|
---|
Category:Letter type:TMI
MONTHYEARTMI-23-018, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation TMI-23-013, Radiological Emergency Plan Document Revision2023-05-30030 May 2023 Radiological Emergency Plan Document Revision TMI-23-009, Submittal of Changes to Technical Specifications Bases2023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases TMI-23-004, Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 12023-03-21021 March 2023 Updated Site-Specific Decommissioning Cost Estimate for Three Mile Island Nuclear Station, Unit 1 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan TMI-23-002, Radiological Emergency Plan Document Revision2023-02-23023 February 2023 Radiological Emergency Plan Document Revision TMI-22-028, Radiological Emergency Plan Document Revisions2022-09-27027 September 2022 Radiological Emergency Plan Document Revisions TMI-22-016, 2021 Annual Radiological Effluent Release Report2022-04-25025 April 2022 2021 Annual Radiological Effluent Release Report TMI-22-017, 2021 Annual Radiological Environmental Operating Report2022-04-25025 April 2022 2021 Annual Radiological Environmental Operating Report TMI-22-018, 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20212022-04-19019 April 2022 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2021 TMI-22-015, Submittal of Changes to Technical Specifications Bases2022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases TMI-22-009, Registration of Use of Casks to Store Spent Fuel2022-03-0909 March 2022 Registration of Use of Casks to Store Spent Fuel TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 TMI-22-004, Registration of Use of Casks to Store Spent Fuel2022-02-0606 February 2022 Registration of Use of Casks to Store Spent Fuel TMI-21-027, Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-08-30030 August 2021 Supplement to License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme TMI-21-024, 90-Day Notification Prior to First Storage of Spent Fuel2021-06-15015 June 2021 90-Day Notification Prior to First Storage of Spent Fuel TMI-21-025, Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities2021-06-15015 June 2021 Notification Pursuant to 10 CFR 72.140(d) of Intent to Apply Previously Approved 10 CFR 50, Appendix B, Quality Assurance Program to Independent Spent Fuel Storage Installation Activities TMI-21-026, Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation2021-06-15015 June 2021 Demonstration of Compliance with NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Independent Spent Fuel Storage Installation TMI-21-018, License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan2021-04-29029 April 2021 License Amendment Request - Revised Three Mile Island Nuclear Station License in Support of Independent Spent Fuel Storage Installation (ISFSI) Only Security Plan TMI-21-019, Submittal of 2020 Annual Radiological Environmental Operating Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Environmental Operating Report TMI-21-017, Submittal of 2020 Annual Radiological Effluent Release Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Effluent Release Report TMI-21-021, (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 20202021-04-27027 April 2021 (TMI-1) and Unit 2 (TMI-2) - 10 CFR 20.2206(b) Personnel Radiation Exposure Report for 2020 TMI-21-009, License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme2021-03-0404 March 2021 License Amendment Request - Proposed Changes to the Three Mile Island Emergency Plan for Independent Spent Fuel Storage Installation Only Emergency Plan and Emergency Action Level Scheme TMI-20-027, Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License2020-10-0909 October 2020 Request for Rescission of Security and Safeguards Order EA-02-026 ICM B.1.a from Three Mile Island Nuclear Station Renewed Facility License TMI-20-026, Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation2020-09-15015 September 2020 Response to NRC Order EA-20-103, Issuance of Order for Implementation of Additional Security Measures & Fingerprinting for Unescorted Access at Three Mile Island Generating Station Independent Spent Fuel Storage Installation TMI-20-025, Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report2020-07-16016 July 2020 Letter Re Inadvertent Submittal of Exelon Generation Company, LLC - Rev. 95 to NO-AA-10, Quality Assurance Topical Report TMI-20-021, Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative2020-07-0808 July 2020 Response to Request for Additional Information Regarding License Amendment Request - Deletion of PDTS 3/4.1.4, Handling of Irradiated Fuel with the Fuel Handling Building Crane, and Two Minor Administrative TMI-20-015, 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report2020-04-30030 