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MONTHYEARTMI-12-183, Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds2012-12-14014 December 2012 Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds Project stage: Other TMI-13-020, Supplemental Information - Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds2013-01-31031 January 2013 Supplemental Information - Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds Project stage: Supplement ML13193A1452013-07-12012 July 2013 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values (TAC Nos. MF0425 & MF0426) Project stage: Draft RAI ML13193A1752013-07-22022 July 2013 Request for Additional Information Regarding Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values Project stage: RAI ML13324A0862013-12-13013 December 2013 Exemption from Certain Requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61, for Initial RTNDT Values for Linde 80 Welds Project stage: Approval ML13324A0892013-12-13013 December 2013 Company LLC; Three Mile Nuclear Station, Unit 1 Regarding Exemption from Portions of 10 CFR Part 50, Appendix G Project stage: Approval 2013-12-13
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Category:Exemption from NRC Requirements
MONTHYEARML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation TMI-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 ML23167A4632023-07-0505 July 2023 TMI-2S Exemption Appendix G ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23137A2822023-05-17017 May 2023 (TMI-2), Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23026A2332023-05-0202 May 2023 Exemption from 10 CFR 70.24 ML23027A0832023-04-24024 April 2023 Environmental Assessment/Finding of No Significant Impact - Request for Exemption from 10 CFR 70.24 ML23094A2692023-04-20020 April 2023 Safety Evaluation - Exemption from 10 CFR 70.24 ML22271A9752022-10-31031 October 2022 Notice of Partial Exemption and Conforming Amendment from Certain Record Keeping Requirements, Docket No. 50-320 ML22196A3952022-09-16016 September 2022 Enclosure 1 - Three Mile Island, Unit 2 - Partial Exemptions and Conforming Amendment from Certain Record Retention Requirements ML22167A0592022-06-16016 June 2022 Acceptance and Review Schedule Request Regarding Partial Exemption from Certain Record Retention Requirements ML22126A1432022-06-0808 June 2022 Letter to D. Rhoades from A. Snyder - TMI Unit 1 - Exemption - Use of Decommissioning Trust Fund for Site Restoration ML22126A1442022-06-0808 June 2022 Enclosure - Exemption RS-22-062, Supplemental Information to Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-26026 April 2022 Supplemental Information to Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System ML21354A0272021-12-15015 December 2021 Supplemental Letter to Three Mile Island Nuclear Station, Unit 2 (TMl-2) - Request for Exemption from Record Retention Requirements ML21279A2782021-10-0505 October 2021 (TMl-2) - Request for Exemption from Record Retention Requirements ML21063A2812021-03-22022 March 2021 Enclosure - TMI-1 Onsite Exemption ML21040A2692021-03-0909 March 2021 TMI-1 Offsite Indemnity Agreement Revision Letter ML21040A2702021-03-0909 March 2021 Enclosure 1 - TMI Offsite Exemption ML20244A2942020-12-0101 December 2020 L-2019-LLE-0016 Notice of Issuance of Exemption (2020-08-27) ML20244A2932020-12-0101 December 2020 L-2019-LLE-0016 Exemption (2020-08-27) NMP1L3362, Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency2020-11-13013 November 2020 Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency ML20237F3372020-09-17017 September 2020 Environmental Assessment and Finding of No Significant Impact Related to Request for Exemptions from Certain Emergency Planning Requirements ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20161A3912020-06-30030 June 2020 Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel (EPID L-2020-LLE-0096 (COVID-19)) ML20107J6762020-05-21021 May 2020 Federal Register Notice with Partial Exemption from Certain Retention Requirements ML20107J6982020-05-19019 May 2020 Partial Exemption from Certain Record Retention Requirements ML20107J6482020-05-19019 May 2020 Cover Letter with Partial Exemption from Certain Record Retention Requirements ML20003E0962020-01-0303 January 2020 Request for Exemptions from 10 CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance ML19227A0342019-10-0909 October 2019 FRN - Three Mile Island Nuclear Station, Unit 1 -Finding of No Significant Impact with the Associated Environmental Assessment Related to the Use of the Decommissioning Trust Fund for Irradiated Fuel