ML17262A656

Requests Addl Info on Licensee Response to Issue 3 Re Containment Integrity.Informs That Responses to Issues 1,2 & 4 Acceptable

ML17262A656
Person / Time
Site:	Ginna
Issue date:	10/23/1991
From:	Andrea Johnson Office of Nuclear Reactor Regulation
To:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
References
TAC-M80494, NUDOCS 9111190194
Download: ML17262A656 (5)

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Docket Ho. 50-244 UNITEDSTATES, NUCL'EAR REGULATOR%COMMISSION'ASHINGTON, O. C. 20555 October 23, 1991 D'r. Robert C. Mecredy-; Vice President Ginna Nuclear Productiori Rochester Gas Im Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

GINNA CONTAINMENT INTEGRITY - REQUEST FOR ADDITIONAL INFORMATION (RAI) - R.

E.

GINNA NUCLEAR POWER PLANT (TAC NO. 80494)

REFERENCES:

1.

RG&E (Hecredy) Letter to NRC (Document Control Desk Attn: Johnson)

Ginna: Containment..Integrity.

RAI., dated..

July 11, 1991.

2.

NRC (Johnson)

Letter to RGIIE (Necredy),

RAI, dated June 25, 1991.

I The information in the above reference 1 has been reviewed by the NRC staff.

Responses to Issues No. 1, 2, and 4 raised by the staff are acceptable.

RGKEs response to Issue No.

3 (Reference 1 and 2) is incomplete.

Response

No.

3 makes the comparison of the original structural integrity test (SIT) measurements at the base with the displacements obtained from the

.RGE03 analysis.

This is not appropriate, because the RG03 analysis pertains to seismic loading 'only.

A comparison with the RGE08 analysis would be more appropriate, but the calculated displacements from the RGE08 analysis at the base do not match with the original SIT displacements.

The fact that the actual displacements at the base are significantly lower than those obtained from the RGE08 analysis is an indication that the containment is stiffer at the base than originally assumed.

The staff,'s; basic, concern i.s: the.potentia,l, behav.ior.

of-the containment at the.

base, particularly when 'the'ase had been subjected to years of potenti'al water damage

( stiffening of neoprine pad, possible rusting of steel plates, inoperability of tension bars and. expans.ion bellows)..

As this aggregate effect of potential damage can not be verified by inspection, considerati'on should be given to observing the containment base behavior during the next pressure test.

In order to establish the potential behavior

( closest to one of the conditions in Table 3

of Reference 1), it may be necessary to install instrumentation (LVDTs, strain gages on liner, etc.) at the bottom 10 ft. of the containment wall.

Proper instrumentation readings in terms of deflections, rotations, moments and shears could provide a sound basis for comparisons of the various conditions studied by RGSE.:.

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Dr. Robert C. Mecredy October 23, 1991 The staff proposes the instrumentation approach as the most viable approach for determining the potential behavior of the containment base under internal pressure.

Please re-evaluate Issue No.

3 (reference 1 and 2), giving consideration to instrumentation at the bottom of the conta'inment wall.

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.

Sincerely, cc:

See next page Original signed by Allen R. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II DISTRIBUTION:-Docket File.50-244, NRC&Local PDRs, PDI-3 rf, SVarga,

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Dr. Robert C. Hecredy Ginna CC:

Thomas A. Hoslak, Senior Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory-Commiss'ion, 1503 Lake Road'ntario, Hew York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ns.

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

Albany, New York

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12223'harlie Donaldson, Esq.

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

Reynolds Winston 5 Strawn 1400'"L St.

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Washington, DC 20005-3502 tls. Thelma Wideman Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route 31 Lyons',Hew~,.York=. 14489 Ns.

Susan Perry Administrator,, Monroe.County Office of Emergency Preparedness 111 West Fall Road Rochester, New York 14620