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Category:Inspection Report Correspondence
MONTHYEARL-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts IR 05000282/20224012022-05-23023 May 2022 Security Baseline Inspection Report 05000282/2022401 and 05000306/2022401 IR 05000282/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000282/2021403 and 05000306/2021403 ML20352A3462021-01-0404 January 2021 Cover Letter ML18304A0772018-10-30030 October 2018 Ltr. 10/30/18 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Request for Info. for an Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program; Inspection Report 05000282(306)/2019011 ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) IR 05000282/20164042016-09-20020 September 2016 NRC Security Baseline Inspection Report 05000282/2016404; 05000306/2016404 (Cover Letter Only) IR 05000282/20155012016-02-0303 February 2016 NRC Emergency Preparedness Annual Inspection Report No. 05000282/2015501; 05000306/2015501 ML15020A1162015-01-15015 January 2015 Ltr 2014 Prairie Island EP Annual Closeout (Rdj) IR 05000282/20120082012-07-23023 July 2012 IR 05000282-12-008 & 05000306-12-008, on 05/22-25/12, 06/04-08/12 & 06/18-22/12, Prairie Island Nuclear Generating Plant, Units 1 & 2, Triennial Fire Protection Baseline Inspection ML0902206242009-01-22022 January 2009 Ltr. 01/22/09 Prairie Island Request for Information IR 05000282/20074012007-03-19019 March 2007 IR 05000282-07-401 (Drs); 05000306-07-401 (Drs); 02/05/2007 - 02/07/2007 (NMC) and 02/08/2007 - 02/12/2007 (Site); Prairie Island Nuclear Generating Plant (Pingp); Routine Security Baseline Inspection IR 05000282/20060152006-09-28028 September 2006 EA-06-162, Prairie Island Nuclear Generating Plant, Notice of Violation (NRC Inspection Report 05000282/2006015; and 05000306/2006015 and NRC Investigation Report No. 3-2006-004) ML0619804712006-07-13013 July 2006 Re NRC Security Baseline Inspection Report 05000282/2006011(DRS); 05000306/2006011(DRS) IR 05000282/20060112006-07-13013 July 2006 Re NRC Security Baseline Inspection Report 05000282/2006011(DRS); 05000306/2006011(DRS) IR 05000282/20060022006-05-11011 May 2006 IR 05000282-06-002, 05000306-06-002; on 01/01/2006 - 03/31/2006; Prairie Island Nuclear Generating Plant, Units 1 and 2 IR 05000282/20020062002-06-12012 June 2002 IR 05000282-02-06(DRS), 05000306-02-06(DRS), on 05/13-05/17/2002, Nuclear Management Company, LLC, Prairie Island Nuclear Generating Plant, Units 1 and 2. Emergency Preparedness Specialist Report. No Violations Identified IR 05000282/20020022002-04-19019 April 2002 IR 05000282/2002-002; IR 05000306/2002-002, Nuclear Management Company, Prairie Island Nuclear Generating Plant, Units 1 and 2, Resident Inspector Report. No Violations Identified IR 05000282/20010192002-03-13013 March 2002 IR 05000282/2001-019; IR 05000306/2001-019, on 12/30/2001-2/14/2002; Nuclear Management Company, Prairie Island Nuclear Generating Plant, Units 1 &2. Resident Inspector Report. No Violations Identified ML0210504402002-02-12012 February 2002 Nuclaer Generating Plant, Unit 2, Enclosure 1, EOC 20 S/G Inspection Results IR 05000282/20010182002-01-17017 January 2002 IR 05000282/2001-018 & IR 05000306/2001-018, Prairie Island, Inspection on 11/16-12/29/2001 Re Resident Inspector & Licensed Operator Requalification Program. No Violations Noted 2022-09-20
[Table view] Category:Letter
MONTHYEARIR 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 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 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 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections 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 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 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 IR 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, IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 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 ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota 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 2024-08-05
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Text
rch 19, 2007
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 NRC SECURITY BASELINE INSPECTION REPORT 05000282/2007401(DRS);
05000306/2007401(DRS)
Dear Mr. Palmisano:
On February 12, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on February 12, 2007, with Mr. Northard and Mr. Clewett, and other members of your staff.
This inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
This report documents two findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiencies were EXEMPT FROM PUBLIC DISCLOSURE May be exempt from public release under the Freedom of Information Act (5 U.S.C. 552)
Exemption number: 5 Nuclear Regulatory Commission review required before Enclosure Contains .
public release. Upon separation, this page is Decontrolled.
Dale Lawver, RIII/DRS/PSB Name and organization of person making determination.
Date of determination: 03/09/2007 promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspector left the site.
NRC is treating these violations as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy because of the very low security significance of the violations and because they were entered into your corrective action program. If you contest these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Prairie Island Nuclear Generation Plant.
The findings were all licensee-identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter 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). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters enclosure will not be available for public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response Security-Related Information-Withhold Under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Enclosure Contains .
Upon separation, this page is Decontrolled. Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
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 05000282/2007401(DRS);
05000306/2006701(DRS)
( )
cc w/encl ( )
B. Westreich, NSIR/DSO/RSOB M. Layton, NSIR/DSP/MTWSB Licensing Assistant, NSIR/DSO/RSOB cc w/o encl ( ):
D. Cooper, Senior Vice President, Group Operations M. Sellman, President and Chief Executive 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 Enclosure Contains .
Upon separation, this page is Decontrolled.
DOCUMENT NAME: C:\FileNet\ML070800359.wpd G Publicly Available G Non-Publicly Available G Sensitive G Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME DLawver:co RSkokowski DFunk KRiemer DATE 03/15/07 03/15/07 03/15/07 03/19/07 OFFICIAL RECORD COPY Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
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 05000282/2007401(DRS);
05000306/2006701(DRS)
( )
cc w/encl ( )
B. Westreich, NSIR/DSO/RSOB M. Layton, NSIR/DSP/MTWSB Licensing Assistant, NSIR/DSO/RSOB cc w/o encl ( ):
D. Cooper, Senior Vice President, Group Operations M. Sellman, President and Chief Executive 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 Enclosure Contains .
Upon separation, this page is Decontrolled. ADAMS Distribution w/o encl ( ):
TEB MLC RidsNrrDirsIrib GEG KGO GLS JTA CAA1 LSL DRPIII DRSIII PLB1 TXN ROPreports@nrc.gov Enclosure Contains .
Upon separation, this page is Decontrolled.