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MONTHYEARML23354A1092023-10-26026 October 2023 Protective Measures Coordinator Checklist Project stage: Request ML23338A0392023-12-0101 December 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Unacceptable with Opportunity to Supplement - Callaway - RR from Requirements of ASME BPV Code, Section Xl, Subsect IWL-Exam & Test-Unbonded Post Tensioning System - EPID L-2023-LLR-0061 Project stage: Acceptance Review ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System Project stage: Acceptance Review ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) Project stage: Supplement ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) Project stage: Acceptance Review ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections Project stage: Other ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections Project stage: Approval ML24225A1012024-08-13013 August 2024 Authorization and Safety Evaluation for Alternative Request C3R-01 Project stage: Approval 2023-12-21
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Category:Audit Plan
MONTHYEARML24247A3042024-09-11011 September 2024 Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML23065A3212023-03-28028 March 2023 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23068A3772023-03-20020 March 2023 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request and Exemption for Fuel Transition to Framatome Gaia Fuel (EPID L-2022-LLA-0150 and EPID L-2022-LLE-0030) - Nonproprietary ML22061A0042022-03-0707 March 2022 Audit Questions for License Amendment Request to Revise Technical Specifications to Adopt TSTF-505 and TSTF-439, Revision 2 ML22048A0022022-02-18018 February 2022 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2 and TSTF-439, Revision 2 ML21197A0632021-07-23023 July 2021 Audit Plan and Setup of Online Reference Portal for License Amendment Request Risk-Informed Approach for Closure of Generic Safety Issue-191 ML21110A1232021-04-27027 April 2021 Audit Questions for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21039A2222021-02-18018 February 2021 Audit Plan and Setup of Online Reference Portal for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18156A4042018-06-19019 June 2018 Regulatory Audit Plan for September 18-19, 2018, in Support of License Amendment Request to Incorporate New Technical Specification 3.7.20 ML17177A4462017-07-0606 July 2017 Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task Force ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML15309A3262015-11-0909 November 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2024-09-11
[Table view] Category:Code Relief or Alternative
MONTHYEARML24225A1012024-08-13013 August 2024 Authorization and Safety Evaluation for Alternative Request C3R-01 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML20225A2922020-08-12012 August 2020 Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI ML19079A1482019-04-0101 April 2019 Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051 ML18313A0692018-11-26026 November 2018 Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping ULNRC-06420, Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds2018-04-0909 April 2018 Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds ML17262A7002017-10-0303 October 2017 Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval ML17254A1202017-09-25025 September 2017 Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval ML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML16223A7122016-08-30030 August 2016 Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval ML16055A4642016-03-17017 March 2016 Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737) ML16027A1582016-01-29029 January 2016 Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval ML15064A1252015-05-12012 May 2015 Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval ML15035A1482015-02-10010 February 2015 Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval ML14239A0972014-09-0404 September 2014 Request for Relief I3R-15, ASME Code Class 1 Pressure-Retaining Piping/Components Leakage Testing at Full Pressure, Third 10-Year Inservice Inspection Interval ML14234A4512014-09-0404 September 2014 Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval ML14178A7692014-07-15015 July 2014 Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval ML14027A0572014-01-29029 January 2014 Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval ML13246A3042013-08-30030 August 2013 Verbal Authorization Email, Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval ML13126A3202013-05-0707 May 2013 Summary of Telephone Conference, Verbal Authorization of Relief Request I3R-14. Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year ISI Interval. ML12258A0452012-09-18018 September 2012 Relief Request VR-01 from Requirements of ASME OM Code, Mandatory Appendix I, One-time Extension for 5-Year Replacement Interval, from 4/11/12 to 6/2013, Main Steam Isolation Valve Actuator Rupture Disks ML1211502472012-05-0303 May 2012 Memo to File, Verbal Authorization, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks ML1201907482012-02-16016 February 2012 Relief Request 13R-13, Alternative to ASME Code Section XI Requirements for Performance of Second Successive Exam of C Cold Leg Safe-End to Elbow Weld, Third 10-Year Inservice Inspection ML0831002882008-11-0707 November 2008 Relief Request 13R-10 Approved on October 31, 2008, for Third 10-Year Inservice Inspection Interval for Use of Polyethylene Pipe in Lieu of Carbon Steel Pipe in Buried Essential Service Water Piping System ML0818406062008-07-0303 July 2008 Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. ML0731114422007-12-10010 December 2007 Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval ML0729803972007-10-30030 October 2007 Relief Request ISI-38, Reactor Pressure Vessel Inlet Safe-End to-Elbow Welds Proposed Alternative Examination for Second 10-Year Inservice Inspection Interval ML0724000922007-09-17017 September 2007 Issuance of Relief Requests (Rrs) ISI-36, ISI-37, and ISI-38 for Second Year Inservice Inspection (ISI) Interval ML0725504882007-08-30030 August 2007 10 CFR 50.55a Request: Proposed Alternative to ASME Section Xi Requirements for Replacement of Class 3 Buried Piping ML0715203292007-07-10010 July 2007 Request for Alternatives for Application of Structural Weld Overlays to Pressurizer Dissimilar Metal Nozzle Welds for Third 10-Year Inservice Inspection Program Interval ML0705803332007-03-15015 March 2007 Authorization of Relief Request No. ISI-33 for Second 10-Year and Third 10-Year ISI Interval ML0635203182007-01-18018 January 2007 Request for Relief No. ISI-35 for Second 10-year Inservice Inspection Interval ML0700303362007-01-18018 January 2007 Relief Request ISI-41 for the Second 10-year Inservice Inspection Interval ML0630604782006-12-0707 December 2006 Relief Request 13R-04 for the Third 10-Year Interval Inservice Inspection ML0629302822006-11-17017 November 2006 Relief Requests I3R-05 and I3R-06 for the Third Inservice Inspection Interval ULNRC-05183, Requests for Relief from ASME Section XI Code Inservice Examination Requirements2006-10-25025 October 2006 Requests for Relief from ASME Section XI Code Inservice Examination Requirements ML0614301312006-06-15015 June 2006 Relief, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02 ML0520802152005-08-18018 August 2005 Relief, Use a Subsequent Edition of ASME Code Examinations for the Third Inservice Inspection Interval ML0515302072005-06-22022 June 2005 6/22/05 Callaway, Unit 1 - Relief Requests ISI-24,ISI-25 and ISI-26 of the Second 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4435 and MC4436) ML0507601292005-05-19019 May 2005 Relief, Request for Relief from Certain ASME Code Examinations for the Second Inservice Inspection Interval ULNRC-05092, Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program2004-11-18018 November 2004 Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program ULNRC-05049, Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements2004-09-0303 September 2004 Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements ML0414100712004-05-19019 May 2004 Relief, ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping. ML0414100352004-05-19019 May 2004 Relief, Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method ULNRC-04993, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement2004-05-0707 May 2004 Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement ML0409806642004-04-0707 April 2004 4/7/04 Callaway Plant - Request for Relief from ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements2003-08-14014 August 2003 Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements ML0318305352003-07-0101 July 2003 Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method (Tac. MB6534) ML0134602652002-01-30030 January 2002 Relief, Application of Risk-Informed Inservice Inspection Program for the American Society of Mechanical Engineers Boilers and Pressure Vessel Code Class 1 and 2 TAC No MB1205) 2024-08-13
[Table view] Category:Letter
MONTHYEARIR 05000483/20240032024-10-23023 October 2024 Integrated Inspection Report 05000483/2024003 IR 05000483/20240132024-10-21021 October 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2024013 IR 05000483/20244012024-10-0909 October 2024 Material Control and Accounting Program Inspection Report 05000483/2024401 Public ULNRC-06901, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)2024-10-0101 October 2024 Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter) ML24247A3042024-09-11011 September 2024 Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary IR 05000483/20244032024-08-28028 August 2024 Security Baseline Inspection 05000483-2024-403 IR 05000483/20240052024-08-14014 August 2024 Updated Inspection Plan for Callaway Plant (Report 05000483/2024005) IR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20240022024-07-18018 July 2024 And Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ML24144A0492024-06-11011 June 2024 Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML24158A5222024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008) ML24178A1132024-06-0606 June 2024 Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site