JPN-96-016, Forwards Application for Amend to License & TS Re Changes to Ts,Incorporating Option B to 10CFR50,App J

Forwards Application for Amend to License & TS Re Changes to Ts,Incorporating Option B to 10CFR50,App J

ML20108D107
Person / Time
Site:	FitzPatrick
Issue date:	04/24/1996
From:	William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20108D109	List: JPN-96-016, Forwards Application for Amend to License & TS Re Changes to Ts,Incorporating Option B to 10CFR50,App J ML20108D115 ML20108D117
References
JPN-96-016, JPN-96-16, NUDOCS 9605070276
Download: ML20108D107 (3)

Text

123 Abn Street Whdo Piams New York UX.01 914-0814840 914-287 3309 WAX)

William J. Cahill, Jr, 4# Authon.ty c-"- c~

April 24,1996 JPN-96-016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Revision to Proposed Changes to the Technical Specifications to incorporate Option B to 10CFR50, Appendix J (JPTS-96-003)

Reference:

1. NYPA letter, W.J. Cahill, Jr. to NRC (JPN-96-011), " Proposed Changes to the Technical Specifications to incorporate Option B to 10CFR50, Appendix J (JPTS-96-003)," dated March 27,1996.

2. Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

3. NYPA letter, W.J. Cahill, Jr. to NRC (JPN-96-002), "10CFR50 Appendix J Exemption Request Local Leak Rate Testing of Containment isolation Valves in the Reverse Direction," dated January 12,1996.

Dear Sir:

The New York Power Authority is revising a FitzPatrick Technical Specification (TS) amendment application (Reference 1) to include an exception to the guidelines of Regulatory Guide 1.163 (Reference 2) for Type C testing of primary containment isolation valves in the reverse (non-accident) direction. The revised Safety Evaluation provides justification and supporting analysis for this exception as required by Option B of 10CFR50 Appendix J, Section V.B.3. The conclusions and the significant hazards consideration are not altered by these changes.

The proposed TS changes support adoption of the primary containment leakage rate testing requirements of Option B to 10 CFR 50, Appendix J at the FitzPatrick plant, and clarify the numerical value of the allowable containment leakage rate (L ) as 1.5 percent per day. Implementation of Option B to 10 CFR 50, Appendix J will be controlled under 07 ' 11 of 9605070276 960424 PDR ADOCK 05000333 gI p PDR

I the Primary Containment Leakage Rate Testing Program. Under this program, pnmary containment leakage rate testing will be performed in accordance with the requirements of Option B to 10 CFR 50, Appendix J, Regulatory Guide 1.163 (Reference 2) with approved exceptions, and exemptions currently approved by the NRC for the FitzPatrick Plant.

l The Authority requests NRC approval of this proposed amendment prior to July 1, 1996 in order to adopt these changes prior to the upcoming refueling outage currently scheduled for Fall 1996. Based on this proposed change, the Authority withdraws the exemption request transmitted to the NRC as JPN-96-002 (Reference 3).

The signed original of the Application for Amendment to Operating License is enclosed for filing. Attachments I and ill to this application contain the proposed TS changes and a markup of the current TS pages, respectively. Attachment 11 contains the revised Safety Evaluation. These attachments supersede and replace those submitted with Reference 1. No changes are rnade to Attachment IV which contains the plan for implementing the new leakage rate testing requirements as required by Option B of 10 CFR 50 Appendix J Section V.B.2. Attachment V summarizes the commitments made in this submittal.

A copy of this application and the associated 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 Mr. A. Zaremba.

Very Truly Yours,

• \

William ahill, Jr.

l Chief Nuclear Officer I

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att:' as stated cc: U.S. Nuclear Regulatory Commission 475 Allendale Road l

King of Prussia, PA 19406 )

l l Office of the Resident inspector i l U.S. Nuclear Regulatory Commission j P.O. Box 136 Lycoming, NY 13093 i

l Ms. K. Cotton, Acting Project Manager )

l Project Directorate 1-1 ,

Division of Reactor Projects - 1/11 l U.S. Nuclear Regulatory Commission 'l l Mail Stop 14 B2 )

! Washington, DC 20555 i l

Mr. F. William Valentino, President

' New York State Energy, Research and Development Authority

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l l 2 Rockefeller P;aza l Albany, NY 12223-1253 )

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