ML17326A136
| ML17326A136 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/16/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER SERVICE CORP. |
| Shared Package | |
| ML17326A137 | List: |
| References | |
| 50-315-99-07, 50-316-99-07, NUDOCS 9909240011 | |
| Download: ML17326A136 (6) | |
See also: IR 05000315/1999007
Text
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CCESSION NBR:9909240011
DOC.DATE: 99/09/16
NOTARIZED: NO
DOCKET
FACIL: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-
AUTH.NAME
AUTHOR AFFILIATION
GROBE,J.A.
Region
3
(Post
820201)
RECIP . NAME
RECIPIENT AFFILIATION
POWERS,R.P.
American Electric Power Service
Corp.
SUBJECT:
Forwards insp repts
50-315/99-07
& 50-316/99-07
on 990712-30
0816.Seven violations of NRC requirements
occurred
6 being
treated
as NCVs,consistent with App
C of enforcement policy.
DISTRIBUTION CODE: IEOIP
COPIES
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SIZE:
V 7 Zf
TITLE: General
(50 Dkt) -Insp Rept/Notice of Violation Response
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16
ENCL
16
I
September
18, 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 50-315/99007(DRS); 50-316/99007(DRS)
Dear Mr. Powers:
On August 16, 1999, the NRC completed a special inspection at your Donald C. Cook Units 1
and 2 reactor facilities. The purpose of the inspection was to examine the activities related to
the discovery phase of the Expanded System Readiness
Review (ESRR) program.
Our
inspection generally focused on two risk-significant systems to evaluate the ESRR program's
effectiveness at verifying that the plant was modiTied, tested, operated and maintained
consistent with the design and licensing bases.
The enclosed report documents the results of
the inspection.
Based on our inspection, we concluded that, overall, your staff effectively implemented the
discovery phase of the ESRR process.
For the systems we evaluated, the scope of the reviews
was broad and conceptually consistent with the purpose of confirming the performance of
system safety functions.
Further, the breadth and depth of material reviewed during the ESRRs
were considered appropriate.
The overall effectiveness of the ESRR teams was demonstrated
by their identification of substantive issues which could potentially impact system safety
functions.
There were several instances where the NRC team identified deficiencies that were not
specifically identified during the ESRRs.
In most cases, the ESRRs or programmatic area
reviews had already revealed more general or broader deficiencies, and there was reasonable
assurance
that the specific deficiency would be captured by subsequent
corrective actions.
In a
few limited cases, we determined that the ESRRs should have identified our specific finding and
other processes
would probably not have revealed the issue.
Because the number of later
cases were limited and they did not directly impact a system safety function, these represented
isolated implementation weaknesses
and not broad deficiencies in the ESRR process.
While the ESRRs have been completed for the risk significant systems, several broad
deficiencies were identified through the system reviews and programmatic readiness reviews
that could affect many systems.
The extent of the impact of those deficiencies is still being
evaluated through the corrective action process.
The effectiveness of the corrective action
program willbe essential to ensure that problems continue to be identified and are effectively
resolved.
99092400ii 9909i6
ADOCK 050003i5
8
R. Powers
-2-
During the inspection, the NRC also identified an example where your staff did not exercise
appropriate sensitivity to the potential impact on operability of fuse control deficiencies identified
during the ESRR of the 250 Volt direct current system.
This was of particular concern since a
problem regarding the sensitivity to equipment required for Modes 5 and 6 was identified by the
NRC following two electrical faults which occurred on April 19, and April24, 1999. Two
examples of operability evaluations which failed to adequately address structural deficiencies
were also identified. Collectively, these examples indicated that continued management
attention is warranted in the operability evaluation area.
Based on the results of this inspection, the NRC has determined that seven violations of NRC
requirements occurred.
