Text

Technical Specifications
	ML13357A053
Person / Time
Site:	Watts Bar
Issue date:	12/12/2013
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML13357A047	List: ML13357A048; ML13357A050; ML13357A051; ML13357A053; ML13357A054;
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	Download: ML13357A053 (369)
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TECHNICAL SPECIFICATIONS 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 N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FH ........ 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 .............. 3.3-58 3.3.8 Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation . 3.3-62 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 3.6-33 3.6.15 Shield Building . 3.6-35 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 ............... 3.8-25 3.8.6 Battery Parameters .................... 3.8-28 3.8.7 Inverters - Operating ............................ 3.8-33 3.8.8 Inverters - Shutdown ............................ 3.8-34 3.8.9 Distribution Systems - Operating ............. 3.8-37 3.8.10 Distribution Systems - Shutdown .. 3.8-39 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 THIS SECTION NOT USED ... 3.9-5 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation -

High Water Level .. 3.9-6 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation -

Low Water Level 3.9-8 3.9.7 Refueling Cavity Water Level 3.9-10 3.9.8 THIS SECTION NOT USED ... 3.9-11 3.9.9 Spent Fuel Pool Boron Concentration .. 3.9-12 3.9.10 Decay Time ............................................................................................ 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) ..................... 5.0-29 5.9 Reporting Requirements . 5.0-30 5.10 Record Retention ............................. 5.0-36 5.11 High Radiation Area ......................... 5.0-37 Watts Bar - Unit 2 v (developmental) G

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 Feature 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 .... 3.3-57 3.3.7-1 CREVS Actuation Instrumentation ..... 3.3-61 3.3.8-1 ABGTS Actuation Instrumentation ..... 3.3-64 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 H

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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 Fuel of Various 4.0-8 Initial Enrichments ................................................

4.3-4 Minimum Required Burnup for a Checkerboard Arrangement of 2 Spent and 2 New Fuel Assemblies of 5wt% U-235 Enrichment (Maximum) ........................................................................................ 4.0-9 Watts Bar - Unit 2 vii (developmental) H

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 1.1-8 A ii A 1.2-1 A iii B 1.2-2 A iv H 1.2-3 A v G 1.3-1 A vi H 1.3-2 A vii H 1.3-3 A viii A 1.3-4 A ix B 1.3-5 A x H 1.3-6 A xi G 1.3-7 A xii H 1.3-8 A xiii H 1.3-9 A xiv H 1.3-10 A xv H 1.3-11 A xvi H 1.3-12 A xvii B 1.4-1 A xviii A 1.4-2 A xix A 1.4-3 A 1.1-1 A 1.4-4 A 1.1-2 A 2.0-1 A 1.1-3 A 2.0-2 A 1.1-4 A 3.0-1 A 1.1-5 B 3.0-2 A 1.1-6 A 3.0-3 A 1.1-7 A 3.0-4 A (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 3.0-5 A 3.2-5 A 3.1-1 A 3.2-6 A 3.1-2 A 3.2-7 A 3.1-3 A 3.2-8 A 3.1-4 A 3.2-9 F 3.1-5 A 3.2-10 F 3.1-6 A 3.2-11 B 3.1-7 A 3.3-1 A 3.1-8 A 3.3-2 A 3.1-9 A 3.3-3 A 3.1-10 A 3.3-4 A 3.1-11 A 3.3-5 F 3.1-12 A 3.3-6 A 3.1-13 A 3.3-7 A 3.1-14 A 3.3-8 A 3.1-15 F 3.3-9 A 3.1-16 E 3.3-10 A 3.1-17 D 3.3-11 G 3.1-18 A 3.3-12 A 3.1-19 A 3.3-13 A 3.1-20 A 3.3-14 A 3.1-21 A 3.3-15 F 3.2-1 A 3.3-16 G 3.2-2 A 3.3-17 G 3.2-3 A 3.3-18 G 3.2-4 B 3.3-19 F (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 3.3-20 A 3.3-46 B 3.3-21 A 3.3-47 F 3.3-22 A 3.3-48 B 3.3-23 A 3.3-49 A 3.3-24 A 3.3-50 A 3.3-25 A 3.3-51 A 3.3-26 A 3.3-52 A 3.3-27 A 3.3-53 H 3.3-28 B 3.3-54 H 3.3-29 A 3.3-55 B 3.3-30 A 3.3-56 A 3.3-31 B 3.3-57 H 3.3-32 F 3.3-58 A 3.3-33 F 3.3-59 A 3.3-34 F 3.3-60 A 3.3-35 F 3.3-61 H 3.3-36 F 3.3-62 A 3.3-37 F 3.3-63 H 3.3-38 G 3.3-64 H 3.3-39 F 3.4-1 A 3.3-40 F 3.4-2 B 3.3-41 B 3.4-3 A 3.3-42 B 3.4-4 A 3.3-43 B 3.4-5 A 3.3-44 H 3.4-6 A 3.3-45 B 3.4-7 A (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 3.4-8 A 3.4-34 F 3.4-9 B 3.4-35 H 3.4-10 A 3.4-36 H 3.4-11 A 3.4-37 A 3.4-12 B 3.4-38 G 3.4-13 A 3.4-39 G 3.4-14 A 3.5-1 B 3.4-15 A 3.5-2 A 3.4-16 A 3.5-3 A 3.4-17 A 3.5-4 B 3.4-18 F 3.5-5 B 3.4-19 A 3.5-6 F 3.4-20 F 3.5-7 A 3.4-21 A 3.5-8 A 3.4-22 A 3.5-9 A 3.4-23 F 3.5-10 A 3.4-24 B 3.5-11 A 3.4-25 B 3.6-1 A 3.4-26 G 3.6-2 F 3.4-27 B 3.6-3 A 3.4-28 F 3.6-4 A 3.4-29 A 3.6-5 A 3.4-30 F 3.6-6 A 3.4-31 F 3.6-7 A 3.4-32 A 3.6-8 B 3.4-33 B 3.6-9 B (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 3.6-10 A 3.6-36 A 3.6-11 B 3.7-1 F 3.6-12 B 3.7-2 A 3.6-13 A 3.7-3 A 3.6-14 A 3.7-4 A 3.6-15 A 3.7-5 A 3.6-16 A 3.7-6 A 3.6-17 A 3.7-7 A 3.6-18 A 3.7-8 A 3.6-19 B 3.7-9 A 3.6-20 A 3.7-10 A 3.6-21 A 3.7-11 A 3.6-22 F 3.7-12 A 3.6-23 A 3.7-13 A 3.6-24 A 3.7-14 A 3.6-25 A 3.7-15 A 3.6-26 D 3.7-16 H 3.6-27 A 3.7-17 H 3.6-28 A 3.7-18 F 3.6-29 A 3.7-19 A 3.6-30 A 3.7-20 A 3.6-31 F 3.7-21 F 3.6-32 H 3.7-22 A 3.6-33 A 3.7-23 A 3.6-34 A 3.7-24 F 3.6-35 A 3.7-25 A (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 3.7-26 H 3.8-22 H 3.7-27 A 3.8-23 H 3.7-28 A 3.8-24 H 3.7-29 A 3.8-25 H 3.7-30 A 3.8-26 H 3.8-1 F 3.8-27 H 3.8-2 F 3.8-28 H 3.8-3 A 3.8-29 H 3.8-4 A 3.8-30 H 3.8-5 A 3.8-31 H 3.8-6 H 3.8-32 H 3.8-7 H 3.8-33 B 3.8-8 H 3.8-34 A 3.8-9 H 3.8-35 A 3.8-10 H 3.8-36 A 3.8-11 A 3.8-37 A 3.8-12 H 3.8-38 A 3.8-13 H 3.8-39 A 3.8-14 A 3.8-40 A 3.8-15 B 3.9-1 F 3.8-16 A 3.9-2 F 3.8-17 A 3.9-3 F 3.8-18 A 3.9-4 A 3.8-19 A 3.9-5 H 3.8-20 A 3.9-6 A 3.8-21 H 3.9-7 A (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 3.9-8 A 5.0-12 A 3.9-9 A 5.0-13 A 3.9-10 A 5.0-14 G 3.9-11 H 5.0-15 G 3.9-12 A 5.0-16 G 3.9-13 H 5.0-17 A 4.0-1 C 5.0-18 H 4.0-2 H 5.0-19 H 4.0-3 A 5.0-20 H 4.0-4 A 5.0-21 A 4.0-5 A 5.0-22 A 4.0-6 A 5.0-23 A 4.0-7 A 5.0-24 A 4.0-8 H 5.0-25 H 4.0-9 H 5.0-26 A 5.0-1 A 5.0-27 H 5.0-2 A 5.0-28 H 5.0-3 B 5.0-29 A 5.0-4 A 5.0-30 H 5.0-5 A 5.0-31 B 5.0-6 A 5.0-32 B 5.0-7 A 5.0-33 A 5.0-8 A 5.0-34 B 5.0-9 A 5.0-35 G 5.0-10 A 5.0-36 A 5.0-11 A 5.0-37 A (continued)

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES (continued)

PAGE AMENDMENT PAGE AMENDMENT NUMBER NUMBER NUMBER NUMBER 5.0-38 A 5.0-39 A 5.0-40 B Watts Bar - Unit 2 xvii (developmental) B

TECHNICAL SPECIFICATIONS - AMENDMENT LISTING (This listing is an administrative tool maintained by WBN Licensing. It may be updated without formally revising the Technical Specifications Table of Contents.)

Amendments Issued Subject Watts Bar - Unit 2 xviii (developmental) A

TECHNICAL SPECIFICATIONS - LIST OF APPROVED EXEMPTIONS (This listing is an administrative tool maintained by WBN Licensing. It may be updated without formally revising the Technical Specifications Table of Contents.)

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Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

NOTE----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux signals (AFD) between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known input. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. Whenever a sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing element.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.

(continued)

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Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or other reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the initial and current reload cycle. These cycle specific parameter limits shall be determined for the initial and each reload cycle in accordance with Specification 5.9.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977.

(continued)

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Definitions 1.1 1.1 Definitions (continued)

- AVERAGE shall be the average (weighted in proportion to the DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.

La The maximum allowable primary containment leakage rate, La, shall be .25% of primary containment air weight per day at the calculated peak containment pressure (Pa).

(continued)

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Definitions 1.1 1.1 Definitions (continued)

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary-to-secondary LEAKAGE);

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE LEAKAGE (except primary-to-secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing each master relay and verifying the OPERABILITY of each relay.

The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

(continued)

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Definitions 1.1 1.1 Definitions (continued)

OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PDMS The Power Distribution Monitoring System (PDMS) is a real-time three dimensional core monitoring system. The system utilizes existing core instrumentation data and an on-line neutronics code to provide surveillance of core thermal limits.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Chapter 14, Initial Test Program of the FSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS RCS pressure and temperature limits for heatup, cooldown, REPORT (PTLR) low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.9.6. Plant operation within these operating limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," and LCO 3.4.12, "Cold Overpressure Mitigation System (COMS)."

(continued)

Watts Bar - Unit 2 1.1-5 (developmental) B

Definitions 1.1 1.1 Definitions (continued)

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore RATIO (QPTR) detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 3411 MWt.

REACTOR TRIP SYSTEM The RTS RESPONSE TIME shall be that time interval from (RTS) RESPONSE TIME when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level.

SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay.

The SLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.

(continued)

Watts Bar - Unit 2 1.1-6 (developmental) A

Definitions 1.1 1.1 Definitions (continued)

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip actuating device OPERATIONAL TEST and verifying the OPERABILITY of required alarm, interlock, (TADOT) display, and trip functions. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

Watts Bar - Unit 2 1.1-7 (developmental) A

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES AVERAGE REACTIVITY % RATED REACTOR COOLANT CONDITION THERMAL TEMPERATURE MODE TITLE (keff) POWER (a) (°F) 1 Power Operation 0.99 >5 NA 2 Startup 0.99 <5 NA 3 Hot Standby < 0.99 NA 350 4 Hot Shutdown (b) < 0.99 NA 350 > Tavg > 200 5 Cold Shutdown (b) < 0.99 NA < 200 6 Refueling (c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

Watts Bar - Unit 2 1.1-8 (developmental) A

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

(continued)

Watts Bar - Unit 2 1.2-1 (developmental) A

Logical Connectors 1.2 1.2 Logical Connectors (Continued)

EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify . . .

AND A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

(continued)

Watts Bar - Unit 2 1.2-2 (developmental) A

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Watts Bar - Unit 2 1.2-3 (developmental) A

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

Watts Bar - Unit 2 1.3-1 (developmental) A

Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent train, subsystem, component, or variable (continued) expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended.

(continued)

Watts Bar - Unit 2 1.3-2 (developmental) A

Completion Times 1.3 1.3 Completion Times (continued)

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

Watts Bar - Unit 2 1.3-3 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

(continued)

Watts Bar - Unit 2 1.3-4 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

(continued)

Watts Bar - Unit 2 1.3-5 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore Function X 7 days train train to OPERABLE inoperable. status. AND 10 days from discovery of failure to meet the LCO B. One Function Y B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train train to OPERABLE inoperable. status AND 10 days from discovery of failure to meet the LCO C. One Function X C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train train to OPERABLE inoperable. status.

AND OR One Function Y C.2 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable train to OPERABLE status.

(continued)

Watts Bar - Unit 2 1.3-6 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

(continued)

Watts Bar - Unit 2 1.3-7 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (including the extension) expires while one or more valves are still inoperable, Condition B is entered.

(continued)

Watts Bar - Unit 2 1.3-8 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

ACTIONS

NOTE--------------------------------------------

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required Action B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion AND Time not met.

B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

(continued)

Watts Bar - Unit 2 1.3-9 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to 50% RTP.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "Once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

(continued)

Watts Bar - Unit 2 1.3-10 (developmental) A

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable subsystem isolated.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required Action B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion AND Time not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

(continued)

Watts Bar - Unit 2 1.3-11 (developmental) A

Completion Times 1.3 1.3 Completion Times IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Watts Bar - Unit 2 1.3-12 (developmental) A

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

(continued)

Watts Bar - Unit 2 1.4-1 (developmental) A

Frequency 1.4 1.4 Frequency (Continued)

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3 EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

(continued)

Watts Bar - Unit 2 1.4-2 (developmental) A

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

(continued)

Watts Bar - Unit 2 1.4-3 (developmental) A

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE--------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP.

Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches 25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency and the provisions of SR 3.0.3 would apply.

Watts Bar - Unit 2 1.4-4 (developmental) A

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the SLs specified in Figure 2.1.1-1.

2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

2.2.3 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.4 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the Plant Manager and Site Vice President.

2.2.5 Within 30 days a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the NSRB, the Plant Manager, and Site Vice President.

2.2.6 Operation of the unit shall not be resumed until authorized by the NRC.

Watts Bar - Unit 2 2.0-1 (developmental) A

SLs 2.0 Figure 2.1.1-1 (page 1 of 1)

Reactor Core Safety Limits Watts Bar - Unit 2 2.0-2 (developmental) A

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; (continued)

Watts Bar - Unit 2 3.0-1 (developmental) A

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 b. After performance of a risk assessment addressing inoperable (continued) systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, additional evaluations and limitations may be required in accordance with Specification 5.7.2.18, "Safety Function Determination Program (SFDP)."

If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

(continued)

Watts Bar - Unit 2 3.0-2 (developmental) A

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued)

LCO 3.0.7 Test Exception LCOs 3.1.9 and 3.1.10 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

Watts Bar - Unit 2 3.0-3 (developmental) A

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.

Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per . . ."

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

(continued)

Watts Bar - Unit 2 3.0-4 (developmental) A

SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Watts Bar - Unit 2 3.0-5 (developmental) A

SDM - Tavg > 200°F 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) - Tavg > 200°F LCO 3.1.1 SDM shall be > 1.6% k/k.

APPLICABILITY: MODE 2 with keff < 1.0, MODES 3 and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is > 1.6% k/k. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Watts Bar - Unit 2 3.1-1 (developmental) A

SDM - Tavg < 200°F 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 SHUTDOWN MARGIN (SDM) - Tavg < 200°F LCO 3.1.2 The SDM shall be 1.0% k/k.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify SDM is 1.0% k/k. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Watts Bar - Unit 2 3.1-2 (developmental) A

Core Reactivity 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Core Reactivity LCO 3.1.3 The measured core reactivity shall be within +/- 1% k/k of predicted values.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core reactivity A.1 Re-evaluate core design 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months not within limit. and safety analysis, and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months operating restrictions and SRs.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Watts Bar - Unit 2 3.1-3 (developmental) A

Core Reactivity 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 ------------------------------NOTE-------------------------------

The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading.

Verify measured core reactivity is within +/- 1% k/k of Once prior to predicted values. entering MODE 1 after initial fuel loading and each refueling AND

NOTE---------

Only required after 60 EFPD 31 EFPD thereafter Watts Bar - Unit 2 3.1-4 (developmental) A

MTC 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 The MTC shall be maintained within the limits specified in the COLR. The maximum upper limit shall be 0 k/k°F at hot zero power.

APPLICABILITY: MODE 1 and MODE 2 with keff 1.0 for the upper MTC limit, MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper limit. A.1 Establish administrative 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time keff < 1.0.

of Condition A not met.

C. MTC not within lower limit. C.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.1-5 (developmental) A

MTC 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify MTC is within upper limit Once prior to entering MODE 1 after initial fuel loading and each refueling SR 3.1.4.2 Verify MTC is within 300 ppm Surveillance limit ----------NOTE---------

specified in the COLR. Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm Once each cycle SR 3.1.4.3 -------------------------------NOTES---------------------------- ----------NOTE---------

1. If the MTC is more negative than the 300 ppm Not required to be Surveillance limit (not LCO limit) specified in the performed until COLR, SR 3.1.4.3 shall be repeated once per 7 EFPD after 14 EFPD during the remainder of the fuel cycle. reaching the equivalent of an

2. SR 3.1.4.3 need not be repeated if the MTC equilibrium measured at the equivalent of equilibrium RTP-ARO boron RTP-ARO boron concentration of < 60 ppm is concentration of less negative than the 60 ppm Surveillance limit 300 ppm specified in the COLR. ---------------------------

Verify MTC is within lower limit. Once each cycle Watts Bar - Unit 2 3.1-6 (developmental) A

Rod Group Alignment Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Rod Group Alignment Limits LCO 3.1.5 All shutdown and control rods shall be OPERABLE, with all individual indicated rod positions within 12 steps of their group step counter demand position.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months untrippable. 1.6% k/k.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. One rod not within B.1 Restore rod to within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months alignment limits. alignment limits.

OR B.2.1.1 Verify SDM is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1.6% k/k.

OR B.2.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND (continued)

Watts Bar - Unit 2 3.1-7 (developmental) A

Rod Group Alignment Limits 3.1.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < 75% RTP.

AND B.2.3 Verify SDM is Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.6% k/k.

AND B.2.4 Perform SR 3.2.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2.5 Perform SR 3.2.2.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2.6 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B not met.

D. More than one rod not D.1.1 Verify SDM is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within alignment limit. 1.6% k/k.

OR D.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required SDM to within limit.

AND D.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Watts Bar - Unit 2 3.1-8 (developmental) A

Rod Group Alignment Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify individual rod positions within alignment limit. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when the rod position deviation monitor is inoperable SR 3.1.5.2 Verify rod freedom of movement (tripability) by 92 days moving each rod not fully inserted in the core 10 steps in either direction.

SR 3.1.5.3 Verify rod drop time of each rod, from the fully Prior to reactor withdrawn position, is < 2.7 seconds from the criticality after initial beginning of decay of stationary gripper coil voltage fuel loading and to dashpot entry, with: each removal of the reactor head

a. Tavg 551°F; and

b. All reactor coolant pumps operating.

Watts Bar - Unit 2 3.1-9 (developmental) A

Shutdown Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Shutdown Bank Insertion Limits LCO 3.1.6 Each shutdown bank shall be within insertion limits specified in the COLR.

APPLICABILITY: MODE 1, MODE 2 with any control bank not fully inserted.

NOTE--------------------------------------------

This LCO is not applicable while performing SR 3.1.5.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.1.1 Verify SDM is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months banks not within limits. 1.6% k/k.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Restore shutdown banks 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Watts Bar - Unit 2 3.1-10 (developmental) A

Shutdown Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify each shutdown bank is within the limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR Watts Bar - Unit 2 3.1-11 (developmental) A

Control Bank Insertion Limits 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Control Bank Insertion Limits LCO 3.1.7 Control banks shall be within the insertion, sequence, and overlap limits specified in the COLR APPLICABILITY: MODE 1, MODE 2 with keff 1.0.

NOTE--------------------------------------------

This LCO is not applicable while performing SR 3.1.5.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion limits A.1.1 Verify SDM is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not met. 1.6% k/k.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Restore control bank(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months within limits.

(continued)

Watts Bar - Unit 2 3.1-12 (developmental) A

Control Bank Insertion Limits 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence or B.1.1 Verify SDM is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months overlap limits not met. 1.6% k/k.

