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MONTHYEARML22306A0512022-10-27027 October 2022 Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) in Accordance with 10 CFR 50.82(a)(7), Revision 5 Project stage: Request ML23058A0642023-02-22022 February 2023 License Amendment Request - Three Mile Island, Unit 2, Historic and Cultural Resources Review Project stage: Request ML23121A2492023-05-0101 May 2023 License Amendment Request, Historic and Cultural Resources Review, Response to Request for Additional Information Project stage: Response to RAI ML23187A0332023-06-29029 June 2023 TMI Unit 2, PSDAR Rev. 5 RAIs Project stage: Other 2023-02-22
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Category:Legal-Affidavit
MONTHYEARML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications ML22194A9082022-07-13013 July 2022 NAC, Submittal of an Amendment Request for the NAC International Magnastor Cask System, Amendment No. 13 ML22138A2852022-05-16016 May 2022 (TMl-2) - License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Questions RS-22-044, Unit 1 - Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-03-31031 March 2022 Unit 1 - Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System ML21307A0542021-11-0202 November 2021 Annual Report - Guarantees of Payment of Deferred Premiums ML21272A2772021-09-29029 September 2021 Update to Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications ML21085A6922021-03-15015 March 2021 Plan for Management of Debris Material ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21057A0462021-02-19019 February 2021 License Amendment Request Decommissioning Technical Specifications NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML20310A1152020-11-0404 November 2020 Annual Report - Guarantees of Payment of Deferred Premiums ML20013E5352019-12-12012 December 2019 Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7) ML19318G1702019-11-14014 November 2019 2019 Annual Report - Guarantees of Payment of Deferred Premiums ML18316A0032018-11-0707 November 2018 Submittal of 2018 Annual Report - Guarantees of Payment of Deferred Premiums ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums RS-14-160, Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package2014-07-0202 July 2014 Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package RS-12-227, Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package2012-12-19019 December 2012 Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package ML1031904262010-11-0808 November 2010 Corp. - 2010 Annual Report - Guarantees of Payment of Deferred Premiums 2023-08-08
[Table view] Category:Letter
MONTHYEARML24038A0222024-02-0505 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 ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 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 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess 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 ML23137A2822023-05-17017 May 2023 (TMI-2), Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 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 ML23121A2492023-05-0101 May 2023 License Amendment Request, Historic and Cultural Resources Review, Response to Request for Additional Information ML23117A0012023-04-26026 April 2023 Commitment Revision Summary Report ML23027A0832023-04-24024 April 2023 Environmental Assessment/Finding of No Significant Impact - Request for Exemption from 10 CFR 70.24 ML23108A0802023-04-18018 April 2023 Annual Radiological Effluent Release Report ML23108A0822023-04-18018 April 2023 Annual Radiological Environmental Operating Report IR 05000320/20230012023-04-12012 April 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report No. 05000320/2023001 ML23102A0382023-04-10010 April 2023 Occupational Radiation Exposure Annual Report ML23108A2002023-04-10010 April 2023 CFR 20.2206(b) Personnel Radiation Exposure Report for 2022 ML23094A2582023-04-0606 April 2023 Letter to Sidney Hill, Chief, Onondaga Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0572023-04-0606 April 2023 Letter to Joanna Cain, President, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2362023-04-0606 April 2023 Letter to Carissa Speck, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2542023-04-0606 April 2023 Ltr J Bendremer Thpo Stockbridge-Munsee Community Band of Mohican Indians Re Initiation of Consultation Under Section 106 of the NHPA for Proposed License Amendment Request for TMI 2 ML23086C0652023-04-0606 April 2023 Ltr Larry Heady, Thpo, De. Tribe of Indian; Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI Nuclear Station, Unit 2 ML23093A0562023-04-0606 April 2023 Letter to Steve Minnick, Site Decommissioning Director, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2602023-04-0606 April 2023 Letter to William Tarrant, Seneca-Cayuga Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23094A2392023-04-0606 April 2023 Letter to Courtney Gerzetich, Thpo, Onedia Nation of Wisconsin, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0592023-04-0606 April 2023 Letter to Rebecca Countess, Chair, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 2024-02-05
