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Category:Inspection Plan
MONTHYEARIR 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 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 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) ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) ML22007A1542022-01-0707 January 2022 Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000282/2022010 and 05000306/2022010 ML21363A0542021-12-29029 December 2021 Prairie Nuclear Generating Plant - Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information; Inspection Report 05000282/2022002 05000306/2022002 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 05000282/20200062021-03-0404 March 2021 Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006) ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant 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) ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 IR 05000282/20190062020-03-0303 March 2020 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019006 and 05000306/2019006) IR 05000282/20190052019-08-28028 August 2019 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019005; 05000306/2019005) ML19136A1562019-05-15015 May 2019 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza) ML19071A3532019-03-12012 March 2019 Ltr. 03/12/19 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information; Inspection Report 05000282/2019012; 05000306/2019012 (DRS-A.Dahbur) IR 05000282/20180062019-03-0404 March 2019 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018006 and 05000306/2018006) ML18324A6122018-11-20020 November 2018 Ltr. 11/20/18 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2019001 and 05000306/2019001 (DRS-N.Feliz-Adorn IR 05000282/20180052018-08-28028 August 2018 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018005 and 05000286/2018005) ML18156A5532018-06-0505 June 2018 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2018004; 05000306/2018004 (DRS-M.Holmberg) IR 05000282/20170062018-03-0202 March 2018 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2017006; 05000306/2017006) IR 05000282/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000282/2017005 and 05000306/2017005) IR 05000282/20160062017-03-0101 March 2017 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016006) ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) IR 05000282/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016005; 05000306/2016005) ML16222A7022016-08-0909 August 2016 Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000282/20150062016-03-0202 March 2016 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Inspection Report 05000282/2015006 and 05000306/2015006) ML15261A7182015-09-15015 September 2015 Ltr. 09/15/2015 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000282/2016008; 05000306/2016008. (Dxs) IR 05000282/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2015005; 05000306/2015005) IR 05000282/20140012015-03-0404 March 2015 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2, (Report 05000282/2014001 and 05000306/2014001) ML14245A2012014-09-0202 September 2014 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML14209A9342014-07-28028 July 2014 Notification of NRC Inspection and Request for Information IR 05000282/20130012014-03-0404 March 2014 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2(Report 05000282/2013001; 05000306/2013001) ML13246A2392013-09-0303 September 2013 2013 Prairie Island MOC Letter Combined ML13203A2862013-07-22022 July 2013 Notification of Baseline Inspection and Information Request ML13077A4742013-03-18018 March 2013 Information Request for a Post-approval Site Inspection for License Renewal IR 05000282/20120012013-03-0404 March 2013 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2012001 and 05000306/2012001) ML12249A4252012-09-0404 September 2012 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 IR 05000282/20110072012-03-0505 March 2012 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2011007 and 05000306/2011007) IR 05000282/20110062011-09-0101 September 2011 Mid-Cycle Letter for Prairie Island Nuclear Plant, Units 1 and 2, 05000282-11-006; 05000306-11-006 ML1106203132011-03-0404 March 2011 EOC Annual Assessment Letter and Inspection/Activity Plan ML1024400922010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Prairie Island Nuclear Power Plant IR 05000282/20100012010-03-0303 March 2010 Prairie Island Power Plant EOC Assessment Letter (05000282-10-001; 05000306-10-001) ML0924403672009-09-0101 September 2009 Prairie Island - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20090012009-03-0404 March 2009 Annual Assessment Letter - Prairie Island Nuclear Generating Plant, Units 1 and 2 (05000282-09-001 and 050000306-09-001) ML0824603142008-09-0202 September 2008 Prairie Island, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20080012008-03-0303 March 2008 Prairie Island, EOC Annual Assessment Letter (Inspection Report 05000282-08-001 and 05000306-08-001) ML0735402802007-12-19019 December 2007 Change to the Inspection Plan 1/1/08 - 12/31/08 ML0724302372007-08-31031 August 2007 8/31/07 Prairie Island - Mid-Cycle Performance Review and Inspection Plan 2024-08-28
[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] Category:Request for Additional Information (RAI)