ML24143A1632024-05-23023 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ML24137A2342024-05-16016 May 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011 ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ML24122A1132024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ML24108A1082024-04-17017 April 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009 ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 ML24088A3212024-04-0101 April 2024 Notification of Commercial Grade Dedication Inspection (05000483/2024013) and Request for Information ML24086A5132024-03-26026 March 2024 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ML24079A1622024-03-19019 March 2024 Re Nuclear Property Insurance Reporting ML24066A1932024-03-0707 March 2024 2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 IR 05000483/20230062024-02-28028 February 2024 Annual Assessment Letter for Callaway Plant Report 05000483/2023006 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ML24036A1712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0079 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) IR 05000483/20230042024-01-19019 January 2024 – Integrated Inspection Report 05000483/2023004 ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 2024-09-11
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Text
February 26, 2024
Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Ameren Missouri Callaway Energy Center 8315 County Road 459 Steedman, MO 65077
SUBJECT:
CALLAWAY PLANT, UNIT NO. 1 - REGULATORY AUDIT PLAN IN SUPPORT OF PROPOSED ALTERNATIVE TO ASME CODE, SECTION XI REQUIREMENTS FOR CONTAINMENT BUILDING INSPECTIONS (EPID L-2023-LLR-0061)
Dear Mr. Diya:
By letter dated October 26, 2023 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML23299A195), as supplemented by )|letter dated December 21, 2023]] (ML23355A180), Union Elec tric Company, doing business as Ameren Missouri (the licensee), submitted a proposed alternative to subsection IWL of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, regarding the frequency of certain containment unbonded post-tensioning system ins ervice inspection at Callaway Plant, Unit No. 1.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensees alternative request and determined that a regulatory audit would support its review of the proposed alternative. The NRC staff will conduct a regulatory audit to support its review in accordance with the enclosed audit plan. A regulatory audit is a planned activity that includes the examination and evaluation of primarily non-docketed information.
The audit will be conducted to increase the NRC staffs understanding of the request and identify information that will need to be docketed to support the NRC staffs regulatory findings.
The audit will be conducted from March 15, 2024, through May 15, 2024, through an online portal (also known as electronic portal, ePortal, or electronic reading room) established by the licensee.
F. Diya
If you have any questions, please contact me at 301-415-8371 or via email at Mahesh.Chawla@nrc.gov.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-483
Enclosure:
Audit Plan
cc: Listserv
REGULATORY AUDIT PLAN
IN SUPPORT OF PROPOSED ALTERNATIVE TO ASME CODE, SECTION XI
REQUIREMENTS FOR CONTAINMENT BUILDING INSPECTIONS
UNION ELECTRIC COMPANY
CALLAWAY PLANT, UNIT NO. 1
DOCKET NO. 50-483
1.0 BACKGROUND
By letter dated October 26, 2023 (Agencywi de Documents Access and Management System
( A D A MS ) Package A c c es s i o n N o. ML23299A195), as supplemented by )|letter dated December 21, 2023]] (ML23355A180), Union Electr ic Company, doing business as Ameren Missouri (the licensee), submitted a proposed alternative to subsection IWL of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, regarding the frequency of certain containment unbonded post-tensioning system inservice inspections at Callaway Plant, Unit No. 1 (Callaway).
The U.S. Nuclear Regulatory Commission (NRC) staff has determined the need for a regulatory audit to be conducted in accordance with the Office of Nuclear Reactor Regulation Office Instruction LIC-111, Revision 1, Regulatory Audits (ML19226A274), for the NRC staff to examine the licensees non-docketed information with the intent to gain a better understanding of the alternative request, to verify information, and to identify information that may require docketing to support the basis of the NRC staffs licensing decision.
2.0 REGULATORY AUDIT BASES
The NRC staff (i.e., audit team) will perform the audi t to support its evaluation of whether the licensees request provides plant-specific examination results on Callaway, as a basis for the proposed deviations from the ASME Code,Section XI, subsection IWL requirements.
3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY
The audit team will review the licensees tendon surveillance reports, calculations, and analyses supporting the proposed alternative. The audit team will use this review to determine if the licensee needs to submit any additional information in support of the requested changes in order to support conclusions for the NRC staffs safety evaluation.
