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Category:Letter
MONTHYEARIR 07200077/20240012024-06-18018 June 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 07200077/2024001 ML24157A3672024-06-13013 June 2024 Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter ML24135A1972024-06-13013 June 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0091 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24120A3242024-05-24024 May 2024 TMI-2 Email to Fws RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24120A2552024-04-29029 April 2024 Annual Radiological Environmental Operating Report ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24113A0212024-04-18018 April 2024 (TMI-2), Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24065A0042024-03-28028 March 2024 Submittal of 2023 Aircraft Movement Data Annual Report ML24092A0012024-03-28028 March 2024 (TMI-2), Decommissioning Trust Fund Annual Report ML24088A0122024-03-28028 March 2024 Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) in Accordance with 10 CFR 50.82(a)(7), Revision 6 ML24085A2152024-03-25025 March 2024 (TMI-2) - Annual Notification of Property Insurance Coverage RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24052A0602024-03-20020 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0061 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24074A3922024-03-14014 March 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML24075A0062024-03-14014 March 2024 List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24044A0092024-02-12012 February 2024 License Amendment Request – Three Mile Island, Unit 2, Historic and Cultural Resources Review, Response to Request for Additional Information IR 05000320/20230042024-02-0707 February 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023004 ML24038A0222024-02-0505 February 2024 Achp Letter on Section 106 Programmatic Agreement Participation IR 05000289/20230062024-01-29029 January 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006 ML23342A1242024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23325A1092024-01-0505 January 2024 Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000320/20230032023-11-28028 November 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003 ML23243A9082023-08-29029 August 2023 Shpo Letter to TMI-2 Regarding Section 106 Activities IR 05000320/20230022023-08-17017 August 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23200A1882023-07-31031 July 2023 TMI-2 Correction Letter Amendment 67 ML23209A7632023-07-28028 July 2023 Letter from PA Shpo to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning ML23192A8272023-07-10010 July 2023 TMI-2 Solutions, LLC - Response to Shpo Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23167A0312023-06-28028 June 2023 Acceptance Review and Schedule for the Request for Exemption from a Requirement from 10 CFR 20, Appendix G, Section Iii.E, EPID L-2023-LLE-0016 ML23171B0222023-06-19019 June 2023 (TMI-2) - Notification Pursuant to 10 CFR 72.140(d) Regarding Application of Previously Approved TMI-2 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 ML23137A2822023-05-17017 May 2023 (TMI-2), Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23026A3132023-05-0202 May 2023 Issuance of Exemption from 10 CFR 70.24 (EPID-L-2023-LLE-0003) ML23122A1842023-05-0101 May 2023 Shpo_Er_Summary_Letter 2024-06-03
[Table view] Category:Report
MONTHYEARML23073A3982023-03-31031 March 2023 TMI-2 ISFSI Biennial Update Report for 2023 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan ML22335A4632022-12-0101 December 2022 Chronology of Significant Events in Operator Licensing Since the Three Mile Island Accident (1979) ML22101A0792022-03-23023 March 2022 TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 ML22105A0932021-12-16016 December 2021 Attachment 3 - RSCS Technical Support Document (Tsd) No. 21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG ML21236A2882021-08-10010 August 2021 TMI-2 Pdms SAR Update 14 & QA Plan (Rev 18 & 19) Biennial Submittal 08-10-21 ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications ML21084A2292021-03-17017 March 2021 Notification of Amended Post-Shutdown Decommissioning Activities Report Accordance with 10 CFR 50.82(a)(7), Revision 4 ML21085A6922021-03-15015 March 2021 Plan for Management of Debris Material ML21056A0052021-02-25025 February 2021 2020 Aircraft Movement Data Annual Report ML21133A2652021-02-0101 February 2021 Calculation TMI2-EN-RPT-0002, Revision 0, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library ML18107A2152018-04-10010 April 2018 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2016 and 2017 ML17289A0532017-10-15015 October 2017 Case Study Overview ML17165A4092017-06-14014 June 2017 T1R22 Refuel Outage