ML19206B376
| ML19206B376 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, Crane |
| Issue date: | 04/02/1979 |
| From: | Hendrie J NRC COMMISSION (OCM) |
| To: | Jonathan Brown CALIFORNIA, STATE OF |
| References | |
| NUDOCS 7905090259 | |
| Download: ML19206B376 (12) | |
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9 DRAFT 4/2/79
Dear Gavernar Brown:
My colleagues of the Commission and I have received your telegram requesting a precautior ary and temporary closing of the Rancho Seco Nuclear Power Plant in light of events at the Three Mile Island Plant in Pennsylvania.
I would like to make you aware of steps we are taking in respect to all plants of this type to assure an immediate review and analysis of safety considerations in light of experience to date and what we know of the Three Mile Island incident.
Each of these plants has been instructed by our Office of Inspection and Enforcement to take a series of specific actions which encompass:
Review of any transients of a similar nature which have occurred at the facility and determine whether any significant deviations fro.n expected performance occurred.
If any significant deviations are found, provide the details and an analysis of the significance and any corrective actions taken.
Review of the actions recuired by operating prccedures for coping with transients.
i Review of operating modes and procedures for all systems designed to transfer potentially radioactive gases and liquids out of the containment to assure that undesired pumping of radioactive liquids and gases will not occur inadvertently.
Review of prompt reporting procedures for NRC notification.to assure very early notification of serious events.
A copy of the entire bulletin is enclosed for your further information.
As you know, the NRC has assigned a resident inspector to the Rancho Seco Plant, and he will be keeping a close eye on operatiens there.
As soon as we receive the response from the Metropolitan Edison Ccmpany. we will
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. carefully review that information and take whatever action would be appropriate in those circumstances. Meanwhile, our own review of operating data and conditions does not suggest the need for immediate shutdown.
I have asked the Director of our Regional Office in Walnut Creek, Mr. Robert H.
Engelken, to keep in close touch with your Office to keep you advised of matters as they progress; and, of course, I stand ready to be of assistance in any way that 1 can. As soon as our analysis is completed, I will be in touch again to apprise you of the results.
Sincerely, Joseph M. Hendrie Chairman
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IllSERT Review of all safety related valve positions and positioning requirements to assure that engineered safety features and related equipment such as the auxiliary feedwater system, can perform their intended functions. Also review of related procedures, such as those for maintenance and testing, to assure that such valves are returned to their correct positions following necessary nanipulations, sQ2
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UNITED STATES
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t'UCLEAR REGULATORY CC:'/1ISSION OFFICE OF INSPECTION AND ENFCRCEMENT WASHIt;GTON, D.C.
20555 April 1,1979 IE aulletin No. 79-05 NUCLEAR INCIDENT AT THREE MILE ISLAND Description of Circumstances:
Cn March 28, 1979 the Three t'.ile Island Nuclear Power Plant, Unit 2 experienced core damage v hich resulted from a series of events which were initiated by a loss of feedviater transient.
Several aspects of the incident may have general applicability in addition to ap:arent generic applicability at operating Babcock and Wilcox reactori.
This bulletin is provided to inform you of the nuclear intident and L request certain actions.
Acticr s To Se Taken By Licensees (Although the specific caJses have not been de ermined for individual sequer.ces in the Three Mile Island event, scme of the folic. ling ay have contributed.)
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For all Sabcock and Wilcox pressurized water reactor facilities wich an operatin; license:
1.
Revie.. the description (Enclosure 1) of the initiating events and subs ecusnt course of the incident.
Also review che evaluaticn by the.;RC staff of a postulated severe feed.;ater transient related to Eab;ock and Wilcox P'.lRs as described in Enclosure 2.
These revie.is should be directed at assessing the adequacy of your reactor systems to safely sustain cooldcun transients such as these.
2.
Review any transients of a similar nature which have occurred at your facility and determine whether any significant deviations from expected performance occurred.
If any significant deviaticns are found, provide the details and an analysis of the sicnificance cnd any corr'ective actions taken.
This raterial may be icentified by reference if previously submitted to the NRC.
3.
Re v i e.- the actions requirec
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wi.q transients.
_ine items DUPLICATE DOCUMENT Entire document previously entered into system under:
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