Letter Sequence Other |
---|
|
|
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
[Table View] |
|
---|
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
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