OR B.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND B.2 Restore control bank 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sequence and overlap to within limits.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify estimated critical control bank position is within Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior the limits specified in the COLR. to achieving criticality (continued)

Watts Bar - Unit 2 3.1-13 (developmental) A

Control Bank Insertion Limits 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.2 Verify each control bank insertion is within the limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR.

AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when the rod insertion limit monitor is inoperable SR 3.1.7.3 Verify sequence and overlap limits specified in the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months COLR are met for control banks not fully withdrawn from the core.

Watts Bar - Unit 2 3.1-14 (developmental) A

Rod Position Indication 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Rod Position Indication LCO 3.1.8 The Rod Position Indication (RPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each inoperable rod position indicator per group and each demand position indicator per bank.

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE----------------- A.1 Verify the position of the Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Rod position monitoring by rods with inoperable Required Actions A.2.1 and position indicators by A.2.2 may only be applied to using the PDMS.

one inoperable RPI and shall only be allowed: (1) until the OR end of the current cycle, or (2) until an entry into MODE 5 A.2.1 Verify the position of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of sufficient duration, whichever rod with the inoperable occurs first, when the repair of position indicator by using AND the inoperable RPI can safely the PDMS.

be performed. Required Once every 31 days Actions A.2.1, A.2.2 and A.2.3 thereafter shall not be allowed after the AND plant has been in MODE 5 or other plant condition, for a 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , if rod control sufficient period of time, in system parameters which the repair of the indicate unintended inoperable RPI could have movement safely been performed.

A. One RPI per group AND inoperable for one or more groups.

(continued)

Watts Bar - Unit 2 3.1-15 (developmental) F

Rod Position Indication 3.1.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Review the parameters of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months the rod control system for indications of unintended AND rod movement for the rod with an inoperable Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months position indicator. thereafter AND A.2.3 Verify the position of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , if the rod rod with an inoperable with an inoperable position indicator by using position indicator is the PDMS. moved greater than 12 steps.

AND Prior to increasing THERMAL POWER above 50% RTP and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of reaching 100% RTP OR A.3 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to less than or equal to 50% RTP.

B. One or more rods with B.1 Verify the position of the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable position rods with inoperable indicators have been moved position indicators by in excess of 24 steps in one using the PDMS.

direction since the last determination of the rod's OR position.

B.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to less than or equal to 50% RTP.

(continued)

Watts Bar - Unit 2 3.1-16 (developmental) E

Rod Position Indication 3.1.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One demand position C.1.1 Verify by administrative Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months indicator per bank means all RPIs for the inoperable for one or more affected banks are banks. OPERABLE.

AND C.1.2 Verify the most withdrawn Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rod and the least withdrawn rod of the affected banks are less than or equal to 12 steps apart.

OR C.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to less than or equal to 50% RTP.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify each RPI agrees within 12 steps of the group 18 months demand position for the full indicated range of rod travel.

Watts Bar - Unit 2 3.1-17 (developmental) D

PHYSICS TESTS Exceptions - MODE 1 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 PHYSICS TESTS Exceptions - MODE 1 LCO 3.1.9 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.5, "Rod Group Alignment Limits";

LCO 3.1.6, "Shutdown Bank Insertion Limits";

LCO 3.1.7, "Control Bank Insertion Limits";

LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)"; and LCO 3.2.4, "QUADRANT POWER TILT RATIO (QPTR)"

may be suspended, provided:

a. THERMAL POWER is maintained 85% RTP;

b. Power Range Neutron Flux - High trip setpoints are 10% RTP above the THERMAL POWER at which the test is performed, with a maximum setting of 90% RTP; and

c. SDM is 1.6% k/k.

APPLICABILITY: MODE 1 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

AND A.2 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TESTS exceptions.

(continued)

Watts Bar - Unit 2 3.1-18 (developmental) A

PHYSICS TESTS Exceptions - MODE 1 3.1.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. THERMAL POWER not B.1 Reduce THERMAL 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limit. POWER to within limit.

OR B.2 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TESTS exceptions C. Power Range Neutron C.1 Restore Power Range 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Flux - High trip setpoints Neutron Flux - High trip

> 10% RTP above the setpoints to 10% above PHYSICS TEST power the PHYSICS TEST level. power level, or to 90% RTP, whichever is OR lower.

Power Range Neutron OR Flux - High trip setpoints

> 90% RTP. C.2 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TESTS exceptions.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify THERMAL POWER is 85% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.1.9.2 Verify Power Range Neutron Flux - High trip Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior setpoints are 10% above the PHYSICS TESTS to initiation of power level, and 90% RTP. PHYSICS TESTS SR 3.1.9.3 Perform SR 3.2.1.1 and SR 3.2.2.1. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.1.9.4 Verify SDM is 1.6% k/k. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Watts Bar - Unit 2 3.1-19 (developmental) A

PHYSICS TESTS Exceptions - MODE 2 3.1.10 3.1 REACTIVITY CONTROL SYSTEMS 3.1.10 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.10 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.4, "Moderator Temperature Coefficient (MTC)";

LCO 3.1.5, "Rod Group Alignment Limits";

LCO 3.1.6, "Shutdown Bank Insertion Limits";

LCO 3.1.7, "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended, and the number of required channels for LCO 3.3.1, RTS Instrumentation, Functions 2, 3, 6, and 16.e, may be reduced to 3 required channels provided:

a. RCS lowest loop average temperature is 541°F; and

b. SDM is 1.6% k/k.

APPLICABILITY: MODE 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

AND A.2 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TESTS exceptions.

B. THERMAL POWER not B.1 Open reactor trip Immediately within limit. breakers.

(continued)

Watts Bar - Unit 2 3.1-20 (developmental) A

PHYSICS TESTS Exceptions - MODE 2 3.1.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RCS lowest loop average C.1 Restore RCS lowest loop 15 minutes temperature not within limit. average temperature to within limit.

D. Required Action and D.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.10.1 Perform a CHANNEL OPERATIONAL TEST on Prior to initiation of power range and intermediate range channels per PHYSICS TESTS SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1-1.

SR 3.1.10.2 Verify the RCS lowest loop average temperature is 30 minutes 541°F.

SR 3.1.10.3 Verify SDM is 1.6% k/k. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Watts Bar - Unit 2 3.1-21 (developmental) A

FQ (Z) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ (Z))

LCO 3.2.1 FQ (Z), as approximated by FQC (Z) and FQW (Z), shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FQC (Z) not within limit. A.1 Reduce THERMAL 15 minutes POWER 1% RTP for each 1% FQC (Z) exceeds limit.

AND A.2 Reduce Power Range 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Neutron FluxHigh trip setpoints > 1% for each 1% FQC (Z) exceeds limit.

AND A.3 Reduce Overpower T 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip setpoints 1% for each 1% FQC (Z) exceeds limit.

AND A.4 Perform SR 3.2.1.1. Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)

Watts Bar - Unit 2 3.2-1 (developmental) A

FQ (Z) 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. FQW (Z) not within limits. B.1 Reduce AFD limits 1% 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for each 1% FQW (Z) exceeds limit.

C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Watts Bar - Unit 2 3.2-2 (developmental) A

FQ (Z) 3.2.1 SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.

SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify FQC (Z) is within limit. Once after initial fuel loading and each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQC (Z) was last verified AND 31 EFPD thereafter (continued)

Watts Bar - Unit 2 3.2-3 (developmental) A

FQ (Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 -------------------------------NOTE------------------------------

If FQW (Z) is within limits and measurements indicate maximum over z has increased since the previous evaluation of FQC (Z):

a. Increase FQW (Z) by the appropriate factor specified in the COLR and reverify FQW (Z) is within limits; or

b. Repeat SR 3.2.1.2 once per 7 EFPD using the Power Distribution Monitoring System (PDMS) until two successive incore power distribution measurements indicate maximum over z has not increased.

Verify FQW (Z) is within limit. Once after initial fuel loading and each refueling prior to THERMAL POWER exceeding 75% RTP AND (continued)

Watts Bar - Unit 2 3.2-4 (developmental) B

FQ (Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued) Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQW (Z) was last verified AND 31 EFPD thereafter Watts Bar - Unit 2 3.2-5 (developmental) A

N FH 3.2.2 3.2 POWER DISTRIBUTION LIMITS N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH )

LCO 3.2.2 N FH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE----------------- A.1.1 N 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Restore FH to within Required Actions A.2 limit.

and A.3 must be completed whenever Condition A is OR entered.

A.1.2.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 50% RTP.

N FH not within limit.

AND A.1.2.2 Reduce Power Range 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Neutron FluxHigh trip setpoints to 55% RTP.

AND A.2 Perform SR 3.2.2.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND (continued)

Watts Bar - Unit 2 3.2-6 (developmental) A

N FH 3.2.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 -------------NOTE------------

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1. Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER reaching 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 N Once after initial fuel Verify FH is within limits specified in the COLR.

loading and each refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter Watts Bar - Unit 2 3.2-7 (developmental) A

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.

NOTE--------------------------------------------

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL 30 minutes POWER to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore 7 days channel.

AND Once within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months thereafter with the AFD monitor alarm inoperable Watts Bar - Unit 2 3.2-8 (developmental) A

QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be 1.02.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER 3% from RTP for each 1% of QPTR

> 1.00.

AND A.2 Perform SR 3.2.4.1 and Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reduce THERMAL thereafter POWER 3% from RTP for each 1% of QPTR

> 1.00.

AND A.3 Perform SR 3.2.1.1 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.2.2.1.

AND Once per 7 days thereafter AND A.4 Reevaluate safety Prior to increasing analyses and confirm THERMAL POWER results remain valid for above the limit of duration of operation Required Action A.1 under this condition.

AND (continued)

Watts Bar - Unit 2 3.2-9 (developmental) F

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. A.5 ------------NOTE-------------

Perform Required Action A.5 only after Required Action A.4 is completed.

Calibrate excore Prior to increasing detectors to show QPTR THERMAL POWER of 1.0. above the limit of Required Action A.1 AND A.6 ------------NOTE-------------

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1 and Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after SR 3.2.2.1. reaching RTP OR Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1 B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to 50% RTP.

Time not met.

Watts Bar - Unit 2 3.2-10 (developmental) F

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 -------------------------------NOTES----------------------------

a. With input from one power range neutron flux channel inoperable and THERMAL POWER

< 75% RTP, the remaining three power range channels can be used for calculating QPTR.

b. SR 3.2.4.2 may be performed in lieu of this Surveillance if adequate power range neutron flux channel inputs are not OPERABLE.

Verify QPTR is within limit by calculation. 7 days AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter with the QPTR alarm inoperable SR 3.2.4.2 -------------------------------NOTE------------------------------

Only required to be performed if input from one or more power range neutron flux channels are inoperable with THERMAL POWER 75% RTP.

Verify QPTR is within limit using the PDMS. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Watts Bar - Unit 2 3.2-11 (developmental) B

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Enter the Condition Immediately one or more required referenced in channels inoperable. Table 3.3.1-1 for the channel(s).

B. One Manual Reactor Trip B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months channel inoperable. OPERABLE status.

OR B.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Open reactor trip 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months breakers (RTBs).

(continued)

Watts Bar - Unit 2 3.3-1 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train C.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

OR C.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months D. One Power Range Neutron --------------------NOTE-------------------

Flux-High channel The inoperable channel may be inoperable. bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment of other channels.

D.1.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND D.1.2 Reduce THERMAL 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to 75% RTP.

OR D.2.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND

NOTE-------------------

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

D.2.2 Perform SR 3.2.4.2. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR D.3 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

Watts Bar - Unit 2 3.3-2 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. --------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months F. THERMAL POWER > P-6 F.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and < P-10, one POWER to < P-6.

Intermediate Range Neutron Flux channel OR inoperable.

F.2 Increase THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to > P-10.

G. THERMAL POWER > P-6 G.1 Suspend operations Immediately and < P-10, two involving positive Intermediate Range reactivity additions.

Neutron Flux channels inoperable. AND G.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < P-6.

H. THERMAL POWER < P-6, H.1 Restore channel(s) to Prior to increasing one or two Intermediate OPERABLE status. THERMAL POWER Range Neutron Flux to > P-6 channels inoperable.

I. One Source Range Neutron I.1 Suspend operations Immediately Flux channel inoperable. involving positive reactivity additions.

(continued)

Watts Bar - Unit 2 3.3-3 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. Two Source Range Neutron J.1 Open RTBs. Immediately Flux channels inoperable.

K. One Source Range Neutron K.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Flux channel inoperable. OPERABLE status.

OR K.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months L. Required Source Range L.1 Suspend operations Immediately Neutron Flux channel involving positive inoperable. reactivity additions.

AND L.2 Close unborated water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months source isolation valves.

AND L.3 Perform SR 3.1.1.1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

Watts Bar - Unit 2 3.3-4 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. One channel inoperable. --------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

M.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR M.2 Reduce THERMAL 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-7.

N. One Reactor Coolant --------------------NOTE-------------------

Flow - Low channel One channel may be bypassed for inoperable. up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

N.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR N.2 Reduce THERMAL 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-7.

(continued)

Watts Bar - Unit 2 3.3-5 (developmental) F

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. One Low Fluid Oil Pressure --------------------NOTE-------------------

Turbine Trip channel The inoperable channel may be inoperable. bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

O.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR O.2 Reduce THERMAL 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-9.

P. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

P.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR P.2 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months (continued)

Watts Bar - Unit 2 3.3-6 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. One RTB train inoperable. --------------------NOTE-----------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing, provided the other train is OPERABLE.

Q.1 Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR Q.2 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months R. One channel inoperable. R.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required state for existing unit conditions.

OR R.2 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months S. One channel inoperable. S.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required state for existing unit conditions.

OR S.2 Be in MODE 2. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months (continued)

Watts Bar - Unit 2 3.3-7 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One trip mechanism T.1 Restore inoperable trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable for one RTB. mechanism to OPERABLE status.

OR T.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND T.2.2 Open RTB. 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months U. One Steam Generator --------------------NOTE-------------------

Water Level - Low-Low One channel may be bypassed channel inoperable. for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

U.1.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND U.1.2 For the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

OR U.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

Watts Bar - Unit 2 3.3-8 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME V. One Vessel T channel --------------------NOTE-------------------

inoperable. One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

V.1 Set the Trip Time Delay 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months threshold power level for (Ts) and (Tm) to 0% power.

OR V.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months W. One channel inoperable. --------------------NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

W.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR W.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months X. One channel inoperable. --------------------NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

X.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR X.2 Reduce THERMAL 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-7.

(continued)

Watts Bar - Unit 2 3.3-9 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Y. One, two or three Turbine Y.1 Place channel(s) in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Stop Valve Closure channels inoperable. OR Y.2 Reduce THERMAL 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-9.

Z. Two RTS Trains inoperable. Z.1 Enter LCO 3.0.3. Immediately SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2 -------------------------------NOTES----------------------------

1. Adjust NIS channel if absolute difference is > 2%.

2. Required to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculation to Nuclear Instrumentation System (NIS) channel output.

(continued)

Watts Bar - Unit 2 3.3-10 (developmental) A

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.3 -------------------------------NOTES----------------------------

1. Adjust NIS channel if absolute difference is 3%.

2. Required to be performed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after THERMAL POWER is 25% RTP.

Compare results of the PDMS measurements to 31 effective full NIS AFD. power days (EFPD)

SR 3.3.1.4 -------------------------------NOTE------------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT. 62 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.1.6 -------------------------------NOTE------------------------------

Required to be performed within 6 days after THERMAL POWER is 50% RTP.

Calibrate excore channels to agree with the PDMS 92 EFPD measurements.

(continued)

Watts Bar - Unit 2 3.3-11 (developmental) G

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.7 -------------------------------NOTE------------------------------

For Functions 2 and 3 (Power Range Instrumentation), this Surveillance shall include verification that interlock P-10 is in the required state for existing unit conditions.

Perform COT. 184 days SR 3.3.1.8 -------------------------------NOTES---------------------------- ----------NOTE---------

1. Not required to be performed for Source Range Only required when instrumentation prior to entering MODE 3 from not performed within MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3. previous 31 days

2. This Surveillance shall include verification that interlock P-6 is in the required state for existing unit conditions.

Perform COT. Prior to reactor startup AND Four hours after reducing power below P-10 for intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 31 days thereafter (continued)

Watts Bar - Unit 2 3.3-12 (developmental) A

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.9 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT. 92 days SR 3.3.1.10 -------------------------------NOTE------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.11 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.12 Perform COT. 18 months SR 3.3.1.13 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months (continued)

Watts Bar - Unit 2 3.3-13 (developmental) A

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.14 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT. Prior to exceeding the P-9 interlock whenever the unit has been in Mode 3, if not performed within the previous 31 days.

SR 3.3.1.15 -------------------------------NOTE------------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits. 18 months on a STAGGERED TEST BASIS Watts Bar - Unit 2 3.3-14 (developmental) A

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

1. Manual Reactor Trip 1, 2 2 B SR 3.3.1.13 NA NA (a) (a) (a) 3 ,4 ,5 2 C SR 3.3.1.13 NA NA

2. Power Range Neutron Flux

a. High 1, 2 4 D SR 3.3.1.1 111.4% RTP 109% RTP SR 3.3.1.2 (b)(c)

SR 3.3.1.7 (b)(c)

SR 3.3.1.11 SR 3.3.1.15 (d)

b. Low 1 ,2 4 E SR 3.3.1.1 27.4% RTP 25% RTP (b)(c)

SR 3.3.1.7 (b)(c)

SR 3.3.1.11 SR 3.3.1.15

3. Power Range Neutron Flux Rate (b)(c)

a. High Positive 1, 2 4 E SR 3.3.1.7 6.3% RTP 5% RTP (b)(c)

Rate SR 3.3.1.11 with time with time constant constant 2 sec 2 sec

b. High Negative Rate - DELETED (d) (e)

4. Intermediate Range 1 ,2 2 F, G SR 3.3.1.1 40% RTP 25% RTP (b)(c)

Neutron Flux SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (f) 2 2 H SR 3.3.1.1 40% RTP 25% RTP (b)(c)

SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (continued)

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b) If the as found channel setpoint is outside its predefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(d) Below the P-10 (Power Range Neutron Flux) interlocks.

(e) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

Watts Bar - Unit 2 3.3-15 (developmental) F

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT (f)

5. Source Range 2 2 I, J SR 3.3.1.1 1.33 E5 cps 1.0 E5 cps (b)(c)

Neutron Flux SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (a) (a) (a) 3 ,4 ,5 2 J, K SR 3.3.1.1 1.33 E5 cps 1.0 E5 cps (b)(c)

SR 3.3.1.8 (b)(c)

SR 3.3.1.11 SR 3.3.1.15 (g) (g) (g) 3 ,4 ,5 1 L SR 3.3.1.1 N/A N/A (b)(c)

SR 3.3.1.11

6. Overtemperature T 1, 2 4 W SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 Note 1 SR 3.3.1.6 (Page 3.3-21) (Page 3.3-21)

(b)(c)

SR 3.3.1.7 (b)(c)

SR 3.3.1.10 SR 3.3.1.15

7. Overpower T 1, 2 4 W SR 3.3.1.1 Refer to Refer to (b)(c)

SR 3.3.1.7 Note 2 Note 2 SR 3.3.1.10 (b)(c) (Page 3.3-22) (Page 3.3-22)

SR 3.3.1.15

8. Pressurizer Pressure (h)

a. Low 1 4 X SR 3.3.1.1 1964.8 psig 1970 psig (b)(c)

SR 3.3.1.7 (b)(c)

SR 3.3.1.10 SR 3.3.1.15

b. High 1, 2 4 W SR 3.3.1.1 2390.2 psig 2385 psig (b)(c)

SR 3.3.1.7 (b)(c)

SR 3.3.1.10 SR 3.3.1.15 (continued)

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b) If the as found channel setpoint is outside its predefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(g) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock.

Watts Bar - Unit 2 3.3-16 (developmental) G

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT (h)

9. Pressurizer Water 1 3 X SR 3.3.1.1 92.7% span 92% span (b)(c)

Level-High SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (h)

10. Reactor Coolant Flow - 1 3 per loop N SR 3.3.1.1 89.7% flow 90% flow (b)(c)

Low SR 3.3.1.7 (b)(c)

SR 3.3.1.10 SR 3.3.1.15 (h)

11. Undervoltage RCPs 1 1 per bus M SR 3.3.1.9 5112 V 5400 V (b)(c)

SR 3.3.1.10 SR 3.3.1.15 (h)

12. Underfrequency RCPs 1 1 per bus M SR 3.3.1.9 56.9 Hz 57.5 Hz (b)(c)

SR 3.3.1.10 SR 3.3.1.15 (continued)

(b) If the as found channel setpoint is outside its predefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock.

