ML18151A030

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Forwards Request for Addl Info on Util Response to IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transient Due to Improper Switch Settings. Info Requested within 30 Days of Ltr Date
ML18151A030
Person / Time
Site: Surry  
Issue date: 08/18/1987
From: Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
IEB-85-003, IEB-85-3, NUDOCS 8708310032
Download: ML18151A030 (3)


Text

I AUG 1 8 1987.

vl\\Jirginia Electric and Power. Compan,y.

ATTN:

  • Mr. W. L. Stewart, Vice President, Nuclear~Operations P. 0. Box 26666 Richmond, VA 23261
  • Gentlemen:

SUBJECT*:.* REQUEST FOR ADDITIONAL INFORMATION CONCERNIN.G SURRY I S RESPONSES TO IEB 85-03 (DOCKET NOS~ 50-280 AND 50-281)

I

    • .The Nuclear Regulatory Commission iscontinuing its review of responses to IEB 85-03, * "Motor Operated Valve Common 'Mode Failures Durin*g Plant Transient Due to Improper Switch Settings."

The review indicates the need for additional.

information before the program to assure valve operabjlity can be approved for your facility.

  • Please provid~ the additional information as stated in the enclosure. * *It is requested that you submit the additional information within 30 days of the date of this letter.

Should you ~ave any questions concerning thi~ lette~, please contact us.

Enclosure:

R~quest for Additional Information pc w/encl:

VD. L~ Benson,,3Strition Manager jN.*, E. Clark, Manager - Nuclear

. Programs and Licensing

.. Sincerely,

      • 1s I Alan R. Herdt, Chief*.

Engineering Branch Division of Reactor Safety l bee w/encl:...

  • -J NRC *Resident Inspector 8708310032 870818.

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  • Co11111onwealth of VA.

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-e ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:

ReYiev of Responses to Action Itea e of IE Bulletin 85-03 Licensee:

V_irginia Electr.ic.and Power Company P *. O. Box* 26666 Richmond, Virginia 23261 Unit(s): Surry 1,2

~~t~ ~f Resp~ns~: 05~13-86 10-17-86 02-24-87

.R~Gpondentz W. L. Stewart Vice President, Nuclear Operations

. The information proYided in your response to Action Item e of IE Bulletin 85-03 was found to be deficient in some* areas. Please proYide the additional information necessary to resolve the follov1D8 eoiiiii!llta and questions:

1. Has water hammer due to valYe closure been considered in the*

.determination of pressure differentials? If not, please explain *

. 2. Please explain why the following MOVs are not included in of the response of 10-17-86, or reYise Attachment 2 to in~lude thea.

As required by Action Ite-a of the bulletin, assume inadYertent equipment operations.

(a) 1275A(2275A), 1275B(2275B), 1275C(2275C), 1381(2381) and 1373(2373) in miniflov lines leading from the charging pumps to the seal water heat exchanger are shown normally open, on UFSAR figures 9.1-2 and 9.1-5. Siailarly located YalYes are listed for five other Westinghouse three-loop facilities *

. (b) 1287A_(2287J), 1287B(2287B), 1287C(2287C), 1869A(2869A), and 1869B(2869B) in safety injection lines of the charging pumps to the hot legs are shown on UFSAR figures 9.1-~ and 9.1-5.

3. Please expand the proposed program for action items b, c and d of the bulletin to include the following 1etails as a ainimum:

(a) commitment to a training program for setting svitche.a, maintaining valve _operators, using signature testina equipment and interpreting signatures,

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(b) comaitaent to justify contin-ed ~peration of* *alJe deterained to be inope~able, and (c).~eacription of a method possibly needed to eztrapolate *alve ate* thru~t aeaaured at lea~ than aazimu~ differential preaaure.