MONTHYEARML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23096A3082023-04-0707 April 2023 Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 ML23053A1432023-02-22022 February 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment IR 05000282/20224022022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21147A5232021-06-0303 June 2021 Prarie Island Nuclear Generating Plant, Units 1 and 2 - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21131A0752021-05-10010 May 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2021004; 05000306/2021004 ML21099A0972021-04-0909 April 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000282/2021012 and 05000306/2021012 ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant ML21033A6112021-02-0101 February 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010 ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 ML20133K0692020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20077K6242020-04-13013 April 2020 License Amendment Request - Request for Additional Information ML20052F4102020-02-21021 February 2020 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18264A1912018-09-19019 September 2018 NRC Information Request (9/19/2018); Part B Items (Onsite) IP 71111.08 - E-Mailed 09/19/18 (DRS-M.Holmberg) ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18169A4202018-06-25025 June 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Modify Renewed Facility Operating License Paragraph 2.C(4)(c) ML18025C0152018-01-24024 January 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000282/2018011; 05000306/2018011 (DRS-A.Dunlop) ML17277B3332017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information Prairie Island Special Heavy Lifting Devices LAR ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) ML17235A9982017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Prairie Island EAL Scheme Change ML17221A3892017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17219A0762017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17038A5132017-02-0707 February 2017 NRR E-mail Capture - Prairie Island NFPA 805 LAR, PRA RAI 21.01 ML17018A4272017-01-18018 January 2017 NRR E-mail Capture - Request for Additional Information: Prairie Island License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action ML16326A3532016-11-18018 November 2016 NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) ML16189A2052016-07-0707 July 2016 Notification of NRC Inspection and Request for Information ML16113A1612016-04-21021 April 2016 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant, Units 1 and 2 2024-07-15
[Table view] |
See also: IR 05000282/2020004
Text
July 06, 2020
Mr. Scott Sharp
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 NOTIFICATION
OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000282/2020004; 05000306/2020004
Dear Mr. Sharp:
On September 21, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin the
Baseline Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be
performed September 21, 2020, through October 2, 2020.
Experience has shown that this inspection is resource intensive both for the NRC inspector and
your staff. In order to minimize the impact to your onsite resources, and to ensure a productive
inspection for both sides, we have enclosed a request for documents needed for this inspection.
These documents have been divided into two groups.
The first group identifies information necessary to ensure that the inspector is adequately
prepared. The second group identifies the information the inspector will need upon arrival at the
site. It is important that all of these documents are up-to-date, and complete, in order to
minimize the number of additional documents requested during the preparation and/or the
onsite portions of the inspection.
We have discussed the schedule for inspection activities with your staff and understand that our
regulatory contact for this inspection will be Ms. Pam Johnson, of your organization. If there are
any questions about this inspection or the material requested, please contact the lead inspector
Mr. Holmberg at 630-829-9748, or via e-mail at msh@nrc.gov.
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget, Control
Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget Control
Number.
S. Sharp -2-
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Sincerely,
/RA/
Mel Holmberg, Senior Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-282; 50-306
License Nos. DPR-42; DPR-60
Enclosure:
Document Request for Inservice Inspection
cc: Distribution via LISTSERV
S. Sharp -3-
Letter to S. Sharp from M. Holmberg dated July 06, 2020.
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 NOTIFICATION
OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION;
INSPECTION REPORT 05000282/2020004; 05000306/2020004
DISTRIBUTION:
Jessie Quichocho
Elise Burket
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDroIrib Resource
John Giessner
Kenneth OBrien
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML20189A178
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII
NAME MHolmberg:mb via
e-mail
DATE 07/06/2020
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR INSERVICE INSPECTION
Inspection Report: 05000282/2020004; 05000306/2020004
Inspection Dates: September 21, 2020, through October 2, 2020
Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection
Lead Inspector: M. Holmberg, DRS
630-829-9748
msh@nrc.gov
A. Information for the In-Office Preparation Week
The following information (electronic copy if possible (e.g. CERTREC online database,
or CD ROM) is requested by September 4, 2020, to facilitate the selection of specific
items that will be reviewed during the onsite inspection week. The inspector will select
specific items from the information requested below and request a list of additional
documents needed onsite to your staff. We request that the specific items selected from
the lists be available and ready for review on the first day of inspection. The following
information is applicable to the outage Unit unless otherwise indicated. If you have any
questions regarding this information, please call the inspector as soon as possible.