Enclosure
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY AUDIT
The NRC staff requests that the licensee has the following information readily available and accessible for the NRC staffs review via an internet-based portal:
The 10th, 15th, 20th, 25th, 30th, and 3 5th year detailed inspection reports for the general visual examinations of containment c oncrete components, and the detailed visual examinations of suspect areas, as required by table IWL-2500-1(L-A) Examination Category L-A, Concrete, at Callaway.
The 10th, 15th, 20th, 25th, 30th, and 3 5th year detailed reports for the containment building tendon surveillance, as required by table IWL-2500-1(L-B) Examination Category L-B, Unbounded Post-Tensioning System, at Callaway, including but not limited to the following:
o Tendon force trends and forecasts, elongation measurements, and the minimum required tendon forces;
o Tendon wire sampling and testing results, and their evaluations against the acceptance criteria;
o Visual examination results on the anchorage hardware and surrounding concrete, and their evaluations, and conclusions;
o Corrosion protection medium testing results, their evaluations, and conclusions;
o Free water testing results, their evaluations, and conclusions.
Per enclosure 2, section 3.4.2 of the licensees request dated October 26, 2023:
evaluation reports relating to blocked drains that caused severe corrosion of the vertical tendon wires, reports/redesign documents detailing the corrective actions to remediate corroded wires, and updated maintenance procedures to address root cause of the end cap flooding.
Per enclosure 2, section 3.4.2 of the licensees request dated October 26, 2023:
engineering evaluation reports relating to failing anchor heads, enhanced examination program documents, and corrective action reports for replacing failed or cracked anchor heads.
Applicable calculations for supporting the containment building tendon surveillance and for the acceptability of tendon/wires by the responsible engineer.
Based on the review of the above documents, the NRC staff will determine whether it needs to request any additional documents to be made available on the portal or whether additional information needs to be submitted on the docket for the staff to complete the review of the requested changes.
5.0 AUDIT TEAM
The members of the audit team are:
Mahesh Chawla, Project Manager, NRC (Mahesh.Chawla@nrc.gov)
Shaohua Lai, Structural Engineer, NRC (Shaohua.Lai@nrc.gov)
George Wang, Structural Engineer, NRC (George.Wang@nrc.gov)
6.0 LOGISTICS
The audit will be conducted from March 15, 2024, through May 15, 2024, through an online portal (also known as electronic portal, ePortal, or electronic reading room) established by Callaway.
If requested, the audit team will conduct a webinar with the licensee for the purposes of introducing the team, discussing the scope of the audit, and describing the information to be made available on the internet portal. The audit team expects to request that the licensee answer audit team questions during the audit related to information provided online at a mutually agreeable day and time by webinar. An exit discussion will be held at the conclusion of the audit.
7.0 SPECIAL REQUESTS
The audit team would like access to the documents listed above in section 4.0 through an online portal that allows the audit team to access documents via the internet. Additional documents may be identified as the review progresses. The following conditions associated with the online portal must be maintained throughout the duration that the audit team has access to the online portal.
The online portal will be password-protected, and separate passwords will be assigned to the NRC staff who are participating in the audit.
The online portal will be sufficiently secure to prevent the NRC staff from printing, saving, downloading, or collecting any information on the online portal.
Conditions of use of the online portal will be displayed on the login screen and will require acknowledgement by each user.
Username and password information should be provided directly to the NRC staff. The NRC staff who should be granted access to the portal are those listed in the Audit Team section. All other communications should be coordinated with the NRC project man ager.
8.0 DELIVERABLES
An audit summary will be prepared within 90 days of the completion of the audit. If the NRC staff identifies information during the audit that is needed to support its regulatory decision, the staff will issue requests for additional information to the licensee after the completion of the audit.
ML24052A366 *concurrence via email OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA* NRR/DEX/ESEB/BC*
NAME MChawla PBlechman ISeng DATE 2/20/2024 2/22/2024 2/22/2024 OFFICE NRR/DORL/LPL/BC* NRR/DORL/LPL4/PM*
NAME JRankin MChawla DATE 2/23/2024 2/26/2024