MRP-227-A Reactor Internals Scope Deferral Review RS-16-104, Mitigating Strategies Flood Hazard Assessment Submittal2016-06-29029 June 2016 Mitigating Strategies Flood Hazard Assessment Submittal RS-16-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-06-29029 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15306A5032015-12-17017 December 2015 Closure Evaluation for Report Pursuant to 10 CFR 50.46 Requirements Related to Thermal Conductivity Degradation ML15223A2152015-08-14014 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights TMI-15-076, Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue2015-06-22022 June 2015 Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue ML15043A1442015-02-13013 February 2015 Review of Steam Generator Tube Inspection Report for Fall 2013 Outage ML14297A4112014-12-19019 December 2014 Letter and Non-Proprietary Safety Evaluation of Reactor Vessel Internals Inspection Plan RS-14-301, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14163A0242014-06-10010 June 2014 Response to Request for Additional Information - Review of the Cycle 20 Core Operating Limits Report ML14189A2852014-04-30030 April 2014 Topical Report 213, 40th Year Reactor Building Tendon Surveillance (Period 10), (Rev 0) ML14189A2862014-04-17017 April 2014 Final Report for the 40th Year (10th Period) Tendon Surveillance at Three Mile Island, Unit 1 TMI-14-053, Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 20132014-04-16016 April 2014 Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 2013 ML13225A5522013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6712013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Three Mile Island, Unit 1, TAC MF0803 ML14189A2872013-11-12012 November 2013 TMI 40TH Year Tendon Surveillance, Tendon No. 1-146-34, Tendon End Buddress 4 TMI-14-061, 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs)2013-09-0303 September 2013 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs) TMI-13-107, Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 20132013-08-31031 August 2013 Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 2013 ML13232A2172013-07-31031 July 2013 Attachment 2 - Areva Document No. ANP-3102, Revision 3,Three-Mile Island Unit 1 Appendix G Pressure-Temperature Limits at 50.2 EFPY with Mur, Revision 3, Dated July 2013 TMI-13-041, Post-Shutdown Decommissioning Activities Report Submittal2013-06-28028 June 2013 Post-Shutdown Decommissioning Activities Report Submittal TMI-12-148, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-022013-05-16016 May 2013 Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12362A0422012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-1 Through Page C-161 ML12362A0432012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-162 Through Page C-284 2023-03-31
[Table view] Category:Technical
MONTHYEARML23073A3982023-03-31031 March 2023 TMI-2 ISFSI Biennial Update Report for 2023 ML22101A0792022-03-23023 March 2022 TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning ML22105A0932021-12-16016 December 2021 Attachment 3 - RSCS Technical Support Document (Tsd) No. 21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG ML21236A2882021-08-10010 August 2021 TMI-2 Pdms SAR Update 14 & QA Plan (Rev 18 & 19) Biennial Submittal 08-10-21 ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications ML21084A2292021-03-17017 March 2021 Notification of Amended Post-Shutdown Decommissioning Activities Report Accordance with 10 CFR 50.82(a)(7), Revision 4 ML21133A2652021-02-0101 February 2021 Calculation TMI2-EN-RPT-0002, Revision 0, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library RS-16-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-06-29029 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14189A2852014-04-30030 April 2014 Topical Report 213, 40th Year Reactor Building Tendon Surveillance (Period 10), (Rev 0) ML14189A2862014-04-17017 April 2014 Final Report for the 40th Year (10th Period) Tendon Surveillance at Three Mile Island, Unit 1 ML13225A5522013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6712013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Three Mile Island, Unit 1, TAC MF0803 ML14189A2872013-11-12012 November 2013 TMI 40TH Year Tendon Surveillance, Tendon No. 1-146-34, Tendon End Buddress 4 TMI-14-061, 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs)2013-09-0303 September 2013 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs) TMI-13-107, Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 20132013-08-31031 August 2013 Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 2013 ML13232A2172013-07-31031 July 2013 Attachment 2 - Areva Document No. ANP-3102, Revision 3,Three-Mile Island Unit 1 Appendix G Pressure-Temperature Limits at 50.2 