April 2020 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report TMI-20-016, 2019 Annual Radiological Environmental Operating Report2020-04-30030 April 2020 2019 Annual Radiological Environmental Operating Report TMI-20-017, 2019 Annual Radiological Effluent Release Report2020-04-30030 April 2020 2019 Annual Radiological Effluent Release Report TMI-20-012, Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases2020-04-13013 April 2020 Island Nuclear Station, Unit 1 - Submittal of Changes to Technical Specifications Bases TMI-20-002, Annual Notification of Property Insurance Coverage2020-03-25025 March 2020 Annual Notification of Property Insurance Coverage TMI-20-006, Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7)2020-03-0202 March 2020 Notification of Revision of Commitment for Amended Post-Shutdown Decommissioning Activities Report (PSDAR) for Three Mile Island, Unit 2 in Accordance with 10 CFR 50.82(a)(7) TMI-19-112, Application for Order Approving License Transfer and Conforming License Amendments2019-11-12012 November 2019 Application for Order Approving License Transfer and Conforming License Amendments TMI-19-097, License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-10-31031 October 2019 License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements TMI-18-100, Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition2018-10-29029 October 2018 Supplement 2 to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.0, Definitions, and 6.0, Administrative Controls for Permanently Defueled Condition TMI-18-088, Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report2018-08-21021 August 2018 Response to Request for Additional Information: TMI Fall 2017 Steam Generator Tube Inspection Report TMI-18-024, Biennial 10 CFR 50.59 and Pdms SAR Report2018-04-24024 April 2018 Biennial 10 CFR 50.59 and Pdms SAR Report TMI-18-044, Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 292018-03-29029 March 2018 Transmittal of Radiological Emergency Plans; EP-AA-1009, Revision 28, EP-TM-1000, Revision 0 and EP-AA-1000, Revision 29 TMI-18-004, Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 22018-03-16016 March 2018 Decommissioning Funding Status Report for the Three Mile Island Nuclear Station, Unit 2 TMI-18-017, Annual Report2018-02-12012 February 2018 Annual Report TMI-17-093, Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 252017-08-18018 August 2017 Transmittal of Radiological Emergency Plan Annex Procedure EP-AA-1009, Revision 25 TMI-17-060, Request for Approval of Certified Fuel Handler Training Program2017-07-10010 July 2017 Request for Approval of Certified Fuel Handler Training Program TMI-17-051, Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 20132017-05-16016 May 2017 Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013 TMI-17-035, Submittal of Changes to Technical Specifications Bases2017-04-13013 April 2017 Submittal of Changes to Technical Specifications Bases TMI-17-034, Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04)2017-03-31031 March 2017 Submittal of 2016 Commitment Revision Report as Required by SECY-00-0045 (NEI 99-04) TMI-17-006, Decommissioning Funding Status Report2017-03-24024 March 2017 Decommissioning Funding Status Report TMI-16-097, Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 172016-10-20020 October 2016 Supplemental Information Related to Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 17 TMI-16-082, Notice of Transfer of Transmission Asset2016-09-15015 September 2016 Notice of Transfer of Transmission Asset TMI-16-091, Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-22016-09-0808 September 2016 Response to Draft Request for Additional Information Regarding the Submittal of Relief Request RR-16-01 Concerning the Use of ASME Code Case N-722-2 2023-05-30
[Table view] Category:Technical Specification
MONTHYEARTMI-23-009, Submittal of Changes to Technical Specifications Bases2023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases ML23090A2162023-03-30030 March 2023 Supplement to License Amendment Request - Proposed Changes to TMI-2 Possession Only License and Technical Specifications ML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications TMI-22-015, Submittal of Changes to Technical Specifications Bases2022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases ML22108A0752022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases ML21118A0572021-04-13013 April 2021 Submittal of Changes to Technical Specifications Bases ML21057A0462021-02-19019 February 2021 License Amendment Request Decommissioning Technical Specifications ML20279A3712020-12-0202 December 2020 Enclosure 2, Attachment 2: TMI-2 LTA Draft Tech Spec Changes 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 RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19106A1612019-04-12012 April 2019 Submittal of Changes to Technical Specifications Bases ML18263A1992018-09-20020 September 2018 License Amendment Request-Administrative Changes to Tendon Surveillance Program Technical Specifications ML18108A1762018-04-13013 April 2018 Submittal of Changes to Technical Specifications Bases TMI-17-035, Submittal of Changes to Technical Specifications Bases2017-04-13013 April 2017 Submittal of Changes to Technical Specifications Bases TMI-15-049, Submittal of Changes to Technical Specifications Bases2015-04-14014 April 2015 Submittal of Changes to Technical Specifications Bases ML14191A0592014-07-10010 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process TMI-14-055, Submittal of Changes to Technical Specifications Bases2014-04-10010 April 2014 Submittal of Changes to Technical Specifications Bases TMI-13-064, Submittal of Changes to Technical Specifications Bases2013-04-10010 April 2013 Submittal of Changes to Technical Specifications Bases 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-12-068, Submittal of Changes to Technical Specifications Bases2012-04-12012 April 2012 Submittal of Changes to Technical Specifications Bases TMI-11-064, Submittal of Changes to Technical Specifications Bases2011-04-15015 April 2011 Submittal of Changes to Technical Specifications Bases 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-10-046, Submittal of Changes to Technical Specifications Bases2010-04-22022 April 2010 Submittal of Changes to Technical Specifications Bases TMI-09-052, Submittal of Changes to Technical Specifications Bases2009-04-17017 April 2009 Submittal of Changes to Technical Specifications Bases 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 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0817602792008-06-11011 June 2008 Submittal of Technical Specification Change Request No. 86 to Delete Technical Specification Section 6.5, Review and Audit ML0812702192008-04-28028 April 2008 Submittal of Changes to Technical Specifications Bases ML0728804182007-10-15015 October 2007 Tech Spec Pages for Amendment 262 Regarding Reactor Coolant System Pressure-Temperature Limit RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program ML0720702572007-06-29029 June 2007 Technical Specification Change Request No. 337 - Reactor Building Emergency Sump Ph Control System Buffer Change RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0636200732006-12-13013 December 2006 Technical Specification Change Request (Tscr) No. 85, Removal of Occupational Radiation Exposure Report ML0634804592006-12-12012 December 2006 (TMI Unit 1), Response to Request for Additional Information - Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0635401682006-12-12012 December 2006 Technical Specification Change Request No. 333 - Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors ML0612900502006-04-24024 April 2006 Submittal of Changes to Technical Specification Bases ML0610402842006-04-0606 April 2006 Emergency License Amendment Request No. 332 - Emergency Diesel Generator ML0506105232005-02-24024 February 2005 Response to Request for Additional Information Concerning Technical Specification Change Request on Surveillance Criteria RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program ML0432201012004-11-0808 November 2004 Unit 1 Amendment to Technical Specification ML0412102152004-04-23023 April 2004 Technical Specification Change Request No. 321 - Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling System for Babcock & Wilcox Reactors Using.. ML0409003432004-03-23023 March 2004 Technical Specification Change Request No. 304/320 (Tscr) - Relocation of Independent Onsite Safety Review Group Function to the Quality Assurance Topical Report ML0302805162003-01-16016 January 2003 TS Change Request No. 316-Cycle 15 Core Reload Design ML0302403732003-01-14014 January 2003 Technical Specification Change Request No. 317 - Deletion of Reactor Building Purge Air Treatment System Technical Specification Requirements ML0204403152002-02-0808 February 2002 License Amendment 240, Technical Specification Amendment ML0202302022002-01-22022 January 2002 Technical Specifications Pages, Amendment 239, Incorporation of Changes to 10 CFR 50.59, Changes, Tests and Experiments 2023-04-13
[Table view] Category:Bases Change