Management ML19211C0092019-07-22022 July 2019 Shutdown Decommissioning Activities Report ML19193A0052019-07-12012 July 2019 Request for Exemption from Record Retention Requirements ML19182A1042019-07-0101 July 2019 Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E ML19102A0852019-04-12012 April 2019 Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) ML13324A0862013-12-13013 December 2013 Exemption from Certain Requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61, for Initial RTNDT Values for Linde 80 Welds NRC-2010-0221, FRN: General Notice, Three Mile Island Nuclear Station, Unit 1 - Request for Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements2010-06-28028 June 2010 FRN: General Notice, Three Mile Island Nuclear Station, Unit 1 - Request for Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements ML1013101212010-06-28028 June 2010 FRN: General Notice, Three Mile Island Nuclear Station, Unit 1 - Request for Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements ML1013101132010-06-28028 June 2010 Letter, Request for Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements TMI-10-023, Response to Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability2010-03-15015 March 2010 Response to Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability ML0908307082009-03-30030 March 2009 Request for Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements ML0614302462006-06-27027 June 2006 TMI and Zion - Exemption from the Requirements of 10 CFR 50.54(a)(3) Re Submittal of Changes to Quality Assurance Topical Report ML0135404352002-02-0808 February 2002 Exemption the Hydrogen Control Requirement of 10 CFR Part 50, Section 50.44, 10 CFR Part 50, Appendix a, General Design Criteria 41 and 10 CFR Part 50, Appendix E, Section VI (Tac No MB0065) 2023-07-05
[Table view] Category:Federal Register Notice
MONTHYEARML23108A1422023-06-26026 June 2023 Federal Register Notice Criticality Monitoring Exemption Issuance ML23026A2332023-05-0202 May 2023 Exemption from 10 CFR 70.24 ML22271A9752022-10-31031 October 2022 Notice of Partial Exemption and Conforming Amendment from Certain Record Keeping Requirements, Docket No. 50-320 ML22199A2772022-07-15015 July 2022 E-mail Attachment: Federal Register Notice - Volume 87 ML22173A1052022-06-23023 June 2022 Federal Register Notice: Three Mile Island, Unit 2 - Physical Security Plan Amendment Request ML22126A1512022-06-0909 June 2022 FRN Three Mile Island Unit 1 - Exemption ML22126A0612022-06-0101 June 2022 FRN -Constellation Energy Generation, LLC; Three Mile Island Station, Unit 1 ML22068A1682021-07-0606 July 2021 Attachment - Federal Register/Vol. 86, No. 126/Tuesday, July 6, 2021/Notices ML21145A0152021-05-26026 May 2021 FRN Exelon License Transfer - Extend Comment Period ML21145A0142021-05-26026 May 2021 Fleet and the Associated Independent Spent Fuel Storage Installations - Extension of Comment Period for Notice of Consideration of Approval of Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing EPID L-2021-L ML21102A0752021-04-28028 April 2021 Fleet - Notice of Consideration of Approval of Transfer of Licenses and Conforming Amendments and Opportunity for a Hearing (FRN) ML22068A1802021-04-20020 April 2021 Attachment ML21089A255 Federal Register/Vol. 86, No. 74/Tuesday, April 20, 2021/Notices ML21063A3162021-03-0909 March 2021 TMI-1 Onsite Indemnity FRN ML21062A2332021-03-0909 March 2021 Offsite Exemption FRN ML22068A1472021-01-26026 January 2021 Attachment - Federal Register/Vol. 86, No. 15/Tuesday, January 26, 2021/Notices ML20244A2942020-12-0101 December 2020 L-2019-LLE-0016 Notice of Issuance of Exemption (2020-08-27) ML20244A2932020-12-0101 December 2020 L-2019-LLE-0016 Exemption (2020-08-27) ML20237F3382020-09-17017 September 2020 L-2019-LLE-0016 TMI1 EP Exemption EA ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20107J6762020-05-21021 May 2020 Federal Register Notice with Partial Exemption from Certain Retention Requirements ML19259A1822019-10-17017 October 2019 Exemptions from the Requirements of 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) (EPID L-2019-LLE-0009) (Federal Register Notice) ML19227A0342019-10-0909 October 2019 FRN - Three Mile Island Nuclear Station, Unit 1 -Finding of No Significant Impact with the Associated Environmental Assessment Related to the Use of the Decommissioning Trust Fund for Irradiated Fuel Management ML19122A2882019-09-10010 September 2019 Federal Register Notice for TMI Unit 2 Independent Spent Fuel Storage Installation and Finding of No Significant Impact ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19213A0662019-08-14014 