ML20023B981

Confirms 830419 Responses to Questions Raised During 830418 Telcon Re Spent Fuel Pool Expansion

ML20023B981
Person / Time
Site:	Brunswick
Issue date:	05/05/1983
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
References
LAP-83-137, NUDOCS 8305090456
Download: ML20023B981 (2)

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Cp&L Carolina Power & Light Company Serial: LAP-83-137 MAY 051983 Director of Nuclear Reactor Regulation Attention: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SPENT FUEL POOL EXPANSION

Dear Mr. Vassallo:

On April 18, 1983 a conference call was held between members of your staff, Carolina Power & Light Company (CP&L) and General Electric (GE). Two questions were raised during the course of this conversation which were answered in a subsequent call on April 19, 1983. This letter is to confira CP&L's responses provided in that call.

NRC Question (Paraphrased): Please describe the method used in the seismic analysis of the racks to combine the effects of the three spatial components of an earthquake.

Response: The Response Spectra Method described in USNRC Regulatory Guide 1.92, page 1.92-4, paragraph 2.1 was used to combine the data. The method is defined in the Reg. Guide as follows: "When the response spectra method is adopted for seismic analysis, the represented maximum values of the structural responses to each of the three componenets of earthquake motion should be combined by taking the square root of the sums of the squares of the maximum representative values of the codirectional responses caused by each of the three components of earthquake motion at a particular point of the structure or of the mathematical model."

NRC Question (Paraphrased): Please verify that the Safety Factors against overturning of the fuel storage racks as shown in Table 2-12 of GE Report NEDO-2494B are correct.

I 8305090456 830505 PDR ADOCK 05000324 P PDR 411 Fayetteville Street

• P. O. Box 1551

• Raleigh, N. C. 27602 Wx?mWi"7xMMg s :,1emmqgggy

Response: The safety factors shown in the reference table are correct as listed. The numbers are obtained by dividing 0 (in radians) by the maximum rotation experienced by a fuel storage rack during a seismic event, where 0 is defined as the angle, in radians, necessary for overturning to occur. (ref. Fig. 2-9 of GE Report NEDD-24948).

It is CP&L's understanding this satisfactorily answers all of the NRC's structural questions.

If you have any further questions on this subject please contact our staff.

Yours very truly, S. R. . mmerman Manager Licensing & Permits SRZ/ce (6731JSD) cc: Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O' Reilly (NRC-RII)

Mr. S. D. MacKay (NRC) l l

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