MONTHYEARTMI-23-009, Submittal of Changes to Technical Specifications Bases2023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases ML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications TMI-22-015, Submittal of Changes to Technical Specifications Bases2022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases ML22108A0752022-04-13013 April 2022 Submittal of Changes to Technical Specifications Bases ML21118A0572021-04-13013 April 2021 Submittal of Changes to Technical Specifications Bases ML20279A3712020-12-0202 December 2020 Enclosure 2, Attachment 2: TMI-2 LTA Draft Tech Spec Changes 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 ML19106A1612019-04-12012 April 2019 Submittal of Changes to Technical Specifications Bases ML18108A1762018-04-13013 April 2018 Submittal of Changes to Technical Specifications Bases TMI-17-035, Submittal of Changes to Technical Specifications Bases2017-04-13013 April 2017 Submittal of Changes to Technical Specifications Bases TMI-15-049, Submittal of Changes to Technical Specifications Bases2015-04-14014 April 2015 Submittal of Changes to Technical Specifications Bases ML14191A0592014-07-10010 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process TMI-14-055, Submittal of Changes to Technical Specifications Bases2014-04-10010 April 2014 Submittal of Changes to Technical Specifications Bases TMI-13-064, Submittal of Changes to Technical Specifications Bases2013-04-10010 April 2013 Submittal of Changes to Technical Specifications Bases 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-12-068, Submittal of Changes to Technical Specifications Bases2012-04-12012 April 2012 Submittal of Changes to Technical Specifications Bases TMI-11-064, Submittal of Changes to Technical Specifications Bases2011-04-15015 April 2011 Submittal of Changes to Technical Specifications Bases TMI-10-046, Submittal of Changes to Technical Specifications Bases2010-04-22022 April 2010 Submittal of Changes to Technical Specifications Bases TMI-09-052, Submittal of Changes to Technical Specifications Bases2009-04-17017 April 2009 Submittal of Changes to Technical Specifications Bases ML0817602792008-06-11011 June 2008 Submittal of Technical Specification Change Request No. 86 to Delete Technical Specification Section 6.5, Review and Audit ML0812702192008-04-28028 April 2008 Submittal of Changes to Technical Specifications Bases RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program ML0720702572007-06-29029 June 2007 Technical Specification Change Request No. 337 - Reactor Building Emergency Sump Ph Control System Buffer Change RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0635401682006-12-12012 December 2006 Technical Specification Change Request No. 333 - Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors ML0634804592006-12-12012 December 2006 (TMI Unit 1), Response to Request for Additional Information - Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0612900502006-04-24024 April 2006 Submittal of Changes to Technical Specification Bases ML0506105232005-02-24024 February 2005 Response to Request for Additional Information Concerning Technical Specification Change Request on Surveillance Criteria ML0412102152004-04-23023 April 2004 Technical Specification Change Request No. 321 - Application for Technical Specification Improvement to Eliminate Requirements for Post Accident Sampling System for Babcock & Wilcox Reactors Using.. ML0302403732003-01-14014 January 2003 Technical Specification Change Request No. 317 - Deletion of Reactor Building Purge Air Treatment System Technical Specification Requirements 2023-04-13
[Table view] |
Text
200 Exelon Way Kennett Square, PA 19348 www.ConstellationEnergy.com TS 6.18.d TMI-22-015 April 13, 2022 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Three Mile Island Nuclear Station, Unit 1 Renewed Facility License No. DPR-50 NRC Docket No. 50-289
Subject:
Submittal of Changes to Technical Specifications Bases In accordance with the requirements of Three Mile Island Nuclear Station (TMI), Unit 1, Permanently Defueled Technical Specification 6.18.d, Constellation Energy Generation, LLC, hereby submits a complete updated copy of the TMI, Unit 1, Technical Specifications (TS) Bases, which includes the related TS. The enclosed Bases include changes implemented through the date of this letter.
There are no regulatory commitments in this submittal.
If you have any questions or require further information, please contact Richard Gropp at 610-765-5557.
Respectfully, David P. Helker Sr. Manager, Licensing Constellation Energy Generation, LLC
Enclosure:
Three Mile Island Nuclear Station, Unit 1, Technical Specifications and Bases cc: w/ Enclosure USNRC Administrator, Region I NRC Project Manager, NMSS - Three Mile Island Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Protection
Three Mile Island Nuclear Station, Unit 1 Technical Specifications and Bases
3/4. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 GENERAL ACTION REQUIREMENTS AND SURVEILLANCE REQUIREMENT APPLICABILITY 3.0.1 LCOs shall be met during the specified conditions in the TS, except as provided in 3.0.2.
