ML20196F918

Forwards Safety Evaluation Re Third 10-year Interval Inservice Insp Program Relief Requests for Plant

ML20196F918
Person / Time
Site:	FitzPatrick
Issue date:	11/25/1998
From:	Bajwa S NRC (Affiliation Not Assigned)
To:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
Shared Package
ML20196F922	List: ML20196F918 ML20196F925
References
RTR-REGGD-01.147, RTR-REGGD-1.147 TAC-MA0711, TAC-MA711, NUDOCS 9812070158
Download: ML20196F918 (5)

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k UNITED STATES l

l g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001 g

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l Mr. James Knubel 1 Chief NuclearOfficer Power Authority of the State of {

New York '

-123 Main Street I White Plains, NY 10601 i

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SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- THIRD INTERVAL INSERVICE INSPECTION PROGRAM RELIEF REQUESTS (TAC NO. MA0711)

Dear Mr. Knubel:

j On January 26,1998, the New York Power Authority (NYPA, also known as the Power l Authority of the State of New York) submitted the third interval inservice inspection program and relief requests for the James A. FitzPatrick Nuclear Power Plant. The NRC staff requested additionalinformation regarding the relief requests on August 20,1998, which NYPA provided on September 21,1998. NYPA also provided supplementalinformation regarding relief request 10 on November 3,1998.

The NRC staff with the assistance of its contractor, the Idaho National Engineering and Environmental Laboratory, has reviewed the relief requests. Details of this review are discussed in the enclosed safety evaluation and technical letter report, with the conclusions summarized below. ,

The NRC staff concludes that for relief requests 1,2,4,5,6,9,12, and 13 the proposed attematives provide an acceptable level of quality and safety; therefore, the proposed attematives are authorized for the third interval pursuant to 10 CFR 50.55a(a)(3)(i).

For relief request 10, the NRC staff concludes that the proposed attemative provides an acceptable level of quality and safety, but only for an interim period, in order to clarify the acceptance standards used for future examinations and to promote consistent use of the subject attemative, the NRC staff has determined that VT-1 visual examinations should be used for all bolting at FitzPatrick in the future. The NRC staff recognizes that imposition of this requirement would negatively impact the current outage. Therefore, the NRC staff concludes i that the proposed altemative contained in relief request 10 is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for a period not to exceed 1 year from the date of this letter. .

For relief request 3, the NRC staff concludes that the Code requirements would result in a hardship without a compensating increase in the level of quality and safety because the proposed attemative provides reasonable assurance of structuralintegrity of the subject components. Therefore, NRC staff concludes that the proposed altemative is authorized

!. pursuant to 10 CFR 50.55a(3)(ii). dug i J i Relief requests 1 - 6, and 13 relate to application of various Code Cases. The use of these l Code Cases is authorized for the current interval, or until such time as a Code Case is published in a future revision of Regulatory Guide (RG) 1.147. At that time, if the licensee

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. J. Knubel November 25, 1998 9 0 intends to continue to implement those Code Cases, the licensee should follow all provisions in the Code Cases with limitations issued in RG 1.147, if any.

Relief request 12 proposes use of Code Case N-522 as an attemative to the ASME Code requirements. For this relief request, the staff concluded that the licensee's proposed alternative provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for a limited time not to exceed 60 months from the date of the letter forwarding this safety evaluation, or until such time as Code Case N-522 is published in a future revision of Regulatory Guide (RG) 1.147. At that time, if the licensee intends to continue to implement Code Case N-522, the licensee should follow all provisions in Code Case N-522 with limitations issued in RG 1.147, if any.

Relief request 7 was withdrawn by NYPA in a letter dated September 21,1998.

As stated in the letter dated September 21,1998, NYPA has determined that relief request 6 will not be required for the current outage. Therefore, additional information for completion of the review of this relief request will be provided at a later date.

Relief request 11 was previously authorized by the NRC in a letter dated October 14,1998.

If you have any questions regarding this matter, please contact Joe Williams at (301)415-1470.

Sincerely, ORIGINAL SIGNED BY:

S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Safety Evaluation w/ attachment cc w/ encl: See next page DISTRIBUTION:

Docket File S. Little ACRS C. Hehl, Ri PUBLIC J. Williams B.McCabe PDI-1 R/F T. Harris (e-mail SE only to TLH3)

J. Zwolinski OGC S. Bajwa G. Hill (2) T5-C3 DOCUMENT NAME: G:\FITZ\MA0711.LTR To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure E" = Copy with attachment / enclosure "N" = No copy *see previous concurrence OFFICE PM:PDI 1 [h j l E l LA:PDI-10V l l D:PDI-1,(M l l OGC l l l__

NA".E JWittiams/rst W / Sllttle W ' SBajwa 8 " % MYoung*

DATE 11/1lf) /93 i 11/ 3 (1/98 11/ to/98 11/25/98 Official Record Copy

J. Knubel November 25, 1998 intends to continue to implement those Code Cases, the licensee should follow all provisions in the Code Cases with limitations issued in RG 1.147, if any.

