JPN-97-015, Informs NRC That Authority Is Extending Plant Second ten- Year Inservice Insp & Inservice Testing Interval by Period of Three Months

Informs NRC That Authority Is Extending Plant Second ten- Year Inservice Insp & Inservice Testing Interval by Period of Three Months

ML20140D808
Person / Time
Site:	FitzPatrick
Issue date:	04/16/1997
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-97-015, JPN-97-15, NUDOCS 9704240132
Download: ML20140D808 (3)

Text

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April 16,1997 JPN-97-015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk i

Mail Station P1-13'7 Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Extension of the Second Ten-Year Inservice inspection and_ Inservice Testing (ISI/IST) InteLYalsi

References:

1.

14YPA letter, W.A. Josiger to NRC (JPN-94-037), "Second Ten-Year ISillST Interval Extension," dated August 2,1994.

j 2.

NYPA letter, W. J. Cahill, Jr. to NRC (JPN-96-019), " Extension of

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the Second Ten-Year Inservice Inspection and Inservice Testing (ISI/IST) Intervals," dated April 26,1996.

3.

NRC letter, J.E. Menning to W.J. Cahill, Jr., " Extension of Second 10-Year Inservice inspection (ISI) and Inservice Testing (IST)

Interval - James A. FitzPatrick Nuclear Power Plant (TAC No.

M90033)," dated October 26,1994.

Dear Sir:

This letter is submitted to inform the NRC that the Authority is extending the FitzPatrick second ten-year inservice inspection and Inservice Testing (ISI/IST) interval by a period of three (3) months. The extension is being applied to the third period of the second interval currently scheduled to end June 1997. The additional three months will extend this interval through September 1997.

4 The ASME Section XI code applicable to FitzPatrick (1980 Edition with Addenda through Winter 1981), Paragraph IWA-2400(c), permits each inspection interval to be decreased or extended by as much as one year, and allows intervals to be extended when outages greater than six months occur. The Authority previously extended the second ISI/IST Interval by a period of 14 months (Reference 1) to account for the length of the 1992 refueling / maintenance outage. Subsequently, the Authority extended the same interval by another nine months in accordance with the one year extension provision in the Code for the reasons described in Reference 2. These two extensions resulted in the current interval expiration date of June 1997.

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l The Authority is currently developing a risk-based ISI pilot program for the next (third) ten-year interval, and was planning to submit a description of the third ten-year ISI/IST program, along with a request for relief from selected provisions in the code, by the middle of this year. As a result of an expansion in the scope of the ISI program in response to NRC l

requests for information on the risk-based methodologies, and the unavailability of key i

personnel needed for the review of the new ISI/IST program due to a rescheduling of the l

Authority's other nuclear facility (Indian Point 3), this submittal will be delayed until later in the i

year. Accordingly, another extension (three months), that utilizes the remaining time of the 12 month extension provision in the code, is being applied to the current (second) ten-year interval, extending the interval through September 1997. Paragraphs (f)(5)(iv) and (g)(5)(iv) of 10 CFR 50.55a, regarding the IST and ISI regulations, respectively, specifies that for code l

requirements found to be impractical, "the basis for this determination be demonstrated to the satisfaction of the Commission not later than 12 months after the expiration of the interval."

This extension will accommodate the time needed to complete the submittal, and provides more time for NRC review and determination of program acceptability. Extending the interval, I

and deferring the ISI/IST program submittal has no effect on the schedule for initiating the l

inspections since the schedule remains unchanged (next refuel outage currently planned for late 1998).

The NRC staff stated (Reference 3) that, based on the original dates of the second 10-year interval, the Authority L, quire 1 to complete the augmented reactor vessel examinations required by 10 CFR 50.55a(g)(6)(ii)(a) within one 40 month period after July 1995 (i.e., by November 1998). This commitment is not affected by the three month extension.

l The Authority is making no new commitments in this submittal. The Authority's Authorized Nuclear Inservice Inspector (ANil) has reviewed the proposed interval extension 1

and has no concems.

If you have any questions, please contact Ms. C. D. Faison.

l Very truly yours, j

J. Knubel Senior Vice President &

Chief Nuclear Officer cc: next page l

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d cc:

. 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 l

)

Ms. K. Cotton, Acting Project Manager L

- Project Directorate 1-1 Division of Reactor Projects - 1/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 i

Washington, DC 20555 l

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