ML20235H082
| ML20235H082 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/14/1989 |
| From: | Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8902230465 | |
| Download: ML20235H082 (3) | |
Text
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.e Omaha Public Power District 1623 Harney Ornaha. Nebraska 68102-2247 402/536 4000 February 14, 1989 1.IC-89-103 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station P1-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
IEB 85-03, " Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings" 3.
Letter from 0 PPD (R. L. Andrews) to NRC (Document Control Desk), dated May 15, 1986 (LIC-86-224) 4.
Letter from 0 PPD (R. L. Andrews) to NRC (Document Control Desk), dated August 7, 1987 (LIC-87-567)
Gentlemen:
SUBJECT:
IE Bulletin 85-03 Dated November 14, 1985 The purpose of this letter is to amend information previously provided by the Omaha Public Power District (0 PPD) in response to IE Bulletin 85-03, References 3 and 4.
IE Bulletin 85-03 required holders of operating licenses to review the design basis for the operation of High Pressure Safety Injection (HPSI)/ core spray and emergency feedwater system motor-operated valves that are required to be tested for operational readiness. The review was to include a determination of the maximum differential pressure expected during both opening and closing the valve for normal and abnormal events.
OPPD performed an evaluation to determine closure and opening differential I.
pressures for the applicable valves. OPPD's letter, Reference 3, reported tle maximum differential pressure expected for valve operation to be 1445 psi.
HPSI valves were tested for operability in accordance with Special Procedure r,mg SP-SI-HPSI during the 1987 refueling outage. Results of the special test were
".EE re90rted by 0 PPD letter, Reference 4.
$8 e rs The 1987 test data was reviewed. The review determined that the test was conducted at a differential pressure of approximately 1342 psi in lieu of the Q
1445 psi calculated. After allowances for instrument error and gauge readability error, it could not be concluded that the expected maximum eo 8@
differential pressure was satisfied during the test.
Engineering was requested N
to reevaluate the acceptance criteria for the test. An Operations Support Analysis Report (0SAR) was initiated and concluded that the correct maximum om
$8e differential pressure needed to demonstrate operability of the valves is 1401 psi.
Engineering recommended that the test be conducted again to ensure valve operability at the new pressure criterion.
l 4s siza Empioument w m tquai opponunau W---
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Document Control Desk LIC-89-103 Page 2 SP-SI-HPSI was conducted again on December 31, 1988.
It is possible to record pressure readings at two locations in the system.
If pump discharge pressure is read from the High Pressure Header Pressure Indicators, PI-309 or PI-310, the minimum acceptable pressure indication is 1408 psig.
During the December 31, 1988 test both PI-309 and PI-310 read 1420 psig.
If the pump discharge pressure is read from the local discharge pressure gauge, the minimum acceptable pressure is 1417 psig. During the December 31, 1988 test, the local pressure reading was 1435 psig.
Using the acceptance criteria for either indicator position, the test was successful'and satisfies the testing requirements specified by IE Bulletin 85-03. The test demonstrated that the motor-operated valves are operable at the maximum expected differential pressure and that a safety concern does not exist.
If you have any questions please contact us.
Sincerely, W
9
/4 K. J. Morris
(/
Division Manager Nuclear Operations KJM/sa c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, HRC Regional Administrator, Region IV P. D. Milano, NRC Project Manager P. H. Harrell. NRC Senior Resident Inspector
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i
I
.In the Matter of
)
)
Omaha Public Power District
)
Docket No. 50-285 (Fort Calhoun Station
)
Unit No. 1)
)-
AFFIDAVIT W. G. Gates, being duly sworn, hereby deposes and says that he is the Manager -
Fort Calhoun Station of the Omaha Public Power District; that as such he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached information concerning the IE Bulletin 85-03; that he is familiar with the content thereof; and that.the matters set forth therein are true and correct to the best of his knowledge, information, and belief.
AYL / 5 W. G. Gates Manager. -. Fort Calhoun Station STATE OF NEBRASKA)
)
ss COUNTY OF. DOUGLAS)
Subscribed and sworn t4 efore me, a Notary Public in and for the State of b
J4 day of February, 1989.
Nebraska on this
" asaw N E
N Notary Public e, s.. se >
41
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