ML20202F246

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Forwards SALP 6 Board Rept 50-155/86-01 for Nov 1984 - Mar 1986 for Review Prior to 860721 Meeting
ML20202F246
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 07/10/1986
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Buckman F
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
Shared Package
ML20202F249 List:
References
NUDOCS 8607150119
Download: ML20202F246 (2)


See also: IR 05000155/1986001

Text

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JUL 101986

Docket No. 50-155

Censumers Power Company

ATTN: Dr. F. W. Buckman

Vice President

Nuclear Operations

212 West Michigan Avenue

Jackson, MI 49201

Gentlemen:

Enclosed for your review, prior to our scheduled meeting of July 21, 1986, is the

SALP 6 Board Report for the Big Rock Point Plant covering the period November 1,

1984 through March 31, 1986.

In accordance with NRC policy, I have reviewed the SALP Board assessment and

concur with the assigned ratings. It is my view that Consumers Power Company's

conduct of nuclear activities in connection with the Big Rock Point Plant shows

an appropriate concern for nuclear safety. Specific areas I would like to high-

light are:

1. Performance in the area of Licensing Activities improved from a Category 2

to a Category 1 rating this period. Training and Qualification Effective-

ness, a new functional area, was also rated a Category 1.

2. Performance in the areas of Plant Operations and Surveillance and Inservice

Testing were rated as Category 2 during this period. This represents a

decrease from the Category 1 ratings during our last assessment. The

performance decrease in these functional areas was due to: increased

frequency of personnel errors and problems encountered in implementing

administrative controls (Plant Operations); as well as missed surveillances

(Surveillance and Inservice Testing).

3. Performance in the new functional area of Outages is given a Category 3

rating this period. This rating is a reflection of the breakdown of

administrative controls over the outage process and resulted in a Severity

Level III violation during the middle of the SALP period. Since that time

there has been no opportunity to date to evaluate the effectiveness of your

corrective measures.

4. A Category 1 rating was maintained in the area of Emergency Preparedness.

This has also been the case for SALP Cycles 4 and 5. Consequently we plan

to reduce regional inspection activities in this area. Even though you

have maintained a Category 1 rating in the Security area during this

assessment period the level of regional inspection activities will not be

reduced. This is due to the aging security equipment and continued low

morale at the guard force.

While you will have sufficient opportunity to present your comments at the

meeting on July 21, 1986, we also solicit written comments within 30 days after

the meeting to enable us to thoroughly evaluate your coments and provide you

with our conclusions relative to them gqQ

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In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,

i Title 10, Code of Federal Regulations, a copy of this letter and the SALP

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Report will be placed in the NRC Public Document Room. i

No reply to this letter is required at this time; however, should you have any

questions concerning this SALP Report, we would be pleased to discuss them
with you.

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Sincerely,

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v Regional Administrator

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i Enclosure: SALP 6 Board

l Report No. 50-155/86001

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i cc w/ enclosure:

Mr. Kenneth W. Berry, Director

i Nuclear Licensing

D. P. Hoffman, Plant

! Superintendent

! DCS/RSB (RIDS)

! Licensing Fee Management Branch

j Resident Inspector, RIII

Ronald Callen, Michigan

! Public Service Commission

! Nuclear Facilities and

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i Environmental Monitoring

'

Section

J. M. Taylor, Director, IE

l H. R. Denton, Director, NRR

1 Regional Administrators

i RI, RII, RIV, RV

! L. W. Zech, Chairman

i J. K. Asselstine, Commissioner

l F. M. Bernthal, Commissioner

] T. M. Roberts, Commissioner

i NRR Project Manager

l H. L. Thompson, NRR

i J. Axelrad IE

i RIII PRR

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