JPN-87-012, Revised Application for Amend to License DPR-59,modifying Tech Specs Re Reload 7/Cycle 8.Attachment Iii,Consisting of Addendum to NEDC-31317P, ...SAFER/GESTR-LOCA & App U to NEDE-31152P, D-Lattice.... Withheld (Ref 10CFR2.790)

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Revised Application for Amend to License DPR-59,modifying Tech Specs Re Reload 7/Cycle 8.Attachment Iii,Consisting of Addendum to NEDC-31317P, ...SAFER/GESTR-LOCA & App U to NEDE-31152P, D-Lattice.... Withheld (Ref 10CFR2.790)
ML20207S419
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/13/1987
From: Brons J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19292G953 List:
References
JPN-87-012, JPN-87-12, NUDOCS 8703190420
Download: ML20207S419 (2)


Text

'

. 123 Main Street WNt3 Plains, New M 10501

. 914 681.6240 Odbef 'DIseTe*seent se M60th Nuclear Genera + ion March 13, 1987 JPN-87-012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Changes to the Technical Specifications Regarding Reload 7/ Cycle 8 (J PTS-8 6-02 3 )

Reference:

1) NYPA letter to the NRC, J.C. Brons to D.R.

Muller, dated December 23, 1986, JPN-86-63, concerning the same subject.

Dear Sir:

In Reference 1 the Authority applied for an amendment to the FitzPatrick Technical Specifications. This letter provides Revision 1 to that submittal. This revision is based on discussions with the NRC staff and provides clarification of Reference 1.

The enclosed Technical Specification change pages replace the corresponding pages in Attachment I to Reference 1. Page 135h in the Technical Specifications is to remain unchanged and should be removed from the original application. The enclosed Safety Evaluation replaces Attachment II to Reference 1 in its entirety.

Changes to the Safety Evaluation are shown by change bars in the right margin.

n Attachment III to this letter contains an addendum to the nQg General Electric report " James A. Fitzpatrick Nuclear ggt Power Plant SAFER /GESTR - LOCA Loss of Coolant Accident No analysis (NEDC-31317 P) " . This addendum provides

$$ additional clarification of the original report.

. ng No Attachment IV to this letter provides three pages

$@ describing the nuclear design of the Reload 7 BD319A

$< bundle. These pages provide additional clarification of n Reference 1.

l $$ Ut $** *

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mid ' I n,

, I

Attachment III and IV to this letter contain information which General Electric customarily maintains in confidence and witholds from public disclosure. The information in Attachment III has been handled and classified as proprietary to General Electric as indicated in the affidavit submitted in Reference 1. The information in Attachment IV has been handled and classified as proprietary to General Electric as indicated in the affidavit filed with the NRC by General Electric concerning their application for Amendment 18-to GESTAR.

The Authority hereby requests that the information in Attachments III and IV be withheld from the public disclosure in accordance with the provisions of 10 CFR 2.790.

Should you or your staff have any questions regarding this matter, please contact Mr. J.A. Gray, Jr. of my staff.

Very truly yours, U hI' C. Brons denior Vice President Nuclear Generation cc: U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 i Lycoming, NY 13093 I

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue c Bethesda, MD 20014 Attn: Mr. H. Abelson Mail Stop 416 (TO BE OPENED BY ADDRESSEE ONLY)

Mr. Jay D. Dunkleberger, Director Technology Development Programs New York State Energy Office Two Rockefeller Plaza Albany, NY 12223 Attachments: as stated l

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