August 2019 FRN-Three Mile Island Nuclear Station, Unit 1 - Withdrawal Amendment Notice ML19213A0692019-08-14014 August 2019 Withdrawal of an Amendment Request ML19213A0062019-08-13013 August 2019 FRN Notice for Withdrawal of Tendon Amendment ML19176A0072019-07-0808 July 2019 FRN-Three Mile Island Nuclear Station, Unit 1 - Post-Shutdown Decommissioning Activities Report ML19176A4322019-07-0303 July 2019 Notification of the Availability of the Post-Shutdown Decommissioning Activities Report in the Federal Register ML18180A2182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML17115A4622017-06-14014 June 2017 Federal Register Notice - Environmental Assessment and Finding of No Significant Impact; Issuance NRC-2016-0161, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 20162016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16215A2272016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 NRC-2015-0204, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 20152015-08-21021 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 2015 ML15231A8382015-08-21021 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - September 1, 2015 ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 NRC-2015-0185, Federal Register Notice for License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene2015-07-30030 July 2015 Federal Register Notice for License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene ML15208A1202015-07-30030 July 2015 Federal Register Notice for License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene ML15208A3192015-07-30030 July 2015 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 NRC-2014-0917, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 20142014-09-0505 September 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 2014 ML14247A1542014-09-0505 September 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 2014 NRC-2014-0193, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 20142014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 ML14233A2082014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 ML13324A0892013-12-13013 December 2013 Company LLC; Three Mile Nuclear Station, Unit 1 Regarding Exemption from Portions of 10 CFR Part 50, Appendix G ML13324A0862013-12-13013 December 2013 Exemption from Certain Requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61, for Initial RTNDT Values for Linde 80 Welds NRC-2013-0274, Exelon Generation Company LLC; Three Mile Nuclear Station, Unit 1 Regarding Exemption from Portions of 10 CFR Part 50, Appendix G2013-12-13013 December 2013 Exelon Generation Company LLC; Three Mile Nuclear Station, Unit 1 Regarding Exemption from Portions of 10 CFR Part 50, Appendix G ML13294A0392013-11-0707 November 2013 Notice of Consideration of Approval of Transfer of Renewed Facility Operating Licenses and Conforming Amendments,.. ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit 2023-06-26
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 13, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR PART 50, APPENDIX G AND 10 CFR 50.61, FOR INITIAL RTNorVALUES FOR LINDE 80 WELDS (TAC NO. MF0425)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission has approved the enclosed exemption from certain requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix G and 10 CFR 50.61, for Three Mile Island Nuclear Station, Unit 1 (TMI-1 ). This action is in response to your application dated December 14, 2012, as supplemented by letters dated January 31, 2013, and August 13, 2013, which requested an exemption from portions of the requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61, to allow the use of an alternate methodology to evaluate the integrity of the TMI-1 Linde 80 weld materials in the TMI-1 reactor pressure vessel beltline.
A copy of the exemption is enclosed. The exemption has been forwarded to the Office of the Federal Register for publication.
Sin~fJ~
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
Exemption cc w/encl: Distribution via Listserv
____ _____ _J_75_~0_-Q_1-PJ _____
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-289; NRC-2013-XXXX]
Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1; Exemption
1.0 BACKGROUND
Exelon Generation Company, LLC (Exelon, the licensee) is the holder of Renewed Facility Operating License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station, Unit 1 (TMI-1 ). The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect.
The facility consists of a single pressurized-water reactor located in Dauphin County, Pennsylvania.
