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Category:Inspection Report
MONTHYEARIR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) IR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 IR 05000282/20230112023-05-16016 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000282/2023011 and 05000306/2023011 IR 05000282/20230012023-05-10010 May 2023 Integrated Inspection Report 05000282/2023001 and 05000306/2023001 IR 05000282/20220062023-03-0101 March 2023 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006) IR 05000282/20224042023-01-30030 January 2023 Material Control and Accounting Program Inspection Report 05000282/2022404 and 05000306/2022404 (Public) IR 05000282/20220042023-01-26026 January 2023 Integrated Inspection Report 05000282/2022004 and 05000306/2022004 IR 05000282/20224032023-01-24024 January 2023 – Security Baseline Inspection Report 05000282/2022403 and 05000306/2022403 IR 05000282/20220022022-12-0808 December 2022 RE-Issue Prairie Island Nuclear Generating Plant Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 07200010/20222012022-11-0909 November 2022 TN-40HT, Dry Storage Cask, Inspection Report No. 07200010/2022201 IR 05000282/20220032022-11-0101 November 2022 Integrated Inspection Report 05000282/2022003 and 05000306/2022003 IR 05000282/20220112022-09-26026 September 2022 Phase 4 Post-Approval Site Inspection for License Renewal Report 05000282/2022011 and 05000306/2022011 IR 05000282/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000282/2022301; 05000306/2022301 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) IR 05000282/20225012022-08-22022 August 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2022501 and 05000306/2022501 ML22227A1902022-08-16016 August 2022 Island Nuclear Generating Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000282/2022004 ML22222A1732022-08-11011 August 2022 Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 05000282/20220102022-06-24024 June 2022 Triennial Fire Protection Inspection Report 05000282/2022010 and 05000306/2022010 IR 05000282/20224022022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 IR 05000282/20224012022-05-23023 May 2022 Security Baseline Inspection Report 05000282/2022401 and 05000306/2022401 ML22103A2522022-05-0404 May 2022 Review of the 2021 Steam Generator Tube Inspection Report IR 05000282/20220012022-05-0303 May 2022 Integrated Inspection Report 05000282/2022001, 05000306/2022001, and 07200010/2020001 IR 05000282/20210062022-03-0202 March 2022 Annual Assessment Letter (Report 05000282/2021006 and 05000306/2021006) IR 05000282/20210042022-02-11011 February 2022 Integrated Inspection Report 05000282/2021004 and 05000306/2021004 ML22017A0052022-01-17017 January 2022 (PINGP) 2021 Unit 2 180-Day Steam Generator Tube Inspection Report IR 05000282/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000282/2021403 and 05000306/2021403 IR 05000282/20210032021-11-12012 November 2021 Integrated Inspection Report 05000282/2021003 and 05000306/2021003 IR 05000282/20210122021-10-27027 October 2021 NRC Inspection Report 05000282/2021012 and 05000306/2021012 IR 05000282/20210052021-09-0101 September 2021 Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005) IR 05000282/20215012021-08-25025 August 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2021501 and 05000306/2021501 IR 05000282/20210022021-08-0606 August 2021 Integrated Inspection Report 05000282/2021002 and 05000306/2021002 IR 05000282/20214022021-07-28028 July 2021 Security Baseline Inspection Report 05000282/2021402 and 05000306/2021402 IR 05000282/20210102021-06-22022 June 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000282/2021010 and 05000306/2021010 IR 05000282/20210112021-06-0303 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000282/2021011 and 05000306/2021011 IR 05000282/20210012021-05-0606 May 2021 Integrated Inspection Report 05000282/2021001 and 05000306/2021001 2024-09-13
[Table view] Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 2024-09-27
[Table view] |
Text
UNITED STATES ust 19, 2014
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 BASELINE EMERGENCY PREPAREDNESS BIENNIAL EXERCISE INSPECTION REPORT 05000282/2014502; 05000306/2014502
Dear Mr. Davison:
On August 1, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2. The enclosed report documents the results of this inspection which were discussed on August 1, 2014, with you 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. No findings were identified during this inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS)
