ML25196A506
| ML25196A506 | |
| Person / Time | |
|---|---|
| Issue date: | 04/14/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Gossick L NRC/EDO |
| References | |
| Download: ML25196A506 (1) | |
Text
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20665 APR i 4 1975 Lee V. Gossick Executive Director for Operations REVIEW OF GENERAL ELECTRIC MARK III CONTAINMENT DESIGN AND OTHER BWR CONTAINMENTS In recent reviews of nuclear plants utilizing General Electric Mark Ill Containment, the Committee has been aware of a number of technical issues which have been left for,future resolution as generic matters.
These include post-LOCA pressure distribution, platform and pool loading during blowdown, suppression pool make-up requirements, functioning of the RHR systems with a single active failure, and response time testing, from sensor to actuator, of ESF's.
'!be Staff has also identified other items that require resolution. Recently, the question*of drywell pressure testing bas been raised and there bas been a change in the NRC Staff position on the basis for such testing.
'!be CoIIDI1ittee is also aware that some projects utilizing Mark III Containments are reaching the point at which resolution of some of these issues is necessary.
In addition, there is recent operating experience for other BWR contain-ments regarding suppression pool behavior during primary system relief as well as experimental and analytical analyses of this phenomenon on which the Committee would like to be informed.
The Conmittee would like reports during its 181st meeting, May 8-10, 1975, on the status of the NRC Staff's review of BWR Containments.
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W. Kerr Chairman 2204