1. For the upcoming outage, a detailed schedule and description of:
a. Non-Destructive Examinations (NDEs) planned for Class 1 and 2 Systems and
containment, performed as part of your American Society of Mechanical
Engineers (ASME) Code Inservice Inspection (ISI) Program (include edition and
addenda of Code committed to), and NDEs planned for other systems performed
as part of a Risk-Informed ISI Program, or other augmented inspection programs
(e.g., ASME Code Case N-770-1 examination of dissimilar metal welds and
examinations to meet an industry initiative such as Thermal Sleeve wear (MRP
Letter No. 2018-33));
b. Reactor vessel upper head examinations required by Title 10 of the Code of
Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729;
c. Steam generator (SG) tube inspection and repair activities for the upcoming
outage or SG secondary side examinations 1; and
d. Welding on Code Class 1, 2, or 3 components. For each weld examination,
include the weld identification number, description of weld (component name),
category, class, type of exam and procedure number, and date of examination.
1
Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur,
and no further information is required for the items identified above requesting SG related information.
Enclosure
DOCUMENT REQUEST FOR INSERVICE INSPECTION
2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition and
analysis procedures, and welding procedures used to perform the activities identified
in Item A.1 (including NDE calibration and flaw characterization/sizing procedures
and Welding Procedure Qualification Records). For ultrasonic examination
procedures qualified in accordance with Appendix VIII, of Section XI of the ASME
Code, provide documentation supporting the procedure qualification (e.g., the
Electric Power Research Institute performance demonstration qualification summary
sheets). For SG tube ET this includes the acquisition and analysis procedures.
3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations
identified in Item A.1.
4. A copy of the 10-year ISI Program showing those required exams scheduled to be
performed this outage, and those which have been completed.
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye
penetrant), which have identified relevant indications on Code Class 1 and 2
Systems since the beginning of the last refueling outage.
6. List with short description of the welds in Code Class 1 and 2 Systems, which have
been fabricated due to component repair/replacement activities since the beginning
of the last refueling outage and identify the system, weld number, and reference
applicable documentation (e.g., NIS-2 forms with definitions of system and
component acronyms).
7. If reactor vessel weld examinations required by the ASME Code are scheduled to
occur during the inspection period, provide a detailed description of the welds to be
examined, and the extent of the planned examination.
8. List with description of ISI and SG-related issues such as piping or SG tube
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically induced
corrosion) or errors identified during piping/SG tube examinations that have been
entered into your corrective action system since the beginning of the last refueling
outage. Also, include a list of corrective action records associated with foreign
material introduced/identified in the reactor vessel, primary coolant system, SG or
feed systems since the beginning of the last refueling outage. Corrective Actions
records that document actions completed or planned related to Baffle Former Bolts
as identified in Westinghouse Letter NSAL-16-1.
9. Copy of any Title 10 of the Code of Federal Regulations Part 21 reports applicable to
your structures, systems, or components within the scope of Section XI of the ASME
Code that have been identified since the beginning of the last refueling outage.
10. Copy of SG history documentation given to vendors performing ET of the SGs during
the upcoming outage 1.
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur,
and no further information is required for the items identified above requesting SG-related information.
2
DOCUMENT REQUEST FOR INSERVICE INSPECTION
11. Copy of procedure containing screening criteria used for selecting tubes for in-situ
pressure testing and the procedure to be used for in-situ pressure testing1.
12. Copy of previous outage SG tube operational assessment completed following ET of
the SGs (provide this document even if no SG ET is planned for current outage).
13. Copy of most recent SG Degradation Assessment (provide this document even if no
SG ET is planned for current outage).
14. Copy of most recent SG Condition Monitoring Assessments1.
15. Copy of the document defining the planned SG ET scope (e.g., 100 percent of
unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion
transition regions with rotating probe) and identify the scope expansion criteria,
which will be applied. Also identify and describe any deviations in this scope or
expansion criteria from the Electric Power Research Institute Guidelines1.
16. Copy of the document describing the ET acquisition equipment to be applied
including ET probe types. Also identify the extent of planned tube examination
coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches
pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus
3 inches to minus 12 inches) 1.
17. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes 1.
18. Identify and quantify any SG tube leakage experienced during the previous operating
cycle. Also provide documentation identifying which SG was leaking and corrective
actions completed or planned for this condition.
19. Point of contact information (name and site number) for the following activities:
a. ISISite and vendor leads;
b. Boric Acid Inspections and Evaluations;
c. Reactor Vessel Head InspectionSite and vendor leads;
d. SG InspectionSite and vendor leads;
e. Aging Management Programs; and
f. Site Welding Engineer.
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur,
and no further information is required for the items identified above requesting SG related information.
3
DOCUMENT REQUEST FOR INSERVICE INSPECTION
B. Onsite Information to Be Provided to the Inspector on the First Day of the
Inspection (e.g., following the entrance meeting). Please Provide Copies (paper
records) of the Following Documents.
