ML20237K472
| ML20237K472 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| 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 8708270189 | |
| Download: ML20237K472 (3) | |
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Aug 1.81987 -
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. Virginia Electric and Power Company ATTN: 'Mr. W. L. Stewart Vice President, Nuclear Operations P. O. Box 26666 Richmond, VA 23261 Gentlemen:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING NORTH ANNA'S RESPONSES TO IEB 85-03 (DOCKET NOS. 50-338 AND 50-339)
The Nuclear Regulatory Conrnissfon is contiiuing its review of responses to IEB 85-03, "Hotor Operated Valve Common Mode Failures During Plant Transient Due to The review indicates the need for additional Improper Switch Settings."
information before the program to assure valve operability can be approved for your facility.
It is 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, 5)f Alan R. Herdt, Chief Engineering Branch Division of Reactor Safety i
Enclosure:
Request for Additional Information cc w/ enc 1:
dE.W.Harrell,StationManager Q N. E. Clark, Manager - Nuclear Programs and Licensing bec w/ encl:
-A. Gibson A. Herdt
' F. Jape I
R. Kiessel, NRR l-
. Document Control Desk 8708270189 870818 DR ADOCK 0 g
.1NRCResidentinspector O
Commonwealth of VA F. Cantrell
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:
Review of Responses to Action Item e of IE Bulletin 85-03 Licensee Unit (s): North Anna 1,2 Virginia Electric and Power Company Date of Response: 12-23-85
~
P. O. Box 26666 (Unit 1)
Richmond, Virginia 23261 05-02-86 (Unit 2) 05-13-86 10-17-86 I
Respondent:
W. L. Stewart Vice President, Nuclear Operations i
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. Has water hammer due to valve 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 revise Attachment 2 to include them.
As required by Action Item a of the bulletin, assume inadvertent equipment operations.
(a) FW-100i(-200A) and FW-100C(-200C) are shown normally open in discharge lines of the AFW pumps, near the lower left corner of UFSAR Figure 10.4-7, Revision 2, 6/84.
Note that similarly located FW-100B(-200B) and FW-100D(-200D) are listed.
(b) 1275A(2275A), 1275B(2275B), 1275C(2275C), 1381(2381) and 1373(2373) in miniflow lines leading from the charging pumps to the seal water heat exchanger are shown normally open, on UFSAR figures 9.3-41 and 9.3-44 Similarly located valves are listed for five other Westinghouse three-loop facilities.
ENCt.050RE 2
(c) 1287A(2287A),1287B(22878),1287C(2287C),1869A(2869A), and 1869B(2869B) in safety. injection lines of the charging pumps to the hot legs are shown, on UFSAR figurea 9.3-41 and 9.3-44.
- 3. Please expand the proposed program for action items b, e and d of the bulletin to include the following details as a minimum:
(a) commitment to a training program for setting switches, maintaining valve operators, using signature testing equipment and interpreting signatures, (b) commitment to justify continued operation of a valve determined to be inoperable, and-(c) description of a method possibly needed to extrapolate valve stem thrust measured at less than maximum differential pressure.
e e
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