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MONTHYEARML0506304302005-03-0101 March 2005 Tech Spec Pages for Amendments 219 & 214 Elimination of Requirements for Hydrogen Recombiners and Monitors Project stage: Other ML0505304352005-03-0101 March 2005 License Amendments 219 & 214 Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Project stage: Other 2005-03-01
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Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22263A0432022-09-0707 September 2022 Editorial Change to SLC 16.10-5 ML20174A0452020-08-0404 August 2020 Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits RA-17-0051, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2017-11-21021 November 2017 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16124A6942016-06-0202 June 2016 Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ML16081A3332016-04-29029 April 2016 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate ML16075A3012016-04-26026 April 2016 Issuance of Amendments Regarding the Revision of the Steam Generator Technical Specifications to Reflect the Adoption of TSTF-510(CAC Nos. MF6139,MF6140,MF6141,MF6142,MF6143,MF6144. ML16082A0382016-04-18018 April 2016 Issuance of License Amendment Regarding Emergency Action Level Scheme Change ML16067A2292016-04-0808 April 2016 Issuance of Amendments Regarding Removal of Obsolete Technical Specification Requirements ML16007A1762016-01-12012 January 2016 Issuance of Amendments Regarding Non-Conservative Technical Specification Allowable Value ML15320A3332015-12-18018 December 2015 Issuance of Amendments Regarding Non-Conservative Technical Specifications Allowable Value ML15133A4532015-06-11011 June 2015 McGuire Nuclear Station, Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Cyber Security Plan Implementation Schedule Milestone 8 ML15063A2712015-04-14014 April 2015 Issuance of Amendments Technical Specification 3.1.3, Moderator Temperature Coefficient and TS 5.6.5, Core Operating Limits Report. ML15027A3662015-03-25025 March 2015 Issuance of Amendments DPC-NE-3001-P, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology ML15002A3242015-02-12012 February 2015 McGuire Nuclear Station, and Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Areas CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-06-23023 June 2014 License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate ML14056A2172014-02-27027 February 2014 Issuance of Amendments Regarding Exigent License Amendment Request to Revise Technical Specification 3.3.4, Remote Shutdown System (TAC MF3473&74) ML12194A2182012-07-0909 July 2012 Response to NRC Request for Additional Information on Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML12038A1732012-02-0101 February 2012 Proposed Tech Specs Amendment TS 3.4.13, TS 5.5.9, TS 5.6.8, License Amendment Request to Revise TS for Permanent Alternate Repair Criteria ML1106705362011-03-29029 March 2011 Issuance of Amendments Regarding Revision of the Technical Specifications to Relocate Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using a Risk-Informed Justification ML1032700112010-12-20020 December 2010 Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.4 DC Sources - Operating ML1026405372010-09-27027 September 2010 Issuance of Amendment Regarding the Steam Generator Program. ML1025601442010-09-0909 September 2010 Proposed Technical Specifications (TS) Amendment TS 5.5.9, Steam Generator (SG) Program TS 5.6.8, Steam Generator (SG) Tube Inspection Report License Amendment Request to Revise TS for Alternate Repair Criteria ML1021605622010-08-0202 August 2010 Notice of Enforcement Discretion Request, Technical Specification 3.8.1, AC Sources - Operating, TS 3.78, Nuclear Service Water System, TS 3.7.5, Auxiliary Feedwater System, TS 3.6.6, Containment Spray System. ML0925300882010-06-28028 June 2010 License Amendment, Issuance of Amendments Regarding Technical Specification Change to Allow Manual Operation of the Containment Spray System (TAC Nos. MD9752 and MD9753) ML1017303882010-04-28028 April 2010 Proposed Technical Specifications Amendment TS 5.5.9, Steam Generator Program, TS 5.6.8, Steam Generator Tube Inspection Report, License Amendment Request to Revise TS for Alternate Repair Criteria ML1009201602010-03-31031 March 2010 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML0935600772009-12-15015 December 2009 Technical Specifications Revision Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity. ML0923805882009-10-30030 October 2009 License Amendment, Implement Technical Specification Task Force (TSTF) Changes Travelers TSTF-479, Revision 0, Changes to Reflect Revision (Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a) 10 CFR 50.55a,.. ML0924003112009-09-21021 September 2009 Issuance of Amendments Regarding Proposed Implementation of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from Ts. 5.2.2 to Support Compliance with 10 CFR Part 26. Catawba Units 1& 2, McGuire, Units 1 & 2, Oconee, Units 1, 2, & ML0919503552009-07-0101 July 2009 License Amendment Request to Support Plant Modifications to the Nuclear Instrumentation System ML0914102832009-05-18018 May 2009 License Amendment Request to Revise the Definition of Shutdown Margin (SDM) ML0905402522009-02-19019 February 2009 Proposed Technical Specifications Amendment TS 5.5.9, Steam Generator Program, TS 5.6-8, Steam Generator Tube Inspection Report. ML0835704702008-12-18018 December 2008 Units 1 &2 - Proposed Technical Specification Amendment to Relax Completion Times and Surveillance Intervals for the Reactor Trip System Instrumentation TS 3.3.1, Engineered Safety Feature Actuation System Instrumentation. ML0828800982008-10-0808 October 2008 Proposed Technical Specifications and Bases Amendment, TS