ML20154R247

Forwards Safety Insp Rept 50-155/88-06 on 880321-25.No Violations Noted.Acceptability of Certain Engineering Analyses to Satisfy App R Criteria Remains Undetermined Pending Further Review by NRR

ML20154R247
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/18/1988
From:	Harrison J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Heins G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
Shared Package
ML20154R252	List: IR 05000155/1988006 ML20154R247
References
NUDOCS 8806070247
Download: ML20154R247 (2)

See also: IR 05000155/1988006

Text

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MAY 181988

Docket No. 50-155

Consumers Power Company

ATTN: Gordon L. Heins

Senior Vice President

Energy Supply

212 West Michigan Avenue

Jackson, MI 49201

Gentlemen:

This refers to the special safety inspection conducted by Messrs. A. Fresco,

K. Parkinson, and J. M. Ulie of this office on March 21-25, and May 3,1988,

of activities at the Big Rock Point Nuclear Plant authorized by NRC Operating

License No. DPR-06 ard to the discussion of our findings with Mr. T. Elward

and other members of your staff at the conclusion of the inspection. The

purpose of the inspection was to review 10 CFR 50, Appendix R, activities.

The enclosed copy of our inspection report identifies areas examined during

the inspection. Within these areas, the inspection consisted of a selective

examination of procedures and representative records, observations, and

interviews with personnel.

No violations of NRC requirements were identified during the course of this

inspection. However, as was discussed with your staff during the inspection,

the acceptability of certain engineering analyses to satisfy Appendix R

criteria remains undetermined pending further review by NRR. We request that

the three unresolved items discussed in Paragraphs 2.f and 6 of the enclosed

report be specifically addressed.

In addition, as is discussed in Paragraphs 2.f, 7.d and 7.e of the enclosed

report, those areas within Containment intended to meet Section III.G.2 of the

Rule should be identified to NRR if the manner in which the plant meets the

Rule includes an engineering analyses and no exemption has been granted for

these specific areas lacking a fire detection system.

In general, this inspection determined that since our previous Appendix R

inspection, improvement has been made in the documentation and analyses

available to support the Big Rock Point plant compliance with Sections III.G

and L of Appendix R.

t In accordance with 10 CFR 2.790 of the Connission's regulations, a copy of

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'this letter and the enclosed inspection report will be placed in the NRC Public

Document Room.

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MAY 181988

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

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J. J. arrisoa, Chie

Engineering Branch

Enclosures: Inspection Report

No. 50-155/88006(DRS)

cc w/ enclosures:

Mr. Kenneth W. Berry, Director

Nuclear Licensing

Thomas W. E1 ward, Plant

Manager

DCD/DCB (RIDS)

Licensing Fee Management Branch

Resident Inspector, RIII

Ronald Callen, Michigan

Public Service Commission

Michigan Department of

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