EFPY with Mur, Revision 3, Dated July 2013 ML12362A0422012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-1 Through Page C-161 ML12362A0432012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-162 Through Page C-284 TMI-12-161, Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page D-1 Through End2012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page D-1 Through End RS-12-175, Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Cover Through Page B-2092012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Cover Through Page B-209 ML0932208672009-10-27027 October 2009 VVR-042181- l-COIL, Rev 0, Verification and Validation Report for Square D Masterpact Circuit Breaker (Coils Only), Attachment 4 ML0924001762009-08-16016 August 2009 VVR-042181-1, Rev 8, Verification and Validation Report for Square D Masterpact Circuit Breaker (Including the Micrologic Trip Unit). ML0932208662009-08-0707 August 2009 FAT-REPORT-6910327-1, Rev 0, Factory Acceptance Testing Report on Square-D PZ4 Rx Trip Switchgear, Attachment 3 ML1119202582009-07-31031 July 2009 Facility Cpp Report (Final) - Structural Inspection of Horizontal Storage Modules Pad ML0932208652009-05-0606 May 2009 QR-06910327-1, Rev 0, Qualification Report for Square Reactor Trip Switchgear for Three Mile Island, Attachment 2 ML0932208682009-05-0505 May 2009 QR-042181-5, Rev 1, Emi/Rfi Qualification Report for Masterpact Circuit Breaker Shunt Trip and Undervoltage Trip, Attachment 5 ML0911706302009-02-11011 February 2009 Rev. 0 to E16-1555-011, Decommissioning Cost Analysis for Three Mile Island, Unit 1. ML0828803012008-10-14014 October 2008 TMI-1 SEIS Nonradiological Waste Web References ML0825601782008-09-10010 September 2008 Response to NRC Request for Additional Information Related to Three Mile Island Nuclear Station, Unit 1, License Renewal Application ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0805103822008-03-27027 March 2008 NRC Staff Questions Reformatted Into Three Topical Areas ML0805103672008-03-27027 March 2008 NRC Staff Questions for October 31, 2007 Phone Call with Alion ML0805106572008-02-11011 February 2008 NRC Staff Questions with Problem Statements ML0802304852008-01-14014 January 2008 Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report ML0802304842008-01-14014 January 2008 Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier ML0529403472005-10-14014 October 2005 Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria ML0525704522005-08-22022 August 2005 (TMI-2), Update 6 of the Post-Defueling Monitored Storage Safety Analysis Report ML0513006242005-05-0303 May 2005 Draft ECR #02-01121, Rev. 2, Inspection Acceptance Criteria and Leakage Assessment Methodology for TMI OTSG Kinetic Expansion Examinations. ML0828807322005-03-31031 March 2005 SEIS Ch. 8 Air Quality Web References, Technical Support Document ML0507702652005-03-15015 March 2005 PSC Precision Surveillance Corporation, Thirtieth Year Surveillance of the Post-Tensioning System at the Three Mile Island Unit 1 Containment Building, 2004, Volume II of III ML0507702542005-03-15015 March 2005 PSC Precision Surveillance Corporation, 30th Year Surveillance of the Post-Tensioning System at the Three Mile Island Unit 1 Containment Building, 2004, Volume I of III ML0507702712005-03-15015 March 2005 PSC Precision Surveillance Corporation, Thirtieth Year Surveillance of the Post-Tensioning System at the Three Mile Island Unit 1 Containment Building, 2004, Volume III of III ML0505600372005-02-0808 February 2005 12-5023272-01, Risk Assessment for Alternate STS End States. ML0411704032004-04-15015 April 2004 Biennial 10 CFR 50.59 and Commitment Revision Report for 2002 and 2003 ML0326601322003-08-0707 August 2003 Update 5 of the Post-Defueling Monitored Storage Safety Analysis Report ML0305902192003-02-15015 February 2003 Long Range Planning Program (Lrpp) Annual Update of Integrated Schedule ABC Project Listing ML0228405032002-10-0404 October 2002 Additional Information Regarding Kinetic Expansion Inspection & Repair Criteria ML0228307072002-09-30030 September 2002 License Amendment Request No. 318 Integrated Leak Rate Test Deferral 2023-03-31
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AmerGenSM AmerGen Energy Company. LLC Telephone: 717-948-8000 An Exelon Company Three Mile Island Unit 1 Route 441 South, PO. Box 480 Middletown, PA 17057 April 15, 2004 5928-04-20105 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 THREE MILE ISLAND UNIT I (TMI UNIT 1)
OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
SUBJECT:
BIENNIAL 10 CFR 50.59 AND COMMITMENT REVISION REPORT FOR 2002 AND 2003 Enclosed are the 2002-2003 Biennial 10 CFR 50.59 and Commitment Revision Report as required by 10 CFR 50.59 (d)(2) and SECY-00-0045 (NEI 99-04).
