ML19345A858

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Forwards Corrections to 800627 Proposed Change to Tech Specs Resolving Problems Re Operability Requirements for Recirculation Pump Sump Area Sprinkler Sys.Supersedes 800627 Request
ML19345A858
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/22/1980
From: Hoffman D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML19345A859 List:
References
NUDOCS 8011250340
Download: ML19345A858 (2)


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@ Consumcis nicanonyMP wica Power Company a e, a y g 3, Generel offices: 212 West Michigen Avenue, Jackson Michleen 49201 = (517) 788-0550

, e, 3 HUliERVices September 22, 1980 "40H Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 US Nuclear Regulttory Commission W3%ington, DC 20555 DOCKET 50-155 - IICENSE Lt.<-6 BIG ROCK POINT PLANT - PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST - FIRE PROTECTION Co aumers Power Company letter dated June 27, 1980, submitted a proposed change to the Big Rock Point Technical Specifications.

The requested change was to add operability and surveillance testing requirements for fire protec-tion equipment to be added by plant modification in accordance with the requirements of Amendment No 25 to License DPR-6.

Further review has identified that the requested change is in error with respect to operability requirements for the recirculation pump sump area sprinkler system.

The change proposed by Consumers Power Company's June 27, *980, letter added the recirculation pump sump area sprinkler system to the existing limiting condition for operation for other fire protection sprinkler systems. This requirement includes establishment of a continuous fire watch. The recircula-tion pump sump area is inaccessible during reactor operation due to very high radiation levels.

It is thus not possible to establish a continuous fire watch in the area during pcwer operation.

Access to the area is possible during shutdown conditions, but residual radiation levels in the area are such that a continuous fire watch would cause significant personnel radiation exposure to be received; this exposure is unwarranted provided backup fire suppression equipment is available. The proposed change has been revised as shown in the attachment to this letter to resolve these problems.

Other editorial-errors in our previous submittal were identified and have been corrected in the attachment.

For your convenience, the attachment has been prepared as a complete package intended to supersede our June 27, 1980 re-

quest.

This change has been reviewed by the Plant Review Committee and the oc0980-0016a-43 s0312503 %

Director, Nuclear Reactor Regulation 2

Big Rock Point Plant Safety and Audit Review Board and found acceptable. Please consider the attached proposed Technical Specifications change in lieu of that submitted June 27, 1980.

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David P Hoffman Nuclear Licensing Administrator CC Director, Region III, USNRC NRC Resident Inspector-Big Rock Point Attachment oc0980-0016a-43 Y