ML17180A860
| ML17180A860 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/08/1994 |
| From: | Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Lyster M COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17180A861 | List: |
| References | |
| EA-94-148, NUDOCS 9408110052 | |
| Download: ML17180A860 (2) | |
See also: IR 05000237/1994013
Text
Docket No. 50-237
Docket No. 50-249
EA 94-148
Commonwealth Edison Company
ATTN:
Mr. M. D. Lyster
Site Vice President
Dresden Nuclear Power Station
6500 North Dresden Road
Morris, IL
60450
Dear Mr. Lyster:
August 8, 1994
This letter refers to the inspection conducted by Mr. H. A. Walker of this
office from June 24 through July 26, 1994.
The inspection included a review
of authorized *activities for your Dresden Nuclear Power Station. At the
conclusion of the inspection, the findings were discussed with those members
of your staff identified in the enclosed report.
Areas examined during the inspection are identified in the report. Within
these areas, the inspection consisted of selective examinations of procedures
and representative records, interviews with personnel and observation of
activities in progress.
The purpose of the inspection was to review the
actions taken on inspection follow-up item 249/94003-03{DRS) and Licensee
Event Report {LER) 237/94-010.
The LER, dated May 9, 1994, was issued as a
result of licensee actions on the inspection follow-up item.
One apparent violation was noted regarding inadequate and untimely actions to
correct inadequate design calculations.
Inadequate design calculations were
identified by licensee personnel in January of 1992.
Delayed action on the
cal£ulations resulted in a.degraded condition of the.Hig~ Pressure Coolant
Injection {HPCI) ventilation system.
Under degraded voltage conditions, the
HPCI system might not have performed the safety related functions required by
plant Technical Specifications. The failure to promptly determine and correct
noted problems, as in this case, can result in equipment that is not capable
of performing the intended safety function.
This issue is being considered for escalated enforcement action in accordance
with the "General Statement of Policy and Procedure for NRC Enforcement
Actions" {Enforcement Policy), 10 CFR Part 2, Appendix C.
Accordingly, no
Notice of Violation is presently being issued for this inspection finding.
Please be advised that the number and characterization of apparent violations
described in the enclosed inspection report may change as a result of further
NRC review.
You will be notified when further action is required .
~gRs1 l88EK2 o9s4ooosoa .
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0237
- .
Commonwealth Edison Company
2
August 8, 1994
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter and the enclosure will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Enclosure:
Inspection Reports
No. 50-237/94013(DRS);
No. 50-249/94013(DRS)
cc w/enclosure:
J. C. Brons 9 Vice President
Nuclear Support
S. Perry, Vice President
BWR Operations
G. F. Spedl, Station Manager
J. Shields, Regulatory Assurance
Supervisor
D. Farrar, Nuclear Regulatory
Services Manager
OC/LFDCB
Resident Inspectors, LaSalle,
Dresden 9 Quad Cities
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
Licensing Project Manager, NRR
Station Liaison Officer
Chairman, Illinois Commerce
Commission
S. Stein, SRS
J. Lieberman, OE
J. Goldberg, OGC
R. Zimmerman, NRR
bee:
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Walker
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Sincerely,
Is/ M. A. Ring (for)
Geoffrey E. Grant, Director
Division of Reactor Safety
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