ML17326A008
| ML17326A008 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/11/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17326A009 | List: |
| References | |
| 50-315-99-10, 50-316-99-10, NUDOCS 9906170122 | |
| Download: ML17326A008 (4) | |
See also: IR 05000315/1999010
Text
CATEGORY 2
REGULATORY INFORMATION DXSTRIBUTXON SYSTEM (RIDS)
CCESSION NBR:9906170122
DOC DATE: 99/06/11
NOTARIZED: NO
DOCKET
ACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana
M
05000315
50-316 Donald C., Cook Nuclear Power Plant, Unit 2,
Xndiana
M
05000316
AUTH.NAME
AUTHOR AFFILIATION
GROBE,J.A.
Region
3 (Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION
POWERS,R.P.
'merican Electric Power Co., Inc.
SUBJECT: Forwards insp zepts
50-315/99-10
& 50-316/99-10
on
990417-0527.No violations noted.Two violations of NRC
requirements
occurred
&, being treated
as non-cited
violations.
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STATES
NUCLEAR REGULATORY COMMISSION
REGION III
801 WARRENVILLEROAD
LISLE, ILLINOIS80532.4351
June ll, 1999
Mr. R. P. Powers
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
D. C. COOK INSPECTION REPORT 50-315/99010(DRP); 50-316/99010(DRP)
Dear Mr. Powers:
On May 27, 1999, the NRC completed an 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 compliance with the Commission rules and regulations and with the conditions of your
license. Areas reviewed included Operations, Maintenance, Engineering, and Plant Support.
Within these areas, the inspection consisted of selective examinations of procedures and
representative records, interviews with personnel, and observations of activities in progress.
The enclosed report presents the results of that inspection.
Your staff successfully restored the Unit 2 AB diesel generator to an operable condition along
with the associated train of boration control resulting in an increased ability to address
postulated reactor coolant dilution events.
In addition, the continued effort to place both units
on electrical back feed indicated an increased focus on reactor core safety issues.
We also
noted that during the conduct of the Expanded System Readiness
Review process, your staff
demonstrated
a critical questioning attitude by effectively identifying technical issues related to
the Containment Spray System.
While an increased focus on reactor core safety issues was evident, several examples were
Identified by the inspectors where your staff failed to consistently respond in a manner
commensurate with the potential impact of the degraded condition on current plant
configuration. The examples included your staffs'esponse
to degraded and inoperable
Essential Service Water pump discharge strainers, degraded 4 kV breakers, and source range
instrument issues.
In response to the inspectors'oncerns,
your staff took prompt and
appropriate actions, including the initiation of compensatory measures when warranted.
These
actions ensured that equipment which could be required to support maintaining the reactor in a
cold shutdown condition were available or returned to service in an expeditious manner.
During the inspectors review of previously identified regulatory issues, two violations of NRC
requirements were identified. The first violation, identified by the inspectors in 1998, was due to
an inappropriate surveillance procedure for the engineered safeguards ventilation system.
The
surveiHance procedure did not direct the operators to restore the system to an operable
configuration. The second violation, identified by your staff in 1995, involved the failure to
9906170i22 9906ii
ADQCK 050003i5
8
R. Powers
-2-
restore several main steam safety valves to operable status prior to exceeding the Technical
Specification Limiting Condition for Operation time limit.
These Severity Level IVviolations are being treated as Non-Cited Violations (NCVs).
Appendix C of the Enforcement Policy requires that for Severity Level IVviolations to be
dispositioned as NCVs, they be appropriately placed in the licensee's corrective action program.
Implicit in that requirement is that the corrective action program be fullyacceptable.
The 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 program improvement
efforts are underway and captured in the Restart Plan which is under the formal oversight of the
NRC through the NRC Manual Chapter 0350 Process, "Staff Guidelines for Restart Approval."
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 and its
enclosure will be placed in the NRC Public Document Room.
Sincerely,
/s/ J. A. Grobe
Docket Nos. 50-315; 50-316
John A. Grobe, Director
Division of Reactor Safety
Enclosure:
Inspection Report 50-315/99010(DRP);
50-316/99010(DRP)
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
DOCUMENT NAME: G:iCOOKttDCC99010.DRP
To receive a co
of this document. indicate In the box: "C" = Co
w/o attach/enct "E" = Co
w/attach/encl "N"= No co
OFFICE
NAME
DATE
RIII:DRP
Ve el/co
06/0/99
RIII:D
Grob
06/ ) I/
OFFI IALRECORD COPY
R. Powers
Distribution:
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