Watts Bar - Unit 2 3.3-17 (developmental) G

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

13. SG Water Level - 1, 2 3/SG U SR 3.3.1.1 16.4% of 17% of narrow (b)(c)

Low-Low SR 3.3.1.7 narrow range range span SR 3.3.1.10 (b)(c) span SR 3.3.1.15 Coincident with:

(b)(c) a) Vessel T 1, 2 3 V SR 3.3.1.7 Vessel T Vessel T (b)(c)

Equivalent to SR 3.3.1.10 variable input variable input power 52.6% RTP 50% RTP 50% RTP With a time 1.01 Ts Ts delay (Ts) if one (Refer to (Refer to steam generator Note 3, Note 3, is affected Page 3.3-23) Page 3.3-23) or A time delay (Tm) 1.01 Tm Tm if two or more (Refer to (Refer to steam Note 3, Note 3, generators are Page 3.3-23) Page 3.3-23) affected (b)(c) b) Vessel T 1, 2 3 V SR 3.3.1.7 Vessel T Vessel T (b)(c)

Equivalent to SR 3.3.1.10 variable input variable input power 52.6% RTP 50% RTP

> 50% RTP with no time delay (Ts and Tm = 0)

14. Turbine Trip (i)

a. Low Fluid Oil 1 3 O 38.3 psig 45 psig Pressure SR 3.3.1.14 (i)

b. Turbine Stop 1 4 Y SR 3.3.1.10 1% open 1% open Valve Closure SR 3.3.1.14 (continued)

(b) If the as found channel setpoint is outside its predefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(i) Above the P-9 (Power Range Neutron Flux) interlock.

Watts Bar - Unit 2 3.3-18 (developmental) G

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

15. Safety Injection (SI) 1, 2 2 trains P SR 3.3.1.13 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)

16. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 (f)

(1) Enable 2 2 R SR 3.3.1.11 NA 1.66E-04%

Manual SR 3.3.1.12 RTP Block of SR Trip (f)

(2) Auto Reset 2 2 R SR 3.3.1.11 7.65E-5% 0.47E-4% RTP (Unblock SR 3.3.1.12 RTP below setpoint Manual Block of SR Trip)

b. Low Power 1 1 per train S SR 3.3.1.11 NA NA Reactor Trips SR 3.3.1.12 Block, P-7

c. Power Range 1 4 S SR 3.3.1.11 50.4% RTP 48% RTP Neutron Flux, SR 3.3.1.12 P-8

d. Power Range 1 4 S SR 3.3.1.11 52.4% RTP 50% RTP Neutron Flux, SR 3.3.1.12 P-9

e. Power Range 1, 2 4 R SR 3.3.1.11 7.6% RTP 10% RTP Neutron Flux, SR 3.3.1.12 and P-10 12.4% RTP

f. Turbine Impulse 1 2 S SR 3.3.1.10 12.4% 10%

Pressure, P-13 SR 3.3.1.12 full-power full-power pressure pressure (continued)

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

Watts Bar - Unit 2 3.3-19 (developmental) F

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOW-ABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

17. Reactor Trip Breakers 1, 2 2 trains Q SR 3.3.1.4 NA NA (j)

(a) (a) (a) 3 ,4 ,5 2 trains C SR 3.3.1.4 NA NA

18. Reactor Trip Breaker 1, 2 1 each T SR 3.3.1.4 NA NA Undervoltage and per RTB Shunt Trip (a) (a) (a)

Mechanisms 3 ,4 ,5 1 each C SR 3.3.1.4 NA NA per RTB

19. Automatic Trip Logic 1, 2 2 trains P SR 3.3.1.5 NA NA (a) (a) (a) 3 ,4 ,5 2 trains C SR 3.3.1.5 NA NA (a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(j) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

Watts Bar - Unit 2 3.3-20 (developmental) A

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 9)

Reactor Trip System Instrumentation Note 1: Overtemperature T The Overtemperature T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.2% of T span.

1 s 1 s T T K K T T K P P f I 1 s 1 s Where: T is measured RCS T, °F.

T0 is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T is the indicated Tavg at RTP, 588.2°F.

P is the measured pressurizer pressure, psig P is the nominal RCS operating pressure, 2235 psig K1 1.16 K2 0.0183/°F K3 = 0.000900/psig 1 33 sec 2 4 sec 4 3 sec 5 3 sec f1(I) = -2.62{22 + (qt - qb)} when qt - qb < - 22% RTP 0 when -22% RTP qt - qb 10% RTP 1.96{(qt - qb) - 10} when qt - qb > 10% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

Watts Bar - Unit 2 3.3-21 (developmental) A

RTS Instrumentation 3.3.1 able 3.3.1-1 (page 8 of 9)

Reactor Trip System Instrumentation Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.0% of T span.

1 4 s 3 s T T0 K 4 K 5 T K 6 TT f2 I 1 5 s 1 3 s Where: T is measured RCS T, °F.

T0 is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T is the indicated Tavg at RTP, 588.2°F.

K4 1.10 K5 0.02/°F for increasing Tavg K6 0.00162/°F when T > T 0/°F for decreasing Tavg 0/°F when T T 3 5 sec 4 3 sec 5 3 sec f2(I) = 0 for all I.

Watts Bar - Unit 2 3.3-22 (developmental) A

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 9 of 9)

Reactor Trip System Instrumentation NOTE 3: Steam Generator Water Level Low-Low Trip Time Delay:

3 2 Ts A P B P C P D 3 2 Tm E P F P G P H Where:

P = Vessel T Equivalent to power (% RTP), P 50% RTP Ts = Time Delay for Steam Generator Water Level - Low Low Reactor Trip, one Steam Generator affected.

Tm = Time Delay for Steam Generator Water Level - Low Low Reactor Trip, two or more Steam Generators affected.

A = -0.0085041 B = 0.9266400 C = -33.85998 D = 474.6060 E = -0.0047421 F = 0.5682600 G = -23.70753 H = 357.9840 Watts Bar - Unit 2 3.3-23 (developmental) A

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Enter the Condition Immediately one or more required referenced in channels or trains Table 3.3.2-1 for the inoperable. channel(s) or train(s).

B. One channel or train B.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

OR B.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Be in Mode 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

Watts Bar - Unit 2 3.3-24 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. C.1 -------------NOTE------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR C.2.1 Be in Mode 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND C.2.2 Be in Mode 5. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months D. One channel inoperable. D.1 -------------NOTE------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR D.2.1 Be in Mode 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND D.2.2 Be in Mode 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

Watts Bar - Unit 2 3.3-25 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment Pressure E.1 -------------NOTE------------

channel inoperable. One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in bypass. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2.1 Be in Mode 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND E.2.2 Be in Mode 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months F. One channel or train F.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

OR F.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND F.2.2 Be in Mode 4. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months (continued)

Watts Bar - Unit 2 3.3-26 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. One train inoperable. G.1 -------------NOTE------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR G.2.1 Be in Mode 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND G.2.2 Be in Mode 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H. One train inoperable. H.1 -------------NOTE------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR H.2.1 Be in Mode 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND H.2.2 Be in Mode 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Watts Bar - Unit 2 3.3-27 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. One Steam Generator I.1 -------------NOTE------------

Water Level - High High One channel may be channel inoperable. bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR I.2.1 Be in Mode 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND I.2.2 Be in Mode 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months J. One or more Turbine Driven J.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Main Feedwater Pump trip OPERABLE status.

channel(s) inoperable.

OR J.2 Be in Mode 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months K. One channel inoperable. K.1 -------------NOTE------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in bypass. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR K.2.1 Be in Mode 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND K.2.2 Be in Mode 5. 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months (continued)

Watts Bar - Unit 2 3.3-28 (developmental) B

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One P-11 interlock channel L.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit condition.

OR L.2.1 Be in Mode 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND L.2.2 Be in Mode 4. 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months M. One Steam Generator --------------------NOTE-------------------

Water Level - Low-Low One channel may be bypassed for channel inoperable. up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

M.1.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND M.1.2 For the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

OR M.2.1 Be in Mode 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND M.2.2 Be in Mode 4. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

Watts Bar - Unit 2 3.3-29 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. One Vessel T channel --------------------NOTE-------------------

inoperable. One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

N.1 Set the Trip Time Delay 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months threshold power level for (Ts) and (Tm) to 0%

power.

OR N.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months O. One MSVV Room Water --------------------NOTE-------------------

Level High channel The inoperable channel may be inoperable. bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

O.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR O.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months Watts Bar - Unit 2 3.3-30 (developmental) A

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform MASTER RELAY TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.2.4 Perform COT. 184 days SR 3.3.2.5 -------------------------------NOTE------------------------------

Slave relays tested by SR 3.3.2.7 are excluded from this surveillance.

Perform SLAVE RELAY TEST. 92 days OR 18 months for Westinghouse type AR and Potter &

Brumfield MDR Series relays (continued)

Watts Bar - Unit 2 3.3-31 (developmental) B

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.6 -------------------------------NOTE------------------------------

Verification of relay setpoints not required.

Perform TADOT. 92 days SR 3.3.2.7 Perform SLAVE RELAY TEST on slave relays 18 months K603A, K603B, K604A, K604B, K607A, K607B, K609A, K609B, K612A, K625A, and K625B, SR 3.3.2.8 -------------------------------NOTE------------------------------

Verification of setpoint not required for manual initiation.

Perform TADOT. 18 months SR 3.3.2.9 -------------------------------NOTE------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.2.10 -------------------------------NOTE------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 1092 psig in the steam generator.

Verify ESFAS RESPONSE TIMES are within limit. 18 months on a STAGGERED TEST BASIS SR 3.3.2.11 -------------------------------NOTE------------------------------

Verification of setpoint not required.

Perform TADOT. Once per reactor trip breaker cycle Watts Bar - Unit 2 3.3-32 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

1. Safety Injection

a. Manual Initiation 1, 2, 3, 4 2 B SR 3.3.2.8 NA NA

b. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays SR 3.3.2.7

c. Containment 1, 2, 3 3 D SR 3.3.2.1 1.6 psig 1.5 psig (b) (c)

Pressure - High SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (a)

d. Pressurizer 1, 2, 3 3 D SR 3.3.2.1 > 1864.8 psig 1870 psig (b) (c)

Pressure - Low SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (a) (d) (d)

e. Steam Line 1, 2, 3 3 per D SR 3.3.2.1 > 666.6 psig 675 psig (b) (c)

Pressure - Low steam line SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10

2. Containment Spray

a. Manual Initiation 1, 2, 3, 4 2 per train, B SR 3.3.2.8 NA NA 2 trains

b. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

c. Containment 1, 2, 3 4 E SR 3.3.2.1 < 2.9 psig 2.8 psig (b) (c)

Pressure - SR 3.3.2.4 High High SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (a) Above the P-11 (Pressurizer Pressure) Interlock.

(b) If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(d) Time constants used in the lead/lag controller are t1 > 50 seconds and t2 < 5 seconds.

(continued)

Watts Bar - Unit 2 3.3-33 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

3. Containment Isolation

a. Phase A Isolation

1) Manual 1, 2, 3, 4 2 B SR 3.3.2.8 NA NA Initiation

2) Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.5 Actuation SR 3.3.2.7 Relays

3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Injection

b. Phase B Isolation

1) Manual 1, 2, 3, 4 2 per train, B SR 3.3.2.8 NA NA Initiation 2 trains

2) Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.5 Actuation SR 3.3.2.7 Relays

3) Containment 1, 2, 3 4 E SR 3.3.2.1 < 2.9 psig 2.8 psig (b) (c)

Pressure - SR 3.3.2.4 High High SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (continued)

(b) If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

Watts Bar - Unit 2 3.3-34 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

4. Steam Line Isolation (e) (e)

a. Manual Initiation 1, 2 ,3 1/valve F SR 3.3.2.8 NA NA (e) (e)

b. Automatic 1, 2 ,3 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (e) (e)

c. Containment 1, 2 ,3 4 E SR 3.3.2.1 < 2.9 psig 2.8 psig (b) (c)

Pressure - SR 3.3.2.4 High High SR 3.3.2.9 (b) (c)

SR 3.3.2.10

d. Steam Line Pressure (e) (a)(e) (d) (d)

1) Low 1, 2 ,3 3 per D SR 3.3.2.1 > 666.6 psig 675 psig (b) (c) steam line SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (e)(f) (g) (g)

2) Negative 3 3 per D SR 3.3.2.1 < 108.5 psi 100 psi (b) (c)

Rate - High steam line SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (continued)

(b) If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(d) Time constants used in the lead/lag controller are t1 > 50 seconds and t2 < 5 seconds.

(e) Except when all MSIVs are closed and de-activated.

(f) Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-11 when safety injection on Steam Line Pressure Low is manually blocked.

(g) Time constants utilized in the rate/lag controller are t3 and t4 > 50 seconds.

Watts Bar - Unit 2 3.3-35 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

5. Turbine Trip and Feedwater Isolation (h) (h)

a. Automatic 1, 2 ,3 2 trains H SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (h) (h)

b. SG Water Level - 1, 2 ,3 3 per SG I SR 3.3.2.1 < 83.1% 82.4%

(b) (c)

High High (P-14) SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(h)(i)

d. North MSV Vault 1, 2 3 per O SR 3.3.2.6 < 5.31 inches 4 inches Room Water vault room SR 3.3.2.9 Level - High (h)(i)

e. South MSV Vault 1, 2 3 per O SR 3.3.2.6 < 4.56 inches 4 inches Room Water vault room SR 3.3.2.9 Level - High (continued)

(b) If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(h) Except when all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

(i) Mode 2 if Turbine Driven Main Feed Pumps are operating.

Watts Bar - Unit 2 3.3-36 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

6. Auxiliary Feedwater

a. Automatic 1, 2, 3 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

b. SG Water Level 1, 2, 3 3 per SG M SR 3.3.2.1 > 16.4% 17.0%

(b) (c)

- Low Low SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 Coincident with:

(b) (c)

1) Vessel T 1, 2 3 N SR 3.3.2.4 Vessel T Vessel T (b) (c)

Equivalent to SR 3.3.2.9 variable input variable input power 52.6% RTP 50% RTP 50% RTP With a time 1.01 Ts Ts delay (Ts) if (Note 1, (Note 1, one SG is Page 3.3-40) Page 3.3-40) affected or A time delay 1.01 Tm Tm (Tm) if two or (Note 1, (Note 1, more SGs Page 3.3-40) Page 3.3-40) are affected (b) (c)

2) Vessel T 1, 2 3 N SR 3.3.2.4 Vessel T Vessel T (b) (c) equivalent to SR 3.3.2.9 variable input variable input power 52.6% RTP 50% RTP

> 50% RTP with no time delay (Ts and Tm = 0)

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(continued)

(b) If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

Watts Bar - Unit 2 3.3-37 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

6. Auxiliary Feedwater (continued)

d. Loss of Offsite 1, 2, 3 4 per bus F Refer to Function 4 of Table 3.3.5-1 for SRs and Power Allowable Values. Notes (b) and (c) are applicable to SR 3.3.5.2 for this function.

(j) (k) (b)(c)

e. Trip of all 1 ,2 1 per pump J SR 3.3.2.8 > 43.3 psig 50 psig (b) (c)

Turbine Driven SR 3.3.2.9 Main Feedwater SR 3.3.2.10 Pumps

f. Auxiliary 1, 2, 3 3 F SR 3.3.2.6 A) > 0.5 psig A) 1.2 psig (b) (c)

Feedwater SR 3.3.2.9 Pumps SR 3.3.2.10 B) > 1.33 psig B) 2.0 psig Train A and B Suction Transfer on Suction Pressure - Low

7. Automatic Switchover to Containment Sump

a. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

b. Refueling Water 1, 2, 3, 4 4 K SR 3.3.2.1 > 155.6 inches 158 inches (b) (c)

Storage Tank SR 3.3.2.4 from from (RWST) SR 3.3.2.9 (b) (c) Tank Base Tank Base Level - Low SR 3.3.2.10 Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection and Coincident with 1, 2, 3, 4 4 K SR 3.3.2.1 > 37.2 inches 38.2 inches (b) (c)

Containment SR 3.3.2.4 above above Sump SR 3.3.2.9 (b) (c) el. 702.8 ft el. 702.8 ft Level - High SR 3.3.2.10 (continued)

(b) If the as found channel setpoint is outside its redefined as found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The methodologies used to determine the as found and as left tolerances for the NTSP are specified in FSAR Section 7.1.2.

(j) Entry into Condition J may be suspended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when placing the second Turbine Driven Main Feedwater (TDMFW) Pump in service or removing one of two TDMFW pumps from service.

(k) When one or more Turbine Driven Feedwater Pump(s) are supplying feedwater to steam generators.

Watts Bar - Unit 2 3.3-38 (developmental) G

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 7 of 8)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

8. ESFAS Interlocks

a. Reactor Trip, P-4 1, 2, 3 1 per train, F SR 3.3.2.11 NA NA 2 trains

b. Pressurizer Pressure, P-11 (1) Unblock 1, 2, 3 3 L SR 3.3.2.1 < 1975.2 psig 1970 psig (Auto Reset SR 3.3.2.4 of SI Block) SR 3.3.2.9 (2) Enable 1, 2, 3 3 L SR 3.3.2.1 > 1956.8 psig 1962 psig Manual SR 3.3.2.4 Block of SI SR 3.3.2.9 Watts Bar - Unit 2 3.3-39 (developmental) F

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 8 of 8)

Engineered Safety Feature Actuation System Instrumentation NOTE 1: Steam Generator Water Level Low-Low Trip Time Delay:

3 2 Ts A P B P C P D 3 2 Tm E P F P G P H Where:

P = Vessel T Equivalent to power (% RTP), P 50% RTP Ts = Time Delay for Steam Generator Water Level - Low Low Reactor Trip, one Steam Generator affected.

Tm = Time Delay for Steam Generator Water Level - Low Low Reactor Trip, two or more Steam Generators affected.

A = -0.0085041 B = 0.9266400 C = -33.85998 D = 474.6060 E = -0.0047421 F = 0.5682600 G = -23.70753 H = 357.9840 Watts Bar - Unit 2 3.3-40 (developmental) F

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: According to Table 3.3.3-1.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE---------------- A.1 Restore required channel 30 days Not applicable to Functions to OPERABLE status.

3, 4, 14, and 16.

One or more Functions with one required channel inoperable.

B. Required Action and B.1 Initiate action in Immediately associated Completion Time accordance with of Condition A not met. Specification 5.9.8.

(continued)

Watts Bar - Unit 2 3.3-41 (developmental) B

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions with C.1 Restore one channel to 7 days two required channels OPERABLE status.

inoperable.

OR Functions 3, 4, 14, and 16 with one required channel inoperable.

D. Required Action and D.1 Enter the Condition Immediately associated Completion Time referenced in of Condition C not met. Table 3.3.3-1 for the channel.

E. As required by Required E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action D.1 and referenced in Table 3.3.3-1. AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. As required by Required F.1 Initiate action in Immediately Action D.1 and referenced accordance with in Table 3.3.3-1. Specification 5.9.8.

Watts Bar - Unit 2 3.3-42 (developmental) B

PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

SR 3.3.3.1 and SR 3.3.3.2 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 -------------------------------NOTES----------------------------

1. Neutron detectors are excluded from CHANNEL CALIBRATION.

2. Not applicable to Functions 11 and 16.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.3.3 -------------------------------NOTES----------------------------

1. Verification of relay setpoints not required.

2. Only applicable to Functions 11 and 16.

Perform TADOT. 18 months Watts Bar - Unit 2 3.3-43 (developmental) B

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 3)

Post Accident Monitoring Instrumentation APPLICABLE CONDITION MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS / REQUIRED FUNCTION CONDITIONS TRAINS ACTION D.1

1) Intermediate Range Neutron Flux (g) 1(a), 2(b), 3 2 E

2) Source Range Neutron Flux 2(c) , 3 2 E

3) Reactor Coolant System (RCS) Hot Leg 1, 2, 3 1 per loop E Temperature (T-Hot)

4) RCS Cold Leg Temperature (T-Cold) 1, 2, 3 1 per loop E

5) RCS Pressure (Wide Range) 1, 2, 3 3 E

6) Reactor Vessel Water Level (f) 1, 2, 3 2 F

7) Containment Sump Water Level (Wide 1, 2, 3 2 E Range)

8) Containment Lower Comp. 1, 2, 3 2 E Atm. Temperature

9) Containment Pressure (Wide Range) (g) 1, 2, 3 2 E

10) Containment Pressure (Narrow Range) 1, 2, 3 4 E

11) Containment Isolation Valve Position (g) 1, 2, 3 2 per E penetration flow path (d)(i) 2 upper

12) Containment Radiation (High Range) 1, 2, 3 F containment 2 lower containment

13) RCS Pressurizer Level 1, 2, 3 3 E

14) Steam Generator (SG) Water Level 1, 2, 3 1/SG E (Wide Range) (g)

(continued)

Watts Bar - Unit 2 3.3-44 (developmental) H

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 2 of 3)

Post Accident Monitoring Instrumentation APPLICABLE CONDITION MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS / REQUIRED FUNCTION CONDITIONS TRAINS ACTION D.1

15) Steam Generator Water Level (Narrow 1, 2, 3 3/SG E Range)

16) AFW Valve Status (j) 1, 2, 3 1 per valve E

17) Core Exit Temperature-Quadrant 1(f) 1, 2, 3 2 (e) E

18) Core Exit Temperature-Quadrant 2(f) 1, 2, 3 2 (e) E

19) Core Exit Temperature-Quadrant 3(f) 1, 2, 3 2 (e) E

20) Core Exit Temperature-Quadrant 4(f) 1, 2, 3 2 (e) E

21) Auxiliary Feedwater Flow 1, 2, 3 2/SG E

22) Reactor Coolant System Subcooling 1, 2, 3 2 E Margin Monitor (h)

23) Refueling Water Storage Tank Water 1, 2, 3 2 E Level

24) Steam Generator Pressure 1, 2, 3 2/SG E

25) Auxiliary Building Passive Sump Level (j) 1, 2, 3 2 E Watts Bar - Unit 2 3.3-45 (developmental) B

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 3 of 3)

Post Accident Monitoring Instrumentation (a) Below the P-10 (Power Range Neutron Flux) interlocks.

