ML20210T002

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Forwards Request for Addl Info Re Inservice Testing Program Valve Relief Request VR-63 & 64 Submitted on 970214.Response Requested by 980430
ML20210T002
Person / Time
Site: Fermi 
Issue date: 08/27/1997
From: Kugler A
NRC (Affiliation Not Assigned)
To: Gipson D
DETROIT EDISON CO.
References
TAC-M98009, NUDOCS 9709120233
Download: ML20210T002 (4)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION O

l WA8HINGTON, D.C. 30eaH001 49***** $

August 27, 1997 Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSERVICE TESTING PROGRAM VALVE RELIEF REQUESTS VR-63 AND VR-64 AT FERMI-2 (TAC NO. M98009)

Dear Mr. Gipson:

On February 14, 1997 (NRC-97-0001). Detroit Edison submitted inservice testing program valve relief requests VR-63 and VR-64 for NRC staff review.

VR-63 requests relief from stroke time testing requirements for the minimum flow valves in the residual heat removal, emergency diesel generator, and emergency equipment service water systems (RHRSW, EDGSW. and EESW).

VR-64 requests relief from stroke time testing requirements for the temperature control valves in the EESW system that control temperature in the emergency equipment cooling water system.

Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review.

NRC requests that Detroit Edison respond by April 30. 1998.

The staff understands that, pending the resolution of these relief requests. Detroit Edison will perform inservice testing of these valves using the alternate testing as described in the relief requests submitted on February 14, 1997.

If you have any questions concerning this request, please contact me at (301)=415-2828.

Sincerely.

ProjectDirectorate111-1 z.)h)

Andrew J. Kugler, Proiect Manager Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-341 I I s

Enclosure:

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cc w/ encl: See next page 9709120233 970827 DR ADOCK 0500 3 1 k,[

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h Mr. Douglas R. Gipson Ferml2 Detroit Edison Company ec

John Flynn, Esquire Senior Attomey-Detroit Edison Company 2000 Second Avenue l

Detroit, Michigan _48226 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Emergency _ Management Division 963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Region 111 U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Peter W. Smith Director, Nuclear Licensing Detroit Edison Company

Fermi 270 TAC 6400 North Dixie Highway Newport, Michigan 48166 September 1996 i

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!i; REQUEST FOR ADDITIONAL INFORMATION RECATED-T0 INSERVICE TESTING PROGRAM VALVE RELIEF REQUESTS

-VR-63-AND VR 64 AT FERMI 2 (TAC N0. M98009)--

-- As'we discussed in a telephone conversation on August 4,1997, please provide the following information for NRC staff review:

l 1..

Since the required quarterly stroke time test has never been performed for the subject valves. Detroit Edison should provide a documented operability determination for-these valves.

2.

During the phone conversation, Detroit Edison described activities that have been performed or are planned to enhance the reliability of these valves based on the position that stroke time testing is not possible.

Examples of the actions discussed include enhanced preventive maintenance and the future use of diagnostic equipment. These current and planned activities should be documented in the response to this

request.

3.

Detroit Edison has indicated that the valves that are the subject of the relief requests have no remote position indication and, therefore. it isn't possible to perform a repeatable stroke time test. -However, it might be possible to develop a procedure to perform repeatable stroke timing locally during the current fail safe test.

Detroit Edison should provide more detailed information describing why repeatable local measurement of the valve stroke times is not possible for quarterly tests.

Discussion of this issue should include factors affecting the measured stroke times, potential sources and magnitudes of errors, and evaluation of stroke time data obtained from efforts to take

-local measurements during the next three or four regularly scheduled-quarterly inservice tests of the valves.

ENCLOSURE

.c.

Mr. Douglas R. Gipson

. 27, 1997 Senior Vice President August 0

Nuclear Generation--

Detroit Edison Comp y 6400 North Dixie Hi ay Newport, Michigan 4 6

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO INSERVICE TESTING PROGRAM VALVE-RELIEF REQUESTS VR-63 AND VR-64 AT FERMI-2 (TAC NO. M98009) 4

Dear Mr. Gipson:

On February 14, 1997 (NRC-97-0001). Detroit Edison submitted inservice testing program valve relief requests VR-63 and VR-64 for NRC staff review.

VR-63 requests relief from stroke time testing requirements for the minimum flow-3 valves in the residual heat removal, emergency diesel generator, and emergency 4.

equipment service water systems (RHRSW, EDGSW,'and EESW).

VR-64 requests 4

relief from stroke time testing requirements for the temperature control valves in the EESW system that control temperature in the emergency equipment i

cooling water system.

t Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review.

NRC requests that Detroit Edison l

respond by April 30, 1998.

The staff understands that, pending the resolution of these relief requests, Detroit Edison will perform inservice testing of these valves using the alternate testing as described in the relief requests submitted on February 14, 1997.

4 If you have any questions concerning this request, please contact me at (301) 415-28?8, Sincerely, I

ORIGINAL SIGNED BY:

Andrew J. Kugler, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosure:

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