3.0.2 Upon discovery of a failure to meet an LCO, the required actions of the associated Conditions shall be met.
If the LCO is met or is no longer applicable prior to expiration of the specified completion time(s), completion of the required action(s) is not required, unless otherwise stated.
4.0.1 Surveillance requirements shall be met during the specified conditions in the applicability for individual LCOs, unless otherwise stated in the surveillance requirements. Failure to meet a surveillance, whether such failure is experienced during the performance of the surveillance or between performances of the surveillance, shall be failure to meet the LCO. Failure to perform a surveillance within the specified frequency shall be failure to meet the LCO except as provided in 4.0.2.
4.0.2 If it is discovered that a surveillance was not performed within its specified frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the surveillance will be met when performed.
If the surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable condition(s) must be entered.
When the surveillance is performed within the delay period and the surveillance is not met, the LCO must immediately be declared not met, and the applicable condition(s) must be entered.
4.0.3 The specified frequency for each SR is met if the surveillance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance.
3/4-1 Amendment No. 297
BASES LCO 3.0.1 and LCO 3.0.2, and SR 4.0.1 through SR 4.0.3 delineate the actions to be taken for circumstances not directly provided for in the action requirements of individual specifications and whose occurrence would violate the intent of the specification.
LCO 3.0.1 establishes the applicability statement within each individual specification as the requirement for when the LCO is required to be met (i.e., when the facility is in the specified conditions of the applicability statement of each Specification).
LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated actions shall be met. The completion time of each required action for an ACTIONS condition is applicable from the point in time that an actions condition is entered. The required actions establish those remedial measures that must be taken within specified completion times when the requirements of an LCO are not met. This specification establishes that completion of the required actions within the specified completion times constitutes compliance with a specification.
Completing the required actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual specifications.
SR 4.0.1 establishes the requirement that SRs must be met during the specified conditions in the SRs for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This specification is to ensure that surveillances are performed in order to verify that facility conditions are within specified limits. Failure to meet a surveillance within the specified frequency constitutes a failure to meet an LCO.
Variables are assumed to be within limits when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that variables are within limits when the requirements of the surveillance(s) are known not to be met between required surveillance performances.
Surveillances do not have to be performed when the unit is in a specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR.
In this case, the unplanned event may be credited as fulfilling the performance of the SR. This allowance includes those SRs whose performance is normally precluded in a given specified condition.
Surveillances, including surveillances invoked by LCO required actions, do not have to be performed on inoperable equipment because the actions define the remedial measures that apply. Surveillances have to be met and performed in accordance with the specified frequency, prior to returning equipment to OPERABLE status.
SR 4.0.2 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a surveillance has not been performed within the specified frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater, applies from the point in time that it is discovered that the required surveillance has not been performed in accordance with Surveillance Requirement 4.0.2 and not at the time that the specified frequency was not met.
3/4-2 Amendment No. 297
The delay period provides an adequate time to perform surveillances that have been missed.
This delay period permits the performance of a surveillance before complying with required actions or other remedial measures that might preclude performance of the surveillance.
The basis for this delay period includes consideration of facility conditions, adequate planning, availability of personnel, the time required to perform the surveillance, the safety significance of the delay in completing the required surveillance, and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the requirements.
SR 4.0.2 is only applicable if there is a reasonable expectation the associated variables are within limits, and it is expected that the Surveillance will be met when performed. Many factors should be considered, such as the period of time since the Surveillance was last performed, or whether the Surveillance, or a portion thereof, has ever been performed, and any other indications, tests, or activities that might support the expectation that the Surveillance will be met when performed. The rigor of determining whether there is a reasonable expectation a Surveillance will be met when performed should increase based on the length of time since the last performance of the Surveillance. If the Surveillance has been performed recently, a review of the Surveillance history and equipment performance may be sufficient to support a reasonable expectation that the Surveillance will be met when performed. For Surveillances that have not been performed for a long period or that have never been performed, a rigorous evaluation based on objective evidence should provide a high degree of confidence that the equipment is OPERABLE. The evaluation should be documented in sufficient detail to allow a knowledgeable individual to understand the basis for the determination.
