Text

Technical Specifications, Joseph M. Farley Nuclear Plant, Units 1 and 2
	ML051440298
Person / Time
Site:	Farley
Issue date:	05/01/2005
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
	Liu T, NRR, 415-1315
References
	Download: ML051440298 (321)
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Technical Specifications Joseph M. Farley Nuclear Plant Units 1 and 2 Docket Nos. 50-348 and 50-364 Appendix A to License Nos. NPF-2 and NPF-8

Farley Nuclear Plant Units 1 and 2 Page 1 of 2 Technical Specifications List of Effective Pages NOTE: The following amendments (U1/U2) do not affect any TS page: 150/142, 152/144, 154/146, and 158/149.

Amendment No. Amendment No. Amendment No. Amendment No.

Page U-1 U-2 Page U-1 U-2 Page U-1 U-2 Page U-1 U-2 TS 3.3.1-8........... 146 ....137 Appendix "A" Section 3.1 Tab 3.3.1-9........... 146 ....137 Section 3.4 Tab Cover Sheet 3.3.1-10......... 146 ....137 i..................... 146 ... 137 3.1.1-1 ...........146.... 137 3.3.1-11......... 146 ....137 3.4.1-1 ...........151 ... 143 ii.................... 167 ... 159 3.1.2-1 ...........146.... 137 3.3.1-12......... 146 ....137 3.4.1-2 ...........151 ... 143 iii................... 146 ... 137 3.1.2-2 ...........146.... 137 3.3.1-13......... 146 ....137 3.4.2-1 ...........146 ... 137 iv................... 146 ... 137 3.1.3-1 ...........146.... 137 3.3.1-14......... 146 ....137 3.4.3-1 ...........146 ... 137 3.1.3-2 ...........146.... 137 3.3.1-15......... 146 ....137 3.4.3-2 ...........146 ... 137 Section 1.0 Tab 3.1.4-1 ...........146.... 137 3.3.1-16......... 146 ....137 3.4.4-1 ...........146 ... 137 3.1.4-2 ...........146.... 137 3.3.1-17......... 147 ....138 3.4.5-1 ...........146 ... 137 1.1-1.............. 146 ... 137 3.1.4-3 ...........146.... 137 3.3.1-18......... 146 ....137 3.4.5-2 ...........147 ... 138 1.1-2.............. 146 ... 137 3.1.5-1 ...........146.... 137 3.3.1-19......... 146 ....137 3.4.6-1 ...........146 ... 137 1.1-3.............. 149 ... 141 3.1.5-2 ...........146.... 137 3.3.1-20......... 151 ....143 3.4.6-2 ...........147 ... 138 1.1-4.............. 149 ... 141 3.1.6-1 ...........146.... 137 3.3.1-21......... 151 ....143 3.4.7-1 ...........147 ... 138 1.1-5.............. 149 ... 141 3.1.6-2 ...........146.... 137 3.3.2-1........... 146 ....137 3.4.7-2 ...........147 ... 138 1.1-6.............. 149 ... 141 3.1.6-3 ...........146.... 137 3.3.2-2........... 146 ....137 3.4.7-3 ...........146 ... 137 1.1-7.............. 146 ... 137 3.1.7-1 ...........146.... 137 3.3.2-3........... 146 ....137 3.4.8-1 ...........146 ... 137 1.2-1.............. 146 ... 137 3.1.7-2 ...........146.... 137 3.3.2-4........... 146 ....137 3.4.8-2 ...........146 ... 137 1.2-2.............. 146 ... 137 3.1.7-3 ...........146.... 137 3.3.2-5........... 146 ....137 3.4.9-1 ...........146 ... 137 1.2-3.............. 146 ... 137 3.1.7-4 ...........146.... 137 3.3.2-6........... 146 ....137 3.4.9-2 ...........146 ... 137 1.3-1.............. 146 ... 137 3.1.8-1 ...........146.... 137 3.3.2-7........... 146 ....137 3.4.10-1 .........146 ... 137 1.3-2.............. 146 ... 137 3.1.8-2 ...........146.... 137 3.3.2-8........... 146 ....137 3.4.10-2 .........146 ... 137 1.3-3.............. 