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MONTHYEARML0513102802005-04-27027 April 2005
Technical Specifications Change 04-06 - Relocation of Specifications in Accordance with Part 50.36 in Title 10 of the Code of Federal Regulations.
Project stage: Request
ML0534102722005-11-17017 November 2005
Units 1 & 2 - Technical Specifications (TS) Change 04-06, Revision 1 - Relocation of Specifications in Accordance with Part 50.36 in Title 10 of the Code of Federal Regulations (CFR)
Project stage: Request
ML0600402802005-12-28028 December 2005
TS for Amend 295, TAC MC6881, Relocation of Multiple Technical Specifications
Project stage: Other
ML0600402772005-12-28028 December 2005
TS for Amend 305, TAC MC6881, Relocation of Multiple Technical Specifications
Project stage: Other
ML0520600332005-12-28028 December 2005
Issuance of Amendments Regarding Relocation of Multiple Technical Specifications to the Requirements Manual (TAC MC6881 and MC6882) (TS 04-06)
Project stage: Approval
2005-12-28
[Table View] |
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Category:Technical Specification
MONTHYEARCNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023
Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
ML23277A0462023-10-0404 October 2023
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023
Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03
CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023
Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)
CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023
Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)
CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022
and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)
ML22145A1412022-05-16016 May 2022
Technical Specification Bases, Manual
ML22125A1272022-05-0404 May 2022
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
ML22108A2822022-04-27027 April 2022
Summary of Regulatory Audit Regarding the License Amendment Request to Revise TS to Adopt TSTF 505, Rev. 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)2021-10-22022 October 2021
Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)
CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020
Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)
CNL-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2020-09-23023 September 2020
Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)
CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019
Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)
CNL-19-072, Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03)2019-07-14014 July 2019
Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03)
ML19151A5842019-05-31031 May 2019
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018
Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays
ML17333A4012017-11-29029 November 2017
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-03-13013 March 2017
Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)
CNL-16-011, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)2016-03-11011 March 2016
Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)
CNL-15-128, Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 June 2015
Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8
ML15176A6822015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
ML15176A6792015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8
ML15176A7182015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 6 of 8
ML15176A6642015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8
ML15176A7402015-06-19019 June 2015
Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
ML15176A7482015-06-19019 June 2015
Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 8 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 82015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 82015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 82015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 82015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 82015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
ML15176A6812015-06-19019 June 2015
Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8
CNL-14-176, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03)2014-12-0202 December 2014
Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03)
ML14342B0042014-12-0101 December 2014
Cycle 19 - 180-Day Steam Generator Tube Inspection Report
ML13193A0392013-07-0505 July 2013
Revisions to the Technical Requirements Manual and Specification Bases
ML11249A0612011-08-31031 August 2011
Application for Temporary Change to TS to Allow Use of Penetrations in Shield Building Dome During Modes 1 Through 4;and Request for Specific Usage of Alternate Source Term Methodology for Calculating Radiation Doses Associated.
