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MONTHYEARML22067A1522021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 2 ML22067A1532021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 3 ML22067A1542021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 4 L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D2021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D ML20336A3392020-12-0101 December 2020 Refueling Outage Unit 1 R32 Owner'S Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML20272A2932020-09-28028 September 2020 (PINGP) Unit 1 and 2 Revised Pressure and Temperature Limits Report ML16245A7632016-09-16016 September 2016 MSFHI Tables Final 8-31-2016 ML16248A0062016-09-16016 September 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (CAC Nos. MF7710 and MF7711) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports L-PI-15-003, Notification of Change in Commitment Made in Letter Dated November 26, 2012 in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)2015-01-20020 January 2015 Notification of Change in Commitment Made in Letter Dated November 26, 2012 in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) L-PI-12-078, PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 252012-10-0101 October 2012 PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML0920805212009-07-23023 July 2009 Meeting Handout #2 for Public Meeting to Discuss Prairie Island Diesel Generator Test Loads License Amendment Request ML0833805442008-12-0303 December 2008 PINGP - NOAA National Climatic Data Center, July 27, 1987 Tornado in Goodhue County, Minnesota . 2008i ML0833802242008-12-0303 December 2008 PINGP - SEIS Reference - NOAA Regional Climate Centers 2008e ML0833803552008-09-17017 September 2008 PINGP - NOAA Midwestern Regional Climate Center: 1971 - 2000 National Climatic Data Center Normals: Snowfall. 2008g ML0833803332008-09-17017 September 2008 PINGP - NOAA Regional Climate Centers. Midwestern Regional Climate Center: 1971 -2000. Normals: Precipitation. 2008f ML0833802582008-09-12012 September 2008 PINGP - Climate Extremes for Minnesota. Minnesota Climatology Working Group. 2008 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists L-PI-06-031, Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-06-16016 June 2006 Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time ML0430801822004-10-22022 October 2004 Emergency Action Level Matrix (Hot Conditions (RCS ≫ 200 F)) ML0430801792004-10-22022 October 2004 Prairie Nuclear Generating Plant Emergency Action Level Matrix (Cold Conditions (RCS </- 200 F)) L-PI-04-001, 1997 Met Files2004-01-20020 January 2004 1997 Met Files ML0434501802003-12-11011 December 2003 NMC Program Health Status Fleet Program at a Glance ML0317700762003-06-26026 June 2003 Report on the Status of Open TIAs Assigned to NRR 2021-11-30
[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
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~ Xcel Energy 1717 Wakonade Drive Welch, MN 55089 December 1, 2020 L-Pl-20-062 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Unit 1 Docket Nos. 50-282 Renewed Facility Operating License No. DPR-42 Refueling Outage Unit 1 R32 Owner's Activity Report for Class 1, 2, 3 and MC lnservice Inspections Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby submits inservice inspection summary report for inspections conducted prior to and during the Prairie Island Nuclear Generating Plant (PINGP) refueling outage U1 R32 that concluded on October 13, 2020.
The Enclosure to this letter contains Form OAR-1, "Owner's Activity Report" for inservice inspections for Class 1, 2, 3 and MC components.
Summary of Commitments This letter akes no newco-m nts and no revisions to existing commitments.
7 ~l (.
Christopher P. D' mingos Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC
FORM OAR-1 OWNER'S ACTIVITY REPORT Prairie Island Nuclear Generating Plant As required by the provisions of ASME Code Case N-532-5 Repo rt N umber 1 R3 2 Plant _....P....r-=a.,_:..::"-'l=sl=a.,_,_
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Current inspec tion inte rval 5th ISi Inspection I nterval for class 1. 2 , and 3. 3rd IW E I nspection I nterval for c lass MC Cu rrent inspection period 2 nd ISi Inspe ction Period fo r class 1. 2 . and 3. 1 st IW E Inspection period fo r class M C Edit ion and Addenda of Section XI applicab le to the inspection plans 2 007 E dition - 2008 Addenda for class 1. 2 ,
and 3. 20 13 Ed ition for class M C ___
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E dition and Addenda of Section XI applicab le to repai r/replacem ent activities . if different than the inspection plans Sam e as I nspect i on Plan fo r class 1 . 2 . and 3. 2007 Edition - 2008 Add enda fo r class M C Code Cases u sed for inspecti on and eval uation : __""'"N-_,_5 _,_13--= 3 , N - -5 3-= ,5 ""'"N-7 _,_16-"""1-, N--7-=2= 2-1 ___
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this Owner's Activity Report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI: and (c) the repair/replacement activities and evaluations supporting the completion of refueling outage number 1 R32 conform to the requirements of Section XI.
