JAFP-98-0385, Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld

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Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld
ML20197G612
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/03/1998
From: Michael Colomb
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138L977 List:
References
JAFP-98-0385, JAFP-98-385, NUDOCS 9812090120
Download: ML20197G612 (3)


Text

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  • James A. FitzPatrick I
  • Nucle:r Pcwer Plant 268 LsAe Road P.O. Box 41 i Lycoming, New Yuk 13093 315-342 3840

! A NewYorkPower uicnaeia.coiome

& Authority site executive otr>cer 1

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l December 3,1998 JAFP-98-0385 l U.S. Nuclear Regulatory ;ommission ATTN: Document Control Desk Mail Station P1-137 l Washington, DC 20555  ;

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Revision To Proposed Change To The Technical Specifications Regarding Dewgn Features (JPTS-96-012)

REFERENCES:

1. NYPA Letter, J. Knubel to USNRC Document Control Desk, Proposed Change to the Technical Specifications Regarding Design Features (JPN-97-033), dated October 14,1997. )

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2. NYPA Letter, H. P. Salmon, Jr. to USNRC Document Control Desk, Response to NRC Request for AdditionalInformation Regarding Proposed Technical Specifications Change, (JPN 033), dated July 23,1998 i l
3. NRC Letter, J. Knubel to USNRC Document Control Desk, j Changes to the Technical Specifications Regarding the Allowed Containment Leakage Rate (La), (JPN-98-OO7), dated February 26,1998

Dear Sir:

This document revises, in part, the previously submitted application for amendment to the James A. FitzPatrick Technical Specifications (Reference 1). Additionally, this letter contains the Authority's projected ALARA estimate for the installation of fuel rack assembly N3 which was inadvertently omitted from Reference 2.

The attached changes are a result of: (1) the reduction in size of spent fuel rack assembly N3 from 8x13 cells to 8x12 cells); and (2) deleting the proposed inclusion of fuel pool water level inadvertent " Drainage" into the amendment. ,

9812090120 981203 I DR ADOCK 05000333 p PDR; as ~n.

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, m, ISTA t.

l United States Nuclear Regulatory Commission i

Attn: Document Control Desk

Subject:

Revision to Proposed Change to the Technical Specifications l Regarding Design Features (JPTS-96-012) l Page In addition, based on information discussed during r recent conference call with l NRC staff, the Authority provided the calculated offsite doses for a fuel handling accident. The calculation which provide the offsite doses, including assumptions and inputs used, is detailed in JAF-CALC-RAD-0048, Revision 1. This calculation

! was previously provided to NRC staff with Reference 3 and is still applicable, l

l The Authority has reviewed the changes proposed in this letter and has determined that these changes do not affect the bases or conclusions of the no significant hazards evaluation described in the amendment application. Attachment 1 is the revised page for the proposed Technical Specification amendment. Attachment 2

. and Attachment 3 provide the revised Safety Evaluation for the proposed changes,

! and a revised markup of the Technical Specification pages, respectively. l l Attachment 4 is the revised pages to the proprietary licensing report for the addition of storage racks. The affidavit signed by Holtec and submitted with Reference 1 is still applicable and describes the proprietary nature of this licensing report and addresses the considerations listed in 10 CFR 2.790. Therefore, Attachment 4 should be withheld from public disclosure in accordance with 10CFR2.790(a)(4).

Attachment 5 is the revised pages to the non-proprietary licensing report for the addition of storage racks. Attachment 6 is the projected ALARA estimate for the l

installation of fuel rack assembly N3.

There are no commitments contained in this submittal.

If you have any questions, please contact Mr. Richard Plasse, Jr. at (315) 349-6793 Very truly yours, Q n-l MICHAEL J. COLOMB l

Site Executive Officer MJC:GB:las Attachments as stated cc: Next Page i

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Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. J. Williams, Project Manager Proje,.? Directorate 1 1 Divir. ion of Reactor Projects - 1/11 U. S. Nuclear Regulatory Commission Mail Stop 1482

-Washington, DC 20555 M. F. William Valentino, President New York State Energy, Research and Development Authority Corporate Plaza West' 286 Washington Avenue Extension Albany, NY 12203-6399 I

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