Letter Sequence Meeting |
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MONTHYEARML0921200532009-08-0505 August 2009
Individual Plant Actions Pressurized-water Reactor Owners Group Topical Report BAW-2374, Revision 2, Risk-Informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor Coolant System.
Project stage: Other
TMI-09-105, Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 22009-09-0404 September 2009
Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 2
Project stage: Meeting
ML0930104552009-11-0303 November 2009
Once-Through Steam Generator Tube Loads Under Conditions Resulting from Postulated Breaks in Reactor Coolant System Upper Hot-Leg Large-Bore Piping
Project stage: Other
TMI-10-004, Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 22010-01-29029 January 2010
Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 2
Project stage: Other
2009-08-05
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Category:Letter type:TMI
MONTHYEARTMI-23-018, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
TMI-23-013, Radiological Emergency Plan Document Revision2023-05-30030 May 2023
Radiological Emergency Plan Document Revision
TMI-23-009, Submittal of Changes to Technical Specifications Bases2023-04-13013 April 2023
Submittal of Changes to Technical Specifications Bases
TMI-23-004, Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 12023-03-21021 March 2023
Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 1
TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023
Updated Spent Fuel Management Plan
TMI-23-002, Radiological Emergency Plan Document Revision2023-02-23023 February 2023
Radiological Emergency Plan Document Revision
TMI-22-028, Radiological Emergency Plan Document Revisions2022-09-27027 September 2022
Radiological Emergency Plan Document Revisions
TMI-22-016, 2021 Annual Radiological Effluent Release Report2022-04-25025 April 2022
2021 Annual Radiological Effluent Release Report
TMI-22-017, 2021 Annual Radiological Environmental Operating Report2022-04-25025 April 2022
2021 Annual Radiological Environmental Operating Report
TMI-22-018, 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20212022-04-19019 April 2022
10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2021
TMI-22-015, Submittal of Changes to Technical Specifications Bases2022-04-13013 April 2022
Submittal of Changes to Technical Specifications Bases
TMI-22-009, Registration of Use of Casks to Store Spent Fuel2022-03-0909 March 2022
Registration of Use of Casks to Store Spent Fuel
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
TMI-22-004, Registration of Use of Casks to Store Spent Fuel2022-02-0606 February 2022
Registration of Use of Casks to Store Spent Fuel
TMI-21-027, Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-08-30030 August 2021
Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme
TMI-21-024, 90-Day Notification Prior to First Storage of Spent Fuel2021-06-15015 June 2021
90-Day Notification Prior to First Storage of Spent Fuel
TMI-21-025, Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities2021-06-15015 June 2021
Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities
TMI-21-026, Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation2021-06-15015 June 2021
Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation
TMI-21-018, License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan2021-04-29029 April 2021
License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan
TMI-21-019, Submittal of 2020 Annual Radiological Environmental Operating Report2021-04-27027 April 2021
Submittal of 2020 Annual Radiological Environmental Operating Report
TMI-21-017, Submittal of 2020 Annual Radiological Effluent Release Report2021-04-27027 April 2021
Submittal of 2020 Annual Radiological Effluent Release Report
TMI-21-021, (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20202021-04-27027 April 2021
(TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2020
TMI-21-009, License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-03-0404 March 2021
License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme
TMI-20-027, Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License2020-10-0909 October 2020
Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License
TMI-20-026, Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation2020-09-15015 September 2020
Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation
TMI-20-025, Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report2020-07-16016 July 2020
Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report
TMI-20-021, Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative2020-07-0808 July 2020
Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative
TMI-20-015, 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report2020-04-30030 April 2020
2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report
TMI-20-016, 2019 Annual Radiological Environmental Operating Report2020-04-30030 April 2020
2019 Annual Radiological Environmental Operating Report
TMI-20-017, 2019 Annual Radiological Effluent Release Report2020-04-30030 April 2020
2019 Annual Radiological Effluent Release Report
TMI-20-012, Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases2020-04-13013 April 2020
Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases
TMI-20-002, Annual Notification of Property Insurance Coverage2020-03-25025 March 2020
Annual Notification of Property Insurance Coverage
TMI-20-006, Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7)2020-03-0202 March 2020
Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7)
TMI-19-112, Application for Order Approving License Transfer and Conforming License Amendments2019-11-12012 November 2019
Application for Order Approving License Transfer and Conforming License Amendments
TMI-19-097, License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-10-31031 October 2019
License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements
TMI-18-100, Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition2018-10-29029 October 2018
Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition
TMI-18-088, Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report2018-08-21021 August 2018
Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report
TMI-18-024, Biennial 10 CFR 50.59 and Pdms SAR Report2018-04-24024 April 2018
Biennial 10 CFR 50.59 and Pdms SAR Report
TMI-18-044, Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 292018-03-29029 March 2018
Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 29
TMI-18-004, Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 22018-03-16016 March 2018
Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 2
TMI-18-017, Annual Report2018-02-12012 February 2018
Annual Report
TMI-17-093, Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 252017-08-18018 August 2017
Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 25
TMI-17-060, Request for Approval of Certified Fuel Handler Training Program2017-07-10010 July 2017
Request for Approval of Certified Fuel Handler Training Program
TMI-17-051, Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 20132017-05-16016 May 2017
Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013
TMI-17-035, Submittal of Changes to Technical Specifications Bases2017-04-13013 April 2017
Submittal of Changes to Technical Specifications Bases
TMI-17-034, Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04)2017-03-31031 March 2017
Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04)
TMI-17-006, Decommissioning Funding Status Report2017-03-24024 March 2017
Decommissioning Funding Status Report
TMI-16-097, Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 172016-10-20020 October 2016
Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 17
TMI-16-082, Notice of Transfer of Transmission Asset2016-09-15015 September 2016
Notice of Transfer of Transmission Asset
TMI-16-091, Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-22016-09-0808 September 2016
Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-2
2023-05-30
[Table view] |
Text
Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348 TMI-09-105 September 4,2009 www.exeloncorp.com Nuclear U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No.DPR-50 NRC Docket No.50-289
Subject:
Three Mile Island Unit 1-Response to June 25, 2009, Public Meeting Between the U.S.Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG)Related to PWROG Topical Report BAW-2374, Revision 2.
