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Category:Inspection Plan
MONTHYEARIR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 IR 05000266/20220062023-03-0101 March 2023 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022006 and 05000301/2022006) ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22256A3182022-09-13013 September 2022 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection Report 05000266/2023010 05000301/2023010 IR 05000266/20220052022-08-26026 August 2022 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022005 and 05000301/2022005) ML22175A2002022-06-27027 June 2022 Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information: Inspection Report 05000266/2022004: 05000301/2022004 ML22172A2132022-06-22022 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML22173A0172022-06-22022 June 2022 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Point Beach Nuclear Plant IR 05000266/20210062022-03-0202 March 2022 Annual Assessment Letter for Point Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021006 and 05000301/2021006) ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 IR 05000266/20210052021-09-0101 September 2021 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021005 and 05000301/2021005) ML21214A2812021-08-0202 August 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21180A2302021-06-29029 June 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2021004 and 05000301/2021004 ML21074A3962021-03-15015 March 2021 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000266/2021010; 05000301/2021010 IR 05000266/20200062021-03-0404 March 2021 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020006 and 05000301/2020006) IR 05000266/20200052020-09-0101 September 2020 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020005 and 05000301/2020005) ML20218A4322020-08-0505 August 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2020004 ML20168A8912020-06-15015 June 2020 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Point Beach Nuclear Plant, Units 1 and 2 IR 05000266/20190062020-03-0303 March 2020 Annual Assessment Letter for Point Beach Nuclear Plants, Units 1 and 2 (Report 05000266/2019006 and 05000301/2019006) IR 05000266/20190052019-08-28028 August 2019 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2019005 and 05000301/2019005) ML19190A1532019-07-0909 July 2019 Ltr. 07/09/19 Point Beach Nuclear Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information; Inspection Report 05000266/2019012; 05000301/2019012 (DRS-G.Hausman) ML19136A1402019-05-15015 May 2019 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza) ML19094B1182019-04-0404 April 2019 Ltr. 04/04/19 Point Beach Nuclear Plant, Units 1 and 2 - Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the EQ Program; Inspection Report 05000266/2019013 and 05000301/2019013 (DRS-B.Jose) IR 05000266/20180062019-03-0404 March 2019 Annual Assessment Letter for Point Beach Nuclear Plant (Report 05000266/2018006 and 05000301/2018006) ML19037A3102019-02-0505 February 2019 Ltr. 02/05/19 Point Beach Nuclear Plant, Units 1 and 2 - Information Request for the Cyber-Security Full Implementation Inspection, Notification to Perform Inspection; Inspection Report 05000266/2019412; 05000301/2019412 (DRS-G.Hausman) ML19024A2772019-01-24024 January 2019 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2019001 (DRS-M.Domke) IR 05000266/20180052018-08-28028 August 2018 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2018005 and 05000301/2018005) IR 05000266/20170062018-03-0202 March 2018 Annual Assessment Letter for Point Beach Plant, Units 1 and 2 (Report 05000266/2017006 and 05000301/2017006) IR 05000266/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000266/2017005 and 05000301/2017005) ML17088A7242017-03-29029 March 2017 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000266/2017007; 05000301/2017007 IR 05000266/20160062017-03-0101 March 2017 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2016006 and 05000301/2016006) ML17039B0182017-02-0808 February 2017 Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Point Beach Nuclear Plant, Units 1 and 2 - Inspection Report 05000266/2017008; 05000301/2017008 IR 05000266/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Point Beach Nuclear Plant Units 1 and 2 (Report 05000266/2016005; 05000301/2016005) IR 05000266/20150062016-03-0202 March 2016 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Inspection Report 05000266/2015006 and 05000301/2015006) IR 05000266/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2015005; 05000301/2015005) ML15131A3132015-05-0808 May 2015 Ltr. 05/08/15 Point Beach Nuclear Plant, Units 1 and 2 - Information Request for an NRC Triennial Permanent Modifications and 10 CFR 50.59 (Mod/50.59) Baseline Inspection 05000266/2015010; 05000301/2015010 (Jjc) ML15124A9012015-05-0101 May 2015 Ltr. 05/01/15 Point Beach Nuclear Plant, Unit 2 - Notification of NRC Inspection and Request for Information (Msh) IR 05000266/20140012015-03-0404 March 2015 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2014001; 05000301/2014001) ML15050A2702015-02-19019 February 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Point Beach Nuclear Plant, Units 1 and 2 ML14245A1662014-09-0202 September 2014 Mid-Cycle Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 IR 05000266/20130012014-03-0404 March 2014 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2013001; 05000301/2013001) ML14038A3472014-02-0606 February 2014 ISI Request for Information ML13246A2212013-09-0303 September 2013 2013 Point Beach MOC Letter Combined ML13172A4072013-06-20020 June 2013 Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000266-13-010; 05000301-13-010 2024-08-21