There are no regulatory commitments contained in this transmittal.
If you have any questions or require additional information, please contact John Tesmer, of Regulatory Assurance, at 717-948-8477.
Sincerely, George H. Gellrich Plant Manager GHG/awm Enclosure cc: Administrator, Region I TMI-1 Senior Resident Inspector File 04080 a-w LC7
THREE MILE ISLAND UNIT 1 DOCKET NO. 50-298 BIENNIAL 10CFR 50.59 AND COMMITMENT REVISION REPORT TABLE OF CONTENTS 10CFR 50.59 Report 3 Modifications 4 Procedure Changes 5 Commitment Revision Report 11 2
AMERGEN ENERGY THREE MILE ISLAND UNIT I DOCKET NO. 50-289 BIENNIAL 10CFR 50.59 REPORT JANUARY 1, 2002 THROUGH DECEMBER 31, 2003 10CFR50.59 EVALUATION SUMMARIES 3
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report Modifications
Title:
CW Chemical Addition System Improvements (ECR 02-01070)
Year Implemented: 2002 Evaluation Number: SE-000564-001 Brief
Description:
Installation of Circulating Water Chemical Treatment Summary of Evaluation:
A new modification was implemented to allow injection of a different type of chemical treatment into the Circulating Water system to control MIC (Microbiologically Induced Corrosion), growth of slime on equipment and piping surfaces, and eliminate bacteria and algae. The treatment uses four chemicals, NaOCI (sodium hypochlorite), Sodium Bromide, AEC, and HPS-1 in addition to H2SO4 (Sulfuric Acid). NaOCI is the chemical that is the source for chlorine to help kill the bacteria and algae.
The chemical addition system is not safety related or required for safe shutdown of the plant. The chemicals, each by themselves, do not pose a hazard. The mixing of NaOCI and H2SO4 forms the biocide chlorine. This could potentially affect control room habitability and thus is the item of concern.
Generation of chlorine, by design within the CW system is not an issue. The chemicals, NaOCI and H2SO4, are physically separated by the biocide storage building (for H2SO4) and the containment (for NaOCI). The two structures were designed to provide physical separation to prevent uncontrolled mixing of the chemicals. The piping to transfer the NaOCI to the mixing eductor is double wall CPVC pipe to minimize the potential for leakage to the environment. The NaOCI and H2SO4 piping systems are physically separated from each other and drain paths are designed to minimize the potential for the mixing of these chemicals from pipe failure.
Warnings and procedure verifications were implemented to prevent the potential mixing of these chemicals. In addition, signs were posted at the tanks and connections to warn of these hazards.
The activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR:
4
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report The activity does not result in more than a minimal increase in the consequence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the consequence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The activity does not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. The activity does not create the possibility of a malfunction of an SSC important to safety with a different result than any previously evaluated in the UFSAR. The proposed activity does not result in a design basis limit for fission product barrier as described in the UFSAR being exceeded or altered. This is not a change to a method of evaluation.
Procedure Changes
Title:
Interim procedure change for Manual control of RC Pump Seal Injection flow.
Year Implemented: 2002 Evaluation Number: SE-945100-388 Brief
Description:
An interim change to TMI-1 Operations procedure for manual control of seal injection during troubleshooting of the hand-auto station.
Summary of Evaluation:
Makeup valve MU-V-32 provides control for Reactor Coolant Pump Seal injection. Automatic control of the valve became erratic in November 2002.
