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Category:Inspection Report
MONTHYEARIR 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 05000282/20224022022-11-30030 November 2022 Cyber Security Inspection Report 05000282/2022402 and 05000306/2022402 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 05000282/20224012022-05-23023 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 IR 05000282/20214012021-04-21021 April 2021 Security Baseline Inspection Report 05000282/2021401 and 05000306/2021401; Independent Spent Storage Security Inspection Report 07200010/2021401 IR 05000282/20200062021-03-0404 March 2021 Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006) IR 05000282/20200022021-02-16016 February 2021 Reissue - Prairie Island Nuclear Generating Plant - Integrated Inspection Report 05000282/2020002; 05000306/2020002; and 07200010/2020001 IR 05000282/20200042021-02-0404 February 2021 Integrated Inspection Report 05000282/2020004 and 05000306/2020004 ML20352A1562020-12-21021 December 2020 Review of the 2018 Steam Generator Tube Inspection Report IR 05000282/20204022020-11-12012 November 2020 Security Baseline Inspection Report 05000282/2020402 and 05000306/2020402 IR 05000282/20200032020-11-10010 November 2020 Integrated Inspection Report 05000282/2020003; 05000306/2020003; and 07200010/2020002 IR 05000282/20203012020-09-22022 September 2020 NRC Initial License Examination Report 05000282/2020301 and 05000306/2020301 IR 05000282/20200052020-09-0101 September 2020 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2020005 and 05000306/2020005) 2024-02-01
[Table view] Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy 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 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] |
Text
ust 2, 2006
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000282/2006010(DRS); 05000306/2006010(DRS)
Dear Mr. Palmisano:
On July 21, 2006, the NRC completed an inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2. The enclosed report documents the inspection findings, which were discussed on July 21, 2006, with Mr. P. Huffman 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), 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. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure: Inspection Report 05000282/2006010(DRS);
05000306/2006010(DRS)
w/Attachment: Supplemental Information cc w/encl: C. Anderson, Senior Vice President, Group Operations M. Sellman, Chief Executive Officer and Chief Nuclear Officer Regulatory Affairs Manager J. Rogoff, Vice President, Counsel & Secretary Nuclear Asset Manager State Liaison Officer, Minnesota Department of Health Tribal Council, Prairie Island Indian Community Administrator, Goodhue County Courthouse Commissioner, Minnesota Department of Commerce Manager, Environmental Protection Division Office of the Attorney General of Minnesota W. King, DHS, Region V
SUMMARY OF FINDINGS
IR 05000282/2006010(DRS); 05000306/2006010(DRS); 07/17/2006 - 07/21/2006; Prairie
Island Nuclear Generating Plant; Emergency Preparedness Specialist Report.
The report covers a one week baseline inspection by two regional emergency preparedness inspectors and two resident inspectors. 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 April 1, 2005, through March 31, 2006.
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 July 18, 2006, 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 five emergency preparedness drills, which were conducted between February 2005 and June 2006, to verify that those drills scenarios were sufficiently different from the scenario used in the July 2006 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:
- 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, OSC, 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, Revision 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 April 1, 2005, through March 31, 2006. The following three PIs were reviewed:
Common
- ERO Drill Participation; and
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. P. Huffman and other members of licensee management and staff at the conclusion of the inspection on July 21, 2006. The licensee acknowledged the information presented. No proprietary information was identified.
.2 Public and Media Briefing
- On July 21, 2006, an inspector summarized NRCs preliminary exercise inspection conclusions at a public and media briefing hosted by Department of Homeland Security Region V Field Office staff in Red Wing, Minnesota.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- J. Callahan, Emergency Preparedness Manager
- L. Clewett, Business Support Manager
- M. Davis, Regulatory Compliance Analyst
- F. Forrest, Operations Manager
- P. Huffman, Plant Manager
- S. McCall, Engineering Manager
- C. Morgan, Corporate Senior Engineering Analyst
- J. Payton, Emergency Preparedness Coordinator
- K. Petersen, Performance Assessment Supervisor
- M. Vonk, Corporate Senior Emergency Preparedness Specialist
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None.
Attachment
LIST OF DOCUMENTS REVIEWED