ML17265A306

Submits Response to 980519 Telcon Discussion Between Util, Licensee & NRC on Util Spent Fuel Pool Rerack Safety Evaluation

ML17265A306
Person / Time
Site:	Ginna
Issue date:	05/22/1998
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9806020250
Download: ML17265A306 (4)

Text

CATEGORY 1 REGULA INFORMATION DISTRXBUTIO YSTEM (RIDS)

ACCESSION NBR:9806020250 DOC.DATE: 98/05/22 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME 'UTHOR AFFILIATION MECREDY,R.C! Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Submits response to 980519 telcon discussion between util, licensee 8 NRC on util spent fuel pool rerack safety evaluation.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution 1 ENCL Q SIZE:

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PD1-1 LA PD1-1 PD VISSING,G.

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ANn ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EASTAYENIJE, ROCHESTER, N. Y Idrr-0001 AREA CODE7I6 546-2700 ROBERT C. MECREDY Vice President Nvcieoroperotions May 22, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate 1-1 Washington, D.C. 2055

Subject:

Response to Request for Additional Information on the Structural Aspects of the Spent Fuel Pool Rerack R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

This letter is in response to a May 19, 1998 telephone discussion between RG8'cE, Framatome, and the NRC Staff on Rochester Gas and Electric's Spent Fuel Pool Rerack structural safety evaluation.

1 In the original spent fuel pool design, prior to the 1985 rerack, the spent fuel racks were supported laterally on the pool wall. Those supports were removed during the 1985 rerack. The licensing basis of the proposed spent fuel pool design is such that the six remaining racks, as well as the seven new ATEA storage racks, are freestanding, and are therefore vertically supported on the pool floor only. The large gaps between the racks and the pool wall are designed such that the racks do not impose any impact loading on the pool wall. These conditions were verified throughout the current analysis. Because of the removal of the supports, the racks only impose hydrodynamic loads on the pool wall during a seismic event. These hydrodynamic loads are much lower than the lateral support loads produced in the original design. The new spent fuel storage design is consistent with the licensing basis established during the 1985 rerack.

The new racks are high-density storage racks and are capable of storing additional fuel. The number of support legs is designed such that the new racks do not impose any higher loading on the reinforced concrete pool floor than the current design. The spent fuel pool floor is 3.0 feet thick reinforced concrete and rests on solid bedrock. Section 3.5.3.1.9.1.2 of the Licensing Report (Reference 3.44) provides the analysis and results for the loading on the floor. The results, Table 3.5-130 of the Licensing Report, shows a large margin against the allowable concrete bearing stresses of ACI 349-85 (Reference 3.20).

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References (Numbers are kept the same as in the Licensing Report dated February 1997):

3.20 ACI 349-85, "Code Requirements for Nuclear Safety Related Concrete Structures,"

American Concrete Institute, 1985.

3.24 NRC Letter to RG8cE - Mr. Kober, dated November 14, 1984. Safety Evaluation Report to Amendment No. 65, "Increase of the Spent Fuel Storage Capacity," License No.

DPR-18, Docket No. 50-244.

3.44 Letter from RG&E to U. S. NRC, dated March 31, 1997, Application for Amendment to Facility Operating License, Revised Spent Fuel Pool Storage Requirements, RGB, R.E.Ginna Nuclear Power Plant, Docket No. 50-244.

Very truly yours, Robert C. Mecredy RCM/mab xc: U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14B2)

PWR Project Directorate I-1 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector Mr. F. William Valentino, President New York State Energy, Research, and'Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399

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