ML20151G986

Forwards Request for Addl Info to Evaluate Valve Operability Considerations in Accordance W/Ie Bulletin 85-003.Requests Suppl to 860514,0904,1001 & 880115 Responses to IE Bulletin 85-003 W/Info Identified in Encl

ML20151G986
Person / Time
Site:	FitzPatrick
Issue date:	04/11/1988
From:	Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Radford Converse POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
IEB-85-003, IEB-85-3, NUDOCS 8804200206
Download: ML20151G986 (4)

Text

7 1

p 11 APR 1988 .

Docket No. 50-333 i

Power Authority of the State of New York James A. FitzPatrick Nuclear-Power Plant .l ATTN: Mr. Radford J. Converse Resident Manager - I P. O. Box 41 Lycoming, New York 13093 Gentlemen:

Subject:

Additional Information on IEB 85-03 This transmits a request for additional information needed by the NRC to -

evaluate valve operability considerations in accordance with IEB 85-0$,

"Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings."

To facilitate NRC review, we are requesting that you supplement your May 14, 1986, September 4, 1986, October 1, 1986 and January 15, 1988 responses .

to IEB 85-03 with the information identified in the enclosure to this letter, r Please make the submittal within one month of the date of this letter, if  :

practicable. If development and submittal of the information will take longer,  :

please make an interim submittal in one inonth, including the considerat'.ons in  ;

and timing for providing the remaining informaticq.  ;

Your submittal should be made to the NRC Document Control Desk, with copies to >

this office and the NRR Division of Operational Events Asse,sment.

Thank you for your cooperation.  ;

Sincerely, 3

~

fisned 9rs i

i Edward C. Wenzinger,' Chief i Projects Branch No. 2 i Division of Reactor Projects l

Enclosure:

Request for Additional Information (RAI)

Contact:

R. J. Kiessel, NRR  !

(301)492-1154 i

i r

a i

0FFICIAL RECORD COPY LTR IEB 85 0007.0.0  !

04/08/88 7 8804200206 880411 PDR ADOCK 05000333 _ // i g DCD l Q ml ,

Power Authority of the 2 I

State of New York 11 APR 1988 cc w/ enc 1:

J. Phillip Bayne, President Mr. John C. Brons, Executive Vice President A. Klausmann, Senior Vice President - Appraisal and Compliance Services R. L. Patch, Quality Assurance Superintendent George M. Wilverding, Manager Nuclear Safety Evaluation Gerald C. Goldstein, Assistant General Counsel R. E. Beedle, Vice President Nuclear Support S. S. Zulla, Vice President Nuclear Engineering R. Burns, Vice President Nuclear Operation NRC Licensing Project Manager Dept. of Public Service, State of New York Public Document Room (PCR)

Local Public Document Room (LPDR)

Nuclear Saf ety Information Center (NSIC)

NRC Resident Inspector State of New York bcc w/ encl:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

Section Chief, DRP Robert J. Bores, DRSS R. Kiessel, NRR, EAR H. Atelson, NRR, PDI-1 q

RI:DRf JohnsE/hl ift ger 4/(/88 4/[/88 end 0FFICIAL RECORD COPY LTR IEB 95 0008.0.0 04/08/E3

,a 8*

NAR 71988

.t' REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:

Review of Responses to Action Item e of IE Bulletin 85-03 Licensee Unit (s)r FitzPatrick' New York Power Authority Date of Response 05-14-86 P. O. Box 41 09-04-86 Lycoming, New York 13093 10-01-86

+01-15-88

• This response to Action Item f has not been reviewed completely.

Respondent:

Radford J. Converse, Resident Manager The information provided in your response to Action Item e of IE-Bulletin 85-03 was found to be deficient in some areas. Provide the additional information necessary to resolve the following comments and questions:

1. Revise Table 1 of the response dated 05-14-86 to include the following MOVs, or justify their exclusion. According to pages 55 and 60 of BWROG Report NEDC-31322 dated September 1986 (for HPCI and RCIC respectively), these valves have no safety action; however, utilities are expected to report differential pressures for testing, per Note o on Page 66 of that report.

(a) HPCI MOVs 21 and 24 are shown normally closed in the upper right quadrant of FSAR Figure OP-15-1 Revision 6, and as MOVs 5 and 6 on Page 68 of the BWROG Report.

(b) RCIC MOV 30 is shown normally closed in Zone I-3 of FSAR Figure OP-19-1 Revision 6, and as MOV 5 on Page 72 of the BWROG Report.

l

2. Revise Table 1 of the response dated 05-14-86 to include the l following MOVs, or justify their exclusion. According to pages 58 and 62 of the BWROG Report (for HPCI and RCIC respectively), i each of these valves has a safety action for closing.

(a) HPCI MOV 59 is shown normally open in Zone B-6 of FSAR Figure OP-15-1 Revision 6, ar.d as MOV VII on Page 71 of the BWROG Report.

(b) RCIC MOV 130 is shown normally open in Zone F-6 of FSAR Figure OP-19-1 Revision 6, and as MOV VII on Page 74 of the BWROG Report.  ;

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4 Page 2 of 2 MAR 7 1988 RAI for FitzPatrick

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3. Revise Table 1 of the response dated 05-14-86 to include a value of differential pressure for closing Steam Admission Valve MOV-132, or justify exclusion of that pressure.

According to Page 61 of the BWROG Report, this valve has safety actions for opening and closing. "N/A" is the present entry for closing this valve.

4. According to the response of 01-15-88, MOVATS has been included in the MOV testing program. If MOVATS is planned for application to some MOVs which are not included in ito data base, commit to and describe an alternate method for determining the extra thrust necessary to overcome pressure differentials for these valves.

5. The proposed program for action items b, e and d of the bulletin is incomplete. Provide the following details as a minimum:

(a) commitment to a training program for setting switches and '

maintaining valve operators.

(b) commitment to justify continued operation of a valve determined to be inoperable, (c) description of a method possibly needed to extrapolate valve stem thrust determined by testing at less than maximum  ;

differential pressure, '

(d) justification of a possible alternative to testing at maximum differential pressure et the plant, and (e) consideration of pipe break conditions as required by the bulletin.

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l Note: A partial review of the response dated 01-15-88 indicates  !

that these comments apply to it as well as to the earlier l response.

I