These violations are being treated as Non-Cited Violations (NCVs),
consistent with Appendix C of the Enforcement Policy. These NCVs are described in the
subject inspection report. Ifyou contest the violation or severity level of these NCVs, you
should provide a response within 30 days of the date of this inspection report, with the basis
for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk,
Washington, D.C. 20555-0001, with a copy to the Regional Administrator, Region III, and the
Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington,
D.C. 20555-0001.
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 fully
acceptable.
However, the D.C. Cook corrective action program has been identified as
inadequate and has been the focus of significant attention by your staff for improvement.
While
your staff and the NRC have not yet concluded that the corrective action program is fully
effective, the corrective action program improvement efforts underway are captured in the
D.C. Cook Restart Plan which is under the formal oversight of the NRC through the NRC
Manual Chapter 0350, "Staff Guidelines for Restart Approval," process.
Consequently, these
issues will be dispositioned as NCVs.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response, ifyou choose to provide one, willbe placed in the NRC Public
Document Room.
Sincerely,
Original /s/ John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-315; 50-316
Enclosure:
Inspection Report 50-315/99007(DRS);
50-316/99007(DRS)
See Attached Distribution
- SEE PREVIOUS CONCURRENCE
DOCUMENT NAME: G:DRSttDCC99007.wpd
To receNe a co
of this document, Indicate In the boxt
C
~
without atachhment/endosure
'E ~
with attachmenVenclosure
N ~ No
OFFICE
NAME
DATE
Rill
EDuncan:sd
09/
/99
RIII
JJacobson
09/
/99
Rill
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09/
/99
Rill
JGrob
09/4/99
OFFICIALRECORD COPY
R. Powers
-2-
Based on the results of this inspection, the NRC has determined that seven violations of NRC
requirements occurred.
These violations are being treated as Non-Cited Violations (NCVs),
consistent with Appendix C of the Enforcement Policy. These NCVs are described in the
subject inspection report.
Ifyou contest the violation or seventy level of these NCVs, you
should provide a response within 30 days of the date of this inspection report, with the basis for
your denial, to the Nuclear. Regulatory Commission, ATTN: Document Control Desk,
Washington, D.C. 20555-0001, with a copy to the Regional Administrator, Region III, and the
Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington,
D.C. 20555-0001.
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 fully
acceptable.
However, the D.C. Cook corrective action program has been identified as
inadequate and has been the focus of significant attention by your staff for improvement.
While
your staff and the NRC have not yet concluded that the corrective action program is fully
effective, the corrective action program improvement efforts underway are captured in the
D.C. Cook Restart Plan which is under the formal oversight of the NRC through the NRC
Manual Chapter 0350, "Staff Guidelines for Restart Approval," process.
Consequently, these
issues willbe dispositioned as NCVs.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response,
ifyou choose to provide one, willbe placed in the NRC Public
Document Room.
Sincerely,
John A. Grobe, Director
Division of Reactor Safety
Docket Nos. 50-315; 50-316
Enclosure:
Inspection Report 50-315/99007(DRS);
50;316/99007(DRS)
cc w/encl:
A. C. Bakken III, Site Vice President
T. Noonan, Acting 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:DRSiDCC99007.wpd
TO reoelre a CO
Of thta dcoumen
Indlrate In the bOXt 'C'
Wtthaut attaChment/endcaure
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OFFICE
RIII
NAME
EDuncan:s
DATE
09/ol /99
Rill
JJacob
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Rill
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AVe el
09/D/99
RIII
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09/
/99
OFFICIALRECORD COPY
V
0
R. Powers
-3-
cc w/encl:
A. C. Bakken III, Site Vice President
T. Noonan, Acting 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
Distribution:
RRB1 (E-Mail)
RPC (E-Mail)
JFS2 (Project Mgr.) (E-Mail)
J. Caldwell, RIIIw/encl
B. Clayton, Rillw/encl
SRI D. C. Cook w/encl
DRP w/encl
DRS w/encl
Rill PRR w/encl
PUBLIC IE-01 w/encl
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