ML11195A1172011-07-29029 July 2011
Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956)
ML11129A1882011-05-0606 May 2011
TS 11-06, Emergency Technical Specification Change for One-Time Extension of Surveillance Requirements Associated with Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation
ML1014701582010-05-24024 May 2010
Revisions to Technical Requirements Manual and Technical Specification Bases
ML0929503402009-10-20020 October 2009
License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19
ML0833701212008-12-0101 December 2008
Revisions to the Technical Requirements Manual (TRM) and Technical Specification (TS) Bases (Unit 1 Revisions 31, 32, and 33; Unit 2 Revisions 30, 31 and 32)
ML0710101532007-04-0202 April 2007
Additional Information for Technical Specification Change 05-09 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity and Deletion of License Condition
ML0702500312007-01-12012 January 2007
Technical Specification (TS) Change 06-06 - Revised Steam Generator (SG) Voltage-Based Repair Criteria - Probability of Prior Cycle Detection (Popcd)
ML0634700292006-12-0707 December 2006
Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information
ML0635302012006-11-30030 November 2006
Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818
ML0635302082006-11-30030 November 2006
Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819
ML0622300952006-08-0202 August 2006
Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)
ML0622301112006-08-0202 August 2006
Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)
ML0621401022006-07-12012 July 2006
Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes
2023-09-20
[Table view]
Category:Amendment
MONTHYEARCNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023
Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023
Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03
CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023
Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)
CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023
Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)
CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022
and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)
ML22125A1272022-05-0404 May 2022
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
ML22108A2822022-04-27027 April 2022
Summary of Regulatory Audit Regarding the License Amendment Request to Revise TS to Adopt TSTF 505, Rev. 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020
Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)
CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019
Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)
CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-03-13013 March 2017
Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)
ML11195A1172011-07-29029 July 2011
Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956)
ML11129A1882011-05-0606 May 2011
TS 11-06, Emergency Technical Specification Change for One-Time Extension of Surveillance Requirements Associated with Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation
ML0929503402009-10-20020 October 2009
License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19
ML0635302082006-11-30030 November 2006
Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819
ML0635302012006-11-30030 November 2006
Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818
ML0622301112006-08-0202 August 2006
Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)
ML0622300952006-08-0202 August 2006
Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)
ML0610102602006-04-0606 April 2006
Technical Specification Pages Re Allowable Value for Reactor Trip System
ML0611004082006-03-30030 March 2006
Technical Specification Change 05-11, Revision to TS to Support Third 10-Year Interval Inservice Test Program, Rev 1
ML0600402802005-12-28028 December 2005
TS for Amend 295, TAC MC6881, Relocation of Multiple Technical Specifications
ML0600402772005-12-28028 December 2005
TS for Amend 305, TAC MC6881, Relocation of Multiple Technical Specifications
ML0507303032005-03-0909 March 2005
Tech Spec Pages Amendments 299 and 288, RCS & ECCS Enhancements
ML0434905992004-12-0202 December 2004
Technical Specifications Change 03-13, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process Cliip.)
ML0427204482004-09-20020 September 2004
Cycle 12 (U2C12) 12-Month Steam Generator Inspection Report
ML0426102902004-09-15015 September 2004
Issuance of Amendment Regarding, Index - Definitions 1.0
ML0407608732004-03-0505 March 2004
Technical Specifications (TS) Change 04-02, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process.
ML0407608782004-03-0505 March 2004
Technical Specifications (TS) Change 03-14, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process.
ML0227502132002-09-30030 September 2002
Technical Specification Pages for Amendment No. 279. Ice Condenser Basket Weight
ML0220005542002-07-10010 July 2002
Unit 2 - Technical Specification (TS) Change No. 02-03, Essential Raw Cooling Water (ERCW) Operability During Movement of Heavy Loads - One Time TS Change in Support of Steam Generator Replacement Project
2023-09-20
[Table view] |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) ............................................................ 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ (Z) ............................................................ 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR ............................................................ 3/4 2-10 3/4.2.4 QUADRANT POWER TILT-RATIO ............................................................ 3/4 2-12 3/4.2.5 DNB PARAMETERS ............................................................ 3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION ............................................................ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ......... 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION ............................................................ 3/4 3-39 MOVABLE INCORE DETECTORS (Deleted) ............................................................ 3/4 3-43 SEISMIC INSTRUMENTATION (Deleted) ............................................................ 3/4 3-44 METEOROLOGICAL INSTRUMENTATION (Deleted) ........................................................ 3/4 3-47 REMOTE SHUTDOWN INSTRUMENTATION ............................................................ 3/4 3-50 CHLORINE DETECTION SYSTEMS (Deleted) .................................... , . 3/4 3-54 ACCIDENT MONITORING INSTRUMENTATION .34 3-55 FIRE DETECTION INSTRUMENTATION (Deleted) .3/4 3-58 DELETED .3/4 3-70 EXPLOSIVE GAS MONITORING INSTRUMENTATION ... 3/4 3-71 SEQUOYAH - UNIT 1 V Amendment No. 62, 138, 148, 227,-245, 305
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup And Power Operation ..................................................... 3/4 4-1 Hot Standby ..................................................... 3/4 4-1a Shutdown ..................................................... 3/4 4-2 3/4.4.2 SAFETY VALVES - SHUTDOWN (Deleted) ..................................................... 3/4 4-3 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING Safety Valves - Operating ..................................................... 3/4 4-4 Relief Valves - Operating ..................................................... 3/4 4-4a 3/4.4.4 PRESSURIZER ..................................................... 3/4 4-5 3/4.4.5 STEAM GENERATORS ..................................................... 3/4 4-6 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Instrumentation ..................................................... 3/4 4-13 Operational Leakage ..................................................... 3/4 4-14 Reactor Coolant System Pressure Isolation Valve Leakage . ..............................................
