ML20237L112

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Forwards Request for Addl Info Re IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transient Due to Improper Switch Settings. Response Requested within 30 Days Before Valve Program Approved
ML20237L112
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 08/18/1987
From: Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Mcdonald R
ALABAMA POWER CO.
References
IEB-85-003, IEB-85-3, NUDOCS 8708270426
Download: ML20237L112 (2)


Text

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J

-, d'7 Alabama' Power Company ATTN: Mr. R. P. Mcdonald

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Senior Vice President-3

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-P.'O. Box 2641 1

Birmingham, AL 35291-0400 Gentlem6n:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING FARLEY'S RESPONSES TO IEB 85-03 (DOCKET NOS. 50-348 AND 50-364)

The Nuclear Regulatory Comission is continuing its review of responses to IEB j

85-03, " Motor Operated _ Valve Common Mode failures During Plant Transient Due to Improper Switch Settings."

The review indicates the need for additional information before.the program to assure valve operability can be approved for your. facility,

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It is

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Please provide the additional information as stated in the enclosure.

requested that'you submit the additional information within 30 days of the date of this letter.

Should you have any questions concerning this letter, please contact us.

Sincerely, l

i Alan R. Herdt, Chief Engineering Branch Division of Reactor Safety

Enclosure:

Request' for Additional Information r

cc w/ encl:

IW.O.Whitt,ExecutiveVice' President

,/J.D.Woodard,GeneralManager-Nuclear Plant YW. G. Hairston, III, General Manager -

Nuclear Support dJ. W. McGowan, Manager-Safety Audit and Engineering Review sJ. K. Osterholtz, Supervisor-Safety Audit and Engineering Review bec w/ encl:

4NRC Resident Inspector AE. Reeves, Project Manager, NRR A. Gibson A. Herdt F. Jape 8708270426 870018 ~

R. Kiessel, NRR PDR ADOCK 05000349 Document Control Desk G

PDR State of Alabama H. Dance x

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/g/87 08/j;/87 08/sk/87 l f ff //

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?o ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION (RAll RE:

Peview of Responses to Action Item e of IE Bulletin 85-03 Licensee:

Unit (si: Farley 1, 2 Alabama Power Company Date of Response: 05-14-86 600 North 18th Street 09-18-86 P. O. Box 2641 Respondent:

Birmingham, Alabama 35291 R. P. Mcdonald Senior Vice President F.lintridge Building 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 infor-mation necessary to resolve the following coments and questions:

1.

Unlisted MOV 8885 is shown normally closed on UFSAR figures 6.3-1A, Rev. 2, 7/84, (Unit 1) and 6.3-18. Rev. 2, 7/84, (Unit 2) in a dis-charge line of the high head safety injection pumps to the RCS cold legs. Similarly located MOVs of two other Westinghouse three-loop plants are listed for inspection in accordance with bulletin require-ments.

Please revise the listing to include this MOV, or justify its exclusion. As required by Action Item a of the bulletin, consider the effect of inadvertent equipment operations.

2.

Has water hammer due to valve closure been considered in the determination of pressure differentials? If not, please explain.

3.

Please justify extension of the date for completing Action Items b, e and d from 11-15-87 to April 1988 for Unit 1 and the date for completing Action item f from 1-15-88 to June 1988 for Unit 1.

4.

Please expand the proposed program for Action Items b, e and d of the bulletin to include the following detafis as a minimum:

(a) justification of a possible alternative to testing at maximum 1

differential pressure at the plant, and (b) description of a method possibly needed to extrapolate valve stem thrust measured at less than maximum differential pressure.

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