[Table view] Category:Letter
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24215A2092024-08-0101 August 2024 NRR E-mail Capture - Final RAI - Point Beach 1 & 2 - License Amendment Request to Modify Containment Average Air Temperature Requirements ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 ML23136A2802023-05-0505 May 2023 SLRA Second Annual Update RAI Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22266A0872022-09-23023 September 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22172A1192022-06-27027 June 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-505 Provide Risk Informed Extended Complete Times - RITSTF Initiative 4B ML22130A5712022-05-12012 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21362A6812021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6702021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21273A0222021-09-29029 September 2021 SLRA Safety RAI Set 9 Final ML21287A0862021-09-29029 September 2021 SLRA Safety RAI Set 11 Final ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2472021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2202021-08-20020 August 2021 SLRA Safety RAI Set 7 Final ML21242A2142021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email ML21242A0152021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2392021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2032021-08-12012 August 2021 Srla Safety RAIs Set 5 Final ML21242A2382021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A2042021-08-12012 August 2021 SLRA Safety RAIs Set 5 Final Email ML21242A0122021-08-0909 August 2021 SLRA Draft Safety RAIs Set 6 ML21285A1212021-08-0505 August 2021 SLRA Public Meeting Discussion Questions August 5 2021 ML21242A2002021-08-0505 August 2021 SLRA Draft Safety RAIs Set 5 Email ML21242A1992021-08-0505 August 2021 Srla Draft Safety RAIs Set 5 ML21238A2322021-08-0404 August 2021 SLRA Safety RAI Set 4 Final Email ML21238A2332021-08-0404 August 2021 SLRA Safety RAI Set 4 Final ML21237A0062021-08-0202 August 2021 SLRA Draft Safety RAIs Set 4 ML21208A1892021-07-27027 July 2021 SLRA Safety RAIs Set 2 Final 2024-08-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 May 1, 2015 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. McCartney:
On October 12, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin the Baseline Inservice Inspection (Procedure 71111.08). This on-site inspection is scheduled to be performed October 12-29, 2015.
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 on-site 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 on-site 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 Mr. Tom Schneider, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Mr. M. Holmberg at (630) 829-9748 or via e-mail at Mel.Holmberg@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.
E. McCartney In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-301 License No. DPR-27
Enclosure:
Inservice Inspection Document Request cc w/encl: Distribution via LISTSERV
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: October 12-29, 2015 Inspection Procedures: IP 71111-08, Inservice Inspection Lead Inspector: Mel Holmberg, DRS (630) 829-9748 Mel.Holmberg@nrc.gov A. Information for the In-Office Preparation Week The following information is requested as an (electronic copy CD ROM if possible) by September 7, 2015, to facilitate the selection of specific items that will be reviewed during the on-site inspection week. The inspector will select specific items from the information requested below and a list of additional documents needed on-site from 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 Unit 2, 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 ASME Code Inservice Inspection (ISI)
Program (include edition and addenda of Code committed to), and NDE examinations planned for other systems performed as part of a Risk-Informed (RI)-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). 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;
- b. Reactor vessel upper head examinations required by 10 CFR 50.55a(g)(6)(ii)(D) and Code Case N-729-1;
- 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 (including contingency repair welding for dissimilar metal welds).
- 2. A copy of the NDE procedures and welding procedures (including contingency weld repair procedures for dissimilar metal weld repairs) 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 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
INSERVICE INSPECTION DOCUMENT REQUEST of the ASME Code, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets).
