Letter Sequence Acceptance Review |
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MONTHYEARML0320306102003-07-15015 July 2003
Issuance of License Amendment 200 Re. Changes to Title of Shift Supervisor to Shift Manaager and Changes Plant-Specific Titles to Generic Titles Consistent with TSTF-65, Rev. 1
Project stage: Approval
ML0320300092003-07-15015 July 2003
TS Pages for Amendment No. 200 Personnel Title Revisions and Reference Correction to Technical Specification, Section 5.0, Administrative Controls
Project stage: Acceptance Review
2003-07-15
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Category:Technical Specifications
MONTHYEARML23264A8052023-10-11011 October 2023
Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023
License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks
NLS2021041, Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program2021-07-20020 July 2021
Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program
ML20314A2352020-12-0202 December 2020
Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process
ML19238A0072019-10-30030 October 2019
Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
ML18218A4832018-09-0606 September 2018
Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio
ML18137A2102018-05-10010 May 2018
License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio
NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016
Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML15343A3012016-01-22022 January 2016
Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function
ML16021A3222016-01-12012 January 2016
Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
ML15216A2592015-08-27027 August 2015
Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water
ML15168A1712015-07-14014 July 2015
Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications
ML15135A0052015-05-29029 May 2015
Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS)
NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015
License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
ML14055A0232014-04-29029 April 2014
Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML13191A1052013-09-12012 September 2013
Issuance of Amendment No. 247, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report
ML13085A0962013-03-29029 March 2013
Corrected Technical Specification (TS) and Safety Evaluation Pages for Amendment No. 245, Revise TS 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements
ML12157A2062012-05-30030 May 2012
License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio
ML1136302582012-01-31031 January 2012
Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection
NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011
Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves
NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011
License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a
ML1101002912011-01-0505 January 2011
Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves
NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009
Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
ML0906207232009-02-26026 February 2009
Corrected Technical Specification Pages Regarding Reactor Equipment Cooling System Margin Amendment
ML0815402852008-06-30030 June 2008
Technical Specifications, Measurement Uncertainty Recapture Power Uprate
ML0812202892008-05-12012 May 2008
Technical Specification Pages for Issuance of Amendment No. 230 Control Room Habitability, TSTF-448
NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-05-0909 May 2008
Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
NLS2007079, Corrected Technical Specification Pages2007-11-0505 November 2007
Corrected Technical Specification Pages
NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2007-08-16016 August 2007
License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve
ML0630405382006-10-31031 October 2006
Tech Spec Pages for Amendment 226 Regarding MSIV Leakage Exemption from 10 CFR Part 50, Appendix J
ML0629602942006-10-23023 October 2006
Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities
ML0627700902006-10-0303 October 2006
Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval
ML0625003012006-09-0606 September 2006
Technical Specifications, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335
ML0624900372006-09-0505 September 2006
Technical Specifications, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566
NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006
License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation
ML0612403772006-05-0303 May 2006
Correction to Amendment No. 218, Technical Specification Page 3.1-12
ML0612304692006-05-0202 May 2006
Technical Specifications, Changes to TS Leakage Limit for the Main Stream Isolation Valves
ML0611802442006-04-27027 April 2006
Technical Specifications, Revised Pressure Vessel Fluence and Pressure Temp Curve Applicability to 30 Effective Full-Power Years of Operation
ML0611001622006-04-18018 April 2006
Corrected Technical Specification Page 3.9-1 Re Refueling Operations
NLS2006039, Corrected Technical Specification Page from Amendment No. 2182006-04-17017 April 2006
Corrected Technical Specification Page from Amendment No. 218
ML0609004412006-03-30030 March 2006
Technical Specification Pages, Change Request for Various Sections
ML0628404572006-03-10010 March 2006
Tech Spec Pages for Amendment 217 Regarding Revise Technical Specifications Instrumentation Definitions
NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program2006-03-0707 March 2006
License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program
NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006
License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval
NLS2006001, Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-01-30030 January 2006
Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process
ML0602002922006-01-16016 January 2006
Cooper Nuclear Station - Revised and Supplemental Pages to License Amendment Request for Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences
NLS2005102, License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification2005-12-30030 December 2005
License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification
ML0601104792005-12-16016 December 2005
Corrected Technical Specification Pages Re Secondary Containment Isolation Instrumentation
ML0535000852005-12-15015 December 2005
1 TS Page - Cooper Nuclear Station. Issuance of Amd. 214 Unit Staff Qualifications (Tac. MC7346)
NLS2005051, Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation2005-08-0101 August 2005
Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
2023-09-06
[Table view] |
Text
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment, and modification to systems or equipment that affect nuclear safety.
5.1.2 The Shift Manager (SM) shall be responsible for the control room command function. During any absence of the SM from the control room while the unit is in MODE 1, 2, or 3, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SM from the control room while the unit is in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.
200 Cooper 5.0-1 Amendment No. 178 I
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the USAR.
- b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
- c. The corporate officer with direct responsibility for the plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The individuals who train the operating staff, carry out radiological protection functions, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Unit Staff The unit staff organization shall include the following:
- a. A non-licensed operator shall be assigned when the reactor contains fuel and two additional non-licensed operators shall be assigned when the reactor is operating in MODES 1, 2, or 3.
200 Cooper 5.0-2 Amendment No. + 8
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1,2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specification 5.2.2.a for a period of time not to exceed 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- d. A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. The operations supervisor shall hold an SRO license.
- f. The Shift Technical Engineer (STE) shall provide advisory technical support to the Shift Manager (SM) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit when the unit is in MODE 1, 2, or 3. In addition, the STE shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
- 9. Written administrative procedures for shift overtime shall be established, implemented, and maintained.
200 Coonnr 50-3 Amendment No. 4-78
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Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of the American National Standards Institute N-18.1-1971, "Selection and Training of Personnel for Nuclear Power Plants," except for the Shift Manager, Senior Operator, I Licensed Operator, Shift Technical Engineer, and radiological manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 2.
200 Cooper 5.0-4 Amendment +17, 48+ I
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented and maintained.
5.5.1 Offsite Dose Assessment Manual (ODAM)
- a. The ODAM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental
,monitoring program; and
- b. The ODAM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release reports required by Specification 5.6.2 and Specification 5.6.3.
- c. Licensee initiated changes to the ODAM:
- 1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- a. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and
- b. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- 2. Shall become effective after review and acceptance by the Station Operations Review Committee (SORC) and the approval of the plant manager; and
- 3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODAM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODAM was made. Each change shall be identified by 200 Cooper 5.0-6 Amendment No. 4I8
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
- 9. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary shall be limited to the following:
- 1. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and
- 2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days: less than or equal to a dose rate of 1500 mrem/yr to any organ;
- h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix l;
- i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix l; and
- j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR Section 111-3.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.
200 Cooper 5.0-9 Amendment No. I-78