3/4 4-15 3/4.4.7 CHEMISTRY (Deleted) ............................................................. 3/4 4-16 I
3/4.4.8 SPECIFIC ACTIVITY ..................................................... 3/4 4-19 3/4.4.9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System...................................................... 3/4 4-23 Pressurizer (Deleted) ..................................................... 3/4 4-26 3/4.4.10 DELETED ...................................................... 3/4 4-27 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS (Deleted) . ...............................
3/4 4-28 3/4.4.12 LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEM . ........... 3/4 4-29 I
SEQUOYAH - UNIT 1 VI Amendment No. 116, 133, 157, 208, 259, 294, 297, 299, 305
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6.3 CONTAINMENT ISOLATION VALVES .............................................. 3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS (Deleted) ..... 3/4 6-24 ELECTRIC HYDROGEN RECOMBINERS - W (Deleted) ..... 3/4 6-25 HYDROGEN MITIGATION SYSTEM ..... 3/4 6-25a 3/4.6.5 ICE CONDENSER ICE BED .............................................. 3/4 6-26 ICE BED TEMPERATURE MONITORING SYSTEM (Deleted) ........................................ 3/4 6-28 ICE CONDENSER DOORS .............................................. 3/4 6-29 INLET DOOR POSITION MONITORING SYSTEM (Deleted) .......................................... 3/4 6-31 DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EQUIPMENT HATCHES .............................................. 3/4 6-32 CONTAINMENT AIR RETURN FANS .............................................. 3/4 6-33 FLOOR DRAINS .............................................. 3/4 6-34 REFUELING CANAL DRAINS .............................................. 3/4 6-35 DIVIDER BARRIER SEAL .............................................. 3/4 6-36 3/4.6.6 VACUUM RELIEF LINES .............................................. 3/4 6-38 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES ..... 3/4 7-1 AUXILIARY FEEDWATER SYSTEM ..... 3/4 7-5 CONDENSATE STORAGE TANK .......................... 3/4 7-7 ACTIVITY . 3/4 7-8 MAIN STEAM LINE ISOLATION VALVES ......................................................... 3/4 7-10 MAIN FEEDWATER ISOLATION, REGULATING, AND BYPASS VALVES .................. 3/4 7-1Oa 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION (Deleted) ................ 3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM .............................. 3/4 7-12 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM .................................... 3/4 7-13 SEQUOYAH - UNIT I Vill Amendment No. 116, 197, 213, 232, 277, 296, 305
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.5 ULTIMATE HEAT SINK............................................ 3/4 7-14 3/4.7.6 FLOOD PROTECTION (Deleted) ............................................ 3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM ............................................ 3/4 7-17 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM ............................................ 3/4 7-19 3/4.7.9 SNUBBERS (Deleted) ............................................ 3/4 7-21 3/4.7.10 SEALED SOURCE CONTAMINATION (Deleted) ............................................ 3/4 7-29 3/4.7.11 FIRE SUPPRESSION SYSTEMS (Deleted) ............................................ 3/4 7-31 3/4.7.12 FIRE BARRIER PENETRATIONS (Deleted) ............................................ 3/4 7-41 3/4.7.13 SPENT FUEL POOL MINIMUM BORON CONCENTRATION .......................................... 3/4 7-42 3/4.7.14 CASK PIT POOL MINIMUM BORON CONCENTRATION ............................................ 3/4 7-43 3/4.7.15 CONTROL ROOM AIR-CONDITIONING SYSTEM (CRACS) . ............................
