ML20004C592
| ML20004C592 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/01/1981 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8106040306 | |
| Download: ML20004C592 (2) | |
Text
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Generes offices: 212 West Michtgen Avenue, Jackson, MI 49201 * (51'/) 788 0550 June 1, 1981 Director, Nuclear Reactor Regulation Qfg Att Mr Dennis M Crutchfield, Chief
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Operating Reactors Branch No 5 g
'c US Nuclear Regulatory Commission Washington, DC 20555 4p
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887 DOCKET 50-155 - LICENSE Dht BIG ROCK POINT PLANT - PROBABILISTIC RISK s g.
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ASSESSMENT EVALUATION OF TECHNICAL SUPPORT
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'A CENTER AND CONTROL ROOM HABITABILITY Consumers Power Company letter dated March 31, 1981 submitted the Big Rock Point Probabilistic Risk Assessment (FRA) Report and a request for deferral of requirements identified as nonessential by the PRA for review by the NRC.
Attachment T to the request for deferral discussed the basis for continued deferral oi the Technical Support Center (TSC) and Control Room Habitability requirements.
As part of this attachment, Consumers Power proposed to complete specific actions concerning the TSC/ Control Room requirements by June 1, 1981.
The purpose of this letter is to advise you that Consumers Power is continuing its efforts to complete these actions and, except for one item, now expects to submit our findings by September, 1981. This letter also provides a brief cess that has been made to date.
description of the pra The proposed actione described in Attachment 7 and the status of the effort to complete these actions are summarized as follow:
htion Item 1 Design alternate shutdown panel and confirm, based on a formal PRA update, that core damage frequency for fire related sequences is reduced to an acceptably low level.
Status This item has been partially completed, as reported in our letter of May 19, 1981, in that the alternate shutdown panel design has been completed. The design was confirmed, based on PRA analyses, that the core damage frequency for fire related sequences in indeed reduced to an acceptably low level. At this time, however, the benefits of installing alternate shutdown panel read-outs in the control room are still being considered.
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'Mr Dennie M Crutchficid, Chicf 2
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-. Big Rock Point Plant
, June 1, 1981, Action Items 2 and b
. Evaluate need and timing of ingress / egress for.tte TSC and Control Room to-determine if.high radiation levels in access routes causes a significant
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exposure hazard ~for personnel.
Based on ALARA considerations, evaluate the need for simple plant modifications which reduce the dose received by personnel during an accident.
Status Dose calculations reported in the PRA are presently being reviewed for accuracy and completeness. The results of recently completed plant and plant-site walk-downs, new approaches to calculating inhalation doses, and the effects of air-borne contamination on activities outside the plant buildings are being considered l
for incorporation into the PRA analysis. Based on the conclusions of these in--
vestigations and reviews, additional shielding requirements, if any, will be identified.
Action Item 3 Develop conceptual design description of the Technical Support Center based on NUREG-0696 requirements and provide bases for meeting or taking exception to these requirements.
Status Consumers Power has determined that the TSC design for the Big Rock Point Plant e
is satisfactory with regard to the requirements of NUREG-0696.
The conceptual i
design description along with the bases for meeting or taking exception to NUREG-0696 requirements are provided in Consumers Power Company letter, dated June 1, 1981, entitled " Response to Post-TMI Requirements for the Emergency Operations Facility (Generic Letter 81-10)", sent under separate cover.
David P Hoffman (Signed)
David P Hoffhan Nuclear Licensing Administrator
'CC Director, Region III, USNRC NRC Resident Inspector - Big Rock Point f
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