Signed /,t)IV'- ISi Engineer Date _l_l_-_'-/_-_Z.._o____
Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford steam Boiler Inspection and Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XL By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
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TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number B-P, B15.10 SP 1392 Bolted Connections Borated RC-2-1, TBSP dry, white, at body to bonnet Systems Pressure Test accepted by evaluation QIM 501000044639.
B-P, B15.10 SP 1392 Bolted Connections Borated 1FE-459, trace dry, white at bolted connection Systems Pressure Test accepted by evaluation QIM 501000044639.
B-P, B15.10 SP 1392 Bolted Connections Borated CV-31255, trace dry, white, at body to bonnet Systems Pressure Test accepted by evaluation QIM 501000044639.
B-P, B15.10 SP 1392 Bolted Connections Borated 135-011, trace dry, white at bolted connection Systems Pressure Test accepted by evaluation QIM 501000044639.
B-P, B15.10 SP 1392 Bolted Connections Borated MV-32165, 1-2 tsp dry, white, at body to Systems Pressure Test bonnet accepted by evaluation QIM 501000044639.
B-P, B15.10 SP 1392 Bolted Connections Borated MV-32231, 1/4 cup dry, white/brown at packing Systems Pressure Test and body to bonnet accepted by evaluation QIM 501000044639.
B-P, B15.10 SP 1392 Bolted Connections Borated 134-011, trace dry, white at bolted connection Systems Pressure Test accepted by evaluation QIM 501000044639.
C-H, C7.10 SP 1168.14 Containment Spray MV-32097, trace dry boric acid indication at System Pressure Test body to bonnet accepted by evaluation QIM 501000025480.
C-H, C7.10 SP 1168.14 Containment Spray 8-CS-4, < tsp dry white/brown boric acid System Pressure Test indication at flange accepted by evaluation QIM 501000025480.
C-H, C7.10 SP 1168.14 Containment Spray 1-CS-37, Tbsp dry white boric acid indication System Pressure Test at flange accepted by evaluation QIM 501000025480.
C-H, C7.10 SP 1168.14 Containment Spray 2-CS-12A, trace dry white boric acid indication System Pressure Test at flange accepted by evaluation QIM 501000025480.
F-A, F1.20c Aux Feedwater Support 1-AFWH-75, Bolt is tight, washer is loose accepted by evaluation QIM 501000044690 and EC 608000000635.
F-A, F1.30b Cooling Water Support 1-CWH-424, Cracks in weld accepted by evaluation QIM 501000044421 and EC 608000000635.
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TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Date Plant ID # Description of Work Completed R/R Plan #
Class Description Completed ZH system 4-ZH-61 piping Due to MIC, a section of Chilled 121 Control Water (ZH system) piping and valve 2/6/2019 1-31-012 Room Chiller was replaced.
CL-16-4 3 Cooling Water Supply Cooling Replaced segments of Cooling Water 3-CL-88 Water Piping System piping due to MIC.
Segment 3 Cooling 2/20/2020 1-31-031 Replaced segments of Cooling Water 2-1/2-CL-88 Water Piping System piping due to MIC.
Segment Cooling Replaced segments of Cooling Water CW-17-7 Water Valve System piping due to MIC.
Cooling Replaced segment of Cooling Water 3 3-CL-88 Water Piping 9/21/2020 1-31-033 System piping due to MIC.
Segment Cooling Replaced segment of pipe due to 3 20-CL-3 Water Pipe 1/4/2019 1-31-004 MIC.
Segment Cooling Water Replaced segment of Cooling Water 3 3-CL-11 System 1/9/2020 1-31-029 System piping due to MIC.
piping segment CL System Replaced a segment of Cooling 3 3-CL-88 piping 11/5/2019 1-31-030 Water System piping due to MIC.
segment 12 MD AFW Replaced cooling water piping and CL-113-2 PMP CLG valve due to MIC.
WTR SPLY 3 10/30/2019 1-31-024 CL Piping Replaced cooling water piping and 4-CL-90 Segment valve due to MIC.
CL Piping Replaced cooling water piping and 4-CL-23 Segment valve due to MIC.
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