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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
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 ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter 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] Category:Notice of Violation
MONTHYEARIR 05000282/20150082016-01-0505 January 2016 IR 05000282/2015008 and 05000306/2015008; 10/05/2015 - 11/24/2015; Prairie Island Nuclear Generating Plant, Units 1 and 2; Annual Problem Identification and Resolution Inspection (Njf) ML16005A5672016-01-0505 January 2016 IR 05000282/2015008 and 05000306/2015008; 10/05/2015 - 11/24/2015; Prairie Island Nuclear Generating Plant, Units 1 and 2; Annual Problem Identification and Resolution Inspection (Njf) IR 05000282/20134072014-02-12012 February 2014 EA-13-210, Prairie Island Nuclear Generating Plant; Notice of Violation - Closure of NRC Investigation 3-2013-017; NRC Report No. 05000282/2013407; 05000306/2013407 - Cover Letter Only IR 05000282/20130032013-07-30030 July 2013 IR 05000282-13-003 & 05000306-13-003, 04/01/2013 - 06/30/2013, Prairie Island Nuclear Generating Plant, Unit 1 & 2, NRC Integrated Inspection Report and Notice of Violation IR 05000282/20135032013-03-26026 March 2013 EA-12-273, Prairie Island Nuclear Generating Plant, Unit 1, Final Significance Determination of a White Finding with Assessment Followup and Notice of Violation; NRC Inspection Report No. 05000282/2013503 ML12104A1742012-04-12012 April 2012 IA-12-003 Barnes, Final Letter and Notice of Violation IR 05000282/20110112011-08-17017 August 2011 EA-11-110, Prairie Island Nuclear Generating Plant, Units 1 and 2, Final Significance Determination of White Finding with Assessment Followup and Notice of Violation; NRC Inspection Report 05000282-11-011 IR 05000282/20090142009-10-27027 October 2009 IR 050000282-09-014, on 05/01/2009, for Prairie Island, Units 1 and 2, Notice of Violation ML0924506242009-09-0303 September 2009 EA-09-167, Prairie Island Nuclear Generating Plant, Unit 2, Final Significance Determination for a White Finding and Notice of Violation, NRC Inspection Report No. 05000306-09-013 IR 05000282/20090082009-05-0606 May 2009 NRC000021-Final Significance Determining of White Finding and Notice of Violation; NRC Inspection Report No. 05000282/2009008; 05000306/2009008; Prairie Island Nuclear Generating Plant, Units 1 and 2 ML0912700802009-05-0606 May 2009 IR 05000282-09-008, and IR 05000306-09-008, for Prairie Island, Units 1 & 2, Final Significance Determination of White Finding and Notice of Violation 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) ML0701001382006-08-22022 August 2006 Dennis L. Koehl Ltr. Apparent Violation of Employee Protection Requirements (Office of Investigations Report No. 3-2005-010) ML0235002672002-12-13013 December 2002 IA-02-012, Hiedeman, Notice of Violation 2016-01-05
[Table view] |
Text
ber 28, 2006
SUBJECT:
NOTICE OF VIOLATION [NRC INSPECTION REPORT 05000282/2006015; 05000306/2006015 AND NRC INVESTIGATION REPORT NO. 3-2006-004]
PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Dear Mr. Palmisano:
This refers to an inspection by the U.S. Nuclear Regulatory Commission (NRC) that was completed on June 29, 2006, and an investigation by the NRC Office of Investigations (OI) that was completed on April 27, 2006, at the Prairie Island Nuclear Generating Plant, Units 1 and 2, (Prairie Island) operated by the Nuclear Management Company, LLC (NMC). The inspection and investigation identified an apparent violation of 10 CFR 50.9, Completeness and Accuracy of Information, associated with information that NMC provided to the NRC on July 21, 2005, in two applications for reactor operator licenses at the Prairie Island facility. A copy of the inspection report, NRC Inspection Report No. 05000282/2006013;05000306/2006013, was provided to you on July 18, 2006.1 In the letter transmitting the inspection report, we provided you the opportunity to address the apparent violation identified in the report by either attending a predecisional enforcement conference or by providing a written response before we make our final enforcement decision.