References:
1.Letter from P.Bamford (U.S.Nuclear Regulatory Commission) to C.Pardee (Exelon Generation Company, LLC),"Three Mile Island, Unit No.1-Individual Plant Actions Re: Pressurized-Water Reactor Owners Group Topical Report BAW-2374, Revision 2,'Risk-Informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping'(T AC NO.ME1797)," dated August 5, 2009 2.NRC Summary of the June 25, 2009, Category 2 Public Meeting between the U.S.Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG)to discuss issues related to PWROG Topical Report BAW-2374, Revision 2, Risk-Informed Assessment of Once-Through Steam Generator Tube Thermal Loads due to Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping (TAC NO.MD7404), dated July 27,2009 On June 25, 2009, a public meeting was held between the U.S.Nuclear Regulatory Commission (NRC)staff and representatives of the Pressurized Water Reactor Owners Group (PWROG)at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland.The purpose of the meeting was to discuss issues related to PWROG Topical Report (TR)BAW-2374, Revision 2,"Risk-informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping." A meeting summary was published by the NRC for this meeting (Reference 2).In summary, the NRC meeting with the PWROG discussed Topical Report BAW-2374, Revision 2, and the ability of the affected steam generators (SGs)to withstandloadsfrom a postulated design basis hot leg Loss-of-Coolant Accident (LOCA)on a plant-specific basis.During the meeting, the NRC staff and PWROG agreed to a number of steps to bring this issue to resolution.
Pursuant to that agreement, the NRC issued a letter to Three Mile Island Unit 1 (TMI Unit 1)(Reference 1)requesting a written response to the list of actions taken from the meeting summary of the June 25, 2009, meeting (detailed in Reference 2)within 30 days.
u.s.Nuclear Regulatory Commission September 4, 2009 Page 2 In response, TMI Unit 1 is submitting this letter confirming the following information is applicable and factual with regards to TMI Unit 1.*The justification for continued operation for addressing tube integrity following a Large Break Loss-of-Coolant Accident (LBLOCA), based on Engineering Evaluation 00184675 dated June 14, 2000, remains valid.*Operator Actions (compensatory measures), including changes to emergency operating procedures, have been incorporated into plant procedures and operator training has been performed.
- 10 CFR 50.46 (a)(3)reporting requirements have been satisfied.
- All LBLOCAs (including those in the hot leg region)are considered as design basis accidents intheassessments of Steam Generator (SG)tube integrity following each SG tube inspection.
In addition to these statements, Exelon Generation Company, LLC (Exelon)makes the following two (2)new commitments involving TMI Unit1: 1.An analysis will be performed to confirm that the design of the replacement SGs is sufficient to withstand the loads associated with a LBLOCA including the thermal loads associated with a LBLOCA in the hot leg region of the reactor coolant system and the results of that analysis will be provided to the NRC by January 31, 2010.2.Provide the NRC with the structural Iimit(s)associated with the most limiting LBLOCA for the replacement SGs as part of the next SG tube inspection report (required by the technical specifications) following completion of the next inspection of the tubes in the replacement SGs, scheduled for June 30, 2012.These commitments are also identified in the Attachment to this letter.Should you have any questions concerning this letter, please contact Ms.Wendy Croft at (610)765-5726.Respectfully, Pamela B.Cowan Director-Licensing and Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Summary of Regulatory Commitments cc: S.J.Collins, Administrator, Region I, USNRC D.M.Kern, USNRC Senior Resident Inspector, TMI Unit 1 P.J.Bamford, USNRC Project Manager, TMI Unit 1 ATTACHMENT Three Mile Island Unit 1 Summary of Regulatory Commitments ATTACHMENT The following table identifies commitments made in this document.(Any other actions discussed in the submittal represent intended or planned actions.They are described to the NRC for the NRC's information and are not regulatory commitments.)
COMMITTED COMMITMENT TYPE COMMITMENT DATE OR One-Time Action Programmatic 1I0UTAGEII (Yes/No)(Yes/No)An analysis will be performed to confirm that January 31, 2010 Yes No the design of the replacement SGs is sufficient to withstand the loads associated with a LBLOCA including the thermal loads associated with a LBLOCA in the hot leg region of the reactor coolant system and the results of that analysis will be provided to the NRC.Provide the NRC with the structurallimit(s)
June 30, 2012 Yes No associated with the most limiting LBLOCA for the replacement SGs as part of the next SG tube inspection report (required by the technical specifications) following completionofthe next inspectionofthe tubes in the replacement SGs.Page 1 of 1