- 3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in Item A.1. This would include the NRC approved Relief Request for implementing a RI-ISI Program (if applicable).
- 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, MIC) 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, steam generator or feed systems since the beginning of the last refueling outage.
- 9. Copy of any Title 10, Code of Federal Regulations (CFR) 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 eddy current (ET) testing of the SGs during the upcoming outage.1
- 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 testing. 1
- 12. Copy of previous outage SG tube operational assessment completed following ET of the SGs. 1
- 13. 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, 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
INSERVICE INSPECTION DOCUMENT REQUEST which will be applied. Also identify and describe any deviations in this scope or expansion criteria from the EPRI Guidelines.1
- 14. 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).
- 15. Provide procedures with guidance/instructions for identifying (e.g. physically locating the tubes that require repair) and plugging SG tubes.1
- 16. 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.
- 17. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1 that establish the volumetric and visual examination frequency for the reactor vessel head and J-groove welds.
- 18. Point of contact information (name and site number) for the following activities:
- a. Inservice Inspection-Site and vendor leads;
- b. Boric Acid Inspections and Evaluations'
- c. Reactor Vessel Head Inspection-Site and vendor leads, and
- d. SG Inspection-Site and vendor leads.
B. On-Site Information to be Provided to the Inspector on the First Day of the Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies (e.g., 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 Code Edition and Addenda for construction of the weldment (e.g., B31.1 or ASME Section III);
- d. Applicable Code Edition and Addenda for weld procedure qualification;
- e. Applicable weld procedures (WPS) used to fabricate the welds;
- f. Copies of procedure qualification records (PQRs) supporting the WPS; 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
INSERVICE INSPECTION DOCUMENT REQUEST
- g. Copies of welders performance qualification records (WPQ);
- h. Copies of mechanical test reports identified in the PQRs above;
- i. Copies of the nonconformance reports for the selected welds;
- j. Access to radiographs and equipment to view radiographs of the selected welds; and
- k. Copies of the pre-service examination records 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 non-destructive examination 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.
Updated schedules for Item A.1 (including schedule showing contingency repair plans if available).
- 4. 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.
- 5. Copy of:
- a. Engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety significant components (since beginning of last refueling outage); 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.
- 6. 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.
- 7. 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.
- 8. 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).
- 9. Copy of volumetric, surface and visual examination records for the prior inspection of the reactor vessel head and head penetration J-groove welds.
4
INSERVICE INSPECTION DOCUMENT REQUEST
- 10. Provide a copy of the EPRI Examination Technique Specification Sheets and vendor documents, which support qualification of the ET probes to be used during the upcoming SG tube inspections.1
- 11. Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs. 1
- 12. Identify the types of SG tube repair processes which will be implemented for defective SG tubes (including any NRC reviews/evaluation/approval of this repair process). Provide the flaw depth sizing criteria to be applied for ET indications identified in the SG tubes. 1
- 13. Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified. 1
- 14. 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).
- 15. Provide procedures with guidance/instructions for identifying (e.g., physically locating the tubes that require repair) and plugging SG tubes.1
- 16. Provide copies of the following standards at the on-site NRC inspection location for the duration of the inspection:
- a. Sections V, IX, and XI of the ASME Code with Editions applicable to the inservice inspection 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. EPRI and industry standards referenced in the site procedures used to perform the SG tube eddy current examination, which includes EPRI documents: TR-107621-R1, Steam Generator Integrity Assessment Guidelines, TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines, Part 10, and 1003138, Pressurized Water Reactor Steam Generator Examination Guidelines1; and
- d. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.
- 17. Provide training (e.g., Scaffolding, Fall Protection, FME) 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.
5
E. McCartney In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-301 License No. DPR-27
Enclosure:
Inservice Inspection Document Request cc w/encl: Distribution via LISTSERV DISTRIBUTION w/encl:
Kimyata MorganButler RidsNrrDorlLpl3-1 Resource RidsNrrPMPointBeach RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Jim Clay Carmen Olteanu ADAMS Accession Number ML15124A901 Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII NAME MHolmberg:cl DHills DATE 04/30/15 05/01/15 OFFICIAL RECORD COPY