146 ... 137 3.3.2-9........... 146 ....137 3.4.11-1 .........146 ... 137 1.3-4.............. 146 ... 137 Section 3.2 Tab 3.3.2-10......... 146 ....137 3.4.11-2 .........146 ... 137 1.3-5.............. 146 ... 137 3.3.2-11......... 147 ....138 3.4.11-3 .........146 ... 151 1.3-6.............. 146 ... 137 3.2.1-1 ...........146.... 137 3.3.3-1........... 167 ....159 3.4.11-4 .........146 ... 151 1.3-7.............. 146 ... 137 3.2.1-2 ...........146.... 137 3.3.3-2........... 167 ....159 3.4.12-1 .........146 ... 137 1.3-8.............. 146 ... 137 3.2.1-3 ...........146.... 137 3.3.3-3........... 167 ....159 3.4.12-2 .........146 ... 137 1.3-9.............. 146 ... 137 3.2.1-4 ...........146.... 137 3.3.4-1........... 146 ....137 3.4.12-3 .........146 ... 137 1.3-10............ 146 ... 137 3.2.1-5 ...........146.... 137 3.3.4-2........... 146 ....137 3.4.12-4 .........146 ... 137 1.3-11............ 146 ... 137 3.2.2-1 ...........146.... 137 3.3.4-3........... 146 ....137 3.4.13-1 .........163 ... 156 1.3-12............ 146 ... 137 3.2.2-2 ...........146.... 137 3.3.5-1........... 146 ....137 3.4.13-2 .........163 ... 156 1.3-13............ 146 ... 137 3.2.2-3 ...........146.... 137 3.3.5-2........... 146 ....137 3.4.14-1 .........146 ... 137 1.4-1.............. 146 ... 137 3.2.3-1 ...........146.... 137 3.3.5-3........... 146 ....137 3.4.14-2 .........146 ... 137 1.4-2.............. 146 ... 137 3.2.4-1 ...........146.... 137 3.3.5-4........... 146 ....137 3.4.14-3 .........155 ... 147 1.4-3.............. 146 ... 137 3.2.4-2 ...........146.... 137 3.3.6-1........... 146 ....137 3.4.14-4 .........146 ... 137 1.4-4.............. 146 ... 137 3.2.4-3 ...........146.... 137 3.3.6-2........... 146 ....137 3.4.15-1 .........146 ... 137 3.2.4-4 ...........146.... 137 3.3.6-3........... 146 ....137 3.4.15-2 .........146 ... 137 Section 2.0 Tab 3.3.6-4........... 146 ....137 3.4.15-3 .........146 ... 137 Section 3.3 Tab 3.3.7-1........... 146 ....137 3.4.16-1 .........147 ... 138 2.0-1.............. 151 ... 143 3.3.7-2........... 146 ....137 3.4.16-2 .........147 ... 138 3.3.1-1 ...........146.... 137 3.3.7-3........... 146 ....137 3.4.16-3 .........146 ... 137 Section 3.0 Tab 3.3.1-2 ...........146.... 137 3.3.7-4........... 146 ....137 3.4.16-4 .........147 ... 138 3.3.1-3 ...........146.... 137 3.3.8-1........... 146 ....137 3.4.17-1 .........163 ... 156 3.0-1.............. 146 ... 137 3.3.1-4 ...........146.... 137 3.3.8-2........... 146 ....137 3.4.17-2 .........163 ... 156 3.0-2.............. 146 ... 137 3.3.1-5 ...........146.... 137 3.3.8-3........... 146 ....137 3.0-3.............. 153 ... 145 3.3.1-6 ...........146.... 137 3.3.8-4........... 146 ....137 3.3.1-7 ...........146.... 137 Amendment No. 168 (Unit 1)

Amendment No. 160 (Unit 2)

Farley Nuclear Plant Units 1 and 2 Page 2 of 2 Technical Specifications List of Effective Pages NOTE: The following amendments (U1/U2) do not affect any TS page: 150/142, 152/144, 154/146, and 158/149.

Amendment No. Amendment No. Amendment No. Amendment No.

Page U-1 U-2 Page U-1 U-2 Page U-1 U-2 Page U-1 U-2 Section 3.5 Tab 3.7.2-1 ...........146.... 137 3.8.4-1........... 164 ....137 5.3-1 ..............146 ... 137 3.7.2-2 ...........146.... 137