2.0 REQUEST/ACTION Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix G, "Fracture Toughness Requirements," specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light water nuclear power reactors to provide adequate margins of safety during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime. Section 50.61, "Fracture toughness requirements for protection against pressurized thermal shock [PTS] events,"
provides fracture toughness requirements for protection against PTS events. By letter dated December 14, 2012, (Agencywide Documents Access and Management System (ADAMS)
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Accession No. ML12353A319), as supplemented by letters dated January 31, 2013, and August 13, 2013, (ADAMS Accession Nos. ML13032A312 and ML13232A214, respectively), Exelon proposed exemptions from portions of the requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61, to revise certain TMI-1 reactor pressure vessel (RPV) initial (unirradiated) properties using AREVA Non-Proprietary Topical Report (TR) BAW-2308, Revisions 1A and 2A, "Initial RTNoT [nil-ductility reference temperature] of Linde 80 Weld Materials."
The licensee requested an exemption from portions of 10 CFR Part 50, Appendix G, to replace the required use of the existing Charpy V-notch (Cv) and drop weight-based methodology and allow the use of an alternate methodology to incorporate the use of fracture toughness test data for evaluating the integrity of the TMI-1 Linde 80 weld materials in the RPV beltline. This request for exemption is based on the use of the 1997 and 2002 editions of American Society for Testing and Materials (ASTM) Standard Test MethodE 1921 (ASTM E 1921 ), "Standard Test Method for Determination of Reference Temperature T0 , for Ferritic Steels in the Transition Range," and American Society for Mechanical Engineering (ASME),
Boiler and Pressure Vessel Code (Code), Code Case N-629, "Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials, Section Ill, Division 1, Class 1." Specifically, 10 CFR 50, Appendix G(II)(D)(i), requires that the nil-ductility reference temperature (RT NoT) be evaluated according to the procedures in the ASME Code, Section Ill, Division 1, "Rules for Construction of Nuclear Power Plant Components," Paragraph NB-2331, "Material for Vessels." These procedures require the use of a methodology based on drop weight tests (NB-2331(a)(1)) and Cv test data (NB-2331(a)(2)). In addition, 10 CFR Part 50, Appendix G,(I)(A) requires the use of methods equivalent to Appendix G to ASME Section XI, Division 1, "Rules for lnservice Inspection of Nuclear Power Plant Components," which specifies
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the use of values that have been determined using Cv and drop weight tests described above.
Therefore, an exemption from portions of 10 CFR Part 50, Appendix G, is required.
The licensee also requested an exemption from portions of 10 CFR 50.61 to use an alternate methodology to allow the use of fracture toughness test data for evaluating the integrity of the TM 1-1 RPV Linde 80 beltline welds based on the use of the 1997 and 2002 editions of ASTM E 1921 and ASME Code Case N-629. Similar to the above, 10 CFR 50.61 (a)(5) requires that the initial (unirradiated) RTNoT. be evaluated according to the procedures in the ASME Code, Section Ill, Division 1, Paragraph NB-2331. As stated previously, these procedures require the use of a methodology based on drop weight tests (NB-2331 (a)(1)) and Cv test data (NB-2331 (a)(2)). Therefore, the exemption is required since the methodology for evaluating RPV material fracture toughness in 10 CFR 50.61 requires the use of the Cv and drop weight data to determine the initial RT NOT for establishing the PTS reference temperature (RT PTs).
3.0 DISCUSSION Pursuant to 10 CFR 50.12(a), the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when: (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) special circumstances are present. The special circumstance that applies to these exemptions is consistent with 10 CFR 50.12(a)(2)(ii) in that the application of the regulations in this circumstance is not necessary to achieve the underlying purpose of the rules. This special circumstance allows the licensee an exemption from the use of the Cv and drop weight-based methodology required by 10 CFR Part 50, Appendix G and 10 CFR 50.61. These exemptions
only modify the methodology to be used by the licensee for demonstrating compliance with the requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61, and do not exempt the licensee from meeting any other requirement of 10 CFR Part 50, Appendix G and 10 CFR 50.61.