Automatic control of seal injection is described in FSAR section 9.1.2.1. The remaining analysis in FSAR Section 9 does not depend on this condition. The activity was to operate the seal injection system in manual during troubleshooting and repair (a maintenance activity).
Manual seal injection control was determined to be adequate because alarms and indications were available, there were no protective interlocks to be defeated, instrument qualification requirements were not affected, and no new instruments that were not qualified to function in the environmental conditions were introduced. Errors in manual control were determined to not be irreversible.
The adjustments that might be required could be made with minimum manning during an emergency condition. Manual control of seal injection was described in plant procedures.
The activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.
The activity does not result in more than a minimal increase in the consequence 5
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the consequence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The activity does not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. The activity does not create the possibility of a malfunction of an SSC important to safety with a different result than any previously evaluated in the UFSAR. The proposed activity does not result in a design basis limit for fission product barrier as described in the UFSAR being exceeded or altered. This is not a change to a method of evaluation.
Title:
Material Non-Conformance T2003-0002, associated procedure change Year Implemented: 2003 Evaluation Number: MNCR T2003-0002 Brief
Description:
An interim change to TMI-1 Operations procedure for isolating of the Reactor Coolant Inventory Tracking System.
Summary of Evaluation:
On January 23, 2003, a leak was discovered near RC-V-1 197. The 50.59 evaluation evaluated continued plant power operations with RC-V-1 196 and 1197 closed. The valves were closed to reduce the RCS leakage into the RB atmosphere. The evaluation for conditional release addresses the following issues:
- The closing of these valves rendering both channels of the RCITS System inoperable.
. The closing of RC-V-1 196 and RC-V-1 197 potentially compromises the ability to prevent pressure locking from occurring on DH-V-1, DH-V-2, and the piping between the two valves.
The RCITS system is one of several means that is available to be used by Operators in the event of a large break LOCA or the maximum hypothetical accident to monitor the water inventory of the Reactor Coolant System. The system is not credited in the UFSAR as being a sole or required source of information upon which Operators should base or take accident mitigation actions.
TS 3.24 states that if both channels of the RCITS system are inoperable and at least one channel cannot be restored within 7 days, details of the condition shall 6.
2002-2003 Biennial iOCFR 50.59 and Commitment Revision Report be provided in the Monthly Operating Report including cause, action being taken and projected date for the return of the system to an operable status.
The activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.
The activity does not result in more than a minimal increase in the consequence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the consequence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The activity does not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. The activity does not create the possibility of a malfunction of an SSC important to safety with a different result than any previously evaluated in the UFSAR. The proposed activity does not result in a design basis limit for fission product barrier as described in the UFSAR being exceeded or altered. This is not a change to a method of evaluation.
Title:
RPS Testing with Channel A in Bypass Year Implemented: 2003 Evaluation Number: SE-000641-034 Brief
Description:
A procedure change to TMI-1 Surveillance procedure to allow RPS testing of a differential pressure transmitter used for Reactor Coolant System Flow.
Summary of Evaluation:
RC14A-DPT1 ("A" Loop RCS flow to the "A" RPS Cabinet) drifted high. Over a period of several hours on 2/20/03, the flow signal increased from about 71 Mlbm/hr to 73 Mlbm/hr. The drift was in the non-conservative direction. As a conservative measure, A RPS cabinet was declared inoperable and Channel A was placed in manual bypass.
TMI-A Technical Specification requires periodic surveillance testing of RPS Channels and Power Range Nuclear Instrument calibration. The surveillance test normally places the channel under test in Manual Bypass and substitutes test signals for the normal channel inputs. Channel A will be tested with A Channel in Manual Bypass. Channel B, C or D, RPS will be tested with the associated channel Tripped while Channel A remains in Manual Bypass. Tripping the channel under test while Channel A is in Bypass complies with Tech Spec Table 3.5-1 since two channels will be operable and one is tripped. Degree of redundancy of one is met with the channel under test in a tripped status. Testing 7
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report the channel while it is in the Tripped status does not affect the validity of the test.
All the features are fully tested in accordance with Technical Specification Table 4.1-1.
The activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.
The activity does not result in more than a minimal increase in the consequence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the consequence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The activity does not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. The activity does not create the possibility of a malfunction of an SSC important to safety with a different result than any previously evaluated in the UFSAR. The proposed activity does not result in a design basis limit for fission product barrier as described in the UFSAR being exceeded or altered. This is not a change to a method of evaluation.
Title:
Procedure to Troubleshoot RC14A-DPT1 Drift Year Implemented: 2003 Evaluation Number: SE-000641-035 Brief
Description:
A procedure change to TMI-1 Operations procedure to allow troubleshooting of a differential pressure transmitter used for Reactor Coolant System Flow.
Summary of Evaluation:
RC14A-DPT1 ("A" Loop RCS flow to the "A" RPS Cabinet) drifted high: Over a period of several hours on 2/20/03, the flow signal increased from about 71 Mlbm/hr to 73 Mlbm/hr. The drift was in the non-conservative direction. As a conservative measure, A RPS cabinet was declared inoperable and Channel A was placed in manual bypass.
Troubleshooting the affected channel with that channel in Manual Bypass and another channel in a Tripped condition does not affect the validity of the maintenance, nor does it conflict with the UFSAR description. The system was designed to perform the testing while the channel is in bypass to reduce the risk of tripping the reactor. Performing a maintenance activity on a RPS channel while the channel is tripped meets the Tech Spec Surveillance requirement and does not cause undue risk of a reactor trip.
8
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report This procedure change does not increase the frequency of occurrence of an accident previously evaluated in the UFSAR since the requirements of the LCO are met and the ability of the Reactor Protection System to respond to a valid condition are not compromised. Since the degree of redundancy requirement is met the consequences of equipment failure in other channels meets the assumptions in the UFSAR.
The activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.
The activity does not result in more than a minimal increase in the consequence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the consequence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The activity does not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. The activity does not create the possibility of a malfunction of an SSC important to safety with a different result than any previously evaluated in the UFSAR. The proposed activity does not result in a design basis limit for fission product barrier as described in the UFSAR being exceeded or altered. This is not a change to a method of evaluation.
Title:
Procedure Changes for RPS Testing with RPS Channel B in Manual Bypass due to NI-6 input declared inoperable Year Implemented: 2003 Evaluation Number: SE-000623-004 Brief
Description:
A procedure change to TMI-1 Surveillance procedure to allow testing while 'B' channel of RPS is in manual bypass.
Summary of Evaluation:
On March 18th 2003, spiking was observed on NI-6 from its nominal 100%
reading to slightly above 101 % reactor power. Another nuclear instrument was selected for ICS control and RPS Channel B was tripped to maintain a degree of redundancy of one. TMI-1 Technical Specifications require periodic surveillance testing of RPS channels and Power Range Nuclear Instrumentation calibration.
The surveillance test normally places the channel under test in Manual Bypass and substitutes test signals for the normal channel inputs. RPS Channel B will be tested with the channel in Manual Bypass. RPS Channels A, C and D will be tested with the channel tripped while RPS Channel B remains in Manual Bypass.
Tripping the channel under test while RPS Channel B is in Manual Bypass 9
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report complies with Technical Specification 3.5-1 since two channels will be operable and one is tripped. Degree of Redundancy of One is met with the channel under test in a tripped status. Testing the channel while it is in the tripped status does not affect the validity of the test. All features are fully tested in accordance with Technical Specification able 4.1-1.
The activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.
The activity does not result in more than a minimal increase in the consequence of an accident previously evaluated in the UFSAR. The activity does not result in more than a minimal increase in the consequence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The activity does not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. The activity does not create the possibility of a malfunction of an SSC important to safety with a different result than any previously evaluated in the UFSAR. The proposed activity does not result in a design basis limit for fission product barrier as described in the UFSAR being exceeded or altered. This is not a change to a method of evaluation.