and Bases Administrative Changes ML0819803572008-07-15015 July 2008 Technical Specifications, Issuance of Emergency Amendment Regarding One-Time Extension of the Auxiliary Feedwater System and the Containment Spray System Allowed Outage Time ML0817700602008-06-23023 June 2008 Proposed Technical Specifications (TS) and Bases Amendment, TS and Bases 3.7.8, Nuclear Service Water System, Response to Request for Additional Information ML0806304962008-03-28028 March 2008 Technical Specifications, Issuance of Amendments Regarding a Change in Corporate Name of License & Oconee Independent Spent Fuel Storage Installation (TAC Nos. MD5156 - MD5162) ML0731803132007-11-0808 November 2007 Tech Spec Pages for Amendments 238 and 234 Regarding Emergency Core Cooling System Strainer Modification ML0730904132007-10-31031 October 2007 Technical Specifications, Issuance of Amendment Regarding Technical Specification 5.5.9 Steam Generator Tube Surveillance Program ML0730604052007-10-31031 October 2007 Tech Spec Pages for Amendment 237 Regarding Extension of Time Limit to Complete Emergency Core Cooling Systems Sump Modification ML0717703102007-06-25025 June 2007 Issuance of Amendments Regarding Emergency Diesel Generator Testing (TAC Nos. MD3217 and MD3218) - Technical Specifications ML0707903972007-03-19019 March 2007 Tech Spec Pages for Amendments 235 and 231 Regarding Snubbers, TSTF-372, Rev. 4 ML0635303422006-12-0707 December 2006 Proposed Technical Specifications (TS) Amendments TS 3.7.10 (Catawba)/Ts 3.7.9 (McGuire) - Control Room Area Ventilation System (Cravs) TS 3.7.11 (Catawba)/Ts 3.7.10 (McGuire) - Control Room Area Chilled Water System (Cracws) ML0629003532006-09-30030 September 2006 Tech Spec Pages for Amendments 234 and 230, Revising Reactor Coolant Systems Leakage Detection Instrumentation ML0627105962006-09-27027 September 2006 Tech Spec Pages for Amendments 233 and 229 Revised Storage Criteria for Low-enriched Uranium Fuel ML0626901142006-09-25025 September 2006 Technical Specifications Revision of Temperature Limits for the Standby Nuclear Service Water Pond ML0626901122006-09-25025 September 2006 Tech Spec Pages for Amendments 231 and 227 Regarding Updated Final Safety Analysis Report and Emergency Operating Procedures 2023-08-29
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TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) ......................................... 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ............................... 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality ............................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (PIT) Limits ............................... 3.4.3-1 3.4.4 RCS Loops-MODES 1 and 2 ............................... 3.4.4-1 3.4.5 RCS Loops -MODE 3 ............................... 3.4.5-1 3.4.6 RCS Loops-MODE 4 ............................... 3.4.6-1 3.4.7 RCS Loops-MODE 5, Loops Filled ............................... 3.4.7-1 3.4.8 RCS Loops-MODE 5, Loops Not Filled ............................... 3.4.8-1 3.4.9 Pressurizer................................ 3.4.9-1 3.4.10 Pressurizer Safety Valves .................... 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ..................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ..................................... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ..................................... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ..................................... 3.4.15-1 3.4.16 RCS Specific Activity ...................................... 3.4.16-1 3.4.17 RCS Loops-Test Exceptions ..................................... 3.4.17-1 3.4.18 Steam Generator (SG) Tube Integrity ..................................... 3.4.18-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ............................ 3.5.1-1 3.5.1 Accumulators ..................................... 3.5.1-1 3.5.2 ECCS-Operating ...................................... 3.5.2-1 3.5.3 ECCS-Shutdown ..................................... 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) ..................................... 3.5.4-1 3.5.5 Seal Injection Flow ..................................... 3.5.5-1 3.6 CONTAINMENT SYSTEMS ..................................... 3.6.1-1 3.6.1 Containment ..................................... 3.6.1-1 3.6.2 Containment Air Locks ..................................... 3.6.2-1 3.6.3 Containment Isolation Valves ...................................... 3.6.3-1 3.6.4 Containment Pressure ...................................... 3.6.4-1 3.6.5 Containment Air Temperature ..................................... 3.6.5-1 3.6.6 Containment Spray System..................................... 3.6.6-1 3.6.7 Not Used 3.6.8 Hydrogen Skimmer System (HSS) ...................................... 3.6.8-1 3.6.9 Hydrogen Ignition System (HIS) ..................................... 3.6.9-1 3.6.10 Annulus Ventilation System (AVS) ..................................... 3.6.10-1 3.6.11 Air Retum System (ARS) ..................................... 3.6.11-1 3.6.12 Ice Bed ..................................... 3.6.12-1 3.6.13 Ice Condenser Doors ..................................... 3.6.13-1 3.6.14 Divider Barrier Integrity..................................................................3.6.14-1 3.6.15 Containment Recirculation Drains ...................................... 3.6.15-1 3.6.16 Reactor Building ..................................... 3.6.16-1 3.6.17 Containment Valve Injection Water System (CVIWS) .................... 3.6.17-1 Catawba Units 1 and 2 ii Amendment Nos. 219 and 214
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
I ACTIONS NOTE-Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.3-1 required channels for the channel.
