ML20247C216

Forwards Request for Addl Info Re 890117 Application for Amend to License DPR-59,changing Tech Specs Re Primary Containment & Reactor Bldg Closed Loop Cooling Water Sys Isolation Valves

ML20247C216
Person / Time
Site:	FitzPatrick
Issue date:	05/18/1989
From:	Labarge D Office of Nuclear Reactor Regulation
To:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
TAC-71934, NUDOCS 8905240371
Download: ML20247C216 (4)

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% c May 18. 1989 (6 '!

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, DISTRIBUTION i

Docket No. 50 333 -

Eckernes NRC PDR IPDIsi'Rdg" Local PDR SVarga BBoger Mr. John C. Brons .

RCapra CVogan Executive Vice President, Nuclear Generation s DlaBarge- OGC v Power Authority of the State of New York EJordan BGrimes 123 Main Street ACRS (IO) JJohnson, RI t White Plains, New York' 10601

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PRIMARY CONTAINMENT AND PEACTOR BUILDING CLOSE LOOP COOLING WATER SYSTEM ISOLATIONVALVES(TACNO.71934)

Based on our review of your Technical Specification amendment request dated January 17,1989 -(JPN.89-006) for the James A. FitzPatrick Huclear Power Plant, we have identified the need for additional information in order to '

complete the review. We, therefore, request that you provide a response to I the questions enclosed.

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.The reporting and/or record::eeping requirements of this letter affect fewer than ten respondents; therefore OMB clearance is not required under PL 96-511.

1 Sincerely, Original signed by David E. LaBarge, Project Manager Project Directorate I-1 Division of Reactor Projects I/II

Enclosure:

Request for Additional Information cc: See next page i

[RAI71934]

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

1 Mr. Gerald C. Goldstein Ms. Donna Ross Assistant General Counsel New York State Energy Office Power Authority of the State 2 Empire State Plaza of New York 16th Floor 10 Columbus Circle Albany, New York 12223 New York, New York 10019 Resident Inspector's Office Regional Administrator, Region I U. S. Nuclear Regulatory Comission U. S. Nuclear Regulatory Commission Post Office Box 136 475 Allendale Road Lycoming, New York 13093 King of Prussia, Pennsylvania 19406 Mr. William Fernandez Mr. A. Klausman Resident Manager Senior Vice President - Appraisal James A. FitzPatrick Nuclear and Compliance Services Power Plant Pcwer Authority of the State Post Office Box 41 of New York 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. #4 Power Authority of the State Oswego, New York 13126 of New York 123 Main Street White Plains, New York 10601 Mr. J. P. Bayne, President Fower 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 123 Main Street Mr. Richard Patch White Plains, New York 10601 Quality Assurance Superintendent James A. FitzPatrick Nuclear Power Plant Post Offi r Box 41 Vice President Nuclear Operations Lycoming, New York 13093 Power Authority of the State of New York 123 Main Street Charlie Donaldson, Esquire White Plains, New York 10601 Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271

r ENCLOSURE l

l REQUEST FOR ADDITIONAL INFORMATION QIMARYCONTAINMENTANDREACTORBUILDING CLOSED LOOP COOLING WATCR SYSTEM (RBCLCWS) ISOLATION VALVES Please provide an explanation for the following:

1. The proposed amendment specifies that Valve No. 27 MOV-121 will be used for inerting or deinerting. Since inerting or deinerting will not be allowed unless this valve is operable, describe the testing program which periodically ensures that the valve is operable.

2. The proposed amendment adds Section 4.7.D.1.e. on page 186 which would require that the RBCLCWS isolation valves be fully closed and reopened anytime the reactor is in the cold condition exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if the valves have not been fully closed and reopened during the preceding 92 day s. Since designation of these valves appears to be vaguely worded in the specification, provide assurance that the new requirement will not be rcted misinterp'remon.or are the revise manual" the wording RBCLCWS isolation to show that the valves referencedAlso, valves.

92 days rather than 31 days, which would be consi. stent with recirculation pump discharge valve testing required in Section 4.5.A.5,

3. The proposed amendment incorporates changes to Specification 3.7.D.2 which would allow u) to four hours for an isolation valve listed in Table 3.7-1 to be inopera)1e before the affected penetration must be isolated by deactivating the associated automatic valve in the closed position, or closing a manual valve, or installing a blind flange. Justify use of four hour intervals rather than "Imediately," as defined in Section 1.0.

4. Another proposed change to Specification 3.7.D.2 would allow reopening of isolation valves which were closed to satisfy the penetration isolation criteria in the event that a primary containment isolation valve is inoperable. The proposal would allow them to be reopened on an intermediate basis under administrative control and would allow the containment vent and purge line isolation valves to be reopened for safety related reasons. A proposed change to the corresponding Bases section would state that the " safety related reasons include, but are not limited to, the following: inerting or deinerting (the) prinary containment; maintaining containment oxygen concentration; maintaining drywell and suppression pool atmospheric pressures; and maintaining tne differential precure between the drywell and suppression pool."

a. Explain the administrative controls which are envisioned that would ensure adequate control of primary containment integrity in order to reopen a valve which is shut due to inoperability of a normal primary containment isolation valve.

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- b. Provide a more detailed justification which shows that the integrity of the primary containment is not unnecessarily compromised as a result of reopening the valves.

c. Discuss what is meant by reopening the valves on an

" intermittent basis," including.how long_ the valves will be allowed to be opened, how often, and especially why the proposed change contains a stetement which specifically and separately 3 addresses the vent and purge line isolation valves.. Note that thu proposal would allow the valves'to be opened but does not address reclosing them.

d. Explain how the proposed change-provides greater assurance of containment isolation in the event of-an accident by imposing.

new restrictions on isolation and restoration of inoperable valves to operable status, as presented in the Evaluation of Significant Hazards Consideration section of your letter of January 17, 1989.

5. Describe the' locations where a blind flange could be insta11e'l which /

would satisfy the primary containment integrity requirement when a. valve!

listed in Ttble 3.7-1 is inoperable.

6. Determine if the proposed change to the Bases section should.be expanded' to more' fully discuss the TS proposal items. presently it only discussed the containment isolation valves which are on the containment vent and purge lines, not the other valves which are in Table 3.7-1.

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