ML20090B046
| ML20090B046 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/12/1981 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | Novak T, Novak T, Tedesco R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20090B024 | List: |
| References | |
| FOIA-83-765 NUDOCS 8108270120 | |
| Download: ML20090B046 (2) | |
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UNITED STATES a
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.OYN MEMORANDUM FOR: Robert L. Tedesco, Assistant Director h[ 7
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for Licensing Division of Licensing
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Thomas H. Novak, Assistant Director L< /
for Operating Reactors Division of Licensing il' A )
FROM:
James P. Knight, Assistant Director for Components & Structures Engineerin Division of Engineering x
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SUBJECT:
REPORTING OF UNSATISFACTORY EPRI/PWR TEST RESULTS FOR,
CROSBY !!0 DEL 3K6 SAFETY The attached memorandum from EPRI for the period July 25 - 31, 1981 discusses the results of steam and water tests performed at Combustion Engineering on the Crosby 3K6 safety valve. As discussed in the memorandum, the safety valve failed one or more of the test screening criteria in these tests. The two screening criteria failed most in these tests are:
(a) Valve must open within plus or minus 3% of valve design set pressure.
(b) Valve fully closes when inlet pressure is less than the pressure at/
which the valve opened and greater than 2250 psig.
In addition to failing some specific screening criteria, there was evidence of minor galling and damage to valve internals and indication of fairly high valve leakage - 15 gpm after several high pressure water tests.
Note that all of these tests were perfomed with a short inlet piping config-uration. The valve has not been tested as yet with the long loop seal inlet piping configuration that is normally used on Westinghouse plants. The next series of tests to be performed on the valve will be with the long loop seal piping.
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i It is our understanding that the Operating License and Construction Pemit Holders that utilize or plan to utilize these safety valves and the PWR NSSS vendors have been notified of these test results. These licenses and pemit holders have the responsibility for independently assessing the safety significance of the observed valve behavior for their plants, including the reporting of significant findings to the NRC.
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Page 2 Our information from EPRI indicates that the Crosby 3K6 valve is being or will be used on the following plants:
St. Lucie 1 and 2 Fort Calhoun 1 i
Although the specific safety significance of these test results is still be n evaluated, this information may be relevant for Board notification.
If a decision is made to forward this information t o one or more Boards, we memorantum from Frank Cherny to 22, 1981 recommen6 that a copy of the July A copy of the memorandum Robert J. Bosnak be forwarded to the Board also.It contains the minutes of the July 17, 19R tt meeting between the staff and EPRI and the PWR Owners Group 'at which was previously distributed to you.
d of all of the Safety Valve and PORV testing in the EPRI program was discusse N
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. lames P. ( ght, Assistant Directorfor Compo
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R. Vollmer F. Cherny E. Hemminger H. Gregg R. LaGrange i
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R. Kiessel D. Chaney R. Clark S. Varga W..lohnston R. Bosnak D. Dilanni i
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