3/4 7-44 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING .... 3/4 8-1 SHUTDOWN .... 3/4 8-8 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING ......................... 3/4 8-9 A.C. DISTRIBUTION - SHUTDOWN ......................... 3/4 8-10 D.C. DISTRIBUTION - OPERATING ......................... 3/4 8-11 D.C. DISTRIBUTION - SHUTDOWN ......................... 3/4 8-14 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE
- DEVICES (Deleted).................................. .................................................... 3/4 8-15 SEQUOYAH - UNIT 1 IX Amendment No. 61, 227, 235, 247, 250, 265, 273, 305
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION (Deleted) ......................... 3/48-17 ISOLATION DEVICES (Deleted) .......................................................... 3/4 8-20 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION .3/4 9-1 3/4.9.2 INSTRUMENTATION .3/4 9-2 3/4 9.3 DECAY TIME . 3/49-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS .3/4 9-4 3/4.9.5 COMMUNICATIONS (Deleted) .3/49-5 3/4.9.6 MANIPULATOR CRANE (Deleted) .3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA (Deleted) .3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS . 3/4 9-8 LOW WATER LEVEL .3/4 9-8a 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM .3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL .3/4 9-10 3/4.9.11 SPENT FUEL PIT WATER LEVEL .3/4 9-11 3/4.9.12 AUXILIARY BUILDING GAS TREATMENT SYSTEM . 3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN .3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS .3/4 10-2 3/4.10.3 PHYSICS TESTS .3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS.3/4 10-4 3: .1
. RE C O OO A TL O S* h_..... 4_.:
.J._................................................................... 3: 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN (Deleted) ....3/410-5 SEQUOYAH - UNIT 1 - X - Amendment No.-61, 204, 213,250, 264, 305
INDEX BASES SECTION PAGE 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE ........................................................ B 3/4 4-4b 3/4.4.7 CHEMISTRY (Deleted) ..........................................................B 3/4 4-4r 3/4.4.8 SPECIFIC ACTIVITY .......................................................... B 3/44-5 3/4.4.9 RCS PRESSURE AND TEMPERATURE (PIT) LIMITS ................................................... B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY (Deleted) ........................................................ B 3/44-13 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS (Deleted) .......................................... B 3/4 4-13 3/4.4.12 LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEM ...............B 3/4 4-14 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS ........................................................ B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS ........................................................ B 3/4 5-1 3/4.5.4 BORON INJECTION SYSTEM (Deleted) ............................ ............................ B 3/4 5-2 3/4.5.5 REFUELING WATER STORAGE TANK ........................................................ B 3/4 5-3 3/4.5.6 SEAL INJECTION FLOW ........................................................ B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT............................................................................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS .........................................................B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES ........................................................ B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL ....................... B 3/4 6-4 3/4.6.5 ICE CONDENSER ........................ B 3/4 6-4 3/4.6.6 VACUUM RELIEF LINES ....................... B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE ....................... B 3/4 7-1 314.7.2 -STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION (Deleted) ..................B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM ................................. B 3/4 7-3a
-SEQUOYAH - UNIT I- XlI - - - - Aiehdmieiit No. 157, 197, 259, 294,-297, 305
INDEX BASES SECTION PAGE 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM .. ............................................ B 3/4 7-3a 3/4.7.5 ULTIMATE HEAT SINK (UHS) .............................................. B 3/47-4 3/4.7.6 FLOOD PROTECTION .B - B 3/4 7-4 4.................
