ML19256D721
| ML19256D721 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/21/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910220640 | |
| Download: ML19256D721 (2) | |
Text
r-OCT 211977
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HEMORANDUM FOR: Karl R. Goller, Assistant Director for Operating Reactors, DOR FROM:
Barrell G. Eisenhut, Assistant Director for Operational Technology, DOR
SUBJECT:
B&W OVERPRESSURE HITIGATING SYSTEN PLANT NAMES: Arkansas 1; Crystal River 3; Oconee 1,2,3; Rancho Seco; Three Mlle Island 1 DOCKET NOS.: 50-298, 302, 269, 270, 287, 312,' 289)
RESPONSIBLE BPANCH AND PROJECT F# LAGERS: ORSfTMRBf2, OR8f4 R. Snaider, C. Nelson, D. Neighbors, L. 01shan, G. Zwetzig OPERATING TECHNOLOGY BRANCH INVOLVED: Reactor Safety REVIEW STATUS:
Continuing The Reactor Safety Branch has completed preliminary review of the over-pressure mitigating system on operating B&W reactors and has found that the criteria established by the NRC are not fully met.
' The NRC criteria are satisfied for all the transients pastulated with the exception of an inadvertent safety injection with failure of the single low set point PORY which results in vinlation of Appendix G pressure-temperature limits prior to the time khan operator action is allowed. Al though 'a
-pressurizer bubble is available as backup, operator action is required
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' prior to 10 minutes for this limiting mass addition transient.
Enclosed is a letter to be transmitted to all operating B&W licensees to infom them of the situation and requqst further action on the problem. s
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Davis Besse 1 is different from reactors listed above and shoHd not A
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receive the letter.
T.
i'y Darrell G. Eisenhut, Assistant Directot.
for Operational Technology
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