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23090A2162023-03-30030 March 2023 Supplement to License Amendment Request - Proposed Changes to TMI-2 Possession Only License and Technical Specifications ML23058A0642023-02-22022 February 2023 License Amendment Request - Three Mile Island, Unit 2, Historic and Cultural Resources Review ML22313A0502022-11-0707 November 2022 License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Request for Information Regarding Radiation Protection Program Ventilation Controls ML22138A2852022-05-16016 May 2022 (TMl-2) - License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Questions ML22013A1772022-01-0707 January 2022 License Amendment Request - Three Mile Island, Unit 2, Decommissioning Technical Specifications, Supplemental Information ML22010A0672022-01-0505 January 2022 Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0001 Determination of the Safe Fuel Mass Limit for Decommissioning TMl-2 ML22010A0682022-01-0505 January 2022 Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0002 MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments 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 RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments 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 ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21057A0462021-02-19019 February 2021 License Amendment Request Decommissioning Technical Specifications ML20351A4512020-12-16016 December 2020 License Amendment Request, Proposed Revision to License Conditions and Permanently Defueled Technical Specifications for Permanent Removal of Irradiated Fuel from the Spent Fuel Pool (ISFSI-Only Tech Specs) ML20311A6572020-11-0404 November 2020 Supplemental Information Regarding License Amendment Request - Proposed Changes to the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition 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 ML19316C6592019-11-12012 November 2019 License Amendment Request - Deletion of Pots 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane; and Two Minor Administrative Changes 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-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 ML18283A1382018-10-10010 October 2018 Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition ML18206A5452018-07-25025 July 2018 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML18078A5782018-03-19019 March 2018 License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Post-Shutdown and Permanently Defueled Condition RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML17314A0242017-11-10010 November 2017 License Amendment Request: Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process ML17081A4252017-03-22022 March 2017 License Amendment Request-Administrative Changes to: Technical Specifications (TS) 5.4.2, Spent Fuel Pool Storage; TS 6.1.2; Chief Nuclear Officer Annual Management Directive for Control Room Command Function; and Ts.. ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16258A1912016-09-0808 September 2016 U.S. Dept. of Energy, License Amendment Request to Update the License Delegation of Authority for the Three Mile Island-2 Spent Fuel Storage Installation ML16201A1462016-07-15015 July 2016 License Amendment Request for Approval of Changes to the Three Mile Island Nuclear Station Emergency Plan Related to Staffing TMI-16-073, Attachment 3C - Fire Requiring Evaluation of the Control Room and Plant Shutdown from Remote Location, (Appendix R Fire)2016-07-15015 July 2016 Attachment 3C - Fire Requiring Evaluation of the Control Room and Plant Shutdown from Remote Location, (Appendix R Fire) TMI-15-086, Supplement to License Amendment Request - Temporary Restoration of Borated Water Storage Tank Cleanup and Recirculation Operation2015-07-28028 July 2015 Supplement to License Amendment Request - Temporary Restoration of Borated Water Storage Tank Cleanup and Recirculation Operation ML15204A8432015-07-23023 July 2015 License Amendment Request -Temporary Restoration of Borated Water Storage Tank Cleanup and Recirculation Operation ML14304A0832014-10-30030 October 2014 License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 82014-08-29029 August 2014 License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8 RA-14-032, License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2014-05-30030 May 2014 License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. ML14164A0542014-05-30030 May 2014 License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. NEI 99-01, License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2014-05-30030 May 2014 License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. RA-13-077, Company License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel2013-10-30030 October 2013 Company License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel TMI-13-033, Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report2013-04-10010 April 2013 Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report TMI-11-103, License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes2011-10-18018 October 2011 License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes TMI-10-080, Response to Request for Additional Information, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled2010-09-27027 September 2010 Response to Request for Additional Information, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves2010-09-24024 September 2010 Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves TMI-10-054, Technical Specifications Change Request (Tscr) No. 348 Relocation of Equipment Load List from TS 4.5.1.1 B, Sequence and Power Transfer Test, to the Updated Final Safety Analysis Report2010-09-22022 September 2010 Technical Specifications Change Request (Tscr) No. 348 Relocation of Equipment Load List from TS 4.5.1.1 B, Sequence and Power Transfer Test, to the Updated Final Safety Analysis Report TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2010-03-24024 March 2010 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML0932802342009-11-23023 November 2009 Request for Approval of the Exelon Cyber Security Plan ML0831201222008-11-0606 November 2008 License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification Using the Consolidated Line Item Improvement.. ML0828001742008-09-29029 September 2008 Technical Specification Change Request No. 342 Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods ML0827305202008-09-29029 September 2008 Supplement to License Amendment, Technical Specification Change Request No. 330 Deletion of Technical Specification Requirements for Review & Audit, & Additional Administrative Changes RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications 2023-03-30
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TMl-2 SOLUTIONS May 16, 2022 TMl2-RA-COR-2022-0013 10 CFR 50.90 10 CFR 2.390 10 CFR 50.91 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 2 (TMl-2)
NRC Possession Only License No. DPR 73 NRC Docket No. 50-320
Subject:
License Amendment Request- Three Mile Island, Unit 2, Decommissioning Technical Specifications, Response to Questions
References:
- 1) "TMl2 Accident Analyses Questions," dated February 7, 2022 (ML22038A936)
- 2) Letter TMl2-RA-COR-2022-0002, from Van Noordennen, G. P. (TMl-2 Solutions, LLC),
"License Amendment Request- Three Mile Island, Unit 2, Decommissioning Technical Specifications, Supplemental Information," dated January 7, 2022 (ML22013A177)
- 3) Letter TMl2-RA-COR-2022-0007, from Van Noordennen, G. P. (TMl-2 Solutions, LLC),
"License Amendment Request- Three Mile Island, Unit 2, Decommissioning Technical Specifications, Supplemental Information," dated April 8, 2022 Reference 1 requested additional information to aid in the review of potential events at TMl-2 described by Reference 2. Reference 3 committed to submit a revision of the GPU Nuclear Calculation Reactor Building Fire Analysis 4440-7380-90-017 by May '15, 2022. Via discussions with the NRC PM, this date was extended to May 16, 2022.
The amended responses to the TMl-2 Accident Analysis questions are provided as Attachment
- 1. A copy of the revised Reactor Building Fire Analysis is provided as Attachment 2. TMl-2 Solutions requests that this information be withheld from public disclosure pursuant to 10 CFR 2.390, as described in the Affidavit provided in Attachment 3.
TMl-2 Solutions requests review and approval of this proposed amendment by December 31, 2022, to allow for implementation prior to entering into Decommissioning which is scheduled.::._ SD}
to occur in January 2023. fJ H ~.I:..
A/)D f(J, Ni0>S
In accordance with 10 CFR 50.91 (7)(b)(1 ), a copy of this submittal has been sent to the Commonwealth of Pennsylvania.
There are no Regulatory Commitments contained in this submittal.
In the event that the NRC has any questions with respect to the content of this document or wishes to obtain any additional information, please contact me at 509-420-3078 or Mr. Tim Devik, TMl-2 Licensing Manager, at 603-384-0239.
Sincerely,
- ___ D1g11allys19nadbyM1chaelB M ch ae' I ,. -oN.,:c=_u_s, I l,admy'. -
CN_::Mlchoel 8_ Lackey, 1 , E11 m~Lilckey@emergysolut1ons com
'Reason:1iimtheauthorofthis B- La CkL' ey~~:: 0 1 n~ v1sion oa,e:2022-os-1s,4*s2:01 Mike LackeY FoKitPhantomPDFVorsion:9.7.0 Senior Vice President D&D Operations Energy Solutions Attachments:
- 1) Attachment 1 - Amended Response to Questions
- 2) Attachment 2 - "GPU Nuclear Calculation 4440-7380-90-017, Revision 4, PDMS SAR Section 8.2.5 Fire Analysis Source Terms" (PROPRIETARY)
- 3) Attachment 3 - 10 CFR 2.390 Proprietary Information Affidavit cc: w/Attachments Regional Administrator- NRC Region I NRC Lead Inspector- Three Mile Island Nuclear Station - Unit 2 NRC Project Manager- Three Mile Island Nuclear Station - Unit 2
TMl-2 Service List Ken Robuck Director, Bureau of Radiation Protection, President and CEO Department of Environmental Protection, Energy Solutions Commonwealth of Pennsylvania 299 South Main Street, Suite 1700 Rachel Carson State Office BLDG.