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2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report AMERGEN ENERGY THREE MILE ISLAND UNIT I DOCKET NO 50-289 BIENNIAL COMMITMENT REVISION REPORT JANUARY 1, 2002 THROUGH DECEMBER 31, 2003 11
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report Letter Source: LER 98-010-00 Exelon Tracking No.: 1920-98-20496.002 Nature of Commitment: Adjust alarm setpoint for grid low voltage during single transformer operation.
Summary of Justification:
TMI replaced the Unit Auxiliary Transformers during the TI R14 refueling outage in October 2001. These GE Prolec Auxiliary Transformers have load tap changers that allow voltage control on the 4160-volt Class I E busses. Calculation C-I 101-700-E51 0-010 was revised in December 2001 with 'as-tested' impedance values.
The revised calculation has removed restrictions on low grid voltage from single transformer operation.
Letter Source: NUREG 0680, IEB 79-05A ITEM 4 Exelon Tracking No.: 1980T0075 Nature of Commitment: Re-verify plant conditions using alternate indications Summary of Justification:
Commitments were made for NUREG 0680 concerning Emergency Operating Procedure event mitigation strategies in 1980. TMI subsequently committed in 1989 to prepare and maintain the Emergency Operating procedures in accordance with the B&W owners group GEOG Technical Basis Document (TBD). Commitment was made per correspondence 5450-89-0103 (Exelon tracking number 1989T0014). As a result, commitments made per NUREG 0680 have been superceded by the commitment to the TBD.
Letter Source: NUREG 0680, IEB 79-05C ITEM 5 Exelon Tracking No.: 1980T0078 Nature of Commitment: B&W Small Break Operating Guidelines Summary of Justification:
Commitments were made for NUREG 0680 concerning Emergency Operating Procedure event mitigation strategies in 1980. TMI subsequently committed in 1989 to prepare and maintain the Emergency Operating procedures in 12
2002-2003 Biennial 10CFR 50.59 and Commitment Revision Report accordance with the B&W owners group GEOG Technical Basis Document (TBD). Commitment was made per correspondence 5450-89-0103 (Exelon tracking number 1989T0014). As a result, commitments made per NUREG 0680 have been superceded by the commitment to the TBD.
Letter Source: TMI Inspection Report IR 84-06 Exelon Tracking No.: 1984T0083 Nature of Commitment: Set load tap changers to meet requirement of Degraded Grid analysis Summary of Justification:
TMI committed to the NRC (within the inspection report) to change taps on the Auxiliary Transformers UATIA and UATIB from 230 kV to 224.25 kV during power operations. TMI replaced the Unit Auxiliary Transformers during the TI R14 refueling outage in October 2001. These GE Prolec Auxiliary Transformers have load tap changers that allow voltage control on the 4160-volt Class I E busses.
Calculation C-1 101 -700-E51 0-010 was revised in December 2001 with 'as-tested' impedance values. The load tap changers no longer require setting of manual taps during power operation. As a result, this is a historical commitment.
Letter Source: NUREG 0737 I.D.1 Exelon Tracking No.: 1984T0106 Nature of Commitment: Throttling of building spray flow Summary of Justification:
Commitments were made for NUREG 0737 to satisfy building spray NPSH requirements. Procedure 1210-7 was changed to reduce the runout limit of 1800 gpm to a value of 1750 gpm. In November 2001, TMI replaced the Building Spray flow orifice to maintain flow <1750 GPM with modification ECR TM 01-00406. Operator manual throttling of building spray is no longer required, and this portion of the commitment is historical.
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2002-2003 Biennial IOCFR 50.59 and Commitment Revision Report Letter Source: NUREG 0737 III.D.3.4 Exelon Tracking No.: 1987T0064 Nature of Commitment: Control Room Habitability Damper And Fan Ops Summary of Justification:
Commitments were made for NUREG 0737 to satisfy control building habitability requirements. To maintain a positive pressure in the control room, operators were required to take manual control of damper AH-D-39 on a single failure of damper AH-D-28. In 2000, TMI implemented modifications MD-J007-001 and MD-J007-002. These modifications removed the single failure vulnerability of AH-D-28.
AH-D-39 became a manual damper. As a result, operator action to position damper AH-D-39 is no longer required to maintain a positive pressure.
End of Commitment Revision Report 14