Similar Documents at Cook |
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Category:Inspection Report
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[Table view] Category:Letter
MONTHYEARAEP-NRC-2024-62, Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask2024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. 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Cook Nuclear Plant, Emergency Plan Revision 49 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring IR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. 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Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump 2024-08-08
[Table view] |
Inspection Report - Cook - 2005011 |
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Text
ber 30, 2005
SUBJECT:
DONALD C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 NRC EMERGENCY PREPAREDNESS INSPECTION REPORT NO. 05000315/2005011(DRS); 05000316/2005011(DRS)
Dear Mr. Nazar:
On September 23, 2005, the NRC completed an inspection at your Donald C. Cook Nuclear Power Plant. The enclosed report documents the inspection findings, which were discussed on September 23, 2005, with Mr. D. Fadel and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, this inspection focused on emergency preparedness, including your staffs determinations of performance indicators for the Emergency Preparedness Cornerstone.
On the basis of the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document 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 Plant Support Branch Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 Enclosure: Inspection Report 05000315/2005011(DRS);
05000316/2005011(DRS)
cc w/encl: J. Jensen, Site Vice President L. Weber, Plant Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police D. Lochbaum, Union of Concerned Scientists
SUMMARY OF FINDINGS
IR 05000315/2005011(DRS); 05000316/2005011(DRS); 09/19/2005 - 09/23/2005;
Donald C. Cook Nuclear Power Plant, Units 1 & 2; Emergency Preparedness Specialist Report.
The report covers a one-week baseline inspection by two regional emergency preparedness inspectors and a reactor engineer. The inspection focused on the Emergency Preparedness Cornerstone in the Reactor Safety strategic performance area during the biennial emergency preparedness exercise. This inspection also included a review of records related to the three emergency preparedness performance indicators for the period January 1, 2004 through June 30, 2005.
The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A. Inspector-Identified and Self-Revealed Findings None.
Licensee-Identified Violations
None.
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP1 Exercise Evaluation
Main article: IP 71114.01
a. Inspection Scope
The inspectors reviewed the September 20, 2005, biennial emergency preparedness exercises objectives and scenario to ensure that the exercise would acceptably test major elements of the licensees emergency plan and to verify that the exercises simulated problems provided an acceptable framework to support demonstration of the licensees capability to implement its plan. The inspectors also reviewed records of four emergency preparedness drills, which were conducted between June 2004 and early September 2005, to determine whether those drills scenarios were sufficiently different from the scenario used in the September 20, 2005, exercise.
The inspectors evaluated the licensees exercise performance, focusing on the risk-significant activities of emergency classification, notification, and protective action decision making, as well as implementation of accident mitigation strategies in the following emergency response facilities:
- Control Room Simulator; (CRS)
- Operations Support Center (OSC); and
- Emergency Operations Facility (EOF).
The inspectors also assessed the licensees recognition of abnormal plant conditions, transfer of responsibilities between facilities, internal communications, interfaces with offsite officials, readiness of emergency facilities and related equipment, and overall implementation of the licensees emergency plan.
The inspectors attended post-exercise critiques in the TSC and EOF to evaluate the licensees initial self-assessment of its exercise performance. The inspectors later met with the licensees lead exercise evaluators to obtain the licensees refined assessments of its exercise participants performances. These self-assessments were then compared with the inspectors independent observations and assessments to assess the licensees ability to adequately critique its exercise performance.
These activities completed one inspection sample.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
Cornerstone: Emergency Preparedness
.1 Reactor Safety Strategic Area
a. Inspection Scope
The inspectors reviewed the licensees records associated with each of the three emergency preparedness PIs to verify that the licensees program was implemented consistent with the industry guidelines in Nuclear Energy Institute Publication No. 99-02, Regulatory Assessment Performance Indicator Guideline, Revisions 2 and 3, and related licensee procedures. Specifically, licensee records related to the performance of the Alert and Notification System (ANS), key Emergency Response Organization (ERO)members drill participation, and Drill and Exercise Performance (DEP) were reviewed to verify the accuracy and completeness of the PI data submitted to NRC for the period from January 1, 2004 through June 30, 2005. The following three PIs were reviewed:
Common
- ERO Drill Participation; and
- Drill and Exercise Performance.
These activities completed three PI samples.
b. Findings
No findings of significance were identified.
4OA6 Meetings
.1 Exit Meeting
An exit meeting was conducted for:
- Emergency Preparedness with Mr. D. Fadel and other members of licensee management and staff at the conclusion of the inspection on September 23, 2005. The licensee acknowledged the information presented. No proprietary information was identified.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- R. Brown, Human Performance Manager
- P. Carteaux, Emergency Planning Manager
- D. Fadel, Engineering Vice President
- M. Mierau, Operations Training Manager
- J. Newmiller, Regulatory Affairs Specialist
- M. Scarpello, Regulatory Assurance Supervisor
- D. Schroeder, Emergency Planning Coordinator
- S. Simpson, Safety Assurance Specialist
- S. Vazquez, System Engineering Manager
- V. Woods, Public Affairs Manager
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened and Closed
None.
Discussed
None.
LIST OF DOCUMENTS REVIEWED