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| | project = TAC:MD3027 | | | project = TAC:MD3027 |
| | stage = Other | | | stage = Acceptance Review |
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| ====6.8.5 Reactor==== | | ====6.8.5 Reactor==== |
| Building Leakage Rate Testing Program The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained as follows: A program shall be established to implement the leakage rate testing of the Reactor Building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. | | Building Leakage Rate Testing Program The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained as follows: A program shall be established to implement the leakage rate testing of the Reactor Building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. |
| This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J": a. Section 9.2.3: The first Type A test performed after the September 1993 Type A test shall be performed prior to startup from the T1 R18 refueling outage. The T1 R1 8 refueling outage will begin no later than November 1, 2009.The peak calculated Reactor Building internal pressure for the design basis loss of coolant accident, Pc, is 50.6 psig.The maximum allowable Reactor Building leakage rate, La, shall be 0.1 weight percent of containment atmosphere per 24 hours at Pac.Reactor Building leakage rate acceptance criteria is < 1.0 La. During the first plant startup following each test performed in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the Type B and Type C tests and -< 0.75 La for the Type A tests.6-11 c Amendment No. 2 0 1, 2 4 4 , 259}} | | This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J": a. Section 9.2.3: The first Type A test performed after the September 1993 Type A test shall be performed prior to startup from the T1 R18 refueling outage. The T1 R1 8 refueling outage will begin no later than November 1, 2009.The peak calculated Reactor Building internal pressure for the design basis loss of coolant accident, Pc, is 50.6 psig.The maximum allowable Reactor Building leakage rate, La, shall be 0.1 weight percent of containment atmosphere per [[estimated NRC review hours::24 hours]] at Pac.Reactor Building leakage rate acceptance criteria is < 1.0 La. During the first plant startup following each test performed in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the Type B and Type C tests and -< 0.75 La for the Type A tests.6-11 c Amendment No. 2 0 1, 2 4 4 , 259}} |
Revision as of 21:08, 17 April 2019
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MONTHYEARML0705803012007-02-26026 February 2007 Additional Information Concerning Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension Project stage: Other ML0714302192007-05-22022 May 2007 Response to Request for Additional Information Concerning Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension Project stage: Response to RAI ML0715606022007-06-0505 June 2007 Response to Request for Additional Information Concerning Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension Project stage: Response to RAI ML0718003192007-06-29029 June 2007 Tech Spec Pages for Amendment 259, One-Time Type a Test Interval Extension Project stage: Acceptance Review ML0716505192007-06-29029 June 2007 Issuance of License Amendment 259, One-Time Type a Test Interval Extension Project stage: Approval 2007-05-22
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Category:Technical Specifications
MONTHYEARML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications ML22087A3942022-03-28028 March 2022 Supplemental Information Supporting 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 Technica ML21118A0572021-04-13013 April 2021 Submittal of Changes to Technical Specifications Bases ML20352A3812020-12-18018 December 2020 TMI-2 License Transfer Conforming Amendment ML20261H9252020-12-0202 December 2020 Issuance of Amendment No. 299 for Unit 1 Permanently Defueled Emergency Plan and Emergency Action Level Scheme Changes ML19065A1142019-04-18018 April 2019 Issuance of Amendment No. 296 for Unit 1 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML19065A2172019-03-0606 March 2019 Supplement - License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML15225A1582015-10-0101 October 2015 Issuance of Amendment for Temporary Restoration of the Borated Water Storage Tank Cleanup and Recirculation Operation (TAC No. 6504) ML15090A5842015-07-28028 July 2015 Issuance of Amendments Technical Specifications to Modify Reactor Coolant System Pressure Isolation Check Valve Maximum Allowable Leakage Limits ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) TMI-15-072, Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts2015-06-10010 June 2015 Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts TMI-15-064, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2015-05-0707 May 2015 Supplement to the 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-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-12-169, Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements2013-02-0404 February 2013 Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements TMI-12-064, Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications2012-04-11011 April 2012 Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications TMI-11-171, Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications2012-01-20020 January 2012 Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications 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-10-035, 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 ML1003204932010-03-11011 March 2010 License Amendment Technical Specification Changes Adopting TSTF-490-A, Revision 0, Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification ML0927104632009-10-22022 October 2009 Renewed Facility Operating License ML0927104012009-10-22022 October 2009 Issuance of Renewed Facility Operating License No. DPR-50 for Three Mile Island, Unit 1 TMI-09-082, Response to Request for Additional Information Related to 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....2009-07-0202 July 2009 Response to Request for Additional Information Related to 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.... 