component of NRC's Agencywide Documents Access and Management System (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Richard A. Skokowski, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60
Enclosure:
IR 05000282/2014502; 05000306/2014502 w/Attachment: Supplemental Information
REGION III==
Docket No: 50-282; 50-306 License No: DPR-42; DPR-60 Report No: 05000282/2014502; 05000306/2014502 Licensee: Northern States Power Company, Minnesota Facility: Prairie Island Nuclear Generating Plant, Units 1 and 2 Location: Welch, MN Dates: July 28 - August 1, 2014 Inspectors: R. Jickling, Senior Emergency Preparedness Inspector J. Beavers, Emergency Preparedness Inspector K. Anderson, Physical Security Inspector P. Zurawski, Senior Resident Inspector M. Speck, Senior Emergency Preparedness Inspector Approved by: R. Skokowski, Chief Plant Support Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000282/2014502, 05000306/2014502; 07/28/2014 - 08/01/2014; Prairie Island Nuclear
Generating Plant, Units 1 and 2; Baseline Emergency Preparedness Exercise Evaluation -
Hostile Action Event; Exercise Evaluation Scenario Review; Performance Indicator Verification.
This report covers a 1-week period of announced baseline inspection by four regional inspectors and one resident inspector. The significance of most findings is indicated by their color (i.e., Green, White, Yellow, and Red) using Inspection Manual Chapter 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014.
NRC-Identified
and Self-Revealed Findings
Cornerstone: Emergency Preparedness
No findings were identified.
Licensee-Identified Violations
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP7 Exercise Evaluation - Hostile Action Event
Main article: IP 71114.07
.1 Exercise Evaluation
a. Inspection Scope
Title 10, Code of Federal Regulations (CFR), Part 50, Appendix E,Section IV.F.2.j, requires, in part, that nuclear power reactor licensees, in each eight calendar year exercise cycle, provide the opportunity for their Emergency Response Organization (ERO) to demonstrate proficiency in the key skills necessary to respond to a Hostile Action (HA) event directed at the plant site. Prairie Island Nuclear Generating Plant designed the July 29, 2014, exercise to satisfy this requirement, and the NRC inspected the Prairie Island Nuclear Generating Plant HA event exercise to assess the licensees ability to effectively implement their Emergency Plan during a HA event and adequately protect public health and safety.
The exercise evaluation consisted of the following reviews and assessments:
- The adequacy of the licensees performance in the biennial exercise conducted on July 29, 2014, regarding the implementation of the Risk-Significant Planning Standards in 10 CFR 50.47 (b)(4), (5), (9), and (10), which address emergency classification, offsite notification, radiological assessment, and Protective Action Recommendations (PARs), respectively.
- The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Alternative Emergency Response Facility, Incident Command Post, Central Alarm Station, and the Backup Emergency Operations Facility.
- A review of other performance areas such as the licensee EROs recognition of abnormal plant conditions; command and control, including interactions with site security staff; intra and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies, including local law enforcement agencies; staffing and procedure adequacy; and the overall implementation of the Emergency Plan and its implementing procedures.
- Past performance issues from NRC inspection reports to determine the effectiveness of corrective actions, as demonstrated during this exercise, to ensure compliance with 10 CFR 50.47(b)(14).
- The adequacy of the licensees post-exercise critiques, to evaluate Prairie Island Nuclear Generating Plants self-assessment of its ERO performance during the July 29, 2014, exercise and to ensure compliance with 10 CFR Part 50, Appendix E, Section IV.F.2.g.
The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.
This exercise evaluation inspection constituted one sample as defined in Inspection Procedure (IP) 71114.07-06.
b. Findings
No findings were identified.
1EP8 Exercise Evaluation - Scenario Review
Main article: IP 71114.08
a. Inspection Scope
Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenarios submitted to the NRC using IP 71114.08, Exercise Evaluation - Scenario Review, to determine if the exercise would test major elements of the Emergency Plan as required by 10 CFR 50.47(b)(14). This inspection activity represents one sample on a biennial cycle.