Authorized by Law These exemptions would allow the licensee to use an alternate methodology to make use of fracture toughness test data for evaluating the integrity of the TMI-1 RPV Linde 80 beltline materials, and would not result in changes to operation of the plant. Section 50.60(b) of 10 CFR allows the use of proposed alternatives to the described requirements in 10 CFR Part 50, Appendix G, or portions thereof, when an exemption is granted by the Commission under 10 CFR 50.12. As stated above, 10 CFR 50.12(a) allows the NRC to grant exemptions from portions of the requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61. The NRC staff has determined that granting of the licensee's proposed exemptions will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission's regulations. Therefore, the exemptions are authorized by law.
No Undue Risk to Public Health and Safety The underlying purpose of Appendix G to 10 CFR Part 50 is to set forth fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light water nuclear power reactors to provide adequate margins of safety during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime. The methodology underlying the requirements of Appendix G to 10 CFR Part 50 is based on the use of Cv and drop weight data because of reference to the ASME Code, as previously described. The licensee proposes to replace the use of the existing Cv and drop
weight-based methodology by a fracture toughness-based methodology to demonstrate compliance with Appendix G to 10 CFR Part 50.
The NRC staff has concluded that the requested exemption to Appendix G to 10 CFR Part 50 is justified based on the licensee utilizing the fracture toughness methodology specified in TR BAW-2308, Revisions 1A and 2A, within the conditions and limitations delineated in the NRC staff's safety evaluations (SEs), dated August 4, 2005, and March 24, 2008 (ADAMS Accession Nos. ML052070408 and ML080770349, respectively). The use of the methodology specified in the NRC staff's SEs will ensure that pressure-temperature limits developed for the TMI-1 RPV will continue to be based on an adequately conservative estimate of RPV material properties and ensure that the pressure-retaining components of the reactor coolant pressure boundary retain adequate margins of safety during any condition of normal operation, including anticipated operational occurrences. This exemption only modifies the methodology to be used by the licensee for demonstrating compliance with the requirements of 10 CFR Part 50, Appendix G(II){D)(i) and 10 CFR Part 50, Appendix G(I)(A), and does not exempt the licensee from meeting any other requirement of Appendix G to 10 CFR Part 50.
Based on the above information, no new accident precursors are created by allowing an exemption from the use of the existing Cv and drop weight-based methodology and the use of an alternative fracture toughness-based methodology to demonstrate compliance with Appendix G to 10 CFR Part 50; thus, the probability of postulated accidents is not increased. Also, based on the above information, the consequences of postulated accidents are not increased.
Therefore, there is no undue risk to public health and safety associated with the proposed exemption to Appendix G to 10 CFR Part 50.
The underlying purpose of 10 CFR 50.61 is to establish requirements for evaluating the fracture toughness of RPV materials to ensure that a licensee's RPV will be protected from
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failure during a PTS event. The licensee seeks an exemption from portions of 10 CFR 50.61 to use a methodology for the determination of adjusted/indexing reference temperatures. The licensee proposes to use ASME Code Case N-629 and the methodology outlined in its submittal, which are based on the use of fracture toughness data, as an alternative to the Cv and drop weight-based methodology required by 10 CFR 50.61 for establishing the initial, unirradiated properties when calculating RT PTs values. The NRC staff has concluded that the exemption is justified based on the licensee utilizing the methodology specified in the NRC staff's SEs regarding TR BAW-2308, Revisions 1A and 2A, dated August 4, 2005, and March 24, 2008, respectively. This TR established an alternative method for determining initial (unirradiated) material reference temperatures for RPV welds manufactured using Linde 80 weld flux (i.e., "Linde 80 welds") and established weld wire heat-specific and Linde 80 weld generic values of this reference temperature. These weld wire heat-specific and Linde 80 weld generic values may be used in lieu of the RTNOT parameter, the determination of which is specified by paragraph NB-2331 of Section Ill of the ASME Code. Regulations associated with the determination of RPV material properties involving protection of the RPV from brittle failure or ductile rupture include Appendix G to 10 CFR Part 50 and 10 CFR 50.61, the PTS rule.
