ML20087D330

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Responds to NRC 920103 Request for Addl Info Re 910715 & 1018 Applications for Amends to Licenses NPF-2 & NPF-8, Changing TS to Allow Change in Reactor Core Fuel Type from Westinghouse Lopar Fuel to Westinghouse VANTAGE-5 Fuel
ML20087D330
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 01/10/1992
From: Woodard J
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087D332 List:
References
NUDOCS 9201160097
Download: ML20087D330 (1)


Text

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J. D. Woodud ern m Ojwdig Wri1lmily m ment January 10, 1992 the wuthe'" ek t"c wem dicTeYDos.50-340 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. farley Nuclear Plant VANIAGE-5 fuel Design Amendment Supp]AmtDD m 1 Information Centlemen:

By letter dated July 15, 1991, supplemented by letter dateri October 18, 1991, Alabama Power Company proposed to amend the farley Nuclear Plant (FNP) Units 1 and 2 Technical Specifications to allow a change in reactor core fuel type from Westinghouse LOPAR fuel to Westinghouse VANTAGE-5 fuel.

By letter dated January 3, 1992, the NRC requested additional information with regard to RID bypass system removal and the VANTAGE-5 submittal. Southern Nuclear Operating Company hereby supplements the information contained in the above referenced submittals with a response to item 4 of Enclosure 2 of the January 3, 1992 NRC letter. The questions relating to the RTD bypass system removal and the first three items concerning VANTAGE-5 will be addressed by a separate letter.

As requested by the NRC Staff in item 4, Attachments 1 and 2 contain a revision to the July 15, 1991 submittal, updating Technical Specification 6.9.1.11 for both Units 1 and 2, and the Significant Hazards Consideration Analysis, respectively. The revisions were made to require the Radial Peaking factor Limit Report (RPFLR) be submitted to the NRC prior to entering dode 2 for each reload cycle. Only Technical Specification 6.9.1.11 and its corresponding Significant llazards Consideration Analysis are revised by Attachments 1 and 2.

All other proposed changes to Technical Specifications and Significant Haztrds Consideration Analyses given in the July 15, 1991 submitta'. remain applinble and are not updated. The Safety Assessment, LOCA and non-LOCA accident analyses, and Radiological Assessment given in the July 15, 1991 submittal also remain applicable and are not updated.

Respectfully submitted, JDW/ RAH: map 1690 h@..WoodardU nA Attachments 1 and 2 SWORN TO AND SUBSCRIBED BEFORE ME cc: Mr. S. D. Ebneter Mr. S. T. Hoffman THIS /d DAY 0 ( 1 992 .

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