ML17325B469
| ML17325B469 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/19/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17325B470 | List: |
| References | |
| 50-315-99-02, 50-315-99-2, 50-316-99-02, 50-316-99-2, NUDOCS 9903250263 | |
| Download: ML17325B469 (8) | |
See also: IR 05000315/1999002
Text
~ i
ACCESSION NBR
FACIL:50-315
50-316
AUTH.NAME
GROBE,J.A.
RECXP.NAME
POWERS,R.P.
REGULATORY INFORMATION DISTRIBUTION SYSTEM
(RZDS)
- 9903250263
DOC.DATE: 99/03/19
NOTARIZED: NO
DOCKET
Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana
M
05000315
Donald C.
Cook Nuclear
Power Plant, Unit 2, Indiana
M
05000316
AUTHOR AFFILIATION.
Region
3
(Post
820201)
RECIPIENT AFFILIATION
American Electric Power Co., Inc.
SUBJECT: Forwards insp repts
50-315/99-02
&. 50-316/99-02
on
990202-19.No violations noted.
DISTRXBUTION CODE: IE01F
COPIES
RECEIVED:LTR
ENCL
SIZE:
TITLE: General
(50 Dkt)-Insp Rept/Notice of Violat.'on Response
NOTES:
XcF
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RECIPIENT
ID CODE/NAME
PD3-3
INTERNAL: AEOD/SPD/RAB
DEDRO
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NRR/DRPM/PERB
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NOTE TO ALL "RIDS" RECIPIENTS:
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17
ENCL
17
y/
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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 50-315/99002(DRS); 50-316/99002(DRS)
Dear Mr. Powers:
On February 19, 1999, the NRC completed a special inspection'onducted
at your Buchanan
Michigan Corporate facility. This inspection was an examination of activities under your license
as they relate to your implementation of the Expanded System Readiness
Review program at
your D. C. Cook Units 1 and 2 reactor facilities. The NRC understands
that these reviews are
intended to provide assurance
that safety-related plant systems fulfilltheir design basis safety
functions and to determine system restart readiness.
The NRC willcontinue to monitor and
assess
the effectiveness of these efforts. The enclosed report documents the results of the
inspection.
Areas examined during the inspection are identified in the report. Within these areas, the
inspection consisted of a selective examination of procedures and representative
records, and
interviews with personnel.
At the conclusion of the inspection, the findings were discussed with
you and members of your staff.
No cited violations of NRC requirements weie identified.
In accordance with 10 CFR 2.790 of
the NRC'S "Rules of Practice," a copy of this letter, the enclosures,
and your response to this
letter, ifyou choose to provide one, will be placed in the NRC Public Document Room (PDR).
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-315; 316
Enclosure:
Inspection Report 50-315/99002(DRS);
50-316/99002(DRS)
See Attached Distribution
OFFICE
Rill
Rill
Rill
Rill
NAME
Holmberg:sd~~
Vegel
Jacobson
Grob
DOCUMENT NAME: G:DRSiDCC99002.wpd
To receive a co
of this document. Indicate In the box: 'C
~ C
vnthout attachmenVenctoaure
'E ~ Co
wth attachment/enctosure
'N'
No
03/
/99
03/> /99
03/~~/99
DATE
OFFICIALRECORD COPY
9903250263
990319
ADOCK 05000315
8
03/i'/99
R. Powers
-2-
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-315; 316
Enclosure:
cc w/encl:
Inspection Report 50-315/99002(DRS);
50-316/99002(DRS)
M. Rencheck, Vice President, Nuclear Engineering
D. Cooper, Plant Manager
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:DRSiDCC99002.wpd
'SEE PREVIOUS CONCURRENCE
To receive a co
of this document, Indicate In the bord 'C'
Cco
without attachment/endosure
'E'
Co
vnth att
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'N'
No cco
OFFICE
Rill
c Rill
NAME
Holmberg:sd ~m<
Vegel
Rill
Jacobson
~
Rill
Grobe
DATE
03/
/99
03/It. /99
03 >/99,
03/
/99
OFFICIAL RECORD COPY
R. Powers
-2-
In accordance with 10 CFR 2.790 of the NRC'S "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.
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
Original /s/ John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-315; 316
Enclosure:
Inspection Report 50-315/99002(DRS);
50-316/99002(DRS)
cc w/encl:
(
, M. Rencheck, Vice President, Nuclear Engineering
D. Cooper, Plant Manager
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:DRSiDCC99002.wpd
'SEE PREVIOUS CONCURRENCE
Torecelveaco
ofthladocument,lndlcatelnihebox:
'C'
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OFFICE
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NAME
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Vegel
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DATE
03/
/99
03/
/99
03/
/99
03/
/
OFFICIAL RECORD COPY
R. Powers
Distribution:
J. Goldberg, OGC w/encl
J. Lieberrna, OE w/encl
B. Boger, NRR w/encl
RRB1 (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/encl
J. Caldwell, Rill w/encl
B. Clayton, Rill w/encl
DRP w/encl
DRS (2) w/encl
Rill PRR w/encl
PUBLIC IE-01 w/encl
Docket File w/encl
GREENS
IEO (E-Mail)
DOCDESK (E-Mail)
March 19,
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 50-315/99002(DRS); 50-316/99002(DRS)
Dear Mr. Powers:
On February 19, 1999, the NRC completed a special inspection conducted at your Buchanan
Michigan.Corporate facility. This inspection was an examination of activities under your license
as they relate to your implementation of the Expanded System Readiness
Review program at
your D. C. Cook Units 1 and 2 reactor facilities. The NRC understands
that these reviews are
intended to provide assurance
that safety-related plant systems fulfilltheir design basis safety
functions and to determine system restart readiness.
The NRC willcontinue to monitor and
assess
the effectiveness of these efforts. The enclosed report documents the results of the
inspection.
5
Areas examined during the inspection are identified in the report. Within these areas, the
inspection consisted of a selective examination of procedures and representative
records, and
interviews with personnel.
At the conclusion of the inspection, the findings were discussed with
you and members of your staff.
Based on the. results of this inspection, the NRC has determined that a violation of NRC
requirements occurred.
The violation pertained to the failure of the quality assurance
program
to assure receipt of all technical information for safety related components provided by nuclear
steam system supply vendors. This violation appears to be another manifestation of the design
control breakdown that contributed to the extended shutdown and improvement initiatives under
way at D. C. Cook. This Severity Level IV violation is being treated as a Non-Cited Violation
(NCV). Appendix C of the Enforcement Policy requires that for Severity Level IV violations to be
dispositioned as NCVs, they be appropriately placed in a licensee corrective action program.
Implicit in that requirement is that the corrective action program be fullyacceptable.
The D. C. Cook Plant corrective action program was not adequate and has been the focus of
significant attention by your staff to improve the program.
While your staff and the NRC have
not yet concluded that the corrective action program is fullyeffective, the corrective action and
design control program improvement efforts are underway and captured in the D. C. Cook Plant
Restart Plan which is under the formal oversight of the NRC through the NRC Manual Chapter 0350 process, "Staff Guidelines for Restart Approval." Consequently, this issue willbe
dispositioned as an NCV.