These regulations require that the initial (unirradiated) material reference temperature, RT NoT.
be determined in accordance with the provisions of the ASME Code, and provide the process for determination of RTPTs. the reference temperature RT NoT. evaluated for the end of license neutron fluence.
In TR BAW-2308, Revision 1, the Babcock and Wilcox Owners Group proposed to perform fracture toughness testing based on the application of the Master Curve evaluation procedure, which permits data obtained from sample sets tested at different temperatures to be combined, as the basis for redefining the initial (unirradiated) material properties of Linde 80
welds. The NRC staff evaluated this methodology for determining Linde 80 weld initial (unirradiated) material properties and uncertainty in those properties, as well as the overall method for combining unirradiated material property measurements based on T0 (initial temperature) values (i.e., initial, unirradiated nil-ductility reference temperature (IRTro)), with property shifts from models in Regulatory Guide (RG) 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," which are based on Cv testing and a defined margin term to account for uncertainties in the NRC staff SE. Table 3 in the staff's SE of BAW-2308, Revision 1, dated August 4, 2005, contains the NRC staff-accepted IRTTo and initial margin (denoted as o;) for specific Linde 80 weld wire heat numbers.
In accordance with the limitations and conditions outlined in the NRC staff's SE of TR BAW-2308, Revision 1, dated August 4, 2005, for utilizing the values in Table 3: ( 1) the licensee has utilized the appropriate NRC staff-accepted IRTTo and O; values for applicable Linde 80 weld wire heat numbers; (2) applied chemistry factors greater than 16rF (the weld wire heat-specific chemical composition, via the methodology of RG 1.99, Revision 2, indicated that chemistry factors higher than 16rF are applicable); (3) applied a value of 28°F for Ot:. (i.e, shift margin) in the margin term; and (4) submitted values for .!lRTNDT and the margin term for each Linde 80 weld in the RPV through the end of the current operating license. Additionally, the NRC's SE for TR BAW-2308, Revision 2, concludes that the revised IRTro and O; values for Linde 80 weld materials are acceptable for referencing in plant-specific licensing applications as delineated in TR BAW-2308, Revision 2, and to the extent specified under Section 4.0, "Limitations and Conditions," of the SE, which states: "Future plant-specific applications for RPVs containing weld wire heat 72105, and weld wire heat 299L44, of Linde 80 welds must use the revised IRTTo and o;, values in TR BAW-2308, Revision 2." The TMI-1 RPV beltline lower nozzle belt to upper shell circumferential weld contains weld heat 72105. The following TMI-1
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RPV beltline welds contain weld heat 299L44: lower shell longitudinal weld (inner diameter 37 percent), and upper shell to lower shell circumferential weld. The licensee used the staff-accepted IRTro and oi values for Linde 80 weld materials containing weld wire heats 299L44 and 72105. The NRC staff concludes that all conditions and limitations outlined in the NRC staff SEs for TR BAW-2308, Revisions 1A and 2A, have been met for TMI-1.
The use of the methodology in TR BAW-2308, Revisions 1A and 2A, will ensure the PTS evaluation developed for the TMI-1 RPV will continue to be based on an adequately conservative estimate of RPV material properties and ensure the RPV will be protected from failure during a PTS event. The NRC staff's SEs dated August 4, 2005, and March 24, 2008, stipulate that licensees utilize the fracture toughness methodology, specified in TR BAW-2308, Revisions 1A and 2A, within the conditions and limitations delineated in theSEs.
Based on the above information, no new accident precursors are created by allowing an exemption to use an alternate methodology to comply with the requirements of 10 CFR 50.61 in determining adjusted/indexing reference temperatures; thus, the probability of postulated accidents is not increased. Also, based on the above information, the consequences of postulated accidents are not increased. Therefore, there is no undue risk to public health and safety.
Consistent with Common Defense and Security The proposed exemptions would allow the licensee to use alternate methodologies from those specified in 10 CFR Part 50, Appendix G, and 10 CFR 50.61, to allow the use of fracture
_toughness test data for evaluating the integrity of the TMI-1 RPV beltline welds. This change has no relation to security issues. Therefore, the common defense and security is not impacted by these exemptions.
