ML20248A535
| ML20248A535 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/19/1989 |
| From: | Axelson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20248A537 | List: |
| References | |
| NUDOCS 8910020243 | |
| Download: ML20248A535 (2) | |
See also: IR 05000155/1989015
Text
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SEP 191989
W ket No. 50-155
Consumers Power Company
ATTN:
David P. Heffman
Vice PresP4nt
Nuclear Optaations
1945 West Parnall Road
- Jackson, MI 49201
Gentlemen:
'This refers to.the routine safety inspection conducted by Messrs. E. Plettner,
N. Williamsen, F. Maura and Ms. P. Lougheed of this office on July 25 through
September 5, 1989, of activities at B'g Rock Point Nuclear Plant authorized by
NRC Operating License No. DPR-6 and to the discussion of our findings with
Mr. T. Elward and others'of his staff at the conclusion of the inspection.
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.
The results of the Containment Integrated Leak Rate Test (CILRT) are discussed
in sections seven through nine of this report.
The present status of the
CILRT is unresolved pending further information from the licensee as to why
the test should not be invalidated. The required information focuses on three
issues:
1.
The temperature of the steel sphere as compared to ambient outside
temperature:
2.
correction to the idealized sphere to account for the portion underground
and/or shaded by the turbine building; and
x
3.
the weather conditions at the plant site during the test period.
A further um esolved item concernt compliance with the requirements of 10 CFR 50
Appendix J in regards to reduced pressure testing.
Determination of Pa
correlation between a CILRT at Pa and one at reduced pressure, and the minimum
acceptable reduced pressure must be verified.
If discrepancies from Appendix J
exist, then verification of an exemption from its requirements should be
provided.
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In order to determine the acceptability of the test, and its compliance to
the regulations, we request that this information be supplied to Rcgion III
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within 30 days from the date of this report.
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SEP 191999
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No violations of NRC requirements were. identified during the course of this
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. inspection.
In accordance with 10 CFR'2.790 of the Commission's regulations, a copy of this
letter and_the enclosed inspection report will be placed in the NRC Public
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. Document Room.
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We will gladly discuss'any questions you have concerning this inspection.
'
Sincerely,
'
Oracinal sienc'l by W. L. holcontt
W. L Axelson, Chief
Reactor Projects Branch 2
. Enclosure:
Inspection Report
No.-50-155/89015(DRP)
cc w/ enclosure:
Mr.'Kenneth W. Berry, Director
Nuclear Licensing
Thomas W. Elward, Plant
Manager
DCD/DCB (RIDS)-
Licensing Fee Management Branch
Resident Inspector, RIII
Ronald Callen, Michigan
Public Service Commission
Michigan Department of
Public Health
Robert Pulsi fer, LPM, NRR-
RIII-
RIII
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