Text

Developmental Revision B - Technical Specifications Table of Contents
	ML100550367
Person / Time
Site:	Watts Bar
Issue date:	02/02/2010
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
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	Download: ML100550367 (21)
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WATTS BAR - UNIT 2 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS

TABLE OF CONTENTS TABLE OF CONTENTS . i LIST OF TABLES vi LIST OF FIGURES . vii LIST OF ACRONYMS viii LIST OF EFFECTIVE PAGES .. x 1.0 USE AND APPLICATION ... 1.1-1 1.1 Definitions . 1.1-1 1.2 Logical Connectors ................... 1.2-1 1.3 Completion Times ... 1.3-1 1.4 Frequency 1.4-1 2.0 SAFETY LIMITS (SLs) . 2.0-1 2.1 SLs . 2.0-1 2.2 SL Violations . 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS . 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) - Tavg > 200°F ............... 3.1-1 3.1.2 SHUTDOWN MARGIN (SDM) - Tavg 200°F . 3.1-2 3.1.3 Core Reactivity . 3.1-3 3.1.4 Moderator Temperature Coefficient (MTC) . 3.1-5 3.1.5 Rod Group Alignment Limits .. 3.1-7 3.1.6 Shutdown Bank Insertion Limits 3.1-10 3.1.7 Control Bank Insertion Limits . 3.1-12 3.1.8 Rod Position Indication ... 3.1-15 3.1.9 PHYSICS TESTS Exceptions - MODE 1 .... 3.1-18 3.1.10 PHYSICS TESTS Exceptions - MODE 2 .... 3.1-20 3.2 POWER DISTRIBUTION LIMITS .. 3.2-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) .. 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH) ...... 3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) ...... 3.2-8 3.2.4 QUADRANT POWER TILT RATIO (QPTR) 3.2-9 (continued)

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TABLE OF CONTENTS (continued) 3.3 INSTRUMENTATION .. 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation ... 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation .. 3.3-24 3.3.3 Post Accident Monitoring (PAM) Instrumentation .. 3.3-41 3.3.4 Remote Shutdown System . 3.3-47 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation . 3.3-50 3.3.6 Containment Vent Isolation Instrumentation ............. 3.3-53 3.3.7 Control Room Emergency Ventilation System (CREVS)

Actuation Instrumentation .............. 3.3-59 3.3.8 Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation . 3.3-63 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality ... 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits . 3.4-4 3.4.4 RCS Loops - MODES 1 and 2 ... 3.4-6 3.4.5 RCS Loops - MODE 3 . 3.4-7 3.4.6 RCS Loops - MODE 4 . 3.4-9 3.4.7 RCS Loops - MODE 5, Loops Filled .... 3.4-12 3.4.8 RCS Loops - MODE 5, Loops Not Filled . 3.4-14 3.4.9 Pressurizer 3.4-16 3.4.10 Pressurizer Safety Valves .. 3.4-18 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) 3.4-20 3.4.12 Cold Overpressure Mitigation System (COMS) .. 3.4-23 3.4.13 RCS Operational LEAKAGE .. 3.4-28 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . 3.4-30 3.4.15 RCS Leakage Detection Instrumentation 3.4-33 3.4.16 RCS Specific Activity ............. 3.4-35 3.4.17 Steam Generator (SG) Tube Integrity .. 3.4-38 (continued)

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TABLE OF CONTENTS (continued) 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .............. 3.5-1 3.5.1 Accumulators 3.5-1 3.5.2 ECCS - Operating ... 3.5-3 3.5.3 ECCS - Shutdown ... 3.5-6 3.5.4 Refueling Water Storage Tank (RWST) .. 3.5-8 3.5.5 Seal Injection Flow .. 3.5-10 3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1 Containment ..... 3.6-1 3.6.2 Containment Air Locks ... 3.6-2 3.6.3 Containment Isolation Valves 3.6-7 3.6.4 Containment Pressure .... 3.6-14 3.6.5 Containment Air Temperature ... 3.6-15 3.6.6 Containment Spray System ... 3.6-17 3.6.7 DELETED . 3.6-19 3.6.8 Hydrogen Mitigation System (HMS) . 3.6-20 3.6.9 Emergency Gas Treatment System (EGTS) .. 3.6-22 3.6.10 Air Return System (ARS) 3.6-24 3.6.11 Ice Bed .. 3.6-25 3.6.12 Ice Condenser Doors .. 3.6-28 3.6.13 Divider Barrier Integrity ... 3.6-31 3.6.14 Containment Recirculation Drains 3.6-34 3.6.15 Shield Building . 3.6-36 3.7 PLANT SYSTEMS .............. 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) ........... 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) .. 3.7-4 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves ........... 3.7-6 3.7.4 Atmospheric Dump Valves (ADVs) ... 3.7-8 3.7.5 Auxiliary Feedwater (AFW) System .. 3.7-10 3.7.6 Condensate Storage Tank (CST) . 3.7-14 3.7.7 Component Cooling System (CCS) .. 3.7-16 3.7.8 Essential Raw Cooling Water (ERCW) System . 3.7-18 3.7.9 Ultimate Heat Sink (UHS) .. 3.7-20 (continued)

