JPN-98-051, Forwards Response to NRC 980820 RAI Re Insp Program Relief Request Number 8,submitted 980126.Response Completes Util Response

Forwards Response to NRC 980820 RAI Re Insp Program Relief Request Number 8,submitted 980126.Response Completes Util Response

ML20198L302
Person / Time
Site:	FitzPatrick
Issue date:	12/21/1998
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-98-051, JPN-98-51, TAC-MA0711, TAC-MA711, NUDOCS 9901040138
Download: ML20198L302 (4)

Text

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123 Main Street VWte Plains, New York 10001 e 914 681.6950 914 287.3309 (Fax)

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December '21, 1998 U.S. Nuclear Regulatory Commission JPN-98-051 Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Additional Information Regarding inservice inspection Proaram Relief Request # 8 (TAC No. MA0711)

References:

1. JPN-98-002, NYPA letter to NRC, " Third Inservice inspection Interval Inspection Program Plan", dated January 26,1998.

2. NRC Letter to NYPA, " Additional Information Regarding inservice Inspection Program Relief Requests (TAC No. MA0711)", dated August 20,1998.

3. JPN-98-042, NYPA letter to NRC, " Response to Request for Additional information Regarding inservice inspection Program Relief Requests (TAC No. MA0711)", dated September 21,1998.

Dear Sir:

On January 26,1998, the New York Power Authority submitted the third ten-year interval inspection program and relief requests for the James A. FitzPatrick Nuclear Power Plant (Reference 1). The NRC staff subsequently requested additionalinformation to complete the review of the relief requests (Reference 2). Reference 3 provided the Authority's response to that request out deferred a response to questions on relief request #8 to a later date. Attachment 1 to this letter transmits the Authority's response to the questions on relief request #8 and completes the Authority's response to Reference 2.

No commitments are made by the Authority in this letter. If you have any questions, please contact Ms. C. D. Faison.

Very truly s,

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. Knubel p

Senior Vice President and 0 4 g }- }- Chief Nuclear Officer y cc: next page y

9901040138 981221 g PDR ADOCK 05000333 G PDR a'

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cc: Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident inspector's Office -

James A. FitzPatrick Nuclear Power Plant U.S. Nuclear Regulatory Commission P.O. Box 136

' Lycoming, NY 13093 Mr. Joseph Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 U S. Nuclear Regulai6ry Commission Mail Stop 14 B2 Washington, DC 20555 Mr. Michael T. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 -

Idaho Falls, Idaho 83415-2209 i l

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Attachment I to JPN-98-051 l

i Response to Request for Additional

!- Information Regarding inservice inspection Program Relief Request #8 (TAC No. MA0711)  :

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i New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 i

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..o Attachment I to JPN-98-051 Page 1 of 1 Response to Request for Additional Information Regarding inservice inspection Program Relief Request #8 (TAC No. MA0711)

Additional Information Reauired E. Request for Relief No. 8 -The licensee has submitted this request for relief relating to the Control Rod Drive System. However, it is unclear as to the specific Code requirement (s) the licensee is seeking relief from. The licensee references Category C-H. However, Category C-H has multiple examination requirements. The licensee states in the Examination Requirements portion of the request that:

. relief should be from the 10 year Inservice / hydro test and Code Case N-496-1 that the Inservice test will be done during a normally scheduled shutdown from plant operation.

In the Reii Requested pc. tion of the Request for Relief the licensee states that:

Relief is requested from the requirements specified in IWC-2000, Table IWC-2500-1, Code Category C-H, All Pressure Retaining Components of the ASME Boiler and Pressure Vessel Code,Section XI,1989 Edition for Inservice pretsure testing of the C.D. System each inspection period. Also Code Case N-498-1 for the third period test.

It is unclear whether the licensee is seeking relief from the interval requirement, period requirement, or both. Identify the specific Code requirement (s) that will not be met (include category and item number (s)). Provide a specific description of the portion of the CRD system requiring relief. Include boundary / isometric drawings identifying the portion of the CRD system requiring relief.

Also, provide a basis for relief, explaining / justifying why the Code requirements cannot be met (see question C). The licensee has provided an altemative examination, explain as applicable:

1 how the alternative examination is equivalent to the Code-required examination and how it provides an acceptable level of quality and safety (10 CFR 50.55a(a)(3)(i)) or,

2. how the a!!emative examination provides reasonable assurance of operational readiness, and why compliance with the Code requirements would result in a hardship without a compensating increase in safety (10 CFR 50.55a(,a)(3)(ii)) or,

3. how the attemative examination provides reasonable assurance of operational readiness, and why compliance with the Code requirements is considered to be impractical (10 CFR 50.55s(g)(6)(i)).

Response -The Authority has determined that the testing performed satisfies the requirements of Code Category C-H, Code Cases N-498-1 and N-416-1 for the CRD system and is acceptable.

The Authority is therefore withdrawing this request for relief.

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