inoperable.
B. One or more Functions B.1 Restore required channel 30 days with one required to OPERABLE status.
channel inoperable.
C. One or more Functions C.1 Restore required channel 30 days with one required to OPERABLE status.
channel inoperable.
AND Diverse channel OPERABLE.
(continued)
Catawba Units 1 and 2 3.3.3-1 Amendment Nos. 219 and 214
PAM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action in Immediately associated Completion accordance with Time of Condition B or C Specification 5.6.7.
not met.
E. One or more Functions E.1 Restore required channel. 7 days with one required to OPERABLE status.
channel inoperable.
OR AND E.2 Restore diverse channel to 7 days Diverse channel OPERABLE status.
inoperable.
F. One or more Functions F.1 Restore one channel to 7 days with two required OPERABLE status.
channels inoperable.
G. Not Used G.1 Not Used H. Required Action and H.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition E or F AND not met.
H.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Catawba Units 1 and 2 3.3.3-2 Amendment Nos. 219 and 214
PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS
-NOTE- - -
SR 3.3.3.1 and SR 3.3.3.3 apply to each PAM instrumentation Function in Table 3.3.3-1.
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
SR 3.3.3.2 Not Used I SR 3.3.3.3 ---- NOTES
- 1. Neutron detectors are excluded from CHANNEL CALIBRATION.
- 2. CHANNEL CALIBRATION may consist of an electronic calibration of the Containment Area -
High Range Radiation Monitor, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma source.
Perform CHANNEL CALIBRATION. 18 months Catawba Units I and 2 3.3.3-3 Amendment Nos. 219 and 214
PAM Instrumentation 3.3.3
.. Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS CONDITIONS
- 1. Reactor Coolant System (RCS) Hot Leg 2 BDFH Temperature (Wide Range)
- 2. RCS Cold Leg Temperature (Wide Range) 2 BD,F,H
- 3. RCS Pressure (Wide Range) 2 B,DF,H
- 4. Reactor Vessel Water Level 2 B,D,FH
- 5. Containment Sump Water Level (Wide Range) 2 B,D.F,H
- 6. Containment Pressure (Wide Range) 2 B,D.F,H
- 7. Containment Area Radiation (High Range) 1 B.D
- 8. Not Used I
- 9. Pressurizer Level 2 B,D,FH
- 10. Steam Generator Water Level (Narrow Range) 2 per steam generator BD.FH
- 11. Core Exit Temperature - Quadrant 1 2(a) BD.FH
- 12. Core Exit Temperature - Quadrant 2 2(a) BD.FH
- 13. Core Exit Temperature - Quadrant 3 2(a) BDF.H
- 14. Core Exit Temperature - Quadrant 4 2(a) B,D,FH
- 15. Auxiliary Feedwater Flow 1 per steam generator C,D,EH
- 16. RCS Radiation Level 1 3,D
- 17. RCS Subcooling Margin Monitor 2 B,D.F.H
- 18. Steam Line Pressure 2 per steam generator B,DF.H
- 19. Refueling Water Storage Tank Level 2 B,D,F.H
- 20. Neutron Flux (Wide Range) 2 BD,FH
- 21. Steam Generator Water Level (Wide Range) 1 per steam generator C,D,E,H (a) A channel consists of two core exit thermocouples (CETs).
Catawba Units 1 and 2 - 3.3.3-4 Amendment Nos. 219 and 214