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TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.10 Control Room Emergency Ventilation System (CREVS) .. 3.7-21 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) 3.7-24 3.7.12 Auxiliary Building Gas Treatment System (ABGTS) .. 3.7-26 3.7.13 Fuel Storage Pool Water Level . 3.7-28 3.7.14 Secondary Specific Activity ........... 3.7-29 3.7.15 Spent Fuel Assembly Storage ... 3.7-30 3.8 ELECTRICAL POWER SYSTEMS .............. 3.8-1 3.8.1 AC Sources - Operating ...................... 3.8-1 3.8.2 AC Sources - Shutdown ...................... 3.8-15 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ............. 3.8-18 3.8.4 DC Sources - Operating ............... 3.8-21 3.8.5 DC Sources - Shutdown .............. 3.8-26 3.8.6 Battery Cell Parameters ............ 3.8-28 3.8.7 Inverters - Operating ........................... 3.8-32 3.8.8 Inverters - Shutdown ........................... 3.8-34 3.8.9 Distribution Systems - Operating ............. 3.8-36 3.8.10 Distribution Systems - Shutdown .. 3.8-38 3.9 REFUELING OPERATIONS .. 3.9-1 3.9.1 Boron Concentration ... 3.9-1 3.9.2 Unborated Water Source Isolation Valves .. 3.9-2 3.9.3 Nuclear Instrumentation ..... 3.9-3 3.9.4 Containment Penetrations .. 3.9-5 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation -

High Water Level .. 3.9-7 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation -

Low Water Level 3.9-9 3.9.7 Refueling Cavity Water Level 3.9-11 3.9.8 Reactor Building Purge Air Cleanup Units .. 3.9-12 3.9.9 Spent Fuel Pool Boron Concentration .. 3.9-13 (continued)

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TABLE OF CONTENTS (continued) 4.0 DESIGN FEATURES 4.0-1 4.1 Site . 4.0-1 4.2 Reactor Core 4.0-1 4.3 Fuel Storage . 4.0-2 5.0 ADMINISTRATIVE CONTROLS .............. 5.0-1 5.1 Responsibility ..................... 5.0-1 5.2 Organization .................................... 5.0-2 5.3 Unit Staff Qualifications .................... 5.0-4 5.4 Training ............................................ 5.0-5 5.5 Reviews and Audits .......................... 5.0-6 5.6 Technical Specifications (TS) Bases Control Program ....................... 5.0-7 5.7 Procedures, Programs, and Manuals .................... 5.0-8 5.8 Safety Function Determination Program (SFDP) ..................... 5.0-26 5.9 Reporting Requirements . 5.0-27 5.10 Record Retention ............................. 5.0-33 5.11 High Radiation Area ......................... 5.0-34 Watts Bar - Unit 2 v (developmental) B

LIST OF TABLES TABLE NO TITLE PAGE 1.1-1 MODES ................. 1.1-8 3.3.1-1 Reactor Trip System Instrumentation .... 3.3-15 3.3.2-1 Engineered Safety Features Actuation System Instrumentation ... 3.3-33 3.3.3-1 Post-Accident Monitoring Instrumentation .... 3.3-44 3.3.4-1 Remote Shutdown System Instrumentation and Controls .. 3.3-49 3.3.5-1 LOP DG Start Instrumentation ....... 3.3-52 3.3.6-1 Containment Vent Isolation Instrumentation .... 3.3-58 3.3.7-1 CREVS Actuation Instrumentation ..... 3.3-62 3.3.8-1 ABGTS Actuation Instrumentation ..... 3.3-66 3.7.1-1 OPERABLE Main Steam Safety Valves Versus Maximum Allowable Power 3.7-3 3.7.1-2 Main Steam Safety Valve Lift Settings .. 3.7-3 3.8.1-1 Diesel Generator Test Schedule ........ 3.8-14 3.8.6-1 Battery Cell Parameter Requirements ... 3.8-31 Watts Bar - Unit 2 vi (developmental) A