(b) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(c) Below the P-6 (Intermediate Range Neutron Flux) interlocks (d) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, pressure relief valve, or check valve with flow through the valve secured.

(e) A channel consists of two core exit thermocouples (CETs).

(f) The Common Q Post Accident Monitoring System provides these functions on a flat screen display.

(g) Regulatory Guide 1.97, non-Type A, Category 1 Variables.

(h) This function is displayed on the Common Q Post Accident Monitoring System flat screen display and digital panel meters.

(i) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(j) Watts Bar specific (not required by Regulatory Guide 1.97) non-Type A Category 1 variable.

Watts Bar - Unit 2 3.3-46 (developmental) B

Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable. Function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.3-47 (developmental) F

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.4.2 Verify each required control circuit and transfer 18 months switch is capable of performing the intended function.

SR 3.3.4.3 -------------------------------NOTE-----------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each required 18 months instrumentation channel.

SR 3.3.4.4 Perform TADOT of the reactor trip breaker 18 months open/closed indication.

Watts Bar - Unit 2 3.3-48 (developmental) B

Remote Shutdown System 3.3.4 Table 3.3.4-1 (page 1 of 1)

Remote Shutdown System Instrumentation and Controls FUNCTION/INSTRUMENT REQUIRED OR CONTROL PARAMETER NUMBER OF FUNCTIONS

1. Reactivity Control

a. Source Range Neutron Flux 1

b. Reactor Trip Breaker Position Indication 1 per trip breaker

2. Reactor Coolant System (RCS) Pressure Control

a. Pressurizer Pressure Indication 1 or RCS Wide Range Pressure Indication

b. Pressurizer Power Operated Relief Valve (PORV) Control and 1 each per relief path Pressurizer Block Valve Control

c. Pressurizer Heater Control 1

3. RCS Inventory Control

a. Pressurizer Level Indication 1

b. Charging and Letdown Flow Control and Indication 1

4. Decay Heat Removal via Steam Generators (SGs)

a. RCS Hot Leg Temperature Indication 1 per loop

b. AFW Controls 1

c. SG Pressure Indication and Control 1 per SG

d. SG Level Indication 1 per SG and AFW Flow Indication

e. SG Tsat Indication 1 per SG

5. Decay Heat Removal via RHR System

a. RHR Flow Control 1

b. RHR Temperature Indication 1 Watts Bar - Unit 2 3.3-49 (developmental) A

LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 The LOP DG Start Instrumentation for each Function in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with --------------------NOTE-------------------

one channel per bus Enter applicable Conditions and inoperable. Required Actions of LCO 3.3.2, "ESFAS Instrumentation," for Auxiliary Feedwater Start Instrumentation made inoperable by LOP DG Start Instrumentation.

A.1 Restore channel to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

B. One or more Functions with B.1 Restore all but one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two or more channels per channel to OPERABLE bus inoperable. status.

(continued)

Watts Bar - Unit 2 3.3-50 (developmental) A

LOP DG Start Instrumentation 3.3.5 ACTIONS continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Time not met. Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.5-1 to determine which SRs apply for each LOP Function.

SURVEILLANCE FREQUENCY SR 3.3.5.1 -------------------------------NOTE------------------------------

Verification of relay setpoints not required.

Perform TADOT. 92 days SR 3.3.5.2 Perform CHANNEL CALIBRATION. 6 months SR 3.3.5.3 Perform CHANNEL CALIBRATION. 18 months Watts Bar - Unit 2 3.3-51 (developmental) A

LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)

LOP DG Start Instrumentation REQUIRED CHANNELS SURVEILLANCE TRIP ALLOWABLE FUNCTION PER BUS REQUIREMENTS SETPOINT VALUE

1. 6.9 kV Emergency Bus Undervoltage (Loss of Voltage)

a. Bus Undervoltage 3 SR 3.3.5.1 5994 V and 5967.6 V SR 3.3.5.2 6006 V

b. Time Delay 2 SR 3.3.5.3 0.73 sec and 0.58 sec and 0.77 sec 0.94 sec

2. 6.9 kV Emergency Bus Undervoltage (Degraded Voltage)

a. Bus Undervoltage 3 SR 3.3.5.1 6593.4 V and 6570 V SR 3.3.5.2 6606.6 V

b. Time Delay 2 SR 3.3.5.3 9.73 sec and 9.42 sec and 10.27 sec 10.49 sec

3. Diesel Generator Start 2 SR 3.3.5.1 4733.4 V and 2295.6 V with SR 3.3.5.2 4926.6 V with an internal time an internal time delay of delay of 0.56 sec at 0.46 sec and zero volts 0.54 sec

4. Load Shed 4 SR 3.3.5.1 4733.4 V and 2295.6 V with SR 3.3.5.2 4926.6 V with an internal time an internal time delay of delay of 3.3 sec at zero 2.79 sec and volts.

3 21 sec Watts Bar - Unit 2 3.3-52 (developmental) A

Containment Vent Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Vent Isolation Instrumentation LCO 3.3.6 The Containment Vent Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation monitoring A.1 Restore the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months channel inoperable. channel to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.3-53 (developmental) H

Containment Vent Isolation Instrumentation 3.3.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with --------------------NOTE-------------------

one or more manual or One train of automatic actuation automatic actuation trains logic may be bypassed and inoperable. Required Action B.1 may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for OR Surveillance testing provided the other train is OPERABLE.

Two radiation monitoring channels inoperable. -----------------------------------------------

OR B.1 Enter applicable Immediately Conditions and Required Required Action and Actions of LCO 3.6.3, associated Completion "Containment Isolation Time of Condition A not Valves," for containment met. purge and exhaust isolation valves made inoperable by isolation instrumentation.

Watts Bar - Unit 2 3.3-54 (developmental) H

Containment Vent Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Vent Isolation Function.

SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2 -------------------------------NOTE------------------------------

This surveillance is only applicable to the actuation logic of the ESFAS instrumentation.

Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.6.3 -------------------------------NOTE------------------------------

This surveillance is only applicable to the master relays of the ESFAS instrumentation.

Perform MASTER RELAY TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT. 92 days SR 3.3.6.5 Perform SLAVE RELAY TEST. 92 days OR 18 months for Westinghouse type AR and Potter &

Brumfield MDR Series relays (continued)

Watts Bar - Unit 2 3.3-55 (developmental) B

Containment Vent Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS (Continued)

SURVEILLANCE FREQUENCY SR 3.3.6.6 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.6.7 Perform CHANNEL CALIBRATION. 18 months Watts Bar - Unit 2 3.3-56 (developmental) A

Containment Vent Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Vent Isolation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 SR 3.3.6.6 NA

2. Automatic Actuation Logic 2 trains SR 3.3.6.2 NA and Actuation Relays SR 3.3.6.3 SR 3.3.6.5

3. Containment Purge 2 SR 3.3.6.1 < 2.8E-02 µCi/cc(b)

Exhaust Radiation Monitors SR 3.3.6.4 (1.14x104 cpm)

SR 3.3.6.7

4. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.

Watts Bar - Unit 2 3.3-57 (developmental) H

CREVS Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation LCO 3.3.7 The CREVS actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6 During movement of irradiated fuel assemblies.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Place one CREVS train in 7 days one channel or train emergency radiation inoperable. protection mode.

(continued)

Watts Bar - Unit 2 3.3-58 (developmental) A

CREVS Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with B.1.1 Place one CREVS train in Immediately two channels or two trains emergency radiation inoperable. protection mode.

AND B.1.2 Enter applicable Immediately Conditions and Required Actions for one CREVS train made inoperable by inoperable CREVS actuation instrumentation OR B.2 Place both trains in Immediately emergency radiation protection mode.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and D.1 Suspend movement of Immediately associated Completion irradiated fuel Time for Condition A or B assemblies.

not met during movement of irradiated fuel assemblies.

E. Required Action and E.1 Initiate action to restore Immediately associated Completion one CREVS train to Time for Condition A or B OPERABLE status.

not met in MODE 5 or 6.

Watts Bar - Unit 2 3.3-59 (developmental) A

CREVS Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.7-1 to determine which SRs apply for each CREVS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.7.2 Perform COT. 92 days SR 3.3.7.3 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.7.4 Perform CHANNEL CALIBRATION. 18 months Watts Bar - Unit 2 3.3-60 (developmental) A

CREVS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CREVS Actuation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 trains SR 3.3.7.3 NA

2. Control Room Radiation 2 SR 3.3.7.1 1.647E-04 C/cc Control Room Air Intakes SR 3.3.7.2 (3,308 cpm)

SR 3.3.7.4

3. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.

Watts Bar - Unit 2 3.3-61 (developmental) H

ABGTS Actuation Instrumentation 3.3.8 3.3 INSTRUMENTATION 3.3.8 Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation LCO 3.3.8 The ABGTS actuation instrumentation for each Function in Table 3.3.8-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.8-1.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Place one ABGTS train in 7 days one channel or train operation.

inoperable.

B. One or more Functions with B.1.1 Place one ABGTS train in Immediately two channels or two trains operation.

inoperable.

AND B.1.2 Enter applicable Immediately Conditions and Required Actions of LCO 3.7.12, "Auxiliary Building Gas Treatment System (ABGTS)," for one train made inoperable by inoperable actuation instrumentation OR (continued)

Watts Bar - Unit 2 3.3-62 (developmental) A

ABGTS Actuation Instrumentation 3.3.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place both trains in Immediately emergency radiation protection mode.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1 -------------------------------NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months Watts Bar - Unit 2 3.3-63 (developmental) H

ABGTS Actuation Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)

ABGTS Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 1,2,3,4 2 SR 3.3.8.1 NA

2. Containment Refer to LCO 3.3.2, Function 3.a., for all Phase A initiating functions and Isolation requirements.

Watts Bar - Unit 2 3.3-64 (developmental) H

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure 2214 psig;

b. RCS average temperature 593.2°F; and

c. RCS total flow rate 380,000 gpm (process computer or control board indication).

APPLICABILITY: MODE 1.

NOTE--------------------------------------------

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months parameters not within limits. parameter(s) to within limit.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Watts Bar - Unit 2 3.4-1 (developmental) A

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is 2214 psig. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.2 Verify RCS average temperature is 593.2°F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.3 Verify RCS total flow rate is 380,000 gpm (process 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months computer or control board indication).

SR 3.4.1.4 -------------------------------NOTE------------------------------

Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 90% RTP.

Verify by precision heat balance method that RCS 18 months total flow rate is 380,000 gpm.

Watts Bar - Unit 2 3.4-2 (developmental) B

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be 551°F.

APPLICABILITY: MODE 1, MODE 2 with keff 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS A.1 Be in MODE 3. 30 minutes loops not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop 551°F. ----------NOTE---------

Only required if Tavg - Tref deviation alarm not reset and any RCS loop Tavg < 561°F.

30 minutes Watts Bar - Unit 2 3.4-3 (developmental) A

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -----------NOTE----------------- A.1 Restore parameter(s) to 30 minutes Required Action A.2 shall within limits be completed whenever this Condition is entered. AND

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for continued Requirements of LCO not operation.

met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5 with RCS 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months pressure < 500 psig C. -----------NOTE----------------- C.1 Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within be completed whenever this limits.

Condition is entered.

AND C.2 Determine RCS is Prior to entering Requirements of LCO not acceptable for continued MODE 4 met any time in other than operation.

MODE 1, 2, 3, or 4.

Watts Bar - Unit 2 3.4-4 (developmental) A

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------------------------------NOTE------------------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS 30 minutes heatup and cooldown rates are within the limits specified in the PTLR.

Watts Bar - Unit 2 3.4-5 (developmental) A

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops - MODES 1 and 2 LCO 3.4.4 Four RCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.4-6 (developmental) A

RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either:

a. Two RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or

b. One RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.

NOTE--------------------------------------------

All reactor coolant pumps may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

APPLICABILITY: MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Restore required RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. loop to OPERABLE status B. Required Action and B.1 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met (continued)

Watts Bar - Unit 2 3.4-7 (developmental) A

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One required RCS loop not C.1 Restore required RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in operation, and reactor trip loop to operation.

breakers closed and Rod Control System capable of OR rod withdrawal.

C.2 De-energize all control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod drive mechanisms (CRDMs).

D. All RCS loops inoperable. D.1 De-energize all CRDMs. Immediately OR AND No RCS loop in operation. D.2 Suspend all operations Immediately involving a reduction of RCS boron concentration.

AND D.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify steam generator secondary side water levels 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are 6% narrow range for required RCS loops.

SR 3.4.5.3 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

Watts Bar - Unit 2 3.4-8 (developmental) A

RCS Loops - MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops - MODE 4 LCO 3.4.6 Two loops shall be OPERABLE, and consist of either:

a. Any combination of RCS loops and residual heat removal (RHR) loops, and one loop shall be in operation, when the rod control system is not capable of rod withdrawal; or

b. Two RCS loops, and both loops shall be in operation, when the rod control system is capable of rod withdrawal.

NOTE--------------------------------------------

No RCP shall be started with any RCS cold leg temperature the COMS arming temperature specified in the PTLR unless the secondary side water temperature of each steam generator (SG) is 50°F above each of the RCS cold leg temperatures.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Only one RCS loop A.1 Initiate action to restore a Immediately OPERABLE. second loop to OPERABLE status AND Two RHR loops inoperable.

B. One required RHR loop B.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable.

AND No RCS loops OPERABLE.

(continued)

Watts Bar - Unit 2 3.4-9 (developmental) B

RCS Loops - MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One required RCS loop not C.1 Restore required RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in operation, and reactor trip loop to operation.

breakers closed and Rod Control System capable of OR rod withdrawal.

C.2 De-energize all control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod drive mechanisms (CRDMs).

D. Required RCS or RHR D.1 De-energize all CRDMs. Immediately loops inoperable.

AND OR D.2 Suspend all operations Immediately No required RCS or RHR involving a reduction of loop in operation RCS boron concentration.

AND D.3 Initiate action to restore Immediately one loop to OPERABLE status and operation.

Watts Bar - Unit 2 3.4-10 (developmental) A

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify two RCS loop are in operation when the rod 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control system is capable of rod withdrawal.

SR 3.4.6.2 Verify one RHR or RCS loop is in operation when the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months rod control system is not capable of rod withdrawal.

SR 3.4.6.3 Verify SG secondary side water levels are greater 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months than or equal to 6% narrow range for required RCS loops.

SR 3.4.6.4 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

Watts Bar - Unit 2 3.4-11 (developmental) A

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a. One additional RHR loop shall be OPERABLE; or

b. The secondary side water level of at least two steam generators (SGs) shall be greater than or equal to 6% narrow range.

NOTES------------------------------------------

1. One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

2. No reactor coolant pump shall be started with one or more RCS cold leg temperatures the COMS arming temperature specified in the PTLR unless the secondary side water temperature of each SG is 50°F above each of the RCS cold leg temperatures.

3. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY: MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable. A.1 Initiate action to restore a Immediately second RHR loop to AND OPERABLE status Required SGs secondary OR side water levels not within limits. A.2 Initiate action to restore Immediately required SG secondary side water levels to within limits (continued)

Watts Bar - Unit 2 3.4-12 (developmental) B

RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required RHR loops B.1 Suspend all operations Immediately inoperable. involving a reduction of RCS boron concentration.

OR AND No RHR loop in operation.

B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or equal to 6% narrow range in required SGs.

SR 3.4.7.3 Verify correct breaker alignment and indicated power 7 days are available to the required RHR pump that is not in operation Watts Bar - Unit 2 3.4-13 (developmental) A

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

NOTE--------------------------------------------

1. All RHR pumps may be de-energized for 15 minutes when switching from one loop to another provided:

a. The core outlet temperature is maintained > 10°F below saturation temperature.

b. No operations are permitted that would cause a reduction of the RCS boron concentration; and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One RHR loop may be inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable. A.1 Initiate action to restore Immediately RHR loop to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.4-14 (developmental) A

RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required RHR loops B.1 Suspend all operations Immediately inoperable. involving reduction in RCS boron concentration OR AND No RHR loop in operation.

B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 Verify correct breaker alignment and indicated power 7 days are available to the required RHR pump that is not in operation.

Watts Bar - Unit 2 3.4-15 (developmental) A

Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level 92%; and

b. Two groups of pressurizer heaters OPERABLE with the capacity of each group 150 kW APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level not A.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit. reactor trip breakers open.

AND A.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. One required group of B.1 Restore required group of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressurizer heaters pressurizer heaters to inoperable. OPERABLE status.

C. Required Action and C.1 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B not AND met.

C.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.4-16 (developmental) A

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 92%. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.9.2 Verify capacity of each required group of pressurizer 92 days heaters is 150 kW.

Watts Bar - Unit 2 3.4-17 (developmental) A

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings 2410 psig and 2560 psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > the COMS arming temperature specified in the PTLR.

NOTE--------------------------------------------

The lift settings are not required to be within the LCO limits during MODE 3 and MODE 4 with all RCS cold leg temperatures > the COMS arming temperature specified in the PTLR for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RCS cold leg temperature Two or more pressurizer < the COMS arming safety valves inoperable. temperature specified in the PTLR.

Watts Bar - Unit 2 3.4-18 (developmental) F

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in In accordance with accordance with the Inservice Testing Program. the Inservice Testing Following testing, lift settings shall be within +/- 1% of Program the nominal lift setting of 2485 psig.

Watts Bar - Unit 2 3.4-19 (developmental) A

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each PORV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable of power to associated block being manually cycled. valve B. One PORV inoperable and B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not capable of being valve manually cycled.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status (continued)

Watts Bar - Unit 2 3.4-20 (developmental) F

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve inoperable C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in manual control AND C.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, or C AND not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two PORVs inoperable and E.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not capable of being valves.

manually cycled AND E.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valves.

AND E.3 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.4 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. Two block valves F.1 Place associated PORVs 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable in manual control.

AND F.2 Restore one block valve 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.4-21 (developmental) A

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition F not AND met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------------------NOTE------------------------------

Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.

Perform a complete cycle of each block valve. 92 days SR 3.4.11.2 Perform a complete cycle of each PORV. 18 months Watts Bar - Unit 2 3.4-22 (developmental) A

COMS 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Cold Overpressure Mitigation System (COMS)

LCO 3.4.12 A COMS System shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated and either a or b below.

a. Two RCS relief valves, as follows:

1. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or

2. One PORV with a lift setting within the limits specified in the PTLR and the RHR suction relief valve with a setpoint 436.5 psig and 463.5 psig.

b. The RCS depressurized and an RCS vent capable of relieving

> 475 gpm water flow.

NOTE--------------------------------------------

1. Two charging pumps may be made capable of injecting for less than or equal to one hour for pump swap operations.

2. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

APPLICABILITY: MODE 4 with any RCS cold leg temperature < the COMS arming temperature specified in the PTLR, MODE 5, MODE 6 when the reactor vessel head is on Watts Bar - Unit 2 3.4-23 (developmental) F

COMS 3.4.12 ACTIONS

NOTE----------------------------------------------------------

LCO 3.0.4.b is not applicable when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more safety injection A.1 Initiate action to verify no Immediately pumps capable of injecting safety injection pumps into the RCS. are capable of injecting into the RCS.

B. Two or more charging B.1 Initiate action to verify a Immediately pumps capable of injecting maximum of one charging into the RCS. pump is capable of injecting into the RCS.

C. An accumulator not isolated C.1 Isolate affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when the accumulator accumulator.

pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

D. Required Action and D.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion temperature to > the Time of Condition C not COMS arming met. temperature specified in the PTLR.

OR D.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

(continued)

Watts Bar - Unit 2 3.4-24 (developmental) B

COMS 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One required RCS relief E.1 Restore required RCS 7 days valve inoperable in MODE 4 relief valve to with any RCS cold leg OPERABLE status.

temperature < the COMS arming temperature specified in the PTLR.

F. One required RCS relief F.1 Restore required RCS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months valve inoperable in MODE 5 relief valve to or 6. OPERABLE status.

G. Two required RCS relief G.1 Depressurize RCS and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months valves inoperable. establish RCS vent.

OR Required Action and associated Completion Time of Condition A, B, D, E, or F not met.

OR COMS inoperable for any reason other than Condition A, B, C, D, E, or F.

Watts Bar - Unit 2 3.4-25 (developmental) B

COMS 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify no safety injection pumps are capable of Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after injecting into the RCS. entering MODE 4 from MODE 3 prior to the temperature of one or more RCS cold legs decreasing below 225°F.

AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter SR 3.4.12.2 Verify a maximum of one charging pump is capable Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after of injecting into the RCS. entering MODE 4 from MODE 3 prior to the temperature of one or more RCS cold legs decreasing below 225°F.

AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter SR 3.4.12.3 Verify each accumulator is isolated. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.4 -------------------------------NOTE------------------------------

Only required to be performed when complying with LCO 3.4.12.b.

Verify RCS vent open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for unlocked open vent paths AND 31 days for locked open vent paths (continued)

Watts Bar - Unit 2 3.4-26 (developmental) G

COMS 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify PORV block valve is open for each required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months PORV.

SR 3.4.12.6 Verify both RHR suction isolation valves are locked 31 days open with operator power removed for the required RHR suction relief valve.

SR 3.4.12.7 -------------------------------NOTE------------------------------

Required to be met within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to the COMS arming temperature specified in the PTLR.

Perform a COT on each required PORV, excluding 31 days actuation.

SR 3.4.12.8 Perform CHANNEL CALIBRATION for each required 18 months PORV actuation channel.

Watts Bar - Unit 2 3.4-27 (developmental) B

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary-to-secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational LEAKAGE A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months not within limits for reasons within limits.

other than pressure boundary LEAKAGE or primary-to-secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met. AND OR B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Pressure boundary LEAKAGE exists.

OR Primary-to-secondary LEAKAGE not within limit.

Watts Bar - Unit 2 3.4-28 (developmental) F

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ------------------------------NOTES-----------------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

2. Not applicable to primary-to-secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months performance of RCS water inventory balance.

SR 3.4.13.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary-to-secondary LEAKAGE is less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or equal to 150 gallons per day through any one SG.

Watts Bar - Unit 2 3.4-29 (developmental) A

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limit.

APPLICABILITY: MODES 1, 2, and 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

ACTIONS

NOTES---------------------------------------------------------

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths with --------------------NOTE-------------------

leakage from one or more Each valve used to satisfy Required RCS PIVs not within limit. Action A.1 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary.

A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND (continued)

Watts Bar - Unit 2 3.4-30 (developmental) F

RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Restore RCS PIV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months within limits B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.4-31 (developmental) F

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------------------NOTE------------------------------

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is equivalent to In accordance with 0.5 gpm per nominal inch of valve size up to a the Inservice Testing maximum of 5 gpm at an RCS pressure 2215 psig Program, and and 2255 psig. 18 months AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve Watts Bar - Unit 2 3.4-32 (developmental) A

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

1. One containment pocket sump level monitor; and

2. One lower containment atmosphere particulate radioactivity monitor.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pocket sump level monitor inoperable. AND A.2 Restore required 30 days containment pocket sump level monitor to OPERABLE status.

B. Required containment B.1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atmosphere particulate the containment radioactivity monitor atmosphere.

inoperable.

OR B.1.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore required 30 days containment atmosphere particulate radioactivity monitor to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.4-33 (developmental) B

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. All required monitors D.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere particulate radioactivity monitor.

SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere particulate radioactivity monitor.

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 18 months containment pocket sump level monitor.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere particulate radioactivity monitor.

Watts Bar - Unit 2 3.4-34 (developmental) F

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) 500°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 --------------------NOTE-------------------

> 0.265 Ci/gm. LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131 14 Ci/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT I-131 to within limit.

B. Gross specific activity of the B.1 Perform SR 3.4.16.2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reactor coolant not within limit. AND B.2 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Tavg < 500°F.

(continued)

Watts Bar - Unit 2 3.4-35 (developmental) H

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tavg < 500°F.

Time of Condition A not met.

OR DOSE EQUIVALENT I-131

> 14 Ci/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity 7 days

< 100/E Ci/gm.

SR 3.4.16.2 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 14 days specific activity 0.265 Ci/gm.

AND Between 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued)

Watts Bar - Unit 2 3.4-36 (developmental) H

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.3 -------------------------------NOTE------------------------------

Required to be performed within 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine from a sample taken in MODE 1 after a 184 days minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Watts Bar - Unit 2 3.4-37 (developmental) A

SG Tube Integrity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained AND All SG tubes satisfying the tube plugging or repair criteria shall be plugged or repaired in accordance with the Steam Generator Program.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube plugging affected tube(s) is or repair criteria and not maintained until the next plugged or repaired in refueling outage or SG accordance with the Steam tube inspection Generator Program AND A.2 Plug or repair the affected Prior to entering tube(s) in accordance MODE 4 following with the Steam Generator the next refueling Program outage or SG tube inspection B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met AND OR B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SG tube integrity not maintained Watts Bar - Unit 2 3.4-38 (developmental) G

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify steam generator tube integrity in accordance In accordance with with the Steam Generator Program. the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the Prior to entering tube plugging or repair criteria is plugged or repaired MODE 4 following a in accordance with the Steam Generator Program. SG tube inspection Watts Bar - Unit 2 3.4-39 (developmental) G

Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with pressurizer pressure > 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable due to boron concentration to within concentration not within limits.

limits.

B. One accumulator B.1 Restore accumulator to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable for reasons other OPERABLE status.

than Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 Reduce pressurizer 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months pressure to 1000 psig.

D. Two or more accumulators C.3 Enter LCO 3.0.3. Immediately inoperable.

Watts Bar - Unit 2 3.5-1 (developmental) B

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.1.2 Verify borated water volume in each accumulator is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 7630 gallons and 8000 gallons.

SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 610 psig and 660 psig.

SR 3.5.1.4 Verify boron concentration in each accumulator is 31 days 3000 ppm and 3300 ppm.

AND

NOTE---------

Only required to be performed for affected accumulators Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of 75 gallons, that is not the result of addition from the refueling water storage tank SR 3.5.1.5 Verify power is removed from each accumulator 31 days isolation valve operator when pressurizer pressure is 1000 psig.

Watts Bar - Unit 2 3.5-2 (developmental) A

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

NOTE--------------------------------------------

1. In MODE 3, both safety injection (SI) pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to perform pressure isolation valve testing per SR 3.4.14.1.

2. In MODE 3, the safety injection pumps and charging pumps may be made incapable of injecting to support transition into or from the Applicability of the LCO 3.4.12, Cold Overpressure Mitigation System (COMS) for up to four hours or until the temperature of all the RCS cold legs exceeds 375°F, whichever occurs first.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.5-3 (developmental) A

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power to the valve operator removed.

Number Position Function 2FCV-63-1 Open RHR Supply 2FCV-63-22 Open SIS Discharge SR 3.5.2.2 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.3 Verify ECCS piping is full of water. 31 days SR 3.5.2.4 Verify each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the Inservice Testing developed head. Program SR 3.5.2.5 Verify each ECCS automatic valve in the flow path 18 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.6 Verify each ECCS pump starts automatically on an 18 months actual or simulated actuation signal.

(continued)

Watts Bar - Unit 2 3.5-4 (developmental) B

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.7 Verify, for each ECCS throttle valve listed below, 18 months each position stop is in the correct position.

Valve Number CCP SI SI Discharge Cold Leg Hot Leg Throttle Throttle Throttle Valves Valves Valves 263-582 263-550 263-542 263-583 263-552 263-544 263-584 263-554 263-546 263-585 263-556 263-548 SR 3.5.2.8 Verify, by visual inspection, each ECCS train 18 months containment sump suction inlet is not restricted by debris and the suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.

Watts Bar - Unit 2 3.5-5 (developmental) B

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

APPLICABILITY: MODE 4.

ACTIONS

NOTE-------------------------------------------------------------

LCO 3.0.4.b is not applicable to ECCS high head (centrifugal charging) subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual --------------------NOTE-------------------

heat removal (RHR) The required ECCS residual heat subsystem inoperable. removal (RHR) subsystem may be inoperable for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing of valves provided that alternate heat removal methods are available via the steam generators to maintain the Reactor Coolant System Tavg less than 350°F and provided that the required subsystem is capable of being manually realigned to the ECCS mode of operation from the main control room.

A.1 Initiate action to restore Immediately required ECCS RHR subsystem to OPERABLE status (continued)

Watts Bar - Unit 2 3.5-6 (developmental) F

ECCS - Shutdown 3.5.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required ECCS centrifugal B.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months charging subsystem centrifugal charging inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition B not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 -------------------------------NOTE------------------------------

An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

The following SRs are applicable for all equipment In accordance with required to be OPERABLE: applicable SRs SR 3.5.2.1 SR 3.5.2.3 SR 3.5.2.4 SR 3.5.2.7 SR 3.5.2.8 Watts Bar - Unit 2 3.5-7 (developmental) A

RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron concentration A.1 Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months not within limits. OPERABLE status.

OR RWST borated water temperature not within limits.

B. RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.5-8 (developmental) A

RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -------------------------------NOTE------------------------------

Only required to be performed when ambient air temperature is < 60°F or > 105°F.

Verify RWST borated water temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 60°F and 105°F.

SR 3.5.4.2 Verify RWST borated water volume is 7 days 370,000 gallons.

SR 3.5.4.3 Verify boron concentration in the RWST is 7 days 3100 ppm and 3300 ppm.

Watts Bar - Unit 2 3.5-9 (developmental) A

Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Seal Injection Flow LCO 3.5.5 Reactor coolant pump seal injection flow shall be 40 gpm with charging pump discharge header pressure 2430 psig and the pressurizer level control valve full open.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow not within A.1 Adjust manual seal 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limit. injection throttle valves to give a flow within limit with charging pump discharge header pressure 2430 psig and the pressurizer level control valve full open.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.5-10 (developmental) A

Seal Injection Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 -------------------------------NOTE------------------------------

Required to be performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the Reactor Coolant System pressure stabilizes at 2215 psig and 2255 psig.

Verify manual seal injection throttle valves are 31 days adjusted to give a flow within limit with charging pump discharge header pressure 2430 psig and the pressurizer level control valve full open.

Watts Bar - Unit 2 3.5-11 (developmental) A

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance with rate testing except for containment air lock testing, in the Containment accordance with the Containment Leakage Rate Leakage Rate Testing Program. Testing Program.

Watts Bar - Unit 2 3.6-1 (developmental) A

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 Two containment air locks shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES-----------------------------------------------------------

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air lock leakage results in exceeding the overall containment leakage rate.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment -------------------NOTES------------------

air locks with one 1. Required Actions A.1, A.2, containment air lock door and A.3 are not applicable if inoperable. both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

(continued)

Watts Bar - Unit 2 3.6-2 (developmental) F

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed in the affected air lock.

AND A.3 -------------NOTE------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.

(continued)

Watts Bar - Unit 2 3.6-3 (developmental) A

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more containment -------------------NOTES------------------

air locks with containment 1. Required Actions B.1, B.2, air lock interlock and B.3 are not applicable if mechanism inoperable. both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND B.3 -------------NOTE------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock.

(continued)

Watts Bar - Unit 2 3.6-4 (developmental) A

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more containment C.1 Initiate action to evaluate Immediately air locks inoperable for overall containment reasons other than leakage rate per Condition A or B. LCO 3.6.1.

AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.6-5 (developmental) A

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 -------------------------------NOTES----------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate testing in In accordance with accordance with the Containment Leakage Rate the Containment Testing Program. Leakage Rate Testing Program SR 3.6.2.2 -------------------------------NOTE------------------------------

Only required to be performed upon entry or exit through the containment air lock.

Verify only one door in the air lock can be opened at 184 days a time.

Watts Bar - Unit 2 3.6-6 (developmental) A

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES-----------------------------------------------------------

1. Penetration flow path(s) may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE---------------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path by penetration flow paths with use of at least one closed two containment isolation and de-activated valves. automatic valve, closed

manual valve, blind flange, or check valve One or more penetration with flow through the flow paths with one valve secured.

containment isolation valve inoperable except for purge AND valve or shield building bypass leakage not within limit.

(continued)

Watts Bar - Unit 2 3.6-7 (developmental) A

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -----------NOTES------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Watts Bar - Unit 2 3.6-8 (developmental) B

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE---------------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one closed two containment isolation and de-activated valves. automatic valve, closed

manual valve, or blind flange One or more penetration flow paths with two containment isolation valves inoperable except for purge valve or shield building bypass leakage not within limit.

C. ------------NOTE---------------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path by penetration flow paths with use of at least one closed only one containment and de-activated isolation valve and a closed automatic valve, closed system. manual valve, or blind

flange One or more penetration AND flow paths with one containment isolation valve C.2 -----------NOTES------------

inoperable. 1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

(continued)

Watts Bar - Unit 2 3.6-9 (developmental) B

Containment Isolation Valves 3.6.3 CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) Verify the affected Once per 31 days penetration flow path is isolated.

D. Shield building bypass not D.1 Restore leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within limit. limit.

E. One or more penetration E.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months flow paths with one or more penetration flow path by containment purge valves use of at least one closed not within purge valve and de-activated leakage limits automatic valve, closed manual valve, or blind flange.

AND (continued)

Watts Bar - Unit 2 3.6-10 (developmental) A

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) E.2 -----------NOTES------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Once per 92 days AND E.3 Perform SR 3.6.3.5 for Once per 92 days the resilient seal purge valves closed to comply with Required Action E.1.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.6-11 (developmental) B

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each containment purge valve is closed, 31 days except when the containment purge valves are open for pressure control, ALARA or air quality considerations for personnel entry, or for Surveillances that require the valves to be open.

SR 3.6.3.2 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual valve and 31 days blind flange that is located outside containment, the containment annulus, and the Main Steam Valve Vault Rooms, and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

SR 3.6.3.3 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment, the MODE 4 from containment annulus, and the Main Steam Valve MODE 5 if not Vault Rooms, and not locked, sealed, or otherwise performed within the secured and required to be closed during accident previous 92 days conditions is closed, except for containment isolation valves that are open under administrative controls.

SR 3.6.3.4 Verify the isolation time of each power operated and In accordance with each automatic containment isolation valve is within the Inservice Testing limits. Program or 92 days (continued)

Watts Bar - Unit 2 3.6-12 (developmental) B

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.5 Perform leakage rate testing for containment purge 184 days valves with resilient seals.

AND Within 92 days after opening the valve SR 3.6.3.6 Verify each automatic containment isolation valve 18 months that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

SR 3.6.3.7 Verify each 24 inch containment lower compartment 18 months purge supply and exhaust isolation valve is blocked to restrict the valve from opening > 50°.

SR 3.6.3.8 Verify the combined leakage rate for all shield In accordance with building bypass leakage paths is 0.25 La when the Containment pressurized to 15.0 psig. Leakage Rate Testing Program Watts Bar - Unit 2 3.6-13 (developmental) A

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be -0.1 and +0.3 psid relative to the annulus.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure not A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limits. pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.6-14 (developmental) A

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be:

a. > 85°F and 110°F for the containment upper compartment, and

b. > 100°F and 120°F for the containment lower compartment.

NOTE--------------------------------------------

The minimum containment average air temperatures in MODES 2, 3, and 4 may be reduced to 60°F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air A.1 Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air temperature limits. to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.6-15 (developmental) A

Containment Air Temperature 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment upper compartment average air 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is within limits.

SR 3.6.5.2 Verify containment lower compartment average air 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is within limits.

Watts Bar - Unit 2 3.6-16 (developmental) A

Containment Spray System 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray System LCO 3.6.6 Two containment spray trains and two residual heat removal (RHR) spray trains shall be OPERABLE.

NOTE--------------------------------------------

The RHR spray train is not required in MODE 4.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable. spray train to OPERABLE status.

B. One RHR spray train B.1 Restore RHR spray train 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months Watts Bar - Unit 2 3.6-17 (developmental) A

Containment Spray System 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.6.2 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal to the Inservice Testing the required developed head. Program SR 3.6.6.3 Verify each automatic containment spray valve in the 18 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.6.4 Verify each containment spray pump starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.5 Verify each spray nozzle is unobstructed. At first refueling AND 10 years SR 3.6.6.6 Perform SR 3.5.2.2 and SR 3.5.2.4 for the RHR In accordance with spray system. Applicable SRs Watts Bar - Unit 2 3.6-18 (developmental) A

DELETED 3.6 CONTAINMENT SYSTEMS 3.6.7 This specification deleted.

Watts Bar - Unit 2 3.6-19 (developmental) B

HMS 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Mitigation System (HMS)

LCO 3.6.8 Two HMS trains shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One HMS train inoperable. A.1 Restore HMS train to 7 days OPERABLE status.

OR A.2 Perform SR 3.6.8.1 on Once per 7 days the OPERABLE train.

B. One containment region B.1 Restore one hydrogen 7 days with no OPERABLE ignitor in the affected hydrogen ignitor. containment region to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Watts Bar - Unit 2 3.6-20 (developmental) A

HMS 3.6.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Energize each HMS train power supply breaker and 92 days verify 33 ignitors are energized in each train.

SR 3.6.8.2 Verify at least one hydrogen ignitor is OPERABLE in 92 days each containment region.

SR 3.6.8.3 Energize each hydrogen ignitor and verify 18 months temperature is 1700°F.

Watts Bar - Unit 2 3.6-21 (developmental) A

EGTS 3.6.9 3.6 CONTAINMENT SYSTEMS 3.6.9 Emergency Gas Treatment System (EGTS)

LCO 3.6.9 Two EGTS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One EGTS train inoperable. A.1 Restore EGTS train to 7 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.9.1 Operate each EGTS train for 10 continuous hours 31 days with heaters operating.

SR 3.6.9.2 Perform required EGTS filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP (continued)

Watts Bar - Unit 2 3.6-22 (developmental) F

EGTS 3.6.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.9.3 Verify each EGTS train actuates on an actual or 18 months simulated actuation signal.

SR 3.6.9.4 Verify each EGTS train produces a flow rate 18 months on a 3600 cfm and 4400 cfm within 20 seconds from STAGGERED TEST the initiation of a Containment Isolation Phase A BASIS signal.

Watts Bar - Unit 2 3.6-23 (developmental) A

ARS 3.6.10 3.6 CONTAINMENT SYSTEMS 3.6.10 Air Return System (ARS)

LCO 3.6.10 Two ARS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ARS train inoperable. A.1 Restore ARS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.10.1 Verify each ARS fan starts on an actual or simulated 92 days actuation signal, after a delay of 8.0 minutes and 10.0 minutes, and operates for 15 minutes.

SR 3.6.10.2 Verify, with the ARS fan dampers closed, each ARS 92 days fan motor current is 54 amps and 94 amps.

SR 3.6.10.3 Verify, with the ARS fan not operating, each ARS fan 92 days damper opens when 92.4 in-lb is applied.

Watts Bar - Unit 2 3.6-24 (developmental) A

Ice Bed 3.6.11 3.6 CONTAINMENT SYSTEMS 3.6.11 Ice Bed LCO 3.6.11 The ice bed shall be OPERABLE APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Ice bed inoperable. A.1 Restore ice bed to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.11.1 Verify maximum ice bed temperature is 27°F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Watts Bar - Unit 2 3.6-25 (developmental) A

Ice Bed 3.6.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.11.2 Verify total weight of stored ice is greater than or 18 months equal to 2,404,500 lb by:

a. Weighing a representative sample of 144 ice baskets and verifying each basket contains greater than or equal to 1237 lb of ice; and

b. Calculating total weight of stored ice, at a 95 percent confidence level, using all ice basket weights determined in SR 3.6.11.2.a.

SR 3.6.11.3 Verify azimuthal distribution of ice at a 95 percent 18 months confidence level by subdividing weights, as determined by SR 3.6.11.2.a, into the following groups:

a. Group 1-bays 1 through 8;

b. Group 2-bays 9 through 16; and

c. Group 3-bays 17 through 24.

The average ice weight of the sample baskets in each group from radial rows 1, 2, 4, 6, 8, and 9 shall be greater than or equal to 1237 lb.

SR 3.6.11.4 Verify, by visual inspection, accumulation of ice on 18 months structural members comprising flow channels through the ice bed is less than or equal to 15 percent blockage of the total flow area for each safety analysis section.

(continued)

Watts Bar - Unit 2 3.6-26 (developmental) D

Ice Bed 3.6.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.11.5 -------------------------------NOTE------------------------------

The requirements of this SR are satisfied if the boron concentration and pH values obtained from averaging the individual sample results are within the limits specified below.

Verify, by chemical analysis of the stored ice in at 54 months least one randomly selected ice basket from each ice condenser bay, that ice bed:

a. Boron concentration is 1800 ppm and 2000 ppm; and

b. pH is 9.0 and 9.5.

SR 3.6.11.6 Visually inspect, for detrimental structural wear, 40 months cracks, corrosion, or other damage, two ice baskets from each azimuthal group of bays.

See SR 3.6.11.3.

SR 3.6.11.7 -------------------------------NOTE------------------------------

The chemical analysis may be performed on either the liquid solution or on the resulting ice.

Verify, by chemical analysis, that ice added to the ice Each ice addition condenser meets the boron concentration and pH requirements of SR 3.6.11.5.

Watts Bar - Unit 2 3.6-27 (developmental) A

Ice Condenser Doors 3.6.12 3.6 CONTAINMENT SYSTEMS 3.6.12 Ice Condenser Doors LCO 3.6.12 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each ice condenser door.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ice condenser A.1 Restore inlet door to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inlet doors inoperable due OPERABLE status.

to being physically restrained from opening.

