ML20148D781

Advises That Based on Util 870415 Response,Standby Liquid Control Sys Meets All Applicable Requirements of ATWS Rule, 10CFR50.62.Addl Info Delineated in Encl Needed to Complete Review of Alternate Rod Insertion Sys

ML20148D781
Person / Time
Site:	FitzPatrick
Issue date:	03/18/1988
From:	Abelson H Office of Nuclear Reactor Regulation
To:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
TAC-59095, NUDOCS 8803240283
Download: ML20148D781 (4)

Text

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g March 18, 1988

~ Docket No. 50-333 DISTIRUBTION

< S 0'Doctet F1Jegib JJohnson NRCPDR'" 0GC-WF Local PDR Newberry-Mr. John C. Brons PDI-Rdg. Li Executive Vice President, Nuclear Generation SVarga EJordan Power Authority of the State BBoger -JPartlow of New York ' CVogan ACRS(10) 123 Main Street HAbelson White Plains, New York 10601

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - ATWS RULE (10CFR 50.6?)

(TAC 59095)

Our letter dated January 8, 1987 requested that you provide plant-specific information concerning the adequacy of the FitzPatrick alternate rod insertion (ARI) system, the standby liquid control (SLC) system and the recirculation pump trip (RPT) system in meeting the requirements of the ATWS rule (10CFR 50.62).

Based on the information provided in your April 15, 1987 response, we have l concluded that the SLC system design meets all applicable requirements of the i rule. Our letter to you dated September 8, 1987 documented this finding.

Concerning the AP,I system, we have identified additional information which I "'" he needed in order to complete our review. This information is delineated I

a enclosure and will require your response.

a- w. regard to the RPT system, it is the staff's position that the original

BWR/4 RPT design has not performed its function in a sufficiently reliable manner to comply with the ATWS Rule. Our January 8, 1987 letter requested l

that you provide a schedule for upgrading the existing system to either the Monticello design or the modified Hatch design, both of which were approved by I the staff in 1979. As an alternative, you were requested to demonstrate that the existing system could perform its function with equivalent reliability.

Your April 15, 1987 response stated that you endorse the BWR Owner's Group position that redundant trip coils in each recirculation system motor-generator set, generator field breaker (as employed in the Monticello and Hatch designs) are not required to comply with the ATWS rule. Your letter further stated that "a submittal from the Owners Group to NRC regarding this matter is expected in the near future" and that "pending resolution of the issue, no modifications to the FitzPatrick RPT system are presently planned."

To date, the NRC has not received a submittal from the Owners Group concerning this matter.

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'In the interest of obtaining a timely resolution of the ATWS Rule compliance issue for FitzPatrick, and in light of your comitment to complete all ATWS-related modifications prior to restart from the next refueling outage, scheduled to begin late in August, we request that you provide us with the information delineated above and in the enclosure, concerning the ARI and RPT systems. ,

Sincerely, Harvey I. Abelson,. Project Manager Project Directorate I-1 Division of Reactor Projects, I/II

Enclosure:

As stated cc: See next page Pd( PDI-1 HA$elson: dig RCapra 3/17/88 3//r/88 y

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Mr. John C. Brons James A. FitzPatrick Nuclear Power Authority of the State of New York Power Plant I Cc:

Mr. Gerald C. Goldstein Ms. Donna Ross Assistant General Counsel New York State Energy Office Power Authority of the State  ? Empire State Plaza of New York 16th Floor 10 Columbus Circle Albany, New York 12223 New York, New York 10019  ;

Resident Inspector's Office U. S. Nuclear Regulatory Commission Regional Administrator, Pegion I Post Office Box 136 U.S. Nuclear Regulatory Comission Lycoming, New York 13093 475 Allendale Road King of Prussia, Pennsylvania 19a06 Mr. Radford J. Converse Mr. A. Klausman Resident Manager Senior Vice President - Appraisal James A. FitzPatrick Nuclear and Compliance Services Power Plant Power Authority of the State Post Office Box 41 of New Ynrk Lycoming, New York 13093 10 Columbus Circle New York, New York 10019 Mr. J. A. Gray, Jr. Mr. George Wilverding, Manager Director Nuclear Licensing - BWR Nuclear Safety Evaluation Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street White Plains, New York 10601 White Plains, New York 10601 ,

Mr. Robert P. Jones, Supervisor Mr. R. E. Beedle Town of Scriba Vice President Nuclear Support R. D. f4 Power Authority of the State Oswego, New York 13126 of New York 123 Main Street Mr. J. P. Bayne, President White Plains, New York 10601 Power Authority of the State of New York Mr. S. S. Zulla 10 Columbus Circle Vice President Nuclear Engineering New York, New York 10019 Power Authority of the State of New York Mr. Richard Patch 123 Main Street Quality Assurance Superintendent White Plains, New York 10601 James A. FitzPatrick Nuclear Power Plant Mr. R. Burns Post Office Box 41 Vice President Nuclear Operations Lycoming, New York 13093 Power Authority of the State of New York 123 Main Street White Plains, New York 10601

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y de ENCLOSURE- .

REQUEST FOR ADDITICNAL INFORMATION CONCERNING f . RECIRCULATION PUMP TRIP (RPT) AND _ >

ALTERNATE ROD INJECTION (ARI) SYSTEMS FOR THE-

. JAMES A. FITZPATRICK NUCLEAR POWER PLANT.

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' Provide. the following design information as supporting documentation to ,

devionstrate compliance with 10CFR 50.62.

1._ Provide electrical functional diagrams for the ARI and RPT systems from sensors to the final actuated devices. IS-the ARI system separate from-the existing RPT system?- Is any portion common to both systems?

2. . Provide the analysis results and test plans which verify that the ARI system design meets the requirements for timely completion.

Also identify the ARI reset capabilities including the time delay to ensure ARI function has coraleted its operation.

3. Describe ~ the ARI _ system manual initiation capabilities and the means provided to protect the system from inadvertent operation.

4. Identify the ARI/RPT information readout and indications provided in the-control room. Will the ARI valve have a positive position indication?

5. Identify the interface between the ARI~ system,and the safety related systems. Gescribe the Class 1E isolators which are used for this interfaces.

6. Describe the systen design which permits maintenance and the test of the system logic while the plant'is in power operation.

7. _ Describe the power = source arrangement fdr.the~ARI and RPT systems, and the capability to function during the' loss-of-offsite-power event.

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