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Special Circumstances Special circumstances, in accordance with 10 CFR 50.12( a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR Part 50, Appendix G and 10 CFR 50.61 is to protect the integrity of the reactor coolant pressure boundary by ensuring that each RPV material has adequate fracture toughness. Therefore, since the underlying purpose of 10 CFR Part 50, Appendix G and 10 CFR 50.61 is achieved by an alternative methodology for evaluating RPV material fracture toughness, the special circumstances required by 10 CFR 50(a)(2)(ii) for the granting of an exemption from portions of the requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61 exist.
4.0 ENVIRONMENTAL CONSIDERATION
The exemptions would authorize exemptions from portions of the requirements of 10 CFR Part 50, Appendix G and 10 CFR 50.61 to allow the licensee to use an alternate methodology to incorporate fracture toughness test data for evaluating the integrity of the TMI-1 Linde 80 weld materials in the TMI-1 RPV beltline based on the use of the 1997 and 2002 editions of ASTM E 1921 and ASME Code Case N-629. Using the standard set forth in 10 CFR 50.92 for amendments to operating licenses, the NRC staff determined that the subject exemptions sought involve use of an alternate methodology to evaluate the integrity of the TMl-1 RPV Linde 80 beltline materials. The NRC has determined that these exemptions involve no significant hazards considerations:
( 1) The proposed exemptions are limited to allowing the licensee to use an alternative to the Cv and drop weight-based methodology required by 10 CFR Part 50, Appendix G and 10 CFR 50.61 to evaluate the integrity of the TMI-1 Linde 80 weld materials in the TMI-1 RPV
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beltline. The alternate methodology does not involve any physical changes to the facility and does not alter the design, function or operation of any plant equipment. Therefore, issuance of this exemption does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) The proposed exemption does not make any changes to the facility and would not create any new accident initiators. Therefore, this exemption does not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) The proposed exemption does not alter the design, function or operation of any plant equipment. Therefore, this exemption does not involve a significant reduction in a margin of safety.
Based on the above, the NRC has concluded that the proposed exemptions do not involve significant hazards considerations under the standards set forth in 10 CFR 50.92, and accordingly, a finding of "no significant hazards consideration" is justified.
The NRC staff has also determined that the exemptions involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite; that there is no significant increase in individual or cumulative occupational radiation exposure; that there is no significant construction impact; and there is no significant increase in the potential for or consequences from a radiological accident.
The NRC staff has further determined that the requirements from which the exemptions are sought involve the factors associated with 10 CFR 51.22( c)(25)(vi)(C)- inspection or surveillance requirements. Specifically, the exemptions address the methodology used to develop the allowable pressure and temperature criteria for determining reactor coolant system heatup/cooldown and inservice leak and hydrostatic testing in accordance with Technical Specification 3.1.2, "Pressurization Heatup and Cooldown Limitations." Therefore, the criteria
specified in 51.22(c)(25)(vi)(C) is satisfied and, accordingly, the exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22( c )(25 ). Pursuant to 10 CFR 51.22(b ),
no environmental impact statement or environmental assessment is required to be prepared in connection with the issuance of the exemption.
5.0 CONCLUSION
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants Exelon exemptions from the requirements of Appendix G to 10 CFR Part 50 and 10 CFR 50.61, to allow an alternative methodology that is based on using fracture toughness test data to determine initial, unirradiated properties for evaluating the integrity of the TMI-1 RPV beltline welds.
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 131h day of December 2013.
FOR THE NUCLEAR REGULATORY COMMISSION Michele G. Evans, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
PKG ML13324A072 LTR (NRR-106) ML13324A086 Exemption FRN (NRR-042) ML13324A089
- memo dated OFFICE DOR ULPLI-2/PM DORULPLI-2/LA DE/EVIB OGC (NLO) DORULPLI-2/BC DORUD NAME JHughey ABaxter SRosenberg* EHouseman Jlamb(Acting) MEvans DATE 12/12 /2013 11/21/2013 11/18/2013 12/06/2013 12/06/2013 12/13 /2013