ML20214S966
| ML20214S966 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/25/1986 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20214S969 | List: |
| References | |
| NUDOCS 8612080437 | |
| Download: ML20214S966 (2) | |
See also: IR 05000454/1986040
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Docket No. 50-454
Comonwealth Edison Company
ATTN: Mr. Cordell Reed
Vice President
Post Office Box 767
Chicago, IL 60690
Gentlemen:
This refers to the routine safety inspection conducted by Messrs. J. M. Hinds
Jr., P. G. Brochman, R. M. Lerch, H. A. Walker, and Ms. J. A. Malloy of this
office on October 1 - October 31, 1986, of activities at Byron Station Unit 1,
authorized by NRC Operating License No. NPF-37 and to the discussion of our
findings with Mr. R. E. Querio and others of your staff at the conclusion of
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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.
During this inspection, certain of your activities appeared to be in violation
of NRC requirements, as specified in the enclosed Notice. A written response
is required.
In your response to violation number 1, you are specifically
requested to discuss the actions you have taken to restore the quality level
of the affected battery charger and the testing performed to verify that no
degradation of its performance has occurred.
Additionally, it is our understanding that your staff has committed to the
actions as described below regarding three unresolved items discussed in the
report.
For the unresolved item concerning performance testing of Essential Service
Water Booster Pump ISX04P, as discussed in paragraph 4 of the report, you
have agreed to perform testing, as practicable, as described in IE Bulletin 83-05 and submit a supplemental response within 30 days of the completion
of testing.
Regarding the two unresolved items concerning the potential loss of
recirculation capability for both Auxiliary Feedwater pumps, should valve
1AF024 fail to open, as discussed in Paragraph 9 of the report, we understand
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that you have agreed to provide an engineering analysis of the minimum
recirculation / flow cooling requirements during pump operation that are
necessary to prevent failure of the Auxiliary Feedwater pumps within 15
days of your receipt of this report.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter, the enclosures, and your response to this letter will be placed
in the NRC Public Document Room.
The responses directed by this letter and the accompanying Notice are not
subject to the clearance procedures of the Office of Management and Budget as
required by the Paperwork Reduction Act of 1980, PL 96-511.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
Charles E. Norelius, Director
Division of Reactor Projects
Enclosures:
1.
2.
Inspection Report
No. 50-454/86040(DRP)
cc w/ enclosures:
D. L. Farrar, Director
of Nuclear Licensing
V. I. Schlosser, Project Manager
Gunner Sorensen, Site Project
Superintendent
R. E. Querio, Plant Manager
DCS/RSB (RIDS)
Licensing Fee Management Branch
Resident Inspector, RIII Byron
Resident Inspector, RIII
Braidwood
Phyllis Dunton, Attorney
General's Office, Environmental
Control Division
D. W. Cassel, Jr., Esq.
Diane Chavez, DAARE/ SAFE
Steve Lewis, 0GC
L. Olshan, NRR LPM
H. S. Taylor, Quality Assurance
Division
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