ML17179B086
| ML17179B086 | |
| Person / Time | |
|---|---|
| Site: | Dresden |
| Issue date: | 09/16/1993 |
| From: | Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17179B087 | List: |
| References | |
| NUDOCS 9309210137 | |
| Download: ML17179B086 (2) | |
See also: IR 05000237/1993021
Text
UNITED STATES
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NUCLEAR REGULATORY COMMISSION
REGION Ill
799 ROOSEVELT ROAD
GLEN ELLYN, ILUNOIS 60137-5927
- ..
Docket No. 50-237
Docket No. 50-249
Commonwealth Edison Company
ATTN:
Mr. L. 0. DelGeorge
Vice President
Nuclear Oversight and
Regulatory Services
Executive Towers West III
1400 Opus Place, Suite 300
Downers Grove, IL
60515
Dear Mr. DelGeorge:
SEP 1 6 1993
This letter refers to the routine safety inspection conducted by
Mr. G. D. Replogle and others of this office on August 2-6 and 16-19, 1993.
The inspection included a review of activities authorized for your Dresden
Nuclear Power Station, Units 2 and 3. 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. These
areas consisted primarily of a review of the implementation of the Dresden
motor operated valve program established in response to Generic Letter 89-10.
Within these areas, the inspection consisted of a selective examination of
procedures and representative records, observations, and interviews with
personnel.
The purpose of the inspection was to determine whether activities '
authorized by the licenses were conducted safely and in accordance with NRC
requirements.
While strengths were noted in your contributions to motor operated valve (MOV}
research testing programs, major deficiencies appear to exist in your MOV
program implementation.
Deficiencies were exhibited in establishing
appropriate program guidance, justification for technical assumptions,
differential pressure testing, conrnitment tracking, switch settings, and
addressing safety issues such as correcting MOV deficiencies and pressure
locking and thermal binding of valves.
I
These issues demonstrate weaknesses in the management oversight of your MOV
program and in your approach to resolving technical issues. Overcoming these
weaknesses will constitute a significant management challenge.
As discussed.with yo~ during the August 26, 1993 meeting held at the Region
III office, you are requested to submit your differential pressure testing
schedule within 30 days of receipt of this inspection report.
We also request
that you include your plan and schedule for addressing the pressure locking
and thermal binding issues .
9309210137 930916
ADOCK 05000237
G
Ji_~ f !1 'r - TF t I
Commonwealth Edison Company
2
SEP 16 1993
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter, its enclosures, and your response will be placed in the NRC
Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
k.~l.::::irector
-
Division of Reactor Safety
Enclosures:
1.
Inspection Reports
No. 50-237/9302l(DRS);
No. 50-249/9302l(DRS)
2.
Appendix A - Advance Information
Request to Support a GL 89-10
Inspection
cc w/enclosures:
M. D. Lyster, Site Vice
President
G. F. Spedl, Station Manager
Ms. J. Shields, Regulatory Assurance
Supervisor
D. Farrar, Nuclear Regulatory
Services Manager
OC/LFDCB
Resident Inspectors-Dresden,
LaSalle, Quad Cities
Richard Hubbard
J. W. McCaffrey, Chief
Public Utilities Division
Robert Newmann, Office of Public
Counsel, State of Illinois Center
J. F. Stang, LPM, NRR
T. Scarbrough, NRR
State Liaison Officer
Chairman, Illinois Commerce
Commission
J. B. Martin, Rill
H. J. Miller, Riii
T. 0. Martin, Rill
J. E. Dyer, NRR
M. J. Jordan, Riii
C. D. Pederson, Riii
S. Stasek, SRI, Davis-Besse