Letter Sequence Other |
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TAC:MC2760, Elimination of Requirements for a Post Accident Sampling System (Approved, Closed) |
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MONTHYEARML0412102152004-04-23023 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..
Project stage: Request
ML0422505202004-11-22022 November 2004
License Amendment 253, Regarding Elimination Requirements for Post-Accident Sampling System
Project stage: Approval
ML0433100342004-11-22022 November 2004
Tech Spec Pages for Amendment 253, Regarding Elimination Requirements for Post-Accident Sampling System
Project stage: Other
2004-11-22
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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
[Table view] |
Text
TABLE OF CONTENTS Page Section DESIGN FEATURES 5-1 5
SITE 5-1 5.1 CONTAINMENT 5-2 5.2 REACTOR BUILDING 5-2 5.2.1 REACTOR BUILDING ISOLATION SYSTEM 5-3 5.2.2 REACTOR 5-4 5.3 5-4 5.3.1 REACTOR CORE REACTOR COOLANT SYSTEM 5-4 5.3.2 NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4 5-6 5.4.1 NEW FUEL STORAGE SPENT FUELSTORAGE 5-6 5.4.2 5-8 5.5 AIR INTAKE TUNNEL FIRE PROTECTION SYSTEMS ADMINISTRATIVE CONTROLS 6-1 6
RESPONSIBILITY 6-1 6.1 6-1 6.2 ORGANIZATION CORPORATE 6-1 6.2.1 6-1 6.2.2 UNIT STAFF UNIT STAFF QUALIFICATIONS 6-3 6.3 TRAINING 6-3 64 6-3 6.5 REVIEW AND AUDIT TECHNICAL REVIEW AND CONTROL 6-4 6.5.1 INDEPENDENT SAFETY REVIEW 6-5 6.5.2 AUDITS 6-7 6.5.3 6-8 6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP REPORTABLE EVENT ACTION 6-10 6.6 6-10 6.7 SAFETY LIMIT VIOLATION PROCEDURES AND PROGRAMS 6-11 6.8 6-12 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6-12 6.9.1 6-14 6.9.2 DELETED ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6-17 6.9.3 6-18 6.9.4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CORE OPERATING LIMITS REPORT 6-19 6.9.5 RECORD RETENTION 6-20 6.10 6-22 6.11 RADIATION PROTECTION PROGRAM HIGH RADIATION AREA 6-22 6.12 6-23 6.13 PROCESS CONTROL PROGRAM OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-24 6.14 DELETED 6-24 6.15 DELETED 6-24 6.16 6-25 6.17 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Amendment No. 11, 47, 72, 77, 129, 150,173, 212, 253
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Licensee initiated changes to the ODCM:
- 1. Shall be submitted to the NRC in the Annual Radioactive Effluent Release Report for the period in which the changes were made.
This submittal shall contain:
- a. sufficiently detailed information to justify the changes without benefit of additional or supplemental information;
- b. a determination that the changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations; and
- c. documentation that the changes have been reviewed and approved pursuant to 6.8.2.
- 2. Shall become effective upon review and approval by licensee management.
6.15 DELETED 6.16 DELETED 6-24 Amendment No. 77, 102, 173,197. 207, 218, 253
