ML17262A523

Forwards Request for Addl Info Re Licensee 910128 Submittal Concerning Facility Containment Integrity

ML17262A523
Person / Time
Site:	Ginna
Issue date:	06/25/1991
From:	Andrea Johnson Office of Nuclear Reactor Regulation
To:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
References
TAC-80494, NUDOCS 9107020361
Download: ML17262A523 (4)

Text

June 25, 1

Docket No. 50-244 Dr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas It Electric Corporation 89 East Avenue Rochester, New Yor k 14649 Distribution:

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HAshar, ESGB

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RE:

GINNA CONTAINMENT INTEGRITY (TAC NO. 80494)

After reviewing your submittal dated January 28, 1991, a number of questions were raised in a teleconference dated March 13, 1991.

During that teleconference a request was made to provide results of a number of analyses incorporating various base conditions of the containment.

Your latest submittal, dated April 15, 1991, provided the requested information related to the analyses performed.

However, it failed to provide adequate justification regarding the potential behavior of the containment, and how the large differences between the resulting forces at the base (new analyses) and those calculated in the original containment design are reconciled with.

This was discussed during a teleconference on June 4, 1991.

Enclosed is a formal request for the information sought during the later teleconference.

Response

to the enclosed Request for Additional Information (RAI) is requested within 30 days from receipt of this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.

Should you have any questions regarding this RAI, please contact your Project Manager.

Enclosure:

As stated Sincerely, iIrigi~aI signa/

by. Pgtlick N. Sears for Project Directorate PDI-3 Division of Reactor Projects Office of Nuclear Reactor Regulation FC cc w/enclosure:

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PDR ocument Name:

GINNA GL 8910 TAC NO. 80494

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Dr. Robert C. Hecredy Ginna CC:

Thomas A. Hoslak, Senior Resident Inspector R.E.

Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

'ntario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Charlie Donaldson, Esq.

Assistant Attorney General New York Department of Law 120 Broadway New York, llew York 10271 Nicholas S.

Reynolds Winston

& Strawn 1400 L St.

N.W.

Washington, DC 20005-3502

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION GINNA NUCLEAR POWER PLANT CONTAINMENT INTEGRITY 1.

In reference 2, it is stated (P.

5 of the report), "For all cases, the results have shown no more than 10% increase from the original design value."

The staff review of attachment 1 of reference 1 indicates that at 3 feet above the base, the magnitude of the meridional moments can be larger than twice the original design value and under some conditions (fixed) they could be in the opposite direction.

Provide justification for 10% claim in the statement.

2.

Provide interaction diagrams for negative meridional moments

( liner in tension).

Provide comparison of meridional moments found in the reanalyses that you have already performed for various base conditions against the capacity at 3 feet and 6 feet above the base.

3.

In the above comparisons where the capacity falls short of the demand induced by the appropriate load combination, provide the necessary justification for assuring containment integrity and propose what physical evidence can be obtained about the true base condition during an integrated leak rate test.

4.

Provide calculations (or results of computer output) for maximum shear stresses in the basemat of the containment under hydrostatic pressure due to highest ground water level to be considered in the design, and how the thinnest basemat sections can withstand the shear stresses.

References 1.

Letter (with five attachments) from Robert C. Mecredy to NRC dated April 15, 1991.

2.

Letter (with six attachments) from Robert C. Mecredy to NRC dated January 28, 1991.