In a letter dated August 14, 2006, you provided a written response to the apparent violation.
Based on the information developed during the NRC inspection, the OI investigation and the information that you provided in your August 14, 2006, written response to the inspection report, the NRC determined that a violation of NRC requirements occurred. The violation is cited in the enclosed Notice of Violation (Notice) and the circumstances surrounding it are described in detail in the subject inspection report. In summary, on July 21, 2005, NMC submitted two NRC Form 398s, Personal Qualification Statement - License, to the NRC, one for an applicant seeking a reactor operator (RO) license and one for an applicant seeking a senior reactor operator (SRO) license at the Prairie Island facility. Both of the NRC Form 398s indicated the applicants had completed on Januarly 18, 2005, a significant manipulation of the reactor controls using the Prairie Island simulator to simulate a reactor startup. The NRC Form 398s
Inspection Report No. 05000282/2006015; 05000306/2006015 was assigned to track the violation described in the enclosed Notice. also indicated that, as of January 18, 2005, NMC had conducted certification testing of the simulator which demonstrated that the simulator replicated the current plant reactor core model.
However, following a subsequent investigation, NMC determined that it could not locate documentation to demonstrate that simulator certification testing for the reactor startup procedure had occurred. Therefore, inaccurate information was submitted on the NRC Form 398s. The licensee subsequently performed testing of the simulator during October 2005, which demonstrated that the simulator replicated the current plant reactor core model.
The information on NRC Form 398 is material to the NRC because it is used to determine that an applicant for license to operate a nuclear power reactor had performed a sufficient number of significant reactivity control manipulations prior to being licensed to operate a nuclear power reactor. On September 23, 2005, the NRC issued a license to operate a nuclear reactor to each applicant based, in part, on the inaccurate information that the NMC submitted to the NRC concerning each applicants use of the Prairie Island simulator to manipulate the controls for a reactor startup. Therefore, this violation has been categorized in accordance with the NRC Enforcement Policy at Severity Level III.
In accordance with the Enforcement Policy, a base civil penalty in the amount of $65,000 is considered for a Severity Level III violation. Because your facility has not been the subject of escalated enforcement actions within the two years preceding the violation, the NRC considered whether credit was warranted for corrective actions in accordance with the civil penalty assessment process in Section VI.C.2 of the Enforcement Policy. Credit was warranted for corrective actions consisting of: (1) revising the procedure on NRC Operator Licensing Requirements to include a checklist to verify that items on the checklist support the requirements for license applications prior to its submittal of the applications; and (2) revising the procedure for simulator testing documentation to strengthen the specific testing and documentation instructions.
Therefore, to encourage prompt and comprehensive correction of violations and in recognition of the absence of previous escalated enforcement action, I have been authorized, after consultation with the Director, Office of Enforcement, not to propose a civil penalty in this case.
However, significant violations in the future could result in a civil penalty.
The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance will be achieved is already addressed on the docket in NRC Inspection Report No. 05000282/2006013;05000306/2006013 and in an August 14, 2006, letter from the Nuclear Management Company, LLC. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to provide additional information, you should follow the instructions specified in the enclosed Notice. Please contact Hironori Peterson, Chief, Operations Branch, with questions. Mr. Peterson can be reached at telephone number (630) 829-9707. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if you choose to respond, will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction. The NRC also includes significant enforcement actions on its Web site at www.nrc.gov; select What We Do, Enforcement, then Significant Enforcement Actions.
Sincerely,
/RA by Geoffrey E. Grant Acting for/
James L. Caldwell Regional Administrator Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure: Notice of Violation 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 Council Administrator President, Prairie Island Tribal Council Goodhue County Sheriff Director, Pierce County Emergency Management Agency Chair, Pierce County Board of Commissioners Chair, Dakota County Board of Commissioners Mayor of Red Wing Director, Goodhue County Emergency Management Agency Chair, Goodhue County Board of Commissioners Pierce County Sheriff Dakota County Sheriff INPO