ML20129C699
| ML20129C699 | |
| Person / Time | |
|---|---|
| Site: | Clinton |
| Issue date: | 07/12/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Spangenberg F ILLINOIS POWER CO. |
| References | |
| NUDOCS 8507290519 | |
| Download: ML20129C699 (4) | |
Text
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Docket No. 50-461 JUL 121985 fir. Frank A. Spangenberg Director of Nuclear Licensing &
Configuration llanagcment Clinton Power Station P.O. Box 306 Mail Code V920 Clinton, Illinois 61727
Dear Mr. Spangenberg:
SUBJECT:
EFFECTS OF VALVE FLEXIBILITY lli DYNAMIC PIPING A!4ALYSES - REQUEST FOR ADDITI0fiAL INFORMATI0fi The Office of Nuclear Reactor Regulation was requested by the Office of Inspection and Enforcement (ISE) to resolve a follow-up item related to the effects of valve flexibility in dynamic piping analyses resulting from the Clinton Independent Design Review (IDR). This item is the result of an I & E inspection team's inspection performed at the Sargent & Lundy offices in Chicago, Illinois between May 6 and May 9, 1985, to evaluate the adequacy and status of corrective actions which originated from the IDR. The request for additional information pertaining to this item is contained in the en-closure.
It is requested that you provide a response within 45 days of the date of this letter.
If you need clarification or extension of the response date, please contact the licensing project manager for your application.
Sincerely, Walter R. Butler, Chief Licensing Branch lio. 2 Division of Licensing
Enclosure:
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oj WASHINGTON, D. C. 20555 JUL 12125 Docket tio. 50-461 Mr. Frank A. Spangenberg Director of Nuclear Licensing &
Configuration !!anagement Clinton Power Station P.O. Box 306 Mail Code V920 Clinton, Illinois 61727
Dear Mr. Spangenberg:
SUBJECT:
EFFECTS OF VALVE FLEXIBILITY IN DYt1AMIC PIPIllG AtlALYSE5 - REQUEST FCR ADDITIONAL INFORilATION The Office of Nuclear Reactor Regulation was requested by the Office of Inspection and Enforcement (I&E) to resolve a follow-up item related to the effects of valve flexibility in cynamic piping analyses resulting from the Clinton Independent Design Review (IDR). This item is the result of an I & E inspection team's inspection performed at the Sargent & Lundy offices in Chicago, Illinois between May 6 and May 9, 1985, to evaluate the adequacy and status of corrective actions which originated from the IDR. The request for additional information pertaining to this item is contained in the en-closure.
It is requested that you provide a response within 45 days of the date of this letter.
If you need clarification or extension of the response date, please contact the licensing project manager for your application.
Sincerely, s
Walter R. Butler, Chief Licensing Brarch No. 2 Division of Licensing
Enclosure:
As stated cc: Soc next page
kr. Frank A. Spangenberg Clinton Power Station Illinois Power Company Unit 1 cc: !!r. Allen Samuelson, Esquire Jean Foy, Esquire Assistant Attorney General 511 W. Nevaca Environnental Centrol bivision Urbana, Illinois 61001 Southern Regicr.
500 South Second Street hichard B. Hubbard Springfield, Illinois 62706 Vice President Technical Associates Mr. D. P. Hall 1723 Hamiltor, Ave. - Suite K Vice President San Jcse, CA 95125 Clinten Pcuer Staticn P. O. Box 678 Clinton, Illinois, 61727 Mr. H. R. Victor flanagcr-Nuclear Station Engineering Dpt.
Clinton Power Station P. O. Box 678 Clinton, Illinois 61727 Sheldon Zabel, Esquire Schiff, Hardin & tlaite 7200 Sears Tower 233 llacker Drive 1
Chicago, Illinois 60606 Resident Inspector U. S. Nuclear Regulatory Ccu.;ission RR 3, Box 225 A Clinton, Illinois 61727 Mr. R. C. Heider Projectlianoger Sargent & Lundy Engineers 55 East Monroe Street 4
Chicagc, Illinois 60603 hr. L. Larson Project flanager General Electric Company 175 Curtner Avenue,I;/C 395 San Jose, California 95125 fir. Janes G. Keppler U.S.130, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 I
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I REQUEST FOR ADDITIONAL INFORMATION ON THE EFFECTS OF VALVE FLEXIBILITY IN DYNAMIC PIPING ANALYSES In conjunction with the Independent Design Review (IDR) conducted by Bechtel Power Corporation for the Clinton Power Station, a follow-up inspection was performed by the NR0 staff during May 6-9, 1985 at the offices of Sargent & Lundy in Chicago, Illinois to evaluate the adequacy and status of corrective actions which originated from the IDR.
During the follow-up inspection, a question was raised regarding the modeling of flexible valves in the piping stress analyses. S & L stated that all valves are as-sumed to be' rigid (frequency greater that 33 hz in the piping model). However, the staff learned that some motor-operated valves could have-a fundamental frequency less than 33hz. Apparently, S & L has not performed any analyses to qualify these flexible valves.
In the FSAR Q & R Chapter 3, in response to MEB (DSER) Item No. 49 (May,1981), the applicant committed to perform an assessment of any valve / operator assemblies with i a natural frequency 1below 33 hz. The staff requests that the applicant address
'the following:
Explain the apparent inconsistency between the FSAR commitment and the S & L a.
consideration of flexible valves.
b.
Provide a list of all valve / operator assemblies with natural frequencies less than 33 hz, the' vendor, the acceleration values for which the valves are qualified, and the cilculated valve acceleration value.
+
c.
Provide an assessment of the effects of the flexible vs. rigid valve modeling in piping stress analyses and include any differences in the calculated valve accelerations, piping stresses, and support loads resulting from the rigid and flexible valve model.
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