JPN-92-028, Forwards Application for Amend to License DPR-59,increasing Authorized Max Power Level by Approx 4.1% to 2536 Mwt from Current Limit of 2436 Mwt.Proprietary TRs NEDC-32016P & NEDC-31317P-1,encl.Without Proprietary TRs

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Forwards Application for Amend to License DPR-59,increasing Authorized Max Power Level by Approx 4.1% to 2536 Mwt from Current Limit of 2436 Mwt.Proprietary TRs NEDC-32016P & NEDC-31317P-1,encl.Without Proprietary TRs
ML20154D241
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/12/1992
From: Ralph Beedle
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20154D245 List:
References
JPN-92-028, JPN-92-28, NUDOCS 9810070171
Download: ML20154D241 (4)


Text

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June 12,1992 JPN-92-028 U.S. N'telear Regulatory Commission ATTN: Document Control Desk Mail Station P1137 Wrahington, D.C. 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 .'

Proposed Changes to the Technical Specifications Regarding Power Uprats (JPTS 91-025)

REFERENCES:

1. NYPA letter, J. C. Brons to the NRC, dated December 28, 1990, (JPN 90 078), "New F4ojects."
2. General Electric Ucensing Topical Report NEDC-31897P A

" Generic Guidelines for General Electric Boiling Water Reactor Power Uprate," (proprietary)

3. General Bectric Uconshg Topical Report NEDC-31984P

" Generic Evalua6cns of General Electric Boiling Water Reactor Power Uprate," July 1991 and Supplement 1, October 1991 (propristwy) 4.. General Eicctic Report NEDC 32016P 'Pcwar Uprete Safety Analysis for the James A. FitzPetrick Nucl ear Power Plant,"

December 1991 (propr:etar/)

5. Giseral Eectric Report NEDC 51317P 1, Rev:sion 1, " James A. FitzPatrick NuclearPower Plant SAFER /GESTR Loss-of- -

Ceolant Accident Safety Analysis Report," August 1991 .,

(proprie+wy). ,

l

Dear. Sir:

This application for an amendment to the James A. FitzPetrick lochnical Specifications proposes to increase the authorized maximum power level by

. approximately 4.1 percertto 2538 megawatts thermal (MWt) from the cutrent limit of 2438 MWt. The Authority outlined it's plans on this and other new picjects to the \\,

NRC staffin Reference 1.

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The analyses and evaluations supporting these changes were completed using the guidelines in General Electric Topical Report NEDC-31897P A " Generic

! Guidelines for General Electric Boiling Water Reactor Power Uprate." Generic issues associated with power uprate were addressed for RtzPatrick in another General i Electric Topical Report NEDC 31964P ' Generic Evaluations of General Electric j Boiling Water Reactor Power Uprate." These reports, References 2 and 3, are

{ proprietary and have been submitted separately to the NRC by General Electric.

The signed original of the ApdW for Amendment to Operating Ucense is enclosed for filing. Attachments I and 11 to this application contain the proposed 4

changes to the Technical Specifications and the associated Safety Evaluation. The change request includes no requests for approval of plant operations using special features such as increased core flow or the Maximum Extended Operating Domain.

l The James A. FitzPatrick safety evaluation for power uprate, Reference 4, is in

Attachment lil, General Electric Report NEDC-32016P " Power Uprate Safety j Analysis for the James A. FitzPatrick Nuclear Power Plant." This safety evaluation 1 complies with the guidelines of NEDC-31897P A and supplements the generic

! evaluations of NEDC-31984P. In accordance with the provisions of 10 CFR 2.790, i those pages of NEDC-32016P containing proprietary information (labelled "GE

!~ Proprietary Information" at the top of each page) should be withheld from public

disclosure. Attachment IV is General Electric's affidavit attesting to the proprietary nature of this information.

i

{ Attachment V is NEDC-31317P 1, " SAFER /GESTR Loss-of-Coolant Accident

Safety Analysis Report" for the James A. FitzPatrick Nuclear Power Plant. This

! report, Reference 5, summarizes loss of coolant accident analyses performed at this i new uprate power level. These analyses used the SAFEP/GESTR methodology and

previously licensed fuel desige.s as outlined in NEDC-31897P-A. In accordance with
the provisions of 10 CFR 2.790, those pages of NEDC 31317P-1 contain proprietary l Information and should be withheld from public disclosure. Attachment VI is General l Electric's affidavit attesting to the proprietary nature of the informaton contained in 3 NEDC-31317P-1.

i To assist the review, Attachment Vil contains a copy of the current technical specification pages that have been marked-up to clearly identify where the proposed

, changes are located.

i There may be revisions to the proposed change to Technical Specifications.

i Bounding calculations have been completed but supporting calculations are still 1 being prepared to address specific issues. The safety evaluation identifies most of j these. Additional reviews and changes to plant procedures and test programs are i

also underway. These and other activities that may cause revisions are being j trackedintamally.

4

L l l .\

l A copy of this application and the associated non-proprietary attachments are being provided to the designated New York State official in accordance with 10 CFR 50.91.

If you have any questions, please contact J. A. Gray, Jr.

I Very truly yours,

, i q[N- ~

Ralph E. Beedle'  ;

Executive Vice President l Nuclear Generation i

Attachrnents: Application for Amendment to Operating Ucense

1. Proposed Technical Specifications Changes Power Uprate (JPTS 91425)

II. Safety Evaluation for Proposed Technical Specification Changes Power Uprate (JPTS-91-025) 111. NEDC-32016P " Power Uprate Safety Analysis for the James A.

FitzPatrick Nuclear Power Plant," December 1991 (proprietary)

IV. GE Affidavit on NEDC-32016P V. NEDC 31317P-1 " James A. FitzPatrick Nuclear Power Pl. ant SAFER /GESTR l.oss-of-Coolant Accident Safety Analysis Report," August 1991 (preft.diry)

VI. GE Affidavit on NEDC-31317P 1 Vll. Mark up of Current Technical Specifications

I cc: Regional AdministrCor IS Nuclear Regulatory Commission 475 Anodaily Road l King of Prosy, PA 19406 l

Office of the Resident inspector ,

IS. Nuclear Regulatory Commission 1 P.O. Box 136 i Loudening, NY 13003 1 Mr. Brian C. McCabe Project Directorate 11 Division of Reactor Projects -1/11 IS. Nuclear Regulatory Commission Mail Stop 14 B2 Washington,DC 20555 Ms. Donna Ross New York State Energy Office 2 Empire State Plaza 16'h Fi m Albarvj.NY 12223 l 1

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