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM ............................................ B 3/4 7-4 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM .. ............................................ B 3/4 7-5 3/4.7.9 SNUBBERS (Deleted) .............................................. B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION (Deleted) ............................................ B 3/4 7-7 3/4.7.11 FIRE SUPPRESSION SYSTEMS (Deleted) ..............................................B 3/4 7-7 3/4.7.12 FIRE BARRIER PENETRATIONS (Deleted) .............................................. B 3/4 7-8 3/4.7.13 SPENT FUEL POOL MINIMUM BORON CONCENTRATION ......................................... B 3/4 7-9 3/4.7.14 CASK PIT POOL MINIMUM BORON CONCENTRATION ............................................ B 3/4 7-13 3/4.7.15 CONTROL ROOM AIR-CONDITIONING SYSTEM (CRACS) ........................................ B 3/4 7-16 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS ..... B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES (Deleted) ..... B 3/4 8-2 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION ................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION .................................. ; B 3/4 9-1 3/4.9.3 DECAY TIME ................................... B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS ................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS (Deleted) ................................. B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE (Deleted) ................................. B 3/4 9-2 3/4.9.7 CRANE TRAVEL --SPENT FUEL PIT AREA (Deleted). ............................................ ;.B-3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ....................................... B 314 9-2 3/4.9.9 CONTAINMENT VENTILATION SYSTEM ...............................................B 3/4 9-3 SEQUOYAH-- UNIT 1 XIV Amendment No.: 157, 204, 227, 235,265, 273, 305
INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 This specification has been deleted.
.. .. I.
i '-, I I~~ .1 ....-
SEQUOYAH - UNIT 1 3/4 3-43 Amendment No. 19, 301, 305
INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 This specification has been deleted.
SEQUOYAH - UNIT 1 3/4 3-47 Amendment No. 301, 305
TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION This table has been deleted.
SEQUOYAH - UNIT 1 3/4 3-48 Amendment No.305
TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS This table has been deleted.
SEQUOYAH - UNIT 1 3/4 3-49 Amnendment No. 305
REACTOR COOLANT SYSTEM 3/4.4.7 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.7 This specification has been deleted.
SEQUOYAH - UNIT 1 3/4 4-16 Amendment No. 305
TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS This table has been deleted.
SEQUOYAH - UNIT 1 3/4 4-1 7 Amnendment No. 305
TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS This table has been deleted.
SEQUOYAH - UNIT 1 3/4 4-18 Amendment No. 305
REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.11 This specification has been deleted.
-SEQUOYAH--UNIT 1 3/4 4 - -Amendment Nos. 116, 123, 133, 213, 301, 305
PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2 This specification has been deleted.
SEQUOYAH - UNIT 1 3/4 7-1 1 Amendment No. 12,305
PLANT SYSTEMS 3/4.7.10 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.10 This specification has been deleted.
SEQUOYAH - UNIT 1 3/4 7-29 Amendment No. 12, 301, 30 5
PLANT SYSTEMS This page intentionally left blank.
SEQUOYAH - UNIT 1 3/4 7-30 Amendment No. 12,305
REFUELING OPERATIONS 3/4.9.5 COMMUNICATIONS LIMITING CONDITION FOR OPERATION 3.9.5 This specification has been deleted.
SEQUOYAH - UNIT 1 3/4 9-5 Amendment No. 305
REFUELING OPERATIONS 3/4.9.6 MANIPULATOR CRANE LIMITING CONDITION FOR OPERATION 3.9.6 This specification has been deleted.
SEQUOYAH - UNIT 1 3/4 9-6 Amendment No. 12,305