B. One or more ice condenser B.1 Verify maximum ice bed Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months doors inoperable for temperature is 27°F.

reasons other than Condition A or not closed. AND B.2 Restore ice condenser 14 days door to OPERABLE status and closed positions.

C. Required Action and C.1 Restore ice condenser 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months associated Completion door to OPERABLE Time of Condition B not status and closed met. positions.

(continued)

Watts Bar - Unit 2 3.6-28 (developmental) A

Ice Condenser Doors 3.6.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or C AND not met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.12.1 Verify all inlet doors indicate closed by the Inlet Door 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Position Monitoring System.

SR 3.6.12.2 Verify, by visual inspection, each intermediate deck 7 days door is closed and not impaired by ice, frost, or debris.

SR 3.6.12.3 Verify, by visual inspection, each inlet door is not 3 months during first impaired by ice, frost, or debris. year after receipt of license AND 18 months SR 3.6.12.4 Verify torque required to cause each inlet door to 3 months during first begin to open is 675 in-lb. year after receipt of license AND 18 months (continued)

Watts Bar - Unit 2 3.6-29 (developmental) A

Ice Condenser Doors 3.6.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.12.5 Perform a torque test on a sampling of 50% of the 3 months during first inlet doors. year after receipt of license AND 18 months SR 3.6.12.6 Verify for each intermediate deck door: 3 months during first year after receipt of

a. No visual evidence of structural deterioration; license

b. Free movement of the vent assemblies; and AND

c. Free movement of the door. 18 months SR 3.6.12.7 Verify, by visual inspection, each top deck door: 92 days

a. Is in place;

b. Free movement of top deck vent assembly; and

c. Has no condensation, frost, or ice formed on the door that would restrict its opening.

Watts Bar - Unit 2 3.6-30 (developmental) A

Divider Barrier Integrity 3.6.13 3.6 CONTAINMENT SYSTEMS 3.6.13 Divider Barrier Integrity LCO 3.6.13 Divider barrier integrity shall be maintained.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -----------NOTE----------------- A.1 Restore personnel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months For this action, separate access doors and Condition entry is allowed equipment hatches to for each personnel access OPERABLE status and door or equipment hatch. closed positions.

One or more personnel access doors or equipment hatches between upper and lower containment open or inoperable, other than for personnel transit.

B. Divider barrier seal B.1 Restore seal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.6-31 (developmental) F

Divider Barrier Integrity 3.6.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.13.1 Verify, by visual inspection, all personnel access Prior to entering doors and equipment hatches between upper and MODE 4 from lower containment compartments are closed. MODE 5 SR 3.6.13.2 Verify, by visual inspection, that the seals and Prior to final closure sealing surfaces of each personnel access door and after each opening equipment hatch have:

AND

a. No detrimental misalignments;

NOTE---------

b. No cracks or defects in the sealing surfaces; and Only required for seals made of

c. No apparent deterioration of the seal material. resilient materials 10 years SR 3.6.13.3 Verify, by visual inspection, each personnel access After each opening door or equipment hatch that has been opened for personnel transit is closed.

SR 3.6.13.4 Not used SR 3.6.13.5 Visually inspect 95% of the divider barrier seal 18 months length, and verify:

a. Seal and seal mounting bolts are properly installed; and

b. Seal material shows no evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance.

Watts Bar - Unit 2 3.6-32 (developmental) H

Containment Recirculation Drains 3.6.14 3.6 CONTAINMENT SYSTEMS 3.6.14 Containment Recirculation Drains LCO 3.6.14 The ice condenser floor drains and the refueling canal drains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ice condenser floor A.1 Restore ice condenser 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months drain inoperable. floor drain to OPERABLE status.

B. One refueling canal drain B.1 Restore refueling canal 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. drain to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.6-33 (developmental) A

Containment Recirculation Drains 3.6.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.14.1 Verify, by visual inspection, that: 92 days

a. Each refueling canal drain plug is removed; AND

b. Each refueling canal drain is not obstructed by Prior to entering debris; and MODE 4 from MODE 5 after each

c. No debris is present in the upper compartment partial or complete or refueling canal that could obstruct the fill of the canal refueling canal drain.

SR 3.6.14.2 Verify for each ice condenser floor drain that the: 18 months

a. Gate opening is not impaired by ice, frost, or debris;

b. Gate seat shows no evidence of damage;

c. Gate opening force is 100 lb; and

d. Drain line from the ice condenser floor to the lower compartment is unrestricted.

Watts Bar - Unit 2 3.6-34 (developmental) A

Shield Building 3.6.15 3.6 CONTAINMENT SYSTEMS 3.6.15 Shield Building LCO 3.6.15 The shield building shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shield building inoperable. A.1 Restore shield building to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

B. ------------NOTE---------------- B.1 Restore annulus pressure 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Annulus pressure within limits.

requirement is not applicable during ventilating operations, required annulus entries, or Auxiliary Building isolations not exceeding 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration.

Annulus pressure not within limits.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.6-35 (developmental) A

Shield Building 3.6.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.15.1 Verify annulus negative pressure is equal to or more 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months negative than -5 inches water gauge with respect to the atmosphere.

SR 3.6.15.2 Verify the door in each access opening is closed, 31 days except when the access opening is being used for normal transient entry and exit.

SR 3.6.15.3 Verify shield building structural integrity by During shutdown for performing a visual inspection of the exposed interior SR 3.6.1.1 Type A and exterior surfaces of the Shield Building. tests SR 3.6.15.4 Verify each Emergency Gas Treatment System train 18 months on a with final flow 3600 cfm and 4400 cfm produces STAGGERED TEST an annulus pressure equal to or more negative than BASIS

- 0.61 inch water gauge at elevation 783 with respect to the atmosphere and with an inleakage of 250 cfm.

Watts Bar - Unit 2 3.6-36 (developmental) A

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 Five MSSVs per steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with one MSSV POWER to 59 % RTP.

inoperable.

B. One or more steam B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with two or more POWER to less than or MSSVs inoperable. equal to the Maximum Allowable % RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

AND

NOTE-------------

Only required in MODE 1.

B.2 Reduce the Power Range Neutron Flux - High reactor trip setpoint to less than or equal to the Maximum Allowable

% RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

(continued)

Watts Bar - Unit 2 3.7-1 (developmental) F

MSSVs 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more steam generators with 4 MSSVs inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per In accordance with Table 3.7.1-2 in accordance with the Inservice the Inservice Testing Testing Program. Following testing, lift settings shall Program be within +/- 1%.

Watts Bar - Unit 2 3.7-2 (developmental) A

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves Versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs MAXIMUM ALLOWABLE POWER PER STEAM GENERATOR (% RTP) 3 42 2 26 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING STEAM GENERATOR (psig +/- 3%)

1 #2 #3 #4 1-522 1-517 1-512 1-527 1224 1-523 1-518 1-513 1-528 1215 1-524 1-519 1-514 1-529 1205 1-525 1-520 1-515 1-530 1195 1-526 1-521 1-516 1-531 1185 Watts Bar - Unit 2 3.7-3 (developmental) A

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Four MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed and de-activated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MODE 1. OPERABLE status.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

C. ----------NOTE----------------- C.1 Close MSIV. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Separate Condition entry is allowed for each MSIV. AND C.2 Verify MSIV is closed and Once per 7 days One or more MSIVs de-activated.

inoperable in MODE 2 or 3.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C AND not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.7-4 (developmental) A

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------------------NOTE------------------------------

Required to be performed in MODE 3.

Verify closure time of each MSIV is 6.0 seconds on In accordance with an actual or simulated actuation signal. the Inservice Testing Program or 18 months Watts Bar - Unit 2 3.7-5 (developmental) A

MFIVs and MFRVs and Associated Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Four MFIVs, four MFRVs, and associated bypass valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 except when MFIV, MFRV, or associated bypass valve is closed and de-activated or isolated by a closed manual valve.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFIVs A.1 Close or isolate MFIV. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND A.2 Verify MFIV is closed or Once per 7 days isolated.

B. One or more MFRVs B.1 Close or isolate MFRV. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND B.2 Verify MFRV is closed or Once per 7 days isolated.

C. One or more MFIV or C.1 Restore bypass valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months MFRV bypass valves OPERABLE status.

inoperable.

(continued)

Watts Bar - Unit 2 3.7-6 (developmental) A

MFIVs and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One MFIV and MFRV in the D.1 Isolate affected flow path. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months same flow path inoperable.

E. One MFIV bypass valve E.1 Restore one MFIV 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and MFRV bypass valve in bypass valve or MFRV the same flow path bypass valve to inoperable. OPERABLE status.

F. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFIV, MFRV, and In accordance with associated bypass valve is 6.5 seconds on an the Inservice Testing actual or simulated actuation signal. Program or 18 months Watts Bar - Unit 2 3.7-7 (developmental) A

ADVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Dump Valves (ADVs)

LCO 3.7.4 Four ADV lines shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ADV line A.1 Restore required ADV 7 days inoperable. line to OPERABLE status.

B. One train (two ADV lines) B.1 Restore ADV lines to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable due to one train OPERABLE status.

of ACAS inoperable.

C. Two or more required ADV C.1 Restore all but one ADV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months lines inoperable for reasons line to OPERABLE other than Condition B. status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 4 without 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months reliance upon steam generator for heat removal.

Watts Bar - Unit 2 3.7-8 (developmental) A

ADVs 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ADV. 18 months SR 3.7.4.2 Verify one complete cycle of each ADV block valve. 18 months Watts Bar - Unit 2 3.7-9 (developmental) A

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

NOTE--------------------------------------------

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

NOTE-------------------------------------------------------------

LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to turbine A.1 Restore steam supply to 7 days driven AFW pump OPERABLE status.

inoperable. AND 10 days from discovery of failure to meet the LCO B. One AFW train inoperable B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in MODE 1, 2 or 3 for OPERABLE status.

reasons other than AND Condition A.

10 days from discovery of failure to meet the LCO (continued)

Watts Bar - Unit 2 3.7-10 (developmental) A

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met.

C.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months OR Two AFW trains inoperable in MODE 1, 2, or 3.

D. Three AFW trains D.1 ------------NOTE-------------

inoperable in MODE 1, 2, LCO 3.0.3 and all other or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

E. Required AFW train E.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

Watts Bar - Unit 2 3.7-11 (developmental) A

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 -------------------------------NOTE------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 1092 psig in the steam generator.

Verify the developed head of each AFW pump at the 31 days on a flow test point is greater than or equal to the required STAGGERED TEST developed head. BASIS SR 3.7.5.3 -------------------------------NOTE------------------------------

Not applicable in MODE 4 when steam generator is relied upon for heat removal.

Verify each AFW automatic valve that is not locked, 18 months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.4 -------------------------------NOTE------------------------------

1. Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 1092 psig in the steam generator.

2. Not applicable in MODE 4 when steam generator is relied upon for heat removal.

Verify each AFW pump starts automatically on an 18 months actual or simulated actuation signal.

(continued)

Watts Bar - Unit 2 3.7-12 (developmental) A

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.5 Verify proper alignment of the required AFW flow Prior to entering paths by verifying flow from the condensate storage MODE 2 after initial tank to each steam generator. fuel loading and whenever unit has been in MODE 5 or 6 for > 30 days Watts Bar - Unit 2 3.7-13 (developmental) A

CST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)

LCO 3.7.6 The CST level shall be 200,000 gal.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CST level not within limit. A.1 Verify by administrative 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months means OPERABILITY of ERCW backup water AND supply.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore CST level to 7 days within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4, without 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months reliance on steam generator for heat removal.

Watts Bar - Unit 2 3.7-14 (developmental) A

CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is 200,000 gal. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.7-15 (developmental) A

CCS 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling System (CCS)

NOTE-------------------------------------------------------------

CCS Pump 1B-B aligned to CCS Train B supports an OPERABLE CCS Train B for Unit 2 only when CCS Pump 1B-B is OPERABLE and operating as verified by SR 3.7.7.5.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCS train inoperable. A.1 -------------NOTE------------

Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4,"

for residual heat removal loops made inoperable by CCS.

Restore CCS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.7-16 (developmental) H

CCS 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify that the alternate feeder breaker to the C-S 7 days pump is open.

SR 3.7.7.2 -------------------------------NOTE------------------------------

Isolation of CCS flow to individual components does not render the CCS inoperable.

Verify each CCS manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.3 Verify each CCS automatic valve in the flow path that 18 months is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.4 Verify each CCS pump starts automatically on an 18 months actual or simulated actuation signal. When CCS Pump 1B-B is substituted for CCS Pump C-S to establish CCS Train B operability, SR 3.7.7.4 does not apply to CCS Pump 1B-B (See SR 3.7.7.5).

SR 3.7.7.5 When CCS Pump 1B-B is substituted for CCS Pump 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C-S for Unit 2 CCS Train B operability, then, Verify CCS 1B-B is aligned to CCS Train B and is operating.

Watts Bar - Unit 2 3.7-17 (developmental) H

ERCW 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Essential Raw Cooling Water (ERCW) System LCO 3.7.8 Two ERCW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ERCW train A.1 ------------NOTES-----------

inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources- Operating,"

for emergency diesel generator made inoperable by ERCW.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," for residual heat removal loops made inoperable by ERCW.

Restore ERCW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.7-18 (developmental) F

ERCW 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -------------------------------NOTE------------------------------

Isolation of ERCW flow to individual components does not render the ERCW inoperable.

Verify each ERCW manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.8.2 Verify each ERCW automatic valve in the flow path 18 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.8.3 Verify each ERCW pump starts automatically on an 18 months actual or simulated actuation signal.

Watts Bar - Unit 2 3.7-19 (developmental) A

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS inoperable. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify average water temperature of UHS is 85°F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Watts Bar - Unit 2 3.7-20 (developmental) A

CREVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)

LCO 3.7.10 Two CREVS trains shall be OPERABLE.

NOTE--------------------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVS train A.1 Restore CREVS train to 7 days inoperable for reasons other OPERABLE status.

than Condition B.

B. One or more CREVS trains B.1 Initiate action to Immediately inoperable due to implement mitigating inoperable CRE boundary actions.

in MODE 1, 2, 3, or 4.

AND B.2 Verify mitigating actions 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure CRE occupant exposures to radiological and chemical hazards will not exceed limits and CRE occupants are protected from smoke hazards.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

(continued)

Watts Bar - Unit 2 3.7-21 (developmental) F

CREVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and D.1 Place OPERABLE Immediately associated Completion CREVS train in Time of Condition A not met emergency mode.

in MODE 5 or 6, or during movement of irradiated fuel OR assemblies.

D.2 Suspend movement of Immediately irradiated fuel assemblies.

E. Two CREVS trains E.1 Restore one CREVS train 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable in MODE 1, 2, 3, to OPERABLE status.

or 4 due to actions taken as a result of a tornado warning.

F. Two CREVS trains F.1 Suspend movement of Immediately inoperable in MODE 5 or 6, irradiated fuel or during movement of assemblies.

irradiated fuel assemblies.

OR One or more CREVS trains inoperable due to inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.

(continued)

Watts Bar - Unit 2 3.7-22 (developmental) A

CREVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two CREVS trains G.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train for 15 minutes. 31 days SR 3.7.10.2 Perform required CREVS filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or 18 months simulated actuation signal.

SR 3.7.10.4 Perform required CRE unfiltered air inleakge testing In accordance with in accordance with the Control Room Envelope the Control Room Habitability Program. Envelope Habitability Program Watts Bar - Unit 2 3.7-23 (developmental) A

CREATCS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS)

LCO 3.7.11 Two CREATCS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREATCS train A.1 Restore CREATCS train 30 days inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met AND in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and C.1 Place OPERABLE Immediately associated Completion CREATCS train in Time of Condition A not met operation.

in MODE 5 or 6, or during movement of irradiated fuel OR assemblies.

C.2 Suspend movement of Immediately irradiated fuel assemblies.

D. Two CREATCS trains D.1 Suspend movement of Immediately inoperable in MODE 5 or 6, irradiated fuel assemblies or during movement of irradiated fuel assemblies.

E. Two CREATCS trains E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4.

Watts Bar - Unit 2 3.7-24 (developmental) F

CREATCS 3.7.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CREATCS train has the capability to 18 months remove the assumed heat load.

Watts Bar - Unit 2 3.7-25 (developmental) A

ABGTS 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Auxiliary Building Gas Treatment System (ABGTS)

LCO 3.7.12 Two ABGTS trains shall be OPERABLE APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ABGTS train A.1 Restore ABGTS train to 7 days inoperable OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Two ABGTS trains inoperable.

Watts Bar - Unit 2 3.7-26 (developmental) H

ABGTS 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each ABGTS train for 10 continuous hours 31 days with the heaters operating.

SR 3.7.12.2 Perform required ABGTS filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.12.3 Verify each ABGTS train actuates on an actual or 18 months simulated actuation signal.

SR 3.7.12.4 Verify one ABGTS train can maintain a pressure 18 months on a between -0.25 inches and -0.5 inches water gauge STAGGERED TEST with respect to atmospheric pressure during the post BASIS accident mode of operation at a flow rate 9300 cfm and 9900 cfm.

Watts Bar - Unit 2 3.7-27 (developmental) A

Fuel Storage Pool Water Level 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Fuel Storage Pool Water Level LCO 3.7.13 The fuel storage pool water level shall be 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool water A.1 -------------NOTE------------

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in the fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify the fuel storage pool water level is 23 ft 7 days above the top of the irradiated fuel assemblies seated in the storage racks.

Watts Bar - Unit 2 3.7-28 (developmental) A

Secondary Specific Activity 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Secondary Specific Activity LCO 3.7.14 The specific activity of the secondary coolant shall be 0.10 Ci/gm DOSE EQUIVALENT I-131.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the specific activity of the secondary coolant is 31 days 0.10 Ci/gm DOSE EQUIVALENT I-131.

Watts Bar - Unit 2 3.7-29 (developmental) A

Spent Fuel Assembly Storage 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Assembly Storage LCO 3.7.15 The combination of initial enrichment and burnup of each spent fuel assembly stored shall be in accordance with Specification 4.3.1.1.

APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 ------------NOTE-------------

not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the initial enrichment Prior to storing the and burnup of the fuel assembly is in accordance fuel assembly.

with Specification 4.3.1.1.

Watts Bar - Unit 2 3.7-30 (developmental) A

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Four diesel generators (DGs) capable of supplying the onsite Class 1E AC Electrical Power Distribution System.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTE-------------------------------------------------------------

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE offsite circuit.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature(s) with no offsite discovery of no offsite power available power to one train inoperable when its concurrent with redundant required inoperability of feature(s) is inoperable. redundant required feature(s)

AND (continued)

Watts Bar - Unit 2 3.8-1 (developmental) F

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 6 days from discovery of failure to meet LCO B. One or more DG(s) in B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Train A inoperable. the offsite circuits.

AND OR Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months One or more DG(s) in thereafter Train B inoperable.

AND B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s) supported by discovery of the inoperable DG(s) Condition B inoperable when its concurrent with required redundant inoperability of feature(s) is inoperable redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

AND (continued)

Watts Bar - Unit 2 3.8-2 (developmental) F

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 Restore required DG(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 6 days from discovery of failure to meet LCO C. Two offsite circuits C.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable. feature(s) inoperable discovery of when its redundant Condition C required feature(s) is concurrent with inoperable. inoperability of redundant required features AND C.2 Restore one offsite circuit 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to OPERABLE status.

D. One offsite circuit --------------------NOTE-------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems - Operating,"

when Condition D is entered with no One or more required DG(s) AC power source to any train.

in Train A inoperable.

OR D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more required DG(s) OPERABLE status.

in Train B inoperable.

OR D.2 Restore required DG(s) to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

(continued)

Watts Bar - Unit 2 3.8-3 (developmental) A

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more required DG(s) E.1 Restore required DGs in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in Train A inoperable. Train A to OPERABLE status.

AND OR One or more required DG(s) in Train B inoperable. E.2 Restore required DGs in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Train B to OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A. B, C, AND D, or E not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Two offsite circuits G.1 Enter LCO 3.0.3. Immediately inoperable.

AND One or more required DG(s) in Train A inoperable.

OR One or more required DG(s) in Train B inoperable.

H. One offsite circuit H.1 Enter LCO 3.0.3. Immediately inoperable.

AND One or more required DG(s) in Train A inoperable.

AND One or more required DG(s) in Train B inoperable.

Watts Bar - Unit 2 3.8-4 (developmental) A

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power 7 days availability for each offsite circuit.

SR 3.8.1.2 -------------------------------NOTES----------------------------

1. Performance of SR 3.8.1.7 satisfies this SR.

2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

Verify each DG starts from standby conditions and As specified in achieves steady state voltage 6800 V and Table 3.8.1-1 7260 V, and frequency 58.8 Hz and 61.2 Hz.

SR 3.8.1.3 -------------------------------NOTES----------------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and As specified in operates for 60 minutes at a load Table 3.8.1-1 3960 kW and 4400 kW.

SR 3.8.1.4 Verify each skid mounted day tank contains 31 days 218.5 gal of fuel oil.