LIST OF FIGURES FIGURE NO. TITLE PAGE 2.1.1-1 Reactor Core Safety Limits . 2.0-2 4.1-1 Site and Exclusion Area Boundaries . 4.0-4 4.1-2 Low Population Zone ....... 4.0-5 4.3-1 Spent Fuel Storage Racks ......... 4.0-6 4.3-2 New Fuel Storage Rack Loading Pattern . 4.0-7 4.3-3 Minimum Required Burnup for Unrestricted Storage of Spent Fuel of Various Initial Enrichments .. 4.0-8 4.3-4 Minimum Required Burnup for 2x2 Checkerboard Arrangement of 2 Spent Fuel Assemblies With 2 New Fuel Assemblies of 5% Enrichment (Maximum) ...... 4.0-9 Watts Bar - Unit 2 vii (developmental) B

LIST OF ACRONYMS (Page 1 of 2)

ACRONYM TITLE ABGTS Auxiliary Building Gas Treatment System ACRP Auxiliary Control Room Panel AFD Axial Flux Difference AFW Auxiliary Feedwater System ARFS Air Return Fan System ARO All Rods Out ARV Atmospheric Relief Valve ASME American Society of Mechanical Engineers BOC Beginning of Cycle CAOC Constant Axial Offset Control CCS Component Cooling Water System CFR Code of Federal Regulations COLR Core Operating Limits Report CREVS Control Room Emergency Ventilation System CSS Containment Spray System CST Condensate Storage Tank DNB Departure from Nucleate Boiling ECCS Emergency Core Cooling System EFPD Effective Full-Power Days EGTS Emergency Gas Treatment System EOC End of Cycle ERCW Essential Raw Cooling Water ESF Engineered Safety Feature ESFAS Engineered Safety Features Actuation System HEPA High Efficiency Particulate Air HVAC Heating, Ventilating, and Air-Conditioning Watts Bar - Unit 2 viii (developmental) A

LIST OF ACRONYMS (Page 2 of 2)

ACRONYM TITLE LCO Limiting Condition For Operation MFIV Main Feedwater Isolation Valve MFRV Main Feedwater Regulation Valve MSIV Main Steam Line Isolation Valve MSSV Main Steam Safety Valve MTC Moderator Temperature Coefficient NMS Neutron Monitoring System ODCM Offsite Dose Calculation Manual PCP Process Control Program PDMS Power Distribution Monitoring System PIV Pressure Isolation Valve PORV Power-Operated Relief Valve PTLR Pressure and Temperature Limits Report QPTR Quadrant Power Tilt Ratio RAOC Relaxed Axial Offset Control RCCA Rod Cluster Control Assembly RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RTP Rated Thermal Power RTS Reactor Trip System RWST Refueling Water Storage Tank SG Steam Generator SI Safety Injection SL Safety Limit SR Surveillance Requirement UHS Ultimate Heat Sink Watts Bar - Unit 2 ix (developmental) B

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER i B 1.2-1 A ii A 1.2-2 A iii B 1.2-3 A iv A 1.3-1 A v B 1.3-2 A vi A 1.3-3 A vii B 1.3-4 A viii A 1.3-5 A ix B 1.3-6 A x B 1.3-7 A xi B 1.3-8 A xii B 1.3-9 A xiii B 1.3-10 A xiv B 1.3-11 A xv B 1.3-12 A xvi B 1.4-1 A xvii B 1.4-2 A 1.1-1 A 1.4-3 A 1.1-2 A 1.4-4 A 1.1-3 A 2.0-1 A 1.1-4 A 2.0-2 A 1.1-5 B 3.0-1 A 1.1-6 A 3.0-2 A 1.1-7 A 3.0-3 A 1.1-8 A 3.0-4 A (continued)

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