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 ML0827402962008-09-15015 September 2008 Supplement: Technical Specification Change Request for Technical Specification Change Request (Tscr) No. 86 Deletion of Technical Specification Sections 6.5, Review and Audit ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 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 ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators 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. ML0809101272008-04-16016 April 2008 Technical Specifications to Amendment ML0807700842008-03-14014 March 2008 Additional Information for Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 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 ML0727100352007-09-27027 September 2007 Tech Spec Pages for Amendment 261 Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Generic Letter 2006-01 ML0726904252007-09-26026 September 2007 Tech Spec Pages for Amendment 260 Regarding Relocation of Technical Specification Requirements for Refueling and Spent Fuel Pool Area Radiation Monitors ML0725402542007-09-0404 September 2007 Additional Information - Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0718003192007-06-29029 June 2007 Tech Spec Pages for Amendment 259, One-Time Type a Test Interval Extension ML0715606022007-06-0505 June 2007 Response to Request for Additional Information Concerning Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension ML0715202332007-05-31031 May 2007 Response to Request for Additional Information - Technical Specification Change Request No. 331 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0715202292007-05-31031 May 2007 Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors. ML0712302682007-04-27027 April 2007 Submittal of Changes to Technical Specification Bases ML0708609682007-03-22022 March 2007 Technical Specification Change Request No. 335, Incorporating Revised Limit or the Variable Low Reactor Coolant System Pressure-Temperature Core Protection Safety Limit ML0628303312006-10-0606 October 2006 Response to Request for Additional Information, Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0626800402006-09-15015 September 2006 Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension ML0614202942006-05-15015 May 2006 Technical Specification Change Request No. 331 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0610100612006-04-0808 April 2006 Technical Specification Page Allowed Outage Time Extension from 7 Days to 10 Days for Emergency Diesel Generator EG-Y-1A ML0528702192005-10-13013 October 2005 Issuance of Amendment Elimination of Containment Equipment Hatch Closure Requirement During Refueling, Technical Specifications ML0522703622005-08-12012 August 2005 Tech Spec Pages for Amendment 256 Missed Surveillance Criteria Requirements and Addition of a Technical Specifications Bases Control Program ML0522304032005-08-10010 August 2005 Technical Specification Pages Extension of Reactor Trip System and Reactor Trip Device Functional Test Intervals ML0517506582005-06-17017 June 2005 Tech Spec Pages for Amendment - Monthly Operating Reports and Annual Occupational Radiation Reports 2023-01-27
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-3-(2) AmerGen Energy Company. LLC, pursuant to the Act and 10 CFR Parts 30.40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as reactor fuel, sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required for reactor operation; (3) AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess at either TMI-I or TMI-2, and use in amounts as required for TMI-1 any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, testing, instrument calibration, or associated with radioactive apparatus or components.
Other than radioactive apparatus and components to be used at TMI Unit 2 in accordance with the TMI-2 License, the radioactive apparatus and components that may be moved from TMI Unit I to TMI Unit 2 under this provision shall be limited to: (1)outage-related items (such as contaminated scaffolding, tools, protective clothing, portable shielding and decontamination equipment);
and (2) other equipment belonging to TMI Unit 1 when storage of such equipment at TMI-2 is deemed necessary for load handling or contamination control considerations; (4) AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess at the TMI Unit 1 or Unit 2 site, but not separate, such byproduct and special nuclear materials as may be produced by the operation of either unit. Radioactive waste may be moved from TMI Unit 2 to TMI Unit 1 under this provision for collection, processing (including decontamination), packaging, and temporary storage prior to disposal.
Radioactive waste that may be moved from TMI Unit 1 to TMI Unit 2 under this provision shall be limited to: (1) dry active waste (DAW) temporarily moved to TMI Unit 2 during waste collection activities, and (2) contaminated liquid contained in shared system piping and tanks. Radioactive waste that may be moved from TMI Unit 1 to TMI Unit 2 under this provision shall not include spent fuel, spent resins, filter sludge, evaporator bottoms, contaminated oil, or contaminated liquid filters.The storage of radioactive materials or radwaste generated at TMI Unit 2 and stored at TMI Unit I shall not result in a source term that, if released, would exceed that previously analyzed in the UFSAR in terms of offsite dose consequences.
The storage of radioactive materials or radwaste generated at TMI Unit 1 and stored at TMI Unit 2 shall not result in a source term that, if released, would exceed that previously analyzed in the PDMS SAR for TMI Unit 2 in terms of off-site dose consequences.
- c. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level AmerGen Energy Company, LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.(2) Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No259 are hereby incorporated in the license. The AmerGen Energy Company, LLC shall operate the facility in accordance with the Technical Specifications.
Amendment No. 259
6.8.5 Reactor
Building Leakage Rate Testing Program The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained as follows: A program shall be established to implement the leakage rate testing of the Reactor Building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J": a. Section 9.2.3: The first Type A test performed after the September 1993 Type A test shall be performed prior to startup from the T1 R18 refueling outage. The T1 R1 8 refueling outage will begin no later than November 1, 2009.The peak calculated Reactor Building internal pressure for the design basis loss of coolant accident, Pc, is 50.6 psig.The maximum allowable Reactor Building leakage rate, La, shall be 0.1 weight percent of containment atmosphere per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> at Pac.Reactor Building leakage rate acceptance criteria is < 1.0 La. During the first plant startup following each test performed in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the Type B and Type C tests and -< 0.75 La for the Type A tests.6-11 c Amendment No. 2 0 1, 2 4 4 , 259