(continued)

Watts Bar - Unit 2 3.8-5 (developmental) A

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.5 Check for and remove accumulated water from each 31 days skid mounted day tank.

SR 3.8.1.6 Verify the fuel oil transfer system operates to 31 days automatically transfer fuel oil from 7 day storage tank to the skid mounted day tank.

SR 3.8.1.7 Verify each DG starts from standby condition and 184 days achieves in 10 seconds, voltage 6800 V, and frequency 58.8 Hz. Verify after DG fast start from standby conditions that the DG achieves steady state voltage 6800 V and 7260 V, and frequency 59.8 Hz and 60.0Hz.

SR 3.8.1.8 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of each 18 months 6.9 kV shutdown board power supply from the normal offsite circuit to each alternate offsite circuit.

(continued)

Watts Bar - Unit 2 3.8-6 (developmental) H

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 -------------------------------NOTES----------------------------

1. This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor 0.8 and 0.9.

Verify each DG rejects a load greater than or equal 18 months to its associated single largest post-accident load, and:

a. Following load rejection, the frequency is 66.75 Hz;

b. Within 3 seconds following load rejection, the voltage is 6555 V and 7260 V; and

c. Within 4 seconds following load rejection, the frequency is 59.8 Hz and 60.0 Hz.

SR 3.8.1.10 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG operating at a power factor 0.8 and 18 months 0.9 does not trip and voltage is maintained 8880 V during and following a load rejection of 3960 kW and 4400 kW and 2970 kVAR and 3300 kVAR.

(continued)

Watts Bar - Unit 2 3.8-7 (developmental) H

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 18 months signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses;

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 10 seconds,

2. energizes auto-connected shutdown loads through automatic load sequencer,

3. maintains steady state voltage 6800 V and 7260 V,

4. maintains steady state frequency 59.8 Hz and 60.0 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for 5 minutes.

(continued)

Watts Bar - Unit 2 3.8-8 (developmental) H

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Engineered Safety 18 months Feature (ESF) actuation signal each Unit 2 DG auto-starts from standby condition and:

a. In 10 seconds after auto-start and during tests, achieves voltage 6800 V and frequency 58.8 Hz;

b. After DG fast start from standby conditions the DG achieves steady state voltage 6800 V and 7260 V, and frequency 59.8 Hz and 60 Hz.

c. Operates for 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized from the offsite power system.

SR 3.8.1.13 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG's automatic trips are bypassed on 18 months automatic or emergency start signal except:

a. Engine overspeed; and

b. Generator differential current (continued)

Watts Bar - Unit 2 3.8-9 (developmental) H

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.14 -------------------------------NOTES----------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. For performance of this test in MODE 1, 2, 3 or 4, three DGs must be maintained operable and in a standby condition.

3. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG operating at a power factor 18 months 0.8 and 0.9 operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 4620 kW and 4840 kW and 3465 kVAR and 3630 kVAR; and

b. For the remaining hours of the test loaded 3960 kW and 4400 kW and 2970 kVAR and 3300 kVAR.

SR 3.8.1.15 -------------------------------NOTES----------------------------

This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 3960 kW and 4400 kW.

Momentary transients outside of load range do not invalidate this test.

Verify each DG starts and achieves, in 10 seconds, 18 months voltage 6800 V, and frequency 58.8 Hz. Verify after DG fast start from standby conditions that the DG achieves steady state voltage 6800 V and 7260 V, and frequency 59.8 Hz and 60.0 Hz.

(continued)

Watts Bar - Unit 2 3.8-10 (developmental) H

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.16 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG: 18 months

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

SR 3.8.1.17 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.

Verify, with each Unit 2 DG operating in test mode 18 months and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

(continued)

Watts Bar - Unit 2 3.8-11 (developmental) A

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.18 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.

Verify the time delay setting for each sequenced load 18 months block is within limits for each accident condition and non-accident condition load sequence.

SR 3.8.1.19 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 18 months signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DGs of the same power train auto-start from standby condition and:

1. energizes permanently connected loads in 10 seconds,

2. energizes auto-connected emergency loads through load sequencer,

3. achieves steady state voltage:

6800 V and 7260 V,

4. achieves steady state frequency 59.8 Hz and 60.0 Hz, and

5. supplies permanently connected and auto-connected emergency loads for 5 minutes.

(continued)

Watts Bar - Unit 2 3.8-12 (developmental) H

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.20 Verify during idle operation that any automatic or 18 months emergency start signal disables the idle start circuitry and commands the engine to full speed.

SR 3.8.1.21 Verify when started simultaneously from standby 10 years condition, each DG achieves, in 10 seconds, voltage 6800 V and frequency 58.8 Hz. Verify after DG fast start from standby conditions that the DG achieves steady state voltage 6800 V and 7260 V, and frequency 59.8 Hz and 60.0 Hz.

Watts Bar - Unit 2 3.8-13 (developmental) H

AC Sources - Operating 3.8.1 Table 3.8.1-1 (page 1 of 1)

Diesel Generator Test Schedule NUMBER OF FAILURES IN LAST 25 VALID TESTS(a) FREQUENCY 3 31 days 4 7 days(b)

(but no less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

(a) Criteria for determining number of failures and valid tests shall be in accordance with Regulatory Position C.2.1 of Regulatory Guide 1.9, Revision 3, where the number of tests and failures is determined on a per DG basis.

(b) This test frequency shall be maintained until seven consecutive failure free starts from standby conditions and load and run tests have been performed. If, subsequent to the 7 failure free tests, 1 or more additional failures occur, such that there are again 4 or more failures in the last 25 tests, the testing interval shall again be reduced as noted above and maintained until 7 consecutive failure free tests have been performed.

Watts Bar - Unit 2 3.8-14 (developmental) A

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown;" and

b. Two diesel generators (DGs) either Train A or Train B capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit --------------------NOTE-------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Declare affected required Immediately feature(s) with no offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS AND (continued)

Watts Bar - Unit 2 3.8-15 (developmental) B

AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to suspend Immediately operations involving positive reactivity additions.

AND A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. One required DG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies.

AND B.3 Initiate action to suspend Immediately operations involving positive reactivity additions.

AND B.4 Initiate action to restore Immediately required DG to OPERABLE status.

Watts Bar - Unit 2 3.8-16 (developmental) A

AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -------------------------------NOTE------------------------------

The following SRs are not required to be performed:

SR 3.8.1.3, SR 3.8.1.6, SR 3.8.1.9 through SR 3.8.1.16, SR 3.8.1.18 and SR 3.8.1.19.

For AC sources required to be OPERABLE, the SRs In accordance with of Specification 3.8.1, "AC Sources-Operating," applicable SRs except SR 3.8.1.8, SR 3.8.1.17, and SR 3.8.1.21, are applicable.

Watts Bar - Unit 2 3.8-17 (developmental) A

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required diesel generator (DG).

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with fuel A.1 Restore fuel oil level to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months level < 56,754 gal and within limits.

> 48,648 gal in storage tank.

B. One or more diesel engines B.1 Restore lube oil inventory 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months with lube oil inventory to within limits.

< 287 gal and > 267 gal.

C. One or more DGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates within limit.

particulates not within limit.

D. One or more DGs with new D.1 Restore stored fuel oil 30 days fuel oil properties not within properties to within limits.

limits.

(continued)

Watts Bar - Unit 2 3.8-18 (developmental) A

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more DGs with E.1 Restore starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months starting air receiver receiver pressure to pressure < 190 psig and 190 psig.

170 psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

Time not met.

OR One or more DGs diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each 7 day fuel oil storage tank contains 31 days 56,754 gal of fuel.

SR 3.8.3.2 Verify lubricating oil inventory is 287 gal per 31 days engine.

SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil are In accordance with tested in accordance with, and maintained within the the Diesel Fuel Oil limits of, the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure is 31 days 190 psig.

(continued)

Watts Bar - Unit 2 3.8-19 (developmental) A

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.3.5 Check for and remove accumulated water from each 31 days of the four interconnected tanks which constitute the 7 day fuel oil storage tank.

SR 3.8.3.6 Perform a visual inspection for leaks in the exposed 18 months fuel oil system piping while the DG is running.

SR 3.8.3.7 For each of the four interconnected tanks which 10 years constitute the 7 day fuel oil storage tank:

a. Drain the fuel oil;

b. Remove the sediment; and

c. Clean the tank.

Watts Bar - Unit 2 3.8-20 (developmental) A

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 Four channels of vital DC and four Diesel Generator (DG) DC electrical power subsystems shall be OPERABLE.

NOTES-------------------------------------------

1. Vital Battery V may be substituted for any of the required vital batteries.

2. Spare Vital Chargers 6-S, 7-S, 8-S, or 9-S may be substituted for required Vital chargers.

3. Spare DG Chargers 1A1, 1B1, 2A1, or 2B1 may be substituted for required DG chargers.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required vital battery A.1 Restore vital battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger inoperable. terminal voltage to greater than or equal to the minimum established float voltage.

AND A.2 Verify vital battery Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months charger float current

< 2 amps.

AND A.3 Restore vital battery 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months charger to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.8-21 (developmental) H

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required vital battery B.1 Restore vital battery to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. OPERABLE status.

C. One required vital DC C.1 Restore vital DC channel 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months channel inoperable for to OPERABLE status reasons other than Condition A or B..

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A, B, or C AND not met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. One required DG battery E.1 Restore DG battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger inoperable. terminal voltage to greater than or equal to the minimum established float voltage.

AND E.2 Verify DG battery charger Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months float current < 2 amps.

AND E.3 Restore DG battery 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months charger to OPERABLE status.

F. One required DG battery F.1 Restore DG battery to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. OPERABLE status.

(continued)

Watts Bar - Unit 2 3.8-22 (developmental) H

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. One required DG DC G.1 Restore DG DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power subsystem power subsystem to inoperable for reasons other OPERABLE status than Condition E or F.

H. Required Action and H.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition E, F, or G not met SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify vital battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.2 Verify DG battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.3 Verify for the vital batteries that the alternate feeder 7 days breakers to each required battery charger are open.

SR 3.8.4.4 Verify correct breaker alignment and indicated power 7 days availability for each DG 125 V DC distribution panel and associated battery charger (continued)

Watts Bar - Unit 2 3.8-23 (developmental) H

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.5 Verify each vital battery charger supplies > 200 amps 18 months at greater than or equal to the minimum established float voltage for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

OR Verify each vital battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.6 Verify each DG battery charger supplies > 200 amps 18 months at greater than or equal to the minimum established float voltage for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

OR Verify each DG battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.7 -------------------------------NOTES---------------------------- 18 months

1. The modified performance discharge test in SR 3.8.4.6 may be performed in lieu of the service test in SR 3.8.4.7 once per 60 months.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads and any connected nonsafety loads for the design duty cycle when subjected to a battery service test.

Watts Bar - Unit 2 3.8-24 (developmental) H

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 Vital DC and Diesel Generator (DG) DC electrical power subsystems shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown" and to support the Diesel Generators (DGs) required by LCO 3.8.2, "AC Sources - Shutdown."

NOTES------------------------------------------

1. Vital Battery V may be substituted for any of the required vital batteries.

2. Spare vital chargers 6-S, 7-S, 8-S, or 9-S may be substituted for required vital chargers.

3. Spare DG chargers 1A1, 1B1, 2A1, or 2B1 may be substituted for required DG chargers.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required vital A.1.1 Declare affected required Immediately DC electrical power feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND (continued)

Watts Bar - Unit 2 3.8-25 (developmental) H

DC Sources - Shutdown 3.8.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to suspend Immediately operations involving positive reactivity additions.

AND A.2.4 Initiate action to restore Immediately required vital DC electrical power subsystems to OPERABLE status.

B. One or more required DG B.1 Declare associated DG Immediately DC electrical power inoperable.

subsystems inoperable.

Watts Bar - Unit 2 3.8-26 (developmental) H

DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 -------------------------------NOTE------------------------------

The following SRs are not required to be performed:

SR 3.8.4.5, SR 3.8.4.6, and SR 3.8.4.7.

For DC sources required to be OPERABLE, the In accordance with following SRs are applicable: applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SR 3.8.4.5 SR 3.8.4.6 SR 3.8.4.7 Watts Bar - Unit 2 3.8-27 (developmental) H

Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters LCO 3.8.6 Battery parameters for 125 V vital batteries and 125 V diesel generator (DG) batteries shall be within the limits.

APPLICABILITY: When associated DC electrical power subsystems and DGs are required to be OPERABLE.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each battery.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required vital battery A.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with one or more battery cells float voltage < 2.07 V. AND A.2 Perform SR 3.8.6.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.3 Restore affected cell float 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months voltage > 2.07 V.

B. One required vital battery B.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with float current > 2 amps.

AND B.2 Restore vital battery float 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months current to < 2 amps.

(continued)

Watts Bar - Unit 2 3.8-28 (developmental) H

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One required DG battery C.1 Perform SR 3.8.4.2. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with one or more battery cells float voltage < 2.07 V. AND C.2 Perform SR 3.8.6.2. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND C.3 Restore affected cell float 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months voltage > 2.07 V.

D. One required DG battery D.1 Perform SR 3.8.4.2. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with float current > 1 amp.

AND D.2 Restore DG battery float 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months current to < 2 amps.

NOTE------------------ --------------------NOTE--------------------

Required Action E.2 shall be Required Actions E.1 and E.2 are completed if electrolyte level only applicable if electrolyte level was below the top of plates. was below the top of plates.

E. One required battery with E.1 Restore electrolyte levels 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months one or more cells with to above top of plates.

electrolyte level less than minimum established AND design limits.

E.2 Verify no evidence of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months leakage.

AND E.3 Restore electrolyte level 31 days to greater than or equal to minimum established design limits.

(continued)

Watts Bar - Unit 2 3.8-29 (developmental) H

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One required battery with F.1 Restore battery pilot cell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months pilot cell electrolyte temperature to greater temperature less than than or equal to minimum minimum established established design limits.

design limits.

G. More than one required vital G.1 Restore battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months batteries with battery parameters to within parameters not within limits. limits.

OR More than one required DG batteries with battery parameters not within limits.

H. Required Action and H.1 Declare associate battery Immediately associated Completion inoperable Time of Condition A, B, C, D, E, F, or G not met.

OR One required vital battery with one or more battery cells float voltage < 2.07 V and float current > 2 amps.

OR One required DG battery with one or more battery cells float voltage < 2.07 V and float current > 2 amps.

Watts Bar - Unit 2 3.8-30 (developmental) H

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 -------------------------------NOTE-------------------------------

Not required to be met when vital battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each vital battery float current is < 2 amps. 7 days SR 3.8.6.2 -------------------------------NOTE-------------------------------

Not required to be met when DG battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.2.

Verify each DG battery float current is < 1 amp. 7 days SR 3.8.6.3 Verify each required vital and DG battery pilot cell 31 days float voltage is > 2.07 V.

SR 3.8.6.4 Verify each required vital and DG battery connected 31 days cell electrolyte level is greater than or equal to minimum established design limits.

SR 3.8.6.5 Verify each required vital and DG battery pilot cell 31 days temperature is greater than or equal to minimum established design limits.

SR 3.8.6.6 Verify each required vital and DG battery connected 92 days cell float voltage is > 2.07 V.

(continued)

Watts Bar - Unit 2 3.8-31 (developmental) H

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.7 -------------------------------NOTE-------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is > 80% of the manufacturers 60 months rating when subjected to a performance discharge test or a modified performance discharge test. AND 12 months when battery shows degradation, or has reached 85% of the expected life with capacity < 100% of manufacturers rating AND 24 months when battery has reached 85% of the expected life with capacity

> 100% of manufacturers rating Watts Bar - Unit 2 3.8-32 (developmental) H

Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 Two inverters in each of four channels shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One inverter in one channel A.1 -------------NOTE------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems-Operating", with any AC Vital Bus deenergized.

Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.8-33 (developmental) B

Inverters - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and 7 days alignment to required AC vital bus and from associated vital battery board and 480 V shutdown board.

Watts Bar - Unit 2 3.8-34 (developmental) A

Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 Inverters shall be OPERABLE to support the onsite Class 1E AC vital bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected required Immediately inverter channels feature(s) inoperable.

inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to suspend Immediately operations involving positive reactivity additions AND A.2.4 Initiate action to restore Immediately required inverters to OPERABLE status Watts Bar - Unit 2 3.8-35 (developmental) A

Inverters - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and 7 days alignments to required AC vital bus and from associated vital battery board and 480 V shutdown board.

Watts Bar - Unit 2 3.8-36 (developmental) A

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Train A and Train B AC, four channels of vital DC, and four channels of AC vital bus electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC electrical A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution power distribution subsystems inoperable. subsystem to AND OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO B. One or more AC vital buses B.1 Restore AC vital bus(es) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in one channel inoperable. to OPERABLE status.

AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO C. One or more vital DC C.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power distribution power distribution bus to buses inoperable. OPERABLE status. AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO (continued)

Watts Bar - Unit 2 3.8-37 (developmental) A

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two trains with one or more E.1 Enter LCO 3.0.3. Immediately inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to 7 days required AC, vital DC, and AC vital bus electrical power distribution subsystems.

Watts Bar - Unit 2 3.8-38 (developmental) A

Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, vital DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC, A.1 Declare associated Immediately vital DC, or AC vital bus supported required electrical power distribution feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate action to suspend Immediately operations involving positive reactivity additions.

AND (continued)

Watts Bar - Unit 2 3.8-39 (developmental) A

Distribution Systems - Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate actions to restore Immediately required AC, vital DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required residual heat removal subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to 7 days required AC, vital DC, and AC vital bus electrical power distribution subsystems.

Watts Bar - Unit 2 3.8-40 (developmental) A

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.

APPLICABILITY: Mode 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE Immediately not within limit. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit specified 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in COLR.

Watts Bar - Unit 2 3.9-1 (developmental) F

Unborated Water Source Isolation Valves 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Unborated Water Source Isolation Valves LCO 3.9.2 Each valve used to isolate unborated water sources shall be secured in the closed position.

APPLICABILITY: Mode 6.

ACTIONS

NOTE------------------------------------------------------------

Separate Condition entry is allowed for each unborated water source isolation valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------------NOTE-------------- A.1 Suspend CORE Immediately Required Action A.3 must ALTERATIONS.

be completed whenever Condition A is entered. AND A.2 Initiate action to secure Immediately One or more valves valve in closed position.

not secured in closed position. AND A.3 Perform SR 3.9.1.1. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated water 31 days sources is secured in the closed position.

Watts Bar - Unit 2 3.9-2 (developmental) F

Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCO 3.9.3 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: Mode 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source range A.1 Suspend CORE Immediately neutron flux monitor ALTERATIONS.

inoperable.

AND A.2 Suspend positive Immediately reactivity additions.

B. Two required source range B.1 Initiate action to restore Immediately neutron flux monitors one source range neutron inoperable. flux monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Watts Bar - Unit 2 3.9-3 (developmental) F

Nuclear Instrumentation 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.3.2 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Watts Bar - Unit 2 3.9-4 (developmental) A

THIS SECTION NOT USED 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 THIS SECTION NOT USED Watts Bar - Unit 2 3.9-5 (developmental) H

RHR and Coolant Circulation - High Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.

NOTE--------------------------------------------

The required RHR loop may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause reduction of the Reactor Coolant System boron concentration.

APPLICABILITY: MODE 6 with the water level 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements not A.1 Suspend operations Immediately met. involving a reduction in reactor coolant boron concentration.

AND A.2 Suspend loading Immediately irradiated fuel assemblies in the core.

AND A.3 Initiate action to satisfy Immediately RHR loop requirements.

AND (continued)

Watts Bar - Unit 2 3.9-6 (developmental) A

RHR and Coolant Circulation - High Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant at a flow rate of 2500 gpm.

Watts Bar - Unit 2 3.9-7 (developmental) A

RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.

AND A.2 Initiate action to establish Immediately 23 ft of water above the top of reactor vessel flange.

(continued)

Watts Bar - Unit 2 3.9-8 (developmental) A

RHR and Coolant Circulation - Low Water Level 3.9.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR loop in operation. B.1 Suspend operations Immediately involving a reduction in reactor coolant boron concentration.

AND B.2 Initiate action to restore Immediately one RHR loop to operation.

AND B.3 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant at a flow rate of 2000 gpm.

SR 3.9.6.2 Verify correct breaker alignment and indicated power 7 days available to the required RHR pump that is not in operation.

Watts Bar - Unit 2 3.9-9 (developmental) A

Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Cavity Water Level LCO 3.9.7 Refueling cavity water level shall be maintained 23 ft above the top of reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water level A.1 Suspend movement of Immediately not within limit. irradiated fuel assemblies within containment.

AND A.2 Initiate action to restore Immediately refueling cavity water level to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling cavity water level is 23 ft above the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months top of reactor vessel flange.

Watts Bar - Unit 2 3.9-10 (developmental) A

THIS SECTION NOT USED 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 THIS SECTION NOT USED Watts Bar - Unit 2 3.9-11 (developmental) H

Spent Fuel Pool Boron Concentration 3.9.9 3.9 REFUELING OPERATIONS 3.9.9 Spent Fuel Pool Boron Concentration LCO 3.9.9 Boron concentration of the spent fuel pool shall be 2000 ppm.

