ML20134E569

Forwards RAI to Complete Review of Licensee 960126 Submittal Re EDG TS Change

ML20134E569
Person / Time
Site:	FitzPatrick
Issue date:	02/04/1997
From:	Cotton K NRC (Affiliation Not Assigned)
To:	William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
TAC-M94611, NUDOCS 9702060357
Download: ML20134E569 (4)

Text

__ _ _ _ . _ _ ..._. _ _ _ ._. ._ _ _ _ _ . _ _ _ _ _ . _ . _ . _ _ _ _ _ _

Mr. William J. Cahill, Jr. February 4, 1997  ;

. Chief Nuclear Officer Power Authority.of the State of New York L i l

l. 123 Main Street E) e" r ,.

White Plains, NY- 10601' '.!  ;

I l

SUBJECT:

JAMESA.FITZPATR'IbK' NUCLEAR'POWERPLANT-REQUESTFORADDITIONAL '

i INFORMATION RELATED TO EMERGENCY DIESEL GENERATOR TECHNICAL

SPECIFICATION CHANGE (TAC,NO."M94611)

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Dear Mr. Cahill:

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ByletterdatedJanuary!26,'1996,'yourequestedtNatFacilityOperating

. License DPR-59 be amended to-modify the' James A'. FitzPatrick Nuclear Power Plant, Technica1' Specifications (TSs)'.! The changes are being made to revise the allowed out-of-service' times,for a single inoperable emergency diesel '

generator (EDG) to accommodate lon-line maintenance of the EDG, By letter -!

dated April 18,1996,'the NRC staff requested additional information related j to the EDG TS change. -Your September >12, 1996 response submittal indicated j that FitzPatrick _ approved and was ' implementing a charge to your work control-i process in which risk assessment would be performed as a matter of routine for i activities at power; It also indicated that, before removing an EDG for extended maintenance, procedure ensures that the required systems, subsystems,

. trains, components, and devices that are-required to :aitigate the consequences j of an accident are available and operable.

i In an effort to complete the review,-the NRC staff has enclosed a request for

. additional information.

Sincerely,

/S/

Karen R. Cotton, Acting Project Manager I Project Directorate I-1 )

Division of Reactor Projects - I/II  ;

[ Office of Nuclear Reactor Regulation i f Docket.No. 50-333 .l

Enclosure:

Request for Additional

! Information i

i cc w/ enc 1: See next page /

DISTRIBUTION:

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DOCUMENT NAME:

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attachment / enclosure "E" - Copynwith attachment / enclosure "N" - No copy

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001

/ February 4, 1997 k ..... f Mr. William J. Cahill, Jr.

Chief Nuclear Officer Power Authority of the State of New York 123 Main Street White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EMERGENCY DIESEL GENERATOR TECHNICAL SPECIFICATION CHANGE (TAC NO. M94611)

Dear Mr. Cahill:

4

, By letter dated January 26, 1996, you requested that Facility Operating License DPR-59 be amended to modify the James A. FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The changes are being made to revise

, the allowed out-of-service times for a single inoperable emergency diesel d

generator (EDG) to accommodate on-line maintenance of the EDG. By letter dated April 18, 1996, the NRC staff requested additional information related to the EDG TS change. Your September 12, 1996, response submittal indicated i

that FitzPatrick approved and was implementing a change to your work control process in which risk assessment would be performed as a matter of routine for

activities at power. It also indicated that, before removing an EDG for l extended maintenance, procedure ensures that the required systems, subsystems, trains, components, and devices that are required to mitigate the consequences of an accident are available and operable.

In an effort to complete the review, the NRC staff has enclosed a request for additional information.

Sincerely, Karen R. Cotton, Acting Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Request for Additional Information cc w/ encl: See next page 4

e' .

William J. Cahill, Jr. James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York cc:

Mr. Gerald C. Goldstein Regional Administrator, Region I Assistant General Counsel U.S. Nuclear Regulatory Commission Power Authority of the State 475 Allendale Road of New York King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President New York State Energy, Research, Resident Inspector's 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 Resident Manager Quality Assurance James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York P.O. Box 41 123 Main Street Lycoming, NY 13093 White Plains, NY 10601 Ms. Charlene D. Faison Mr. Gerard Goering Director Nuclear Licensing 28112 Bayview Driva Power Authority of the State Red Wing, MN 5506o of New York 123 Main Street Mr. James Gagliardo 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 Oswego, NY 13126 Manager James A. FitzPatrick Nuclear Mr. Robert G. Schoenberger, Power Plant Vice President P.O. Box 41 and Chief Operating Officer Lycoming, NY 13093 Power Authority of the State of New York Mr. Paul Eddy 123 Main Street New York State Dept. of White Plains, NY 10601 Public Service 3 Empire State Plaza, loth Floor Charles Donaldson, Esquire Albany, NY 12223 Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271

I o .

l RE0 VEST FOR ADDITIONAL INFORMATION RELATED TO EMERGENCY DIESEL GENERATOR ALLOWED OUTAGE TIMES AT FITZPATRICK j Provide the following information for NRC staff review:

(1) a general description of the approved change to your work control process.

4 (2) a description on how risk information/ insights from your PRA is, or will ,

be, incorporated into your work cont' 1 process, specifically with  !

respect to planning and controlling m;;ntenance activities involving the EDGs.

(3) a discussion on how completeness is assured by consideration of  ;

4 equipment not modeled in your PRA and how it is, or will be, addressed l in your work control process.  ;

(4) a discussion on the extent to which numerical criteria, i.e., core damage frequency or incremental core damage probability, are, or will be, used in your work control process, and (5) a list and brief description of your procedures that govern your risk-informed work control.

Enclosure