1. For welds selected by the inspector from Item A.1.d and A.6 above, provide copies of
the following documents:
a. Document of the weld number and location (e.g., system, train, branch);
b. Document with a detail of the weld construction (e.g., drawing);
c. Applicable portions of the Design Specification and applicable Code of
construction for the weldment (e.g., B31.1 or ASME Section III);
d. Applicable Code Edition and Addenda for weld procedure qualification;
e. Applicable weld procedure specifications and weld data sheets used to fabricate
the welds;
f. Copies of procedure qualification records supporting the weld procedure
specifications;
g. Copies of welders performance qualification records;
h. Copies of mechanical test reports identified in the weld procedure qualification
records above;
i. Copies of the nonconformance reports for the selected welds;
j. Access to radiographs and equipment to view radiographs of the selected welds;
k. ASME Code Section XI repair replacement plan and reconciliation for
replacement components/materials;
l. Certified Material Test Reports for replacement pressure boundary materials; and
m. Copies of the NDE required by the construction Code and the pre-service
examination records required by the ASME Code Section XI for the selected
welds.
2. For the ISI-related corrective action issues selected by the inspector from Item A.8
above, provide a copy of the corrective actions and supporting documentation.
3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems
selected by the inspector from Item A.5 above, provide a copy of the examination
records and associated corrective action documents.
4. Updated schedules for Item A.1 (including schedule showing contingency repair
plans if available).
4
DOCUMENT REQUEST FOR INSERVICE INSPECTION
5. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head
J-groove welds) if any are to be examined during the outage. Also provide any
drawings used by NDE vendors to locate these welds.
6. Copy of the procedures which govern the scope, equipment used, and
implementation of the inspections required to identify boric acid leakage from
systems and components above the vessel head.
7. Copy of:
a. Engineering evaluations/assessments of boric acid related deposits and
associated wastage or corrosion for safety significant components; and
b. Corrective action records for coolant leakage including boric acid deposits on
safety-related components identified since the beginning of the last refueling
outage.
8. Copy of the plant procedures used to perform inspections to identify reactor coolant
system leaks or boric acid deposits and the procedures for resolution of leaks or
boric acid deposits.
9. Copy of the documents which demonstrate that the procedures to be used for
volumetric examination of the reactor vessel head penetration J-groove welds were
qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).
10. Copy of volumetric, surface and visual examination records for the prior inspection of
the reactor vessel head and head penetration J-groove welds.
11. Provide a copy of the Electric Power Research Institute Examination Technique
Specification Sheets and vendor related documents, which support qualification of
the ET probes to be used during the upcoming SG tube inspections 1.
12. Provide a copy of the guidance to be followed if a loose part or foreign material is
identified in the SGs1.
13. Identify the types of SG tube repair processes which will be implemented for
defective SG tubes (including any U.S. Nuclear Regulatory Commission
reviews/evaluation/approval of this repair process). Provide the flaw depth sizing
criteria to be applied for ET indications identified in the SG tubes1.
14. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified1.
15. Provide document which defines the scope of SG secondary side examinations (if
any are planned) and identify site specific operational history related to degradation
of SG secondary side components (if any).
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur,
and no further information is required for the items identified above requesting SG related information.
5
DOCUMENT REQUEST FOR INSERVICE INSPECTION
16. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes1.
17. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory
Commission inspection location for the duration of the inspection:
a. Sections V, IX, and XI of the ASME Code with Editions applicable to the ISI
Program and the Repair/Replacement Program;
b. Copy of the performance demonstration initiative (PDI) generic procedures with
the latest applicable revisions that support site qualified ultrasonic examination of
piping welds and components (e.g., PDI-UT-1, PDI-UT-2, PDI-UT-3, PDI-UT-10
etc.);
c. Electric Power Research Institute and industry standards referenced in the site
procedures used to perform the SG tube ET, which includes Electric Power
Research Institute documents: SG Examination Guidelines, SG Integrity
Assessment Guidelines, SG In-Situ Pressure Test Guidelines 1; and
d. Boric Acid Corrosion Guidebook Revision 1Electric Power Research Institute
Technical Report 1000975.
18. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion) if
required to access the non-destructive examinations selected by the inspector for
observation.
If you have questions regarding the information requested, please contact the lead inspector.
1
Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur,
and no further information is required for the items identified above requesting SG related information.
6