APPLICABILITY: During fuel movement in the flooded spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend fuel movement. Immediately not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.9.1 Verify boron concentration in the spent fuel pool is Prior to movement of 2000 ppm. fuel in the spent fuel pool AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter Watts Bar - Unit 2 3.9-12 (developmental) A

Decay Time 3.9.10 3.9 REFUELING OPERATIONS 3.9.10 Decay Time LCO 3.9.10 The reactor shall be subcritical for > 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

APPLICABILITY: During movement of irradiated fuel assemblies within the containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical for A.1 Suspend all operations Immediately

< 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months . involving movement of irradiated fuel assemblies within the containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.10.1 Verify the reactor has been subcritical for Prior to movement

> 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months by confirming the date and time of of irradiated fuel in subcriticality. the reactor vessel.

Watts Bar - Unit 2 3.9-13 (developmental) H

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries shall be as shown in Figure 4.1-1.

4.1.2 Low Population Zone (LPZ)

The LPZ shall be as shown in Figure 4.1-2 (within the 3-mile circle).

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zirlo fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 57 control rod assemblies. The control material shall be silver indium cadmium as approved by the NRC.

(continued)

Watts Bar - Unit 2 4.0-1 (developmental) C

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks (shown in Figure 4.3-1) are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent (wt%);

b. keff < 0.95 if fully flooded with unborated water, which, includes an allowance for uncertainties as described in Sections 4.3.2.7 and 9.1 of the FSAR;

c. Distances between fuel assemblies are a nominal 10.375 inch center-to-center spacing in the twenty-four flux trap rack modules.

d. Fuel assemblies with initial enrichments less than a maximum of 5 wt% U-235 enrichment (nominally 4.95 +/- 0.05 wt% U-235) may be stored in the spent fuel racks in any one of four arrangements with specific limits as identified below:

1. Fuel assemblies may be stored in the racks in an all cell arrangement provided the burnup of each assembly is in the acceptable domain identified in Figure 4.3-3, depending upon the specified initial enrichment.

2. New and spent fuel assemblies may be stored in a checkerboard arrangement of 2 new and 2 spent assemblies, provided that each spent fuel assembly has accumulated a minimum burnup in the acceptable domain identified in Figure 4.3-4.

3. New fuel assemblies may be stored in 4-cell arrays with 1 of the 4 cells remaining empty of fuel (i.e. containing only water or water with up to 75 percent by volume of non-fuel bearing material.

(continued)

Watts Bar - Unit 2 4.0-2 (developmental) H

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage (continued)

4. New fuel assemblies with a minimum of 32 integral fuel burnable absorber (IFBA) rods may be stored without further restriction, provided the loading of ZrB2 in the coating of each IFBA rod is minimum of 1.25x (1.9625mg/in).

A water cell is less reactive than any cell containing fuel and therefore a water cell may be used at any location in the loading arrangements.

A water cell is defined as a cell containing water or non-fissile material with no more than 75 percent of the water displaced.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum enrichment of 5.0 weight percent U-235 and shall be maintained with the arrangement of 120 storage locations shown in Figure 4.3-2;

b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the FSAR;

c. keff 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the FSAR; and

d. A nominal 21-inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below Elevation 747 feet - 1 1/2 inches.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1386 fuel assemblies in 24 flux trap rack modules.

Watts Bar - Unit 2 4.0-3 (developmental) A

Design Features 4.0 FIGURE 4.1-1 (PAGE 1 OF 1)

SITE AND EXCLUSION AREA BOUNDARIES (continued)

Watts Bar - Unit 2 4.0-4 (developmental) A

Design Features 4.0 FIGURE 4.1-2 (PAGE 1 OF 1)

LOW POPULATION ZONE (continued)

Watts Bar - Unit 2 4.0-5 (developmental) A

SOUTH WALL Watts Bar - Unit 2 (developmental) 4.0-6 WEST WALL FLUX TRAP RACK, TYPICAL FUEL CASK LOADING PIT Design Features PLAN FIGURE 4.3-1 SPENT FUEL POOL SPENT FUEL STORAGE RACKS 4.0 A

(continued)

Design Features 4.0 FIGURE 4.3-2 NEW FUEL STORAGE RACK LOADING PATTERN (continued)

Watts Bar - Unit 2 4.0-7 (developmental) A

Design Features 4.0 ACCEPTABLE BURNUP DOMAIN Burnup, MWD/kgU UNACCEPTABLE BURNUP DOMAIN Initial Enrichment wt% U-235 FIGURE 4.3-3 MINIMUM REQUIRED BURNUP FOR UNRESTRICTED STORAGE OF FUEL OF VARIOUS INITIAL ENRICHMENTS (continued)

Watts Bar - Unit 2 4.0-8 (developmental) H

Design Features 4.0 ACCEPTABLE BURNUP DOMAIN Burnup, MWD/kgU UNACCEPTABLE BURNUP DOMAIN Initial Enrichment wt% U-235 FIGURE 4.3-4 MINIMUM REQUIRED BURNUP FOR A CHECKERBOARD ARRANGEMENT OF 2 SPENT AND 2 NEW FUEL ASSEMBLIES OF 5 wt% U-235 ENRICHMENT (MAXIMUM)

Watts Bar - Unit 2 4.0-9 (developmental) H

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Site Vice-President shall be responsible for overall activities of the site, while the Plant Manager shall be responsible for overall unit operation. The Site Vice-President and the Plant Manager 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 or 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, 3, or 4, 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 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

Watts Bar - Unit 2 5.0-1 (developmental) A

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 shall be documented in the Nuclear Power Organization Topical Report (TVA-NPOD 89-A);

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 Site Vice-President shall have 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; and

d. The individuals who train the operating staff, carry out radiological controls, 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.

(continued)

Watts Bar - Unit 2 5.0-2 (developmental) A

Organization 5.2 5.2 Organization (continued) 5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is being operated in MODES 1, 2, 3, or 4.

b. The shift crew composition may be less than the minimum requirements of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absences of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. A radiological controls technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Deleted

e. The Operations Superintendent shall have a valid SRO license on this unit.

f. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on shift (Generic Letter 86-04 dated 02/13/86).

Watts Bar - Unit 2 5.0-3 (developmental) B

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 for comparable positions, as specified in TVA Nuclear Quality Assurance Plan (TVA-NQA-PLN89-A).

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54 (m).

Watts Bar - Unit 2 5.0-4 (developmental) A

Training 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Training (removed from Technical Specifications)

Watts Bar - Unit 2 5.0-5 (developmental) A

Reviews and Audits 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Reviews and Audits (removed from Technical Specifications)

Watts Bar - Unit 2 5.0-6 (developmental) A

TS Bases Control Program 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Technical Specifications (TS) Bases Control Program This Program provides a means for processing changes to the Bases of these Technical Specifications.

5.6.1 Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

5.6.2 Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

a. A change in the TS incorporated in the license; or

b. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

5.6.3 The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

5.6.4 Proposed changes that meet the criteria of Specification 5.6.2 shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

Watts Bar - Unit 2 5.0-7 (developmental) A

Procedures, Programs, and Manuals 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Procedures, Programs, and Manuals 5.7.1 Procedures 5.7.1.1 Scope Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1 (Generic Letter 82-33);

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.7.2.

5.7.1.2 Review and Approval (removed from Technical Specifications) 5.7.1.3 Temporarily Approved Changes (removed from Technical Specifications)

(continued)

Watts Bar - Unit 2 5.0-8 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.7.2.1 (removed from Technical Specifications) 5.7.2.2 (removed from Technical Specifications) 5.7.2.3 Offsite Dose Calculation Manual (ODCM)

a. The ODCM 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 ODCM 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 Specifications 5.9.2 and 5.9.3.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s),

2. 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 not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after the approval of the Plant Manager; and (continued)

Watts Bar - Unit 2 5.0-9 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.3 Offsite Dose Calculation Manual (ODCM) (continued)

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.7.2.4 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Containment Spray, Safety Injection, Residual Heat Removal, Chemical and Volume Control, Reactor Coolant System Sampling, and Waste Gas. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 18 months.

The provisions of SR 3.0.2 are applicable.

5.7.2.5 (removed from Technical Specifications) 5.7.2.6 (removed from Technical Specifications)

(continued)

Watts Bar - Unit 2 5.0-10 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.7 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.

The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; (continued)

Watts Bar - Unit 2 5.0-11 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.7 Radioactive Effluent Controls Program (continued)

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate 500 mrem/yr to the whole body and a dose rate 3000 mrem/yr to the skin, and

2. For idodine-131, idodine-133, tritium, and all radionuclides in particulate form with halflives greater than 8 days: a dose rate 1500 mrem/yr to any organ.

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

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 each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.7.2.8 (removed from Technical Specifications) 5.7.2.9 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section 5.2.1.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.7.2.10 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulation Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

5.7.2.11 Inservice Testing Program (continued)

Watts Bar - Unit 2 5.0-12 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued)

This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

ASME OM Code and applicable Addenda terminology Required Frequencies for performing for inservice testing activities inservice testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.12 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging or repair of tubes.

Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged, to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, cooldown, all anticipated transients included in the design specification, and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials.

Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse.

In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.12 Steam Generator (SG) Program (continued)

2. Accident induced leakage performance criterion: The primary-to-secondary accident induced leakage rate for any design basis accident, other than an SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed1 gpm per SG, except for specific types of degradation at specific locations as described in paragraph c.

of the Steam Generator Program.

3. The operational leakage performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE."

c. Provisions for SG tube plugging or repair criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged or repaired.

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging or repair criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.12 Steam Generator (SG) Program (continued)

2. After the first refueling outage following SG installation, inspect each SG at least every 24 effective full power months or at least every refueling outage (whichever results in more frequent inspections). In addition, inspect 100% of the tubes at sequential periods of 60 effective full power months beginning after the first refueling outage inspection following SG installation. Each 60 effective full power month inspection period may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube repair criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated. The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period.

3. If crack indications are found in any SG tube, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary-to-secondary LEAKAGE.

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.13 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables;

b. Identification of the procedures used to measure the values of the critical variables;

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage;

d. Procedures for the recording and management of data; Secondary Water Chemistry Program (continued)

e. Procedures defining corrective actions for all off control point chemistry conditions; and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

(continued)

Watts Bar-Unit 2 5.0-17 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.14 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in accordance with Regulatory Guide 1.52, Revision 2; ASME N510-1989, and the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR.

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass within acceptance criterion when tested in accordance with Regulatory Guide 1.52, Revision 2, the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, and ASME N510-1989 at the system flowrate specified below.

ESF VENTILATION ACCEPTANCE FLOW RATE SYSTEM CRITERIA Emergency Gas < 0.05% 4,000 cfm + 10%

Treatment Auxiliary Building Gas < 0.05% 9,000 cfm + 10%

Treatment Control Room Emergency < 1.00% 4,000 cfm + 10%

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.14 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass within acceptance criterion when tested in accordance with Regulatory Guide 1.52, Revision 2, the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, and ASME N510-1989 at the system flowrate specified below.

ESF VENTILATION ACCEPTANCE FLOW RATE SYSTEM CRITERIA Emergency Gas Treatment < 0.05% 4,000 cfm + 10%

Auxiliary Building Gas < 0.05% 9,000 cfm + 10%

Treatment Control Room Emergency < 1.00% 4,000 cfm + 10%

(continued)

Watts Bar-Unit 2 5.0-19 (developmental) H

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.14 Ventilation Filter Testing Program (VFTP) (continued)

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, and the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30°C and greater than or equal to the relative humidity specified below.

METHYL IODIDE RELATIVE ESF VENTILATION SYSTEM PENETRATION HUMIDITY Emergency Gas Treatment < 0.175% 70%

Auxiliary Building Gas < 0.175% 70%

Treatment Control Room Emergency < 1.0% 70%

d. Demonstrate for each of the ESF systems that the pressure drop across the entire filtration unit is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, and ASME N510-1989 at the system flowrate specified below.

ESF VENTILATION FLOW RATE SYSTEM PRESSURE DROP Emergency Gas < 7.6 inches water 4,000 cfm + 10%

Treatment Auxiliary Building Gas < 7.6 inches water 9,000 cfm + 10%

Treatment Control Room Emergency < 3.5 inches water 4,000 cfm + 10%

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.14 Ventilation Filter Testing Program (VFTP) (continued)

e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below when tested in accordance with ASME N510-1989.

ESF VENTILATION SYSTEM AMOUNT OF HEAT Emergency Gas Treatment 20 + 2.0 kW Auxiliary Building Gas Treatment 50 + 5.0 kW The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.7.2.15 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Holdup System, the quantity of radioactivity contained in gas storage tanks and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, Postulated Radioactive Release due to Waste Gas System Leak or Failure. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, Postulated Radioactive Release due to Tank Failures.

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Waste Gas Holdup System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., the system is not designed to withstand a hydrogen explosion);

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.15 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of > 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and

c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations less than the limits of 10 CFR 20.1302(b)(2)(i), at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.7.2.16 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to the 7 day storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within limits,

2. a flash point and kinematics viscosity within limits for ASTM 2D fuel oil, and

3. a clear and bright appearance with proper color; (continued)

Watts Bar-Unit 2 5.0-22 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.16 Diesel Fuel Oil Testing Program (continued)

b. Other properties for ASTM 2D fuel oil are within limits within 31 days following sampling and addition to the 7 day storage tanks; and

c. Total particulate concentration of the fuel oil in each of the four interconnected tanks which constitute a 7 day storage tank is 10 mg/l when tested every 31 days in accordance with ASTM D-2276, Method A-2 or A-3.

5.7.2.17 (removed from Technical Specifications) 5.7.2.18 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists.

Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

(continued)

Watts Bar-Unit 2 5.0-23 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.18 Safety Function Determination Program (SFDP) (continued)

A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

5.7.2.19 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide (RG) 1.163, Performance-Based Containment Leak-Test Program, dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 15.0 psig.

The maximum allowable containment leakage rate, La, at Pa, is 0.25%

of the primary containment air weight per day.

(continued)

Watts Bar-Unit 2 5.0-24 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.19 Containment Leakage Rate Testing Program (continued)

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criterion is 1.0 La.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the combined Type B and Type C tests, and 0.75 La for Type A tests.

b. Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is 0.05 La when tested at > Pa.

2. For each door, leakage rate is 0.01 La when pressurized to 6 psig.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

5.7.2.20 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of the applicable regulatory requirement {i.e., 5 rem Total Effective Dose Equivalent (TEDE) for a fuel handling accident or 5 rem whole body or its equivalent to any part of the body} for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.20 Control Room Envelope Habitability Program (continued)

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate defined in the Ventilation Filter Testing Program (VFTP), at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.

e. The quantitative limits on unfiltered air inleakage into the CRE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.

Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Watts Bar-Unit 2 5.0-26 (developmental) A

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.21 Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (Std) 450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as identified below:

a. The program allows the following RG 1.129, Revision 2 exceptions:

1. Battery temperature correction may be performed before or after conducting discharge tests.

2. RG 1.129, Regulatory Position 1, Subsection 2, "References,"

is not applicable to this program.

3. In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, "Inspections," the following shall be used: "Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery.

4. In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, "State of Charge Indicator," the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements, the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5. In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6, "Restoration", the following may be used: "Following the test, record the float voltage of each cell of the string."

(continued)

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Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.21 Battery Monitoring and Maintenance Program (continued)

b. The program shall include the following provisions:

1. Actions to restore battery cells with float voltage < 2.13 V;

2. Actions to determine whether the float voltage of the remaining battery cells is 2.13 V when the float voltage of a battery cell has been found to be < 2.13 V;

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

(continued)

Watts Bar-Unit 2 5.0-28 (developmental) H

SFDP 5.8 5.0 ADMINISTRATIVE CONTROLS 5.8 Safety Function Determination Program (SFDP)

(moved to 5.7.2.18)

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Reporting Requirements 5.9 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.9.1 DELETED 5.9.2 Annual Radiological Environmental Operating Report

NOTE-------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

(continued)

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Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.3 Radioactive Effluent Release Report

NOTE-------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.9.4 DELETED 5.9.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to the initial and each reload cycle, or prior to any remaining portion of a cycle, and shall be documented in the COLR for the following:

LCO 3.1.4 Moderator Temperature Coefficient LCO 3.1.6 Shutdown Bank Insertion Limits LCO 3.1.7 Control Bank Insertion Limits LCO 3.2.1 Heat Flux Hot Channel Factor LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor LCO 3.2.3 Axial Flux Difference LCO 3.9.1 Boron Concentration

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(continued)

Watts Bar - Unit 2 5.0-31 (developmental) B

Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1. WCAP-9272-P-A, WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY, July 1985 (W Proprietary). (Methodology for Specifications 3.1.4 - Moderator Temperature Coefficient, 3.1.6 -

Shutdown Bank Insertion Limit, 3.1.7 - Control Bank Insertion Limits, 3.2.1 - Heat Flux Hot Channel Factor, 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3 - Axial Flux Difference, and 3.9.1 - Boron Concentration).

2a. WCAP-16009-P-A, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), January 2005 (W Proprietary).(Methodology for Specification 3.2.1 - Heat Flux HotChannel Factor, and 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor).

2b. WCAP-10054-P-A, Small Break ECCS Evaluation Model Using NOTRUMP Code, August 1985. Addendum 2, Rev. 1: Addendum to the Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model, July 1997. (W Proprietary). (Methodology for Specifications 3.2.1 - Heat Flux Hot Channel Factor, and 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor).

3. WCAP-10216-P-A, Revision 1A, RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F(Q) SURVEILLANCE TECHNICAL SPECIFICATION, February 1994 (W Proprietary). (Methodology for Specifications 3.2.1 - Heat Flux Hot Channel Factor (W(Z) Surveillance Requirements For F(Q) Methodology) and 3.2.3 - Axial Flux Difference (Relaxed Axial Offset Control).)

4. WCAP-12610-P-A, VANTAGE + FUEL ASSEMBLY REFERENCE CORE REPORT, April 1995. (W Proprietary). (Methodology for Specification 3.2.1 - Heat Flux Hot Channel Factor).

(continued)

Watts Bar-Unit 2 5.0-32 (developmental) B

Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

5. WCAP-15088-P, Rev. 1, Safety Evaluation Supporting A More Negative EOL Moderator Temperature Coefficient Technical Specification for the Watts Bar Nuclear Plant, July 1999, (W Proprietary), as approved by the NRC staffs Safety Evaluation accompanying the issuance of Amendment No. 20 (Methodology for Specification 3.1.4 - Moderator Temperature Coefficient.).

6. WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.

(Methodology for Specification 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor).

7. WCAP-15025-P-A, Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17 x 17 Rod Bundles with Modified LPD Mixing Vane Grids, April 1999. (Methodology for Specification 3.2.2 -

Nuclear Enthalpy Rise Hot Channel Factor).

8. WCAP-14565-P-A, VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis, October 1999. (Methodology for Specification 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

Watts Bar-Unit 2 5.0-33 (developmental) A

Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

LCO 3.4.3 RCS Pressure and Temperature (P/T) Limits

b. The power operated relief valve lift settings required to support the Cold Overpressure Mitigation System (COMS) and the COMS arming temperature shall be established and documented in the PTLR for the following:

LCO 3.4.12 Cold Overpressure Mitigation System

c. The analytical methods used to determine the RCS pressure and temperature limits and Cold Overpressure Mitigation System setpoints shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. WCAP-14040-A, Rev. 4 Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves.

2. The PTLR will contain the complete identification for each of the TS reference Topical Reports used to prepare the PTLR (i.e., report number, title, revision, date, and any supplements).

d. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

(continued)

Watts Bar-Unit 2 5.0-34 (developmental) B

Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.7 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days.

Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4, or existing Regulatory Guide 1.108 reporting requirement.

5.9.8 PAMS Report When a Report is required by Condition B or F of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.9.9 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.7.2.12, Steam Generator (SG) Program. The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism,

f. The number and percentage of tubes plugged or repaired to date, and the effective plugging percentage in each SG,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h. Repair method utilized and the number of tubes repaired by each repair method.

Watts Bar-Unit 2 5.0-35 (developmental) G

Record Retention 5.10 5.0 ADMINISTRATIVE CONTROLS 5.10 Record Retention (removed from Technical Specifications)

Watts Bar-Unit 2 5.0-36 (developmental) A

High Radiation Area 5.11 5.0 ADMINISTRATIVE CONTROLS 5.11 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.11.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area; or

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)

Watts Bar-Unit 2 5.0-37 (developmental) A

High Radiation Area 5.11 High Radiation Area 5.11.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

(continued)

Watts Bar - Unit 2 5.0-38 (developmental) A

High Radiation Area 5.11 High Radiation Area (continued) 5.11.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or, continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the Shift Manager, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)

Watts Bar - Unit 2 5.0-39 (developmental) A

High Radiation Area 5.11 High Radiation Area 5.11.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Watts Bar - Unit 2 5.0-40 (developmental) B

ML13357A053

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