IR 05000315/2015003
| ML15316A616 | |
| Person / Time | |
|---|---|
| Site: | Cook, 07200072  |
| Issue date: | 11/12/2015 |
| From: | Kenneth Riemer NRC/RGN-III/DRP/B2 |
| To: | Weber L Indiana Michigan Power Co |
| References | |
| IR 2015001, IR 2015003 | |
| Download: ML15316A616 (43) | |
Text
November 12, 2015
SUBJECT:
D. C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000315/2015003; 05000316/2015003; AND 07200072/2015001
Dear Mr. Weber:
On September 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Donald C. Cook Nuclear Power Plant, Units 1 and 2. The enclosed report documents the results of this inspection, which were discussed on October 1, 2015, with Mr. J. Gebbie, and other members of your staff.
Based on the results of this inspection, two NRC-identified and one self-revealed finding of very low safety significance were identified. The NRC-identified findings involved violations of NRC requirements. One of these violations was determined to be SL-IV under the traditional enforcement process. However, because of their very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating the issues as non-cited violations (NCVs) in accordance with Section 2.3.2 of the NRC Enforcement Policy.
Additionally, two licensee-identified findings with associated NCVs are documented in Section 4OA7 of this report.
If you contest the subject or severity of any NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission-Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Donald C. Cook Nuclear Power Plant. In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, and the NRC Resident Inspector at the Donald C. Cook Nuclear Power Plant. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records System (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Kenneth Riemer, Chief Branch 2 Division of Reactor Projects
Docket Nos. 50-315; 50-316;72-072 License Nos. DPR-58; DPR-74
Enclosure:
IR 05000315/2015003; 05000316/2015003; 07200072/2015001 w/Attachment: Supplemental Information
REGION III==
Docket Nos:
05000315; 05000316;72-072 License Nos:
05000315/2015003; 05000316/2015003; 07200072/2015001 Licensee:
Indiana Michigan Power Company Facility:
Donald C. Cook Nuclear Power Plant, Units 1 and 2 Location:
Bridgman, MI Dates:
July 1 through September 30, 2015 Inspectors:
J. Ellegood, Senior Resident Inspector
T. Taylor, Resident Inspector
R. Edwards, Senior Health Physicist
R. Elliott, Reactor Engineer
M. Garza, Emergency Preparedness Inspector
M. Learn, Reactor Engineer
J. Lennartz, Project Engineer
J. Mancuso, Reactor Engineer
Approved by:
Kenneth Riemer, Chief Branch 2 Division of Reactor Projects
SUMMARY OF FINDINGS
......................................................................................................... 2
REPORT DETAILS
.................................................................................................................... 5
Summary of Plant Status
REACTOR SAFETY
.................................................................................................... 5
1R01 Adverse Weather Protection
............................................................. 5
1R04 Equipment Alignment
........................................................................ 5
1R05 Fire Protection
.................................................................................. 6
1R06 Flooding
............................................................................................ 9
1R11 Licensed Operator Requalification Program
.....................................10
1R12 Maintenance Effectiveness
..............................................................11
1R13 Maintenance Risk Assessments and Emergent Work Control
..........12
1R15 Operability Determinations and Functional Assessments
.................13
1R18 Plant Modifications
...........................................................................14
1R19 Post-Maintenance Testing
...............................................................16
1R20 Outage Activities
..............................................................................17
1R22 Surveillance Testing
.........................................................................18 1EP4 Emergency Action Level and Emergency Plan Changes (IP 71114.04)............19
4. other activities............................................................................................................22
4OA1 Performance Indicator Verification
........................................................22
4OA2 Identification and Resolution of Problems
.............................................24
4OA5 Other Activities...................................................................................................26
4OA6 Management Meetings......................................................................................27
4OA7 Licensee-Identified Violations............................................................................28
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- P. Carteaux, Manager, Dry Cask Operations
- K. Harper, Regulatory Affairs
- J. Nimitz, Senior Licensing Activity Coordinator
- P. Schoepf, Nuclear Site Services Director
- R. Sieber, Emergency Preparedness Manager
- K. Simpson, Emergency Preparedness Supervisor
- A. Thompson, Emergency Preparedness Supervisor
Nuclear Regulatory Commission
- K. Riemer, Chief, Reactor Projects Branch 2
- N. Shah, Project Engineer Branch 2
- L. Kozak, Senior Risk Analyst
- B. Passehl, Senior Risk Analyst
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened
- 05000315/2015003-01 NCV Failure to Evaluate Fire Brigade Fire Fighting Techniques (1R05.2)
- 05000316/2015003-02 FIN Failure of Steam Dump Valves Results in Plant Trip (1R18)
- 05000316.2015003-03
URI Deletion of Hot Shutdown Panel Procedures (1R18)
IV Changes to Minimum 60-Minute Emergency Responder Staffing Without Prior Approval (1EP4)
- 05000316/2015003-05 URI PRA Model Errors (4OA1)
Closed
- 05000315/2015003-01 NCV Failure to Evaluate Fire Brigade Fire Fighting Techniques (1R05.2)
- 05000316/2015003-02 FIN Failure of Steam Dump Valves Results in Plant Trip (1R18)
IV Changes to Minimum 60-Minute Emergency Responder Staffing Without Prior Approval (1EP4)
- 05000315/2014005-05 URI Changes to Minimum 60-Minute Emergency Responder Staffing Without Prior Approval (1EP4)
Discussed
None