seismic and other design bases events.

The intent of the proposed modification is to replace six of the eight hydraulic snubbers of each SG with rigid structural members (bumpers).

Subsequent discussions between RGE personnel and NRC staff have identified the need for additional information in order for us to complete the review.

It was also determined that your request for such a modification should be submitted as an amendment to the Technical Specification.

Enclosed is the request for additional information on the snubber replacement program.

To resolve the remaining issues as expeditiously as possible, please provide your proposed amendment no later than 30 days from the receipt of this letter.

If a meeting is required to further c'tarify the enclosed

requests, do not hesitate to call.

Enclosures:

's stated Sincerely, Original Sieved h~

Carl Sta e, R oiect Manager Project Directorate I-3 Division of Reactor Projects I/II cc:

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Re uest For Additional Information on Ginna SG Snubber Re lacement Pro ram 1.

The size and basis of the bumper aaps in the cold condition.

2.

The detailed calculations of the cold-shut-down condition loads in all steam generator

supports, reactor vessel supports and reactor coolant pump supports, when subjected to SSE seismic loading.

3.

The calculation of the minimum, maximum and average steam generator upper stiffnesses and their inclusion in the RCL model.

4.

The justification of the thrust coefficients used for the time-history analysis of the steam generator outlet nozzle and the feedwater nozzles.

5.

Description of the non-linear time-history analyses of the RCL when subjected to loading due to postulated breaks at the pressurizer

surge, RHR and SI.accumulator nozzles, and the SG steam outlet nozzle and the feedwater nozzles.

This should include the specified time-history loading forcing functions.

6.

Provide clarification of the modeling and calculational results of the two analyses which are performed in the hot condition.

Mr. Roger W. Kober Rochester Gas and Electric Corporation R.

E. Ginna Nuclear Power Plant CC:

Harry H. Yoigt, Esquire

LeBoeuf, Lamb, Leihy 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 World Trade Center New York, New York 10047 Mr. Bruce A. Snow, Superientendent Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, N.Y. 14649-0001 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 Pegional Administrator, Region I

U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road

Ontario, New York 14519 Ms.

Donna Ross Division of Policy Analysis 8 Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223