ML17325B637
| ML17325B637 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/03/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17325B638 | List: |
| References | |
| 50-315-99-06, 50-315-99-6, 50-316-99-06, 50-316-99-6, NUDOCS 9906080071 | |
| Download: ML17325B637 (2) | |
See also: IR 05000315/1999006
Text
June 3,
1999
Mr. R. P. Powers
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, MI 49107-1395
SUBJECT:
NRC INSPECTION REPORT 50-315/99006(DRS); 50-316/99006(DRS)
Dear Mr. Powers:
From March 29 through May 5, 1999, the NRC conducted a special inspection at your
D. C. Cook, Units 1 and 2 reactor facilities. The inspection was an examination of activities
conducted under your license as they relate to your Performance Assurance (PA) staff's audit of
the Expanded System Readiness
Review (ESRR) Program.
The enclosed report documents
the results of the inspection.
We note that this is an interim report, issued at this time because
of schedule changes your ESRR program has incurred and the impact of those delays on our
ability to evaluate the full scope of the audit.
We concluded that the PA department developed a well-structured, comprehensive oversight of
the ESRR program.
We observed the audit while it was in progress and determined that the
direct inspection portions of the audit plan were appropriately implemented.
The portion of the
audit that examines and resolves differences in findings between the PA and ESRR teams is not
expected to be completed for several weeks.
We willevaluate that portion of the effort after it is
concluded.
During our inspection we identified a number of aspects of overall station operation where
programs and processes
appeared to have weaknesses.
Among these aspects were the
usability and integrity of management information systems (in particular, plant databases),
the
in-plant instrument calibration program, the motor-operated-valve
preventive maintenance
program, and mechanical bolting and fastening.
Although not directly related to the objectives of
the inspection, we developed these concerns from the integration of many inspection-related
observations.
Because of the nature of our inspection, we made no attempt to determine
whether or not these issues had been previously identified. However, we are aware that you
have programmatic evaluations ongoing in many areas and that some of these weaknesses
may already have been identified and corrective actions are being developed to address them.
In accordance with 10 CFR 2.790 of the NRC "Rules of Practice," a copy of this letter, the
enclosure, and your response to this letter, ifyou choose to provide one, will be placed in the
NRC Public Document Room (PDR).
9'POb08007i
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R. Powers
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We willgladly discuss any questions you have concerning this inspection.
Sincerely,
Original /s/ John A. Grobe
Docket Nos. 50-315; 50-316
John A. Grobe, Director
Division of Reactor Safety
Enclosure:
Inspection Report 50-315/99006(DRS); 50-316/99006(DRS)
cc w/encls:
A. C. Bakken III, Site Vice President
M. Rencheck, Vice President,
Engineering
R. Whale, Michigan Public Service Commission
Michigan Department of Environmental Quality
Emergency Management Division,
Ml Department of State Police
D. Lochbaum, Union of Concerned
Scientists
Distribution:
RRB1 (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/encl
J. Caldwell, Rillw/encl
B. Clayton, Rill w/encl
SRI D. C. Cook w/encl
DRP w/encl
DRS w/encl
Rill PRR w/encl
.PUBLIC IE-01 w/encl
Docket File w/encl
GREENS
IEO (E-Mail)
DOCDESK (E-Mail)
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