Relief request 12 proposes use of Code Case N 522 as an attemative to the ASME Code requirements. For this relief request, the staff concluded that the licensee's proposed attemative provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for a limited time not to exceed 60 months from the date of the letter forwarding this safety evaluation, or until such time as Code Case N-522 is published in a future revision of Regulatory Guide (RG) 1.147. At that tims, if the licensee intends to continue to implement Code Case N-522, the licensee should follow all provisions in Code Case N-522 with limitations issued in RG 1.147, if any.

Relief request 7 was withdrawn by NYPA in a letter dated September 21,1998.

As stated in the letter dated September 21,1998, NYPA has determined that relief request 8 will not be required for the current outage. Therefore, additional information for completion of the review of this relief request will be provided at a later date.

Relief request 11 was previously authorized by the NRC in a letter dated October 14,1998.

If you have any questions regarding this matter, please contact Joe Williams at (301)415-1470.

Sincerely, ORIGINAL SIGNED BY:

S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Safety Evaluation w/ attachment cc w/ encl: See next page DISTRIBUTION:

Ducket File S. Little ACRS C.Heht,RI PUBLIC J. Williams B.McCabe PDI-1 R/F T. Harris (e-mail SE only to TLH3)

J. Zwo!inski OGC S. Bajwa G. Hill (2) TS-C3 DOCUMENT NAME: G:\FITZ\MA0711.LTR To rcceive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy *see previous concurrence OFilCE PM:PDI-1 [k , l E I LA:PDI1[)V l D:PDI 1 , M l OGC l l l NAME JWilliams/rsl N SLittle W ' SBaJwe p ' OL MYoung*

DATE 11/~m /98 'i 11/ 3 0/98 11/ XD/98 11/25/98 Official Record Copy

t 3 J.Knubel intends to continue to implement those Code Cases, the licensee should follow all provisions in the Code Cases with limitations issued in RG 1.147, if any.

Relief request 12 proposes use of Code Case N-522 as an attemative to the ASME Code requirements. For this relief request, the staff concludes that the licensee's proposed '

altemative provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for a liinited time not to exceed 60 months from the date of the letter forwarding this safety evaluation, or until such time as Code C ase N-522 is published in a future revision of Regulatory Guide (RG) 1.147. At that time, if the licensee intends to continue to implement Code Case N-522, the licensee should follow all provisions in Code Case N-522 with limitations issued in RG 1.147, if any.

Relief request 7 was withdrawn by NYPA in a letter dated September 21,1998.

As stated in the letter dated September 21,1998, NYPA has determined that relief request 8 will not be required for the current outage. Therefore, additional information for completion of the review of this relief request will be provided at a later date.

Relief request 11 was previously authorized by the NRC in a letter dated October 14,1998.

If you have any questions regarding this matter, please contact Joe Williams at (301)415-1470.

Sincerely, S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Safety Evaluation w/ attachment cc w/ encl: See next page

$m:s Knubel Jrmts A. FitzPatrick Nuclair '

Power Authority of the State Power Plant of New Yo*

cc:

Mr. Gerald C. Goldstein Regional Administrator, Region 1 I

Assistant General Counsel U.S. Nuclear Regulatory Commission Power Authority of the State 475 Allendale Road of NewYork King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President New York State Energy, Research, Resident inspectors Office and Development Authority U. S. Nuclear Regulatory Commission Corporate Plaza West P.O. Box 136 286 Washington Avenue Extension Lycoming, NY 13093 Albany, NY 12203-6399 Mr. Harry P. Salmon, Jr. Mr. Richard L. Patch, Director Vice President- Engineering Quality Assurance Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street White Plalns, NY 10601 White Plains, NY 10601 Ms. Charlene D. Faison Mr. Gerard Goering Director Nuclear Licensing 28112 Bayview Drive Power Authority of the State Red Wing, MN 55066 of NewYork -

123 Main Street Mr. James Gad,ardo White Plains, NY 10601 Safety Review Committee 708 Castlewood Avenue Supervisor Arlington, TX 76012 Town of Scriba Route 8, Box 382 Mr. Arthur Zaremba, Licensing Manager Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant Mr. Eugene W. Zeltmann P.O. Box 41 President and Chief Operating Lycoming, NY 13093 Officer Power Authority of the State Mr. Paul Eddy of New York New Yo* State Dept. of 99 Washington Ave., Suite No. 2005 Public Service Albany, NY 12210-2820 3 Empire State Plaza,10th Floor Albany, NY 12223 Charles Doncidson, Esquire Assistant Attomey General Michael J. Colomb New York Department of Law Site Executive Officer.

120 Broadway James A. FitzPatrick Nuclear Power Plant New York, NY 10271 P.O. Box 41 Lycoming, NY i3093