Salt Lake City, UT 84111 13TH Floor P.O. Box 8469 John Sauger Harrisburg, PA 17105-8469 President and Chief Nuclear Officer Reactor D&D Chief, Division of Nuclear Safety, Bureau Energy Solutions of Radiation Protection, 121 W. Trade Street, Suite 2700 Department of Environmental Protection, Charlotte, NC 28202 Commonwealth of Pennsylvania Rachael Carson State Office BLDG.
Mike Lackey 13TH Floor Senior Vice President P.O. BOX 8469 D&D Operations Harrisburg, PA 17105-8469 Energy Solutions 121 W. Trade Street, Suite 2700 Chairman, Board of County Charlotte, NC 28202 Commissioners, Dauphin County 112 Market Street Frank Helin 7th Floor Project Director Harrisburg, PA 17101 TMl-2 Solutions 121 W. Trade Street, Suite 2700 Trevor Orth Charlotte, NC 28202 Site Decommissioning Director Three Mile Island Generating Station Russ Workman Route 441 South General Counsel Middletown, PA 17057 Energy Solutions 299 South Main Street, Suite 1700 Craig Smith Salt Lake City, UT 84111 Site Decommissioning Regulatory Assurance Lead Daniel F. Stenger Three Mile Island Generation Station Hogan Lovells US LLP Route 441 South 555 13th St NW Middletown, PA 17057 Washington, D.C. 20004
Attachment 3 l,,i~ense Amendment Request Three Mile lslc1r1cl Nucle&1r Station, Unit 2 NRC Possession 'Only License No. DPR-73 1o CFR 2.390. Proprietary Information Affidavit TMl-2 SolutiQm~ Proprieqary informatic:m Affidavit Affidavit of Mike Lackey, Senior Vice President D&D Operations, EnergySolutions.
TMl-2 Solutions, LLC; contracted with Sargf:!nt & Lyndy respect to the preparation of the following document which is the property of TMl-2 Solutions, LLC, and Which is provided in support of this License Amendment Request:
"GPU Nuclear Calculation 4440-7380-90-017, Revision 4, PDMS .SAR Section 8.2.5 Fire Analysi$ Sourc~ Terrns" This document consists of proprietary information tnaJTMl-2 $olutions, I-LC considers confidential.
Release of this information would ca1.,1se irreparabie hann to the competithie position of TMl-2 Solutions, LJ;.¢. This.basis for this decla'ration is:
- I. This information is owned iand maint~in¢d a:$ propdetary l:!y TMI"'2 Solutions, LLC,
- 11. . Thi$ information is routinely held in confidence by TMl-2 Solutions, LLC, and not disclosed to the public.
Iii. This information is being requested to be held*in co.nfid~:mce by the NRG by this petition,
- Thls information is not available in public sources, This information would cause substantial harm to TMl-2 Solutions, LLC, if it were released publicly, and VI. The information to be withhel.d was transmiUed to the NRC in confidence.
I, Mike Lackey; being duly sworn, state that I am the person who subscribes my name tp the fQregoing statement, I am authorized to execute the Affidavit on behalf of TM!-2 Solutions, LL;C, and that the matters and facts set forth in the statement are true tp the be$t of my knowledge, information, and
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--"'- - raitPftanlmnPDFVaraion:9.7.D Mike Lackey * ***
Senior Vice President D&D Operations
- EnergySo/u(ions Sworn To And Subscribed Before Me This 16th Day of May, 2022 My Commission Expires 1/ece.Jl(-beY-
Attachment 1 License Amendment Request Three Mile Island Nuclear Station, Unit 2 NRC Possession Only License No. DPR-73 Amended Response to Questions TMl2 Accident Analyses Questions, Amended Responses
- 2) The reactor building fire appears to be most limiting of the currently analyzed scenarios. Is credit being taken for the reactor building or not? If the doors are open, would this analyzed scenario be most limiting?
