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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 50.46 TMI-13-150 October 10, 2013 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 - 10 CFR 50.46 30-Day Report
References:
- 1) Letter from M. D. Jesse (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 30-Day Report,"
dated March 21, 2012
- 2) Letter from P. Bamford (U.S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 (TAC NO. ME8237),"
dated November 13, 2012
- 3) Letter from P. Salas (AREVA NP Inc.) to U.S. Nuclear Regulatory Commission, "Generic RAI Response to a 30-Day 10 CFR 50.46 Report of Significant PCT Change," dated December 6, 2012
- 4) Letter from M. D. Jesse (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information - 10 CFR 50.46 30-Day Report," dated December 12, 2012
- 5) Letter from P. Bamford (U.S. Nuclear Regulatory Commission) to M. J. Pacifio (Exelon Generation Company, LLC), "Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 (TAC NO. ME8237),"
dated March 5, 2013
Response to Request for Additional Information 10 CFR 50.46 30~Day Report October 10, 2013 Page 2
- 6) Letter from P. Salas (AREVA NP Inc.) to U.S. Nuclear Regulatory Commission, "Generic RAI Response to a 30~Day 50.46 Report of Significant PCT Change," dated March 28, 2013
- 7) Letter from M. D. Jesse (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information - 10 CFR 50.46 30-Day Report," dated April 2, 2013
- 8) Internal Memorandum from R. Ennis (Senior Project Manager, U.S.
Nuclear Regulatory Commission) to V. Rodriguez (Acting Chief, U.S.
Nuclear Regulatory Commission), "Three Mile Island Nuclear Station, Unit 1, Draft Request for Additional Information (TAC NO. ME8237),"
ML13253A225, dated September 10, 2013 In the Reference 1 letter Exelon Generation Company, LLC (Exelon) submitted a 30-day 10 CFR 50.46 report for Three Mile Island Nuclear Station (TMI), Unit 1. This letter discussed an AREVA NP Inc. (AREVA) notification concerning two Evaluation Model (EM) error corrections. In the Reference 2 and 5 letters the U.S. Nuclear Regulatory Commission requested additional information. References 3, 4, 6, and 7 provided the responses to these requests.
In Reference 8, the U.S. Nuclear Regulatory Commission requested additional information.
Attached is our response.
No new regulatory commitments are established in this submittal. If any additional information is needed, please contact Tom Loomis at (610) 765-5510.
Respectfully, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information - 10 CFR 50.46 30-Day Report cc: USNRC Administrator, Region I USNRC Project Manager, TMI, Unit 1 USNRC Senior Resident Inspector, TMI, Unit 1
Attachment Response to Request for Additional Information - 10 CFR 50.46 aa-Day Report
Response to Request for Additional Information 10 CFR 50.46 30~Day Report October 10, 2013 Page 1 Question:
The RAJ response does not include a proposed schedule for providing a reanalysis. In the response, the licensee states that the PCT error evaluations are supported by explicit analyses using the Babcock and Wilcox (B&W) plant emergency core cooling system (ECCS) evaluation model. Since a schedule for reanalysis was not provided, justify how generic analysis for the B&W plant ECCS evaluation model constitutes "taking other action" to show compliance with 10 CFR 50.46. In particular, while the submitted RAI response addresses the acceptance criteria contained in 10 CFR 50.46(b), the response does not address the requirement, in 10 CFR 50.46(a)(1 )(i), to calculate ECCS cooling performance "in accordance with an acceptable evaluation model." In light of the presently reported, significant, estimated effects of errors and changes, explain how the present ECCS cooling performance has been calculated in accordance with an acceptable evaluation model, such that any other action, as provided in 10 CFR 50.46(a)(3), has been taken to show compliance with 10 CFR 50.46 requirements, including those contained in 10 CFR 50.46(a)(1). Alternatively, submit a schedule for providing a reanalysis or taking other action as may be necessary to show compliance with 10 CFR 50.46 requirements.
Response
The evaluation that supports the 201210 CFR 50.46 LOCA Report for B&W Plants denotes other actions taken to show compliance with 10 CFR 50.46 requirements. The evaluation demonstrated the requirements of 10 CFR 50, Appendix K for a conservative model were fully met based on a reported estimated net zero change in peak clad temperature (PCT).
The evaluation concluded the actual net PCT would decrease; therefore, the existing model results remain conservative and acceptable. As the reported net PCT did not change, local oxidation and whole core hydrogen generation from the original model are unaffected and remain in compliance. In addition, the coolable core geometry and long-term cooling impacts remain unchanged and fully meet 10 CFR 50.46(b) requirements. ECCS cooling performance was calculated with errors corrected and this result comes from an acceptable evaluation model that complies with 10 CFR 50.46(a)(1 )(i) and 50.46(a)(1 )(ii). The analytical technique used approximates realistically the behavior of the reactor system during a loss-of-coolant accident. As such, there is a high level of probability that the criteria will not be exceeded.
In lieu of submitting a proposed schedule for providing a reanalysis, the actions already taken as described above are considered sufficient to satisfy the intent of 10 CFR 50.46(a)(3)(ii), specifically, "or taking other action as may be needed to show compliance with § 50.46 requirements."
