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Category:Inspection Plan
MONTHYEARIR 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 IR 05000282/20070012007-03-0202 March 2007 (EOC) Power Plant Assessment Letter (Report 05000282/2007001; 05000306/2007001) ML0624303382006-08-31031 August 2006 8/31/06 Prairie Island Station-Mid-Cycle Performance Reveiw and Inspection Plan 2023-08-30
[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] Category:Request for Additional Information (RAI)
MONTHYEARML23335A1152023-12-0101 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 ML22145A4152022-05-25025 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 ML16075A0802016-03-15015 March 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 Request for Additional Information Related to License Amendment Request to Adopt TSTF-523, GL 2008-01, Managing Gas Accumulation ML16008A1092016-01-0808 January 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Requests for Additional Information (Afpb) License Amendment Request to Adopt NFPA 805 ML15195A6562015-07-10010 July 2015 Prairie Island Notification of NRC Inspection and Request for Information ML15149A1662015-05-28028 May 2015 Plan - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15121A6512015-04-29029 April 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000282/2015007; 05000306/2015007 (Jen) 2023-09-05
[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