ML20216J678

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Forwards Response to 980311 Telcon Re License Amend Request to Allow Operation at Increased Reactor Core Power Level of 2775 Mwt.Revised Pages 58 & 59 of Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept, Encl
ML20216J678
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 03/16/1998
From: Woodard J
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20216J683 List:
References
NUDOCS 9803240030
Download: ML20216J678 (3)


Text

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', J.D. Woodard Southern N1 clear Operating C:mpany. lac.

h.ecutive %ce President 40 invyness Cemer Parkway R0. Box 1295 i

Birmingham Alabama 35201 j Tel 205.932.5036 l j

1 March 16, 1998 SOUTHERN COMPANY Energy to Serve Nur t%rld*

Docket Nos.: 50-348 10 CFR 50.90 50-364 ,

U. S. Nuclear Regulatc7Commission ATTN.: Document Control Desk 1 Washington, DC 20555 I 4

Joseph M. Farley Nuclear Plant Response to Request for Additional Information Related to Power Uprate

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fac.jjity Operatina Licenses and Techni.cnLSac.sifications Channe Reauest  !

Ladies and Gentlemen: l -

By letter dated February 14,1997, Southem Nuclear Operating Company (SNC) proposed to unend g the Facility Operating Licenses and Technical Speci6 cations for Joseph M. Farley Nuclear Plant (FNP)

Unit I and Unit 2 to allow operation at an increased reactor core power level of 2775 megawatts thermtd (MWt). NRC letters dated July 1,1997; August 21,1997; and October 14,1997 requested j SNC provide additional information. SNC responded by letters dated August 5,1997; September 22, l 1997; and November 19,1997 respectively. SNC letters dated December 17 and 31,1997; January 23, j

1998; February 12 and 26,1998; and March 3 and 6,1998 responded to NRC questions resulting from )

conference call,s. During a telephone conference call on March 11,1998, the NRC Staff requested a I

response to an additional question. Attachment I provides the SNC response to this question. '

Attachment 11 includes corrections to the power uprate BOP Licensing Report (pages 58 & 59) and Attachment I to SNC letter dated August 5,1997 (Table E page 37).

If you have any questions, please advise. l Respect mitted, D '

v~k' Jack TWoodar Sworn to and subscribed before me thi hay of$11998 ohnct w.0 ? - nL W I '

NotGdyc f- t i My Co ission Expires- V 0 79 MGF/maf: pwrup35. doc Attachments

[ cc: Mr. L. A. Reyes, Region 11 Administrator ..1 ~i. . l'l .

l Mr. J.1. Zimmerman, NRR Project Manager Mr. T. M. Ross. Plant Sr Re h inspector 9803240030 980316

! PDR ADOCK 05000348..

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9 ATTACHMENT I j

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l SNC Response to NRC Request For Additional Information Related to  !

Power Uprate Submittal- Joseph M. Farley Nuclear Plant, Units 1 and 2

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I SNC RESPONSE TO NRC QUESTION RESULTING FROM NRC/SNC TELEPHONE l CONFERENCE CALL ON MARCH I1,1998 i

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, SNC Response to NRC Request For. Additional Information Related to Power Uprate Submittal- Joseph M. Farley Nuclear Plant, Units 1 and 2 NRC Ouestion No.1 (Reference March 11.1998 NRC/SNC ConfcIcnne_ Call)

The values in Table E of SNC letter dated August 5,1997 indicate the results of the Main Steam Line Break radiological analysis submitted in the BOP Uprate Licensing Report do not reflect the steam generator tube leak rate for application of alternate repair criteria (ARC) approved in FNP Technical Specifications Amendment Nos.132 (Unit 1) and 124 (Unit 2). Please provide an analysis of the offsite and control room doses reflecting these amendments for power uprate conditions.

SNC Resooitsq to Oucsis No.1 l 1

l The most limiting case of an accident initiated iodine spike has been re-analyzed for the combination 1 of alternate repair criteria and power uprate assumptions. The new input assumptions are listed in  ;

the Table E revision provided in Attachment II. (Reference SNC RAI letter dated August 5,1997 j Attachment 1.) The new analysis results are presented in revised BOP Licensing Report pages 58 and i 59 These results meet the acceptance criteria provided in NRC Safety Evaluation associated with FNP Technical Specifications Amendment Nos.132 (Unit 1) and 124 (Unit 2). The revised BOP Licensing Report pages are provided in Attachment II.

SCS/ jaw- 3/15/97 I

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