Failure to comply with specified surveillance frequencies is expected to be an infrequent occurrence. Use of the delay period established by Surveillance Standard 4.0.2 is a flexibility which is not intended to be used repeatedly to extend surveillance intervals. While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified frequency is provided to perform the missed surveillance, it is expected that the missed surveillance will be performed at the first reasonable opportunity. If a surveillance is not completed within the allowed delay period, then the variable is considered outside the specified limits and the completion times of the required actions for the applicable LCO conditions begin immediately upon expiration of the delay period. If a surveillance is failed within the delay period, then the variable is outside the specified limits and the completion times of the required actions for the applicable LCO conditions begin immediately upon failure of the surveillance.
Completion of the surveillance within the delay period allowed by this specification, or within the completion time of the actions, restores compliance.
SR 4.0.3 permits a 25% extension of the interval specified in the frequency. This extension facilitates Surveillance scheduling and considers facility conditions that may not be suitable for conducting the Surveillance (e.g., other ongoing surveillance or maintenance activities).
The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any Surveillance is the verification of conformance with the SRs.
3/4-3 Amendment No. 297
3/4.1 HANDLING AND STORAGE OF IRRADIATED FUEL IN THE SPENT FUEL POOL 3/4.1.1 SPENT FUEL POOL WATER LEVEL Applicability Applies to the minimum level of water in the Spent Fuel Pool during handling of irradiated fuel in the Spent Fuel Pool.
Objective Ensures that assumptions of Fuel Handling Accident are maintained during handling of irradiated fuel in the Spent Fuel Pool.
Specification 3.1.1.1 Maintain Spent Fuel Pool level greater than 342'4" elevation.
3.1.1.2 With Spent Fuel Pool level less than 342'4" elevation, immediately suspend handling of irradiated fuel in the Spent Fuel Pool.
SURVEILLANCE REQUIREMENTS 4.1.1.1 Verify Spent Fuel Pool level greater than or equal to 342'4" elevation every 7 days.
Bases The top of fuel is at the 3194 elevation. The FHA analysis assumes 23 of water above the fuel assemblies. This dictates a minimum elevation of water in the Spent Fuel Pool of 3424.
This specification provides the controls to ensure the assumptions of the accident analysis while fuel handling evolutions are in progress. This specification will have a SR 4.1.1.1 that will verify the Spent Fuel Pool water level on a frequency of 7 days.
The water contained in the spent fuel pool provides a medium for removal of decay heat from the stored fuel elements, normally via the spent fuel cooling system. The spent fuel pool water also provides shielding to reduce the general area radiation dose during both spent fuel handling and storage. The resultant 2-hour dose to a person at the exclusion area boundary and the 30-day dose at the low population zone are much less than 10 CFR 50.67 limits.
LCO 3.1.1.2 requires that when the water level in the SFP is lower than the required level, the movement of irradiated fuel assemblies in the SFP is to be "immediately" suspended.
"Immediately" as used in this completion time means the required action should be pursued without delay and in a controlled manner, such that the suspension of this activity shall not preclude completion of movement of an irradiated fuel assembly to a safe position. This effectively precludes a spent fuel handling accident from occurring in the SFP when the level is below the required elevation.
Although maintaining adequate spent fuel pool water level is essential to both decay heat removal and shielding effectiveness, the Technical Specification minimum water level limit is based upon maintaining the pool's iodine retention-effectiveness consistent with that assumed 3/4-4 Amendment No. 297
in the evaluation of the Post Permanent Shutdown FHA analysis. The Post Permanent Shutdown FHA analysis assumes that a minimum of 23 feet of water is maintained above the stored fuel. This assumption allows the use of the pool iodine decontamination factor of 200 used in the associated offsite dose calculation.
3/4-5 Amendment No. 297
3/4.1.2 SPENT FUEL POOL BORON CONCENTRATION Applicability Applies to the minimum boron concentration in the Spent Fuel Pool during storage and handling of irradiated fuel in the Spent Fuel Pool.
Objective Ensures that assumptions of Storage Limitations are maintained to prevent inadvertent criticality in the Spent Fuel Pool.
Specification 3.1.2.1 Maintain Spent Fuel Pool boron concentration greater than or equal to 600 ppm.
