ML20238E117

Forwards Request for Addl Info Re Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Response Requested within 30 Days of Ltr Date

ML20238E117
Person / Time
Site:	Crane
Issue date:	09/09/1987
From:	Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Hukill H GENERAL PUBLIC UTILITIES CORP.
References
IEB-85-003, IEB-85-3, NUDOCS 8709140151
Download: ML20238E117 (5)

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i 09 SEP 1987 i

i Docket No. 50-289 j

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GPU Nuclect Corporation l

ATTN: Mr. H. D. Hukill Vice President and Director of TMI-l P. O. Box 480 Middletown, Pennsylvania 17057 Gentlemen:

Subject:

Request for Additional Information Concerning Response to IE Bulletin 1

85-03, " Motor-0perated Valve Common Mode Failures During Plant l

Transients Due to Improper Switch Settings."

l During the NRC review of your response to IEB 85-03, we have identified the need for additional information in order to provide a thorough evaluation prior to approval of the program to assure valve operability.

The specific information necessary for the completion of our review is enclosed with this letter.

Please provide the additional information within 30 days of the date of this letter.

Your cooperation with us in this matter is appreciated.

Sincerely, Sig$iipy;

~

William F. Kane, Director j

Division of Reactor Projects

Enclosure:

As stated l

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GPU Nuclear Corporation 2

09 SEP 1987 I

cc w/ enc 1:

T. G. Broughton, Operations and Maintenance Director, TMI-1 C. W. Smyth, Manager, TMI-1 Licensing R. J. McGoey, Manager, PWR Licensing E. L. Blake, Jr., Esquire J. F. O' Leary, Chairman TMI-1 Hearing Service List Public Document Raom (PDR) local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Commonwealth of Pennsylvania bec w/ enc 1:

Region I Docket Room (with concurrences)

W. D. Travers, Director, TMI-2 Cleanup Project Directorate J. Goldberg, OELD: HQ Management Assistant, DRMA (w/o enc 1)

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ENCLOSURE

'Page 1 of 2 l

REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:

1 Review of Responses to Action Item e of IE Bulletin 85-03 i

Licensee:

Unit (s): THI-1 GPU Nuclear Corporation Date of Response: 05-27-86 I

P. O.

Box 480 09-15-86 Route 441 South 02-27-87 Middletown, PA 17057-0191 Respondent:

H. D. Hubill J

Vice President j

& Director, TMI 1 The information provided in your response to Action Item e of IE Bulletin 85-03 was found to be deficient in some areas.

Please provide the additional information necessary to resolve the following comments and questions:

1.

Unlisted MOVs CF-VIA and CF-V1B in discharge lines of the core flooding tank safety injection system are shown normally open on FSAR figures 6.0-2 (Update 2, 7/83) and 6.1-1 (Update 5, 7/86).

The possible problem that the system would be inoperable if the MOVs were left closed inadvertently should be addressed.

Based on the assumption of inadvertent equipment j

operations as required by Action Item a of the bulletin, revise the attachments of the responses of May 27 and September 15, 1986 to include these valves.

2. The following MOVs are not included in the list of valves of the emergency feedwater system to be examined for maximum differential pressure..

That is, they are not identified in the attachments of the responses of May 27 and September 15, 1986.

As a general question, what controls are placed on these valves to ensure that they will be in the proper position when needed?

In accordance with the request of Action Item a of the bulletin to assume inadvertent equipment operations, revise the response attachments to include these valves.

(a) EF-VIA and EF-V1B are shown normally open in series in suction lines, on Drawing 5130-302-082, Revision 8.

(b) EF-V2A and EF-V2B are shown normally open in series in crossover discharge lines, on the drawing mentioned above in Item 2(a).

3. Has water hammer due to valve closure been considered in the determination of pressure differentials?

If not, please explain.

Pege 2 of 2 RAI for TMI-1

4. The following statement appears on Page 3 of the response of i

Hay 27, 1986:

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"GPUN believes that the calculation and quantitative 3

verification of the torque switch setpoint provides a a sufficient assurance that the valves will perform the_ir j, rafety function.

No special differential pressure testing is planned."

This statement does not comply with the requirement of Attion Item c to demonstrate operability by testing at maximum %)

differential pressure, or by stroke testing if testing with differential pressure cannot be performed.

Furthermore, justification should be provided for any case where testing with the maximum differential pressure cannot be performed because of practical considerations.

Please provide details of the calculation method planned to establish the c[] rect switch settings.

5. Please state the planned date of completion of Action Item f of the bulletin.

Note that the due date specified by the bulletin is January 15, 1988.

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6. Please include the following details as a minimum in a program for action items b, c, and d of the bulletin:

j (a) commitment to a training program for cetting switches, maintaining valve operators, using signature testing equipment and interpreting signatures, sad (b) commitment to justify continued operation of a valve determined to be inoperable, j

l (c) description of a method possibly needed to extrapolate valve

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stem thrust determined by testing at less than maximum l

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

bulletin, (f) stroke testing when necessary to meet bulletin requirements, and (g) consideration of applicable industry recommendations in the preparation of procedures to ensure maintenance of correct switch settings.

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