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MONTHYEARML0226604972002-09-23023 September 2002
TS Page for Amendment 24 Regarding Licensed Operator Qualifications and Training
Project stage: Other
ML0225506752002-09-23023 September 2002
License Amendment Licenced Operator Qualifications and Training (Tac No. MB2699)
Project stage: Other
2002-09-23
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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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Text
6.3 UNIT STAFF QUALIFICATIONS 3.1 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS of 1978 for comparable positions unless otherwise noted in the Technical Specifications, with the following exceptions: 1) the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-02-100, dated June 19, 2002), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure, and 2) individuals who do not meet ANSIIANS 3.1 of 1978, Section 4.5, are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977. Each radiological controls technician/supervisor shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-I Radiation Controls training program. All radiological controls technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents.
6.4 TRAINING 6.4.1 A training program for the Fire Brigade shall be maintained and shall meet or exceed the requirements of Section 600 of the NFPA Code.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The director of each department shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the Review and Approval Matrix. Implementing approvals shall be performed at the cognizant manager level or above.
6-3 Amendment Nos. 11, 32, 55, 77, 92, 129, 131, 132 139"1-71, 207, "212, 2-, 241
