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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
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10 CFR 50.55a TMI-11-030 March 9, 2011 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No.DPR-50 NRC Docket No.50-289
Subject:
Response to Request for Additional Information
-Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds
References:
1)Letter from P.B.Cowan (Exelon Generation Company, LLC)to U.S.Nuclear Regulatory Commission,"Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds," dated September 30, 2010 2)Letter from P.Bamford (U.S.Nuclear Regulatory Commission) to M.J.Pacilio,"Three Mile Island Nuclear Station, Unit 1 Request for Additional Information Regarding Relief Request RR-10-02, Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds (TAC NO.ME4795)," dated February 28,2011 In the Reference 1 letter, Exelon Generation Company, LLC(Exelon)requested relief to perform a weld overlay of pressurizer spray nozzle to safe-end and safe-end to elbow dissimilar metal welds at Three Mile Island Nuclear Station (TMI), Unit 1.In the Reference 2 letter, the U.S.Nuclear Regulatory Commission requested additional information.
Attached is our response to questions 2, 3 and 4.As discussed in Reference 2, the response to question 1 will be provided by April 28, 2011.There are no regulatory commitments contained in this submittal.
If you have any questions conceming this letter, please contact Tom Loomis at (610)765-5510.Respectfully, David P.Helker Manager-Licensing Exelon Generation Company, LLC Response to Request for Additional Information Relief Request RR-10-02 Concerning the Weld Overlay of Dissimilar Metal Welds March 9, 2011 Page 2
Attachment:
Response to Request for Additional Information
-Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle toEnd and Safe-End to Elbow Dissimilar Metal Welds cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI USNRC Project Manager,[TMI]USNRC ATTACHMENT Response to Request for Additional Information
-Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds Response to Request for Additional Information Relief Request RR*10*02 Concerning the Weld Overlay of Dissimilar Metal Welds March 9, 2011 Page 1 of 2 Question: 2.In section 5 of RR*10-02 (page 4, fourth paragraph) the licensee states that weld preheat and heat input are monitored through the use of calibrated contact pyrometers or thermocouples.
Please clarify exactly which instrument, contact pyrometer or thermocouples, will be used.If thermocouples will be used, please identify what steps will be taken to ensure that the temperature reading will be accurate and discuss whether the use of the thermocouples will satisfy subarticles IWA*4610(a) and IWA-4624.1 (d)of the American Society of Mechanical Engineers Boiler and Pressure VesselCode,Section XI, 2004 edition.Response: Weld preheat and heat input will be monitored through the use of a calibrated contact pyrometer.
Thermocouples will not be used during the installation of the weld overlay.Question: 3.On page 5 of RR-10-02, the licensee states that it intends to install one or more weld barrier layer(s)to prevent hot cracking in stainless steel materials similar to that installed during the 2007 weld overlays.The staff notes that some licensees have reported cracking in the weld overlay during and after the installation on Alloy 82/182 welds and stainless steel pipes.Please discuss any measures that will be taken to minimize potential cracking in addition to the barrier layer(s).Response: Exelon Generation Company, LLC (Exelon)and the implementation vendor are aware of the hot cracking that was observed when welding Alloy 52M over a buffer layer that had been applied on cast stainless steel during weld overlay installations at other plants in 2009 and 2010.In order to minimize the potential for cracking during installation of the pressurizer spray nozzle weld overlay at TMI, Unit 1, appropriate criteria and parameters have been established for control of the welding process.As an example, the welding heat input"power ratio" range has been determined to minimize weld metal contamination from the existing plant materials.Theoverlay design includes no welding on cast stainless steel material, as only wrought materials are involved.Additionally, the wrought base material chemistries (from the Certified Material Test Report data)and weld geometry will be reviewed to determine the level of risk for hot cracking when welding Alloy 52M over stainless steel base material.This review will result in the specific mitigation efforts that will be employed during the installation of the weld overlay.Weld parameters and techniques specially developed for welding over stainless steel and Alloy 82/182 welds will be implemented to prevent cracking.Question: 4.Section 6 of RR-10-02 states that the duration of the proposed alternative associated with the weld overlay is the remaining service life ofthecomponents, including future plant life extension.
It does not identify any difference in the duration of the proposed alternative between the design of the overlay, and the aspects of the request that relate to subsequent inservice examinations.
Examination techniques may be improved in the future beyond what is Response to Request for Additional Information Relief Request RR-10-02 Concerning the Weld Overlay of Dissimilar Metal Welds March 9, 2011 Page 2 of 2 specified in the relief request Also, emergent issues could impact what future examination requirements may be appropriate.
Therefore, the staff requests that the application be changed or clarified such that the examination aspects of the proposed alternative apply only to the fourth 10-year inservice inspection interval.Alternatively, please justify why the proposed duration for future inservice examinations is acceptable.
Response: The design and installation of the structural weld overlay are applicable to the remaining service life of the plant As discussed in Section 5 of the relief request: "Subsequent inservice examinations will be scheduled and performed in accordance with the requirements of Nonmandatory Appendix Q or alternate schedules accepted by the NRC (for example adoption of ASME Code Case N-770 as proposed by 75FR24324)." In summary, TMI, Unit 1 will perform the fourth ten-year lSI interval examinations as described above.Subsequent lSI interval examinations will be performed in accordance with NRC requirements applicable to the interval.