ML20094N435
| ML20094N435 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/01/1992 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20094N438 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM LIC-92-103R, NUDOCS 9204060354 | |
| Download: ML20094N435 (2) | |
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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 April 1, 1992 LIC-92-103R V. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter from OPPD (W. G. Gates) to NRC (Document Control Desk) dated July 1, 1991 (LIC-91-182R) 3.
Letter from OPPD (W. G. Gates) to NRC (Document Control Desk) dated December 31,1991 (LIC-91-337R) 4.
LetterfromNRC(D.L.Wigginton)toOPPD(W.G. Gates) dated March 4, 1992 Gentlemen:
SUBJECT:
Results of Prototype Power Operated Relief Valve (PORV) Block Valve Steam Blowdown Testing In Reference 2, Omaha Public Power District (OPPD) committ ad to purchase a prototype PORV block valve from the original equipment manuf acturer and perform steam blowdown testing by December 31, 1991.
This was done to close out Item II.D.1 of NUREG-0737 for Fort Calhoun Station (FCS), demonstrating the capability of the PORV block valves to isolate steam blordawn flow through a stuck open PORV.
Reference 3 submitted the preliminary test report.
As committed in Reference 3, enclosed is OPPD's final report on the steam blowdown testing conducted by WYLE Laboratories. The additional information requested by the NRC in Reference 4 is provided in the report. Certain references as noted in Section 10.0 of the report are included for use by NRC technical reviewers.
The test valve configured with an actuatei and a motor was sent to WYLE Laboratories for steam blowdown testing during the week of November 18, 1991.
The conclusions of the enclosed final test report are:
1.
The test valve and actuator accurately modeled the in-plant PORV block valves in performance characteristics.
2.
The steam blowdown test conditions adequately bounded the design basis conditions of the PORV block valves installed at FCS.
3.
Margin exists at actuator torque switch trip for the installed PORV block valves to perform their safety function of isolating steam blowdown flow through a " stuck open" PORV.
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Therefore, the subject testing confirmed that the in-plant PORV block valves will stroke closed in 10 seconds pressure and flow conditions.(or less) under the maximum expected different alAll remaining NUREG i
been addressed by this te'; ting.
If you should have any questions, please contact me.
Sincerely AV. 5. M W. G. Gates Division Manager Nuclear Operations Enclosures WGG/sel c:
LeBoeuf, Lamb, Leiby & MacRae D. L. Wigginton, NRC Senior Project Manager S. D. Bloom, NRC Project Engineer R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident inspector 6
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