ML18114A256

Response to Requesting Additional Information Regarding Proposed Modification to Augment Spent Fuel Storage Capacity, FP&L Provides Additional Clarification to Fp&L'S 12/8/1977 Letter

ML18114A256
Person / Time
Site:	Saint Lucie
Issue date:	02/08/1978
From:	Robert E. Uhrig Florida Power & Light Co
To:	Desiree Davis Office of Nuclear Reactor Regulation
References
L-78-45
Download: ML18114A256 (5)

Text

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FLORIDA PGWER & LIGHT COMPANY February 8, 1978 L-78-45 Director of Nuclear Reactor Regulation Attention: Mr. Don K. Davis, Acting Chief Operating Reactors Branch ¹2 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, DC 20555

Dear Hr. Davis:

Re: Additional Information

.St. Lucie 1 Au mented S ent Fuel Stora e Your letter of October 27, 1977, requested additional information regarding

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our proposed modification to augment the spent fuel storage capacity at Lucie Unit No. l. Our responses to your questions were provided in my letter to you dated December 8, 1977 (L-77-369). The following is provided in response to discussions with your staff as additional clarification to our December 8 letter.

Regarding question 5 of your October 27, 1977 letter; Subsection NF ot ASNE Code Section III, as it pertains to the material and fabrication specifications and the installation and inspection requirements, was used in the St. Lucie spent fuel rack modification.

Regarding question 7 of your October 27, 1977 letter, an additional SSE check computer analysis and verification has been made gpss for the new St. Lucie spent fuel racks. The computer analysis, verification, and assumptions used are identical to the SSE seismic analysis described in Section 3.2 of our "Spent Fuel Storage Facility Modification Safety Analysis Report" except that no credit was taken for damping due to the racks'ubmergence in water. The results reverify that the peak stresses in the rack modules are within the allowable stress criteria for faulted conditions per Subsection NF.

Additionally, an OBE check computer analysis and verification was made for the new spent fuel racks using OBE floor time histories. The methods and assump-tions used for verifying the OBE case were identical to those used for the gO gO PEOPLE... SERVING PEOPLE

Mr.. Don K. Davis Page Two SSE case described in Section 3.2 of our "Spent Fuel Storage Facility Modification Safety Analysis Report". The results verify that the peak stresses in the rack modules are within the allowable stress criteria for emergency conditions per Subsection NF.

We trust that this completes the information you require.

Yours ver truly, Robert E. Uhrig Vice President REU:JAE:sl cc: Mr. Edward Reeves Harold F. Reis, Esquire

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