ML17335A569
| ML17335A569 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/21/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17335A570 | List: |
| References | |
| 50-315-99-25, 50-316-99-25, NUDOCS 9910270173 | |
| Download: ML17335A569 (5) | |
See also: IR 05000315/1999025
Text
REGULATORY INFORMATION DISTR1BUTION SYSTEM (RIDS)
1
~ ACCESSION NBR:9910270173
DOC.DATE: 99/10/21
NOTARIZED: NO
DOCKET
CIL:50-315 Donald C.
Cook Nuclear. Power Plant, Unit 1, Indiana
M
05000315
50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana
M
05000316
UTH.NAME
AUTHOR AFFILIATION
GROBE,J.A.
Region
3
(Post
820201)
.RECIP.NAME
'RECIPIENT AFFILIATION
POWERS,R.P.
American Electric Power Co., Inc.
SUBJECT:
Forwards insp repts
50-315/99-25
6 50-316/99-25
on 990816-
20.Two violations of NRC requirements identified
&, being
treated
as non-cited violations consistent with App
C
of enforcement 'policy.
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TITLE: General
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16
ENCL
16
October 21, 1999
Mr. R. P. Powers
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
NRC INSPECTION REPORT 50-315/99025(DRS); 50-316/99025(DRS)
Dear Mr. Powers:
On August 16-20, 1999, the NRC conducted an inspection at your Donald C. Cook Nuclear
Generating Plant (D.C. Cook). The inspection was an examination of activities conducted
under your license with respect to compliance with NRC rules and regulations and the
conditions of your license.
The inspection focused on assessing
the effectiveness of
refurbishment activities on the 4-kV and 600-V circuit breakers.
The work was being performed
by ASEA Brown-Boveri (ABB) Service Company technicians under the supervision of plant
staff, under plant quality assurance
controls and using plant procedures.
The inspectors
reviewed these procedures,
related work documents and associated
corrective action
documents, observed work in progress, examined the affected equipment and interviewed
personnel involved.
Based on the results of this inspection, two violations of. NRC requirements were identified. The
first violation involved the failure to translate certain design basis information (specifically,
minimum, worst-case, calculated control voltage available at the breaker) into breaker
refurbishment test procedures as required by Criterion III, "Design Control," of Appendix B, to
Part 50 of Title 10 of the Code ofFederal Regulations (10 CFR Part 50). The second violation
concerned the adequacy of the procedures used to perform the breaker maintenance activities.
Specifically, the breaker refurbishment procedures contained various other errors and
~ omissions (including certain test parameters,
test sequences
and acceptance
criteria) that
rendered them inappropriate to the circumstances, which is contrary to Criterion V,
"Instructions, Procedures and Drawings," of 10 CFR Part 50, Appendix B. As discussed
in
detail in the enclosed report, the violations were of concern because the use of the deficient
procedures resulted in: (1) inadequate evaluation of as-found breaker conditions;
(2) inadequate assurance
that refurbishment was being done satisfactorily; (3) insufficient
determination of baseline performance data for evaluation of future performance trends, and,
most safety significant; (4) inadequate demonstration of safety-related circuit breaker operability
under worst-case design basis conditions.
99i0270i73 99i02i
ADOCK 05000315
6
R. Powers
-2-
These Severity Level IVviolations are being treated as non-cited violations (NCVs) in
accordance with Appendix C of the NRC Enforcement Policy. Appendix C of the Enforcement
Policy requires that for Severity Level IVviolations to be dispositioned as NCVs, they be placed
in the licensee's corrective action program.
Implicitin that requirement is that the violation has
been appropriately characterized
(including root cause(s) ifappropriate), with acceptable
corrective action and preventive measures
committed to, and that the corrective action program
itself is fullyacceptable.
While your staff and the NRC have not yet concluded that your
corrective action program is fullyeffective, the NRC has determined that this issue has been
appropriately captured and is to be appropriately dispositioned.
In addition, the significant
efforts by your staff to improve the corrective action program are underway and are captured in
the D.C. Cook Plant Restart Plan which is under the oversight of the NRC through the process
prescribed in NRC Manual Chapter 0350, "Staff Guidelines for Restart Approval." Accordingly,
no Notice of Violation,willbe issued.
In accordance with 10CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, the
enclosed report and your response will be placed in the NRC Public Document Room.
Sincerely,
Original Signed
by John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-315; 50-316
Enclosure:
Inspection Report 50-315/99025(DRS);
50-316/99025(DRS)
cc w/encl:
A. C. Bakken III, Site Vice President
T. Noonan, Plant Manager
M. Rencheck, Vice President, Nuclear 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
See Attached Distribution
DOCUMENT NAME: G:DRSttDCC99025.WPD
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DATE
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OFFICIALRECORD COPY
R. Powers
Distribution:
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