The basic changes in the Reactor Building in going from PDMS to DEGON is removal of the Equipment Hatch, squaring off of the hole left from Equipment Hatch Removal, and installation of a barrier at the interface between the Reactor Building and the outside structure.
Credit is being taken for the Reactor Building as a passive radiological barrier to the extent that the door between the Reactor Building and the outside structure would only be open for the period of time necessary to allow passage of material or personnel between the two structures.
Additionally, during DEGON, other openings may be made in the containment structure.
Following good ALARA practices these openings will also include passive radiological barriers.
During normal operation, any air flow would be into containment due to operation of the Reactor Building Purge Exhaust System. In the unlikely event that a fire occurs while this interface door is open, it will be closed by personnel involved in the material transfer and/or entry into or exit from the Reactor Building. Additionally, as the Reactor Building Exhaust Ventilation would be operational at that time, the release would be through a filtered pathway.
If the Reactor Building Exhaust Ventilation is secured during repairs or maintenance, the interface door will be closed. Work in the Reactor Building may be allowed on a case-by-case basis as determined by RP Management and consistent with the TMl-2 Fire Protection Program.
This most limiting scenario, Reactor Building fire, is not based on any specific event. Its main purpose is to demonstrate that even if HEPA Filtration was bypassed, the event would not exceed 100 mrem to the maximally-exposed individual, the standard for declaring a Site Area Emergency at an operating nuclear power plant. Because of the concerns expressed in Question 5 below, the Reactor Building Fire scenario has been reanalyzed to '
demonstrate the additional margin that exists. The calculation incorporated a more appropriate fractional airborne release factor as used in NUREG/CR-0130.
Attachment 1 License Amendment Request Three Mile Island Nuclear Station, Unit 2 NRC Possession Only License No. DPR-73 Amended Response to Questions
- 5) References cite the source term uncertainty as plus or minus 50%. Given the 97 mrem dose result is very close to the 100 mrem limit, how has uncertainty in the source term been accounted for?
With respect to the current most limiting accident of the Reactor Building Fire on the Operations Level of the Reactor Building (305' and 347') the offsite whole-body dose is calculated taking credit for the HEPA filtration present in the Reactor Building Exhaust path and using the fractional airborne release factor of 1.SE-4 used in NUREG/CR-0130 rather than 1E-3 used by GPU Nuclear in its 2019 and earlier calculations. The Reactor Building ventilation will be running when active work is being performed. If secured for maintenance or other reasons, work will be limited to reduce the risk of an unfiltered release from the Reactor Building. Any Reactor Building work allowed when the Reactor Building ventilation is not in operation will be approved on a case-by-case basis as determined by RP Management. The calculated result of an offsite dose from a puff release without benefit of the HEPA filters is 14.6 mrem. Considering that the Reactor Building doors would be closed as described in the response to Question 2, the fire would be contained within the Reactor Building, and significant plate out would occur within the Reactor Building and the offsite dose would not approach 14.6 mrem. Additionally, as D&D progresses, the source term available for release is diminished through decontamination, dismantlement, packaging, and removal from the areas. These processes will be administratively controlled to further reduce the risk.
- 9) Please provide the reference "Reactor Building Fire Analysis."
The reference has been provided as Attachment 2.
- 10) It is good to establish limits (dose rate cutoffs) substantially below the regulations to allow for a factor of safety and account for uncertainties. NRC staff would like to be able to establish how those limits were derived.
The reanalysis of a Reactor Building Fire using a more realistic Airborne Release Fraction provides a substantial Safety Margin with a Factor of Safety of approximately 6.