3.1.2.2 With Spent Fuel Pool boron concentration less than 600 ppm, immediately suspend handling of irradiated fuel in the Spent Fuel Pool and immediately restore boron concentration per 3.1.2.1.
SURVEILLANCE REQUIREMENTS 4.1.2.1 Verify Spent Fuel Pool boron concentration greater than or equal to 600 ppm every 7 days.
Bases The acceptance criteria for the fuel storage pool criticality analyses is that a keff of < 0.95 must be maintained for all postulated events. The storage racks are capable of maintaining this keff with unborated pool water at a temperature yielding the highest reactivity (assuming the storage restrictions of LCO 3.1.3 are met). Most abnormal storage locations will not result in an increase in the keff of the racks. However, it is possible to postulate events, such as the mis-loading of an assembly with a burnup and enrichment combination outside the acceptable area in Figure 3.1.3-1 and 3.1.3-2, or dropping an assembly between the pool wall and the fuel racks, which could lead to an increase in reactivity. For such events, credit is taken for the presence of boron in the pool water since the NRC does not require the assumption of two unlikely, independent, concurrent events to ensure protection against a criticality accident (double contingency principle). The reduction in keff, caused by the boron more than offsets the reactivity addition caused by credible accidents. This specification will have a Surveillance Requirement SR 4.1.2.1 that will verify the Spent Fuel Pool Boron on a frequency of 7 days.
LCO 3.1.2.2 requires that when the SFP boron concentration is less than 600 ppm, the movement of irradiated fuel assemblies in the SFP is to be "immediately" suspended.
"Immediately" as used in this completion time means the required action should be pursued without delay and in a controlled manner, such that the suspension of this activity shall not preclude completion of movement of an irradiated fuel assembly to a safe position. This effectively precludes a spent fuel handling accident from occurring in the SFP when the boron concentration is below the required level.
3/4-6 Amendment No. 297
3/4.1.3 SPENT FUEL ASSEMBLY STORAGE Applicability Applies whenever any fuel assembly is stored in Storage Pool A or Storage Pool B of the Spent Fuel Pool.
Objective Ensures that assumptions of Storage Limitations are maintained to prevent inadvertent criticality in the Spent Fuel Pool.
Specification 3.1.3.1 The combination of initial enrichment and burnup of each spent fuel assembly stored in Storage Pool A and Storage Pool B, shall be within the acceptable region of Figure 3.1.3-1 or 3.1.3-2.
3.1.3.2 When requirement of 3.1.3.1 is not met, immediately initiate action to move the noncomplying fuel assembly to an acceptable configuration.
SURVEILLANCE REQUIREMENTS 4.1.3.1 Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3.1.3-1 or Figure 3.1.3-2 prior to storing irradiated spent fuel in the Spent Fuel Pool A or Spent Fuel Pool B.
Bases The function of the spent fuel storage racks is to support safety analyses and protect spent fuel assemblies from the time they are placed in the pool until they are shipped offsite. The spent fuel assembly storage LCO was derived from the need to establish limiting conditions on fuel storage to assure sufficient safety margin exists to prevent inadvertent criticality. The spent fuel assemblies are stored entirely underwater in a configuration that has been shown to result in a reactivity of less than or equal to 0.95 under worse case conditions. The spent fuel assembly enrichment requirements in this LCO are required to ensure inadvertent criticality does not occur in the spent fuel pool. Inadvertent criticality within the fuel storage area could result in offsite radiation doses exceeding 10 CFR 50.67 limits.
LCO 3.1.3.2 requires that when LCO 3.1.3.1 is not met, "immediately" initiate action to move the noncomplying fuel assembly to an acceptable configuration. "Immediately" as used in this completion time means the required action should be pursued without delay and in a controlled manner, to reestablish the safety margins to prevent an inadvertent criticality.
3/4-7 Amendment No. 297
Figure 3.1.3-1 Minimum Burnup Requirements for Fuel in Region II of the Pool A Storage Racks 3/4-8 Amendment No. 297
Figure 3.1.3-2 Minimum Burnup Requirements for Fuel in the Pool B Storage Racks 3/4-9 Amendment No. 297