The inspectors reviewed various documents that are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.
This review of the exercise objectives and scenario constituted one sample as defined in IP 71114.08-06.
b. Findings
No findings were identified.
OTHER ACTIVITIES
Cornerstone: Emergency Preparedness
4OA1 Performance Indicator Verification
.1 Drill/Exercise Performance
a. Inspection Scope
The inspectors sampled licensee submittals for the Drill/Exercise Performance (DEP)
Performance Indicator (PI) for the period from the second quarter 2013 through the second quarter 2014. To determine the accuracy of the DEP data reported during those periods, PI definitions and guidance contained in the Nuclear Energy Institute (NEI)document NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes, including procedural guidance on assessing opportunities for the PI, assessments of PI opportunities during pre-designated control room simulator training sessions, and performance during other drills. Documents reviewed are listed in the Attachment to this report.
This inspection constituted one DEP sample as defined in IP 71151-05.
b. Findings
No findings were identified.
.2 Emergency Response Organization Drill Participation
a. Inspection Scope
The inspectors sampled licensee submittals for the ERO Drill Participation PI for the period from the second quarter 2013 through the second quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI, performance during the 2013 and 2014 drills, and revisions of the roster of personnel assigned to key ERO positions. Documents reviewed are listed in the Attachment to this report.
This inspection constituted one ERO Drill Participation sample as defined in IP 71151-05.
b. Findings
No findings were identified.
.3 Alert and Notification System
a. Inspection Scope
The inspectors sampled licensee submittals for the Alert and Notification System (ANS)
PI for the period from the second quarter 2013 through the second quarter 2014. To determine the accuracy of the PI data reported during those periods, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used. The inspectors reviewed the licensees records associated with the PI to verify that the licensee accurately reported the indicator in accordance with relevant procedures and the NEI guidance. Specifically, the inspectors reviewed licensee records and processes including procedural guidance on assessing opportunities for the PI and results of periodic scheduled ANS operability tests.
Documents reviewed are listed in the Attachment to this report.
This inspection constituted one ANS sample as defined in IP 71151-05.
b. Findings
No findings were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
On August 1, 2014, the inspectors presented the biennial exercise inspection results to Mr. K. Davison and other members of the licensee staff. The licensee acknowledged the issues presented.
The inspectors confirmed that none of the potential report input discussed was considered proprietary.
.2 Public and Media Briefing
On August 1, 2014, the inspector summarized the NRCs preliminary exercise inspection conclusions at a public and media briefing hosted by Department of Homeland Security/Federal Emergency Management Agency Region V Field Office staff at the Goodhue County Emergency Operations Center in Red Wing, Minnesota.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- K. Davison, Site Vice President
- S. Northard, General Manager Nuclear Fleet Operations
- T. Allen, Assistant Plant Manager
- J. Callahan, Corporate Emergency Preparedness Manager
- J. Corwin, Security Manager
- I. Estevez, Emergency Preparedness Intern
- K. DeFusco, Emergency Preparedness Manager
- B. Hammargren, Regulatory Affairs
- J. Johnson, Control Room Supervisor
- N. Keeney, Emergency Preparedness Coordinator
- S. Lappegaard, Fukushima Production Manager
- R. Lexvold, Operations Training
- S. McCall, Prairie Island Projects
- G. Medina, Emergency Preparedness Training
- C. Murphy, Emergency Preparedness Assistant
- P. Oleson, Regulatory Affairs Analyst
- T. Ouret, Operations Training General Supervisor
- N. Penman, Emergency Preparedness Coordinator
- F. Sienczak, Regulatory Affairs
- R. Sitek, Emergency Preparedness Coordinator
- S. Teigen, Security Operations Supervisor
- E. Weinkam, Corporate Emergency Preparedness Director
Nuclear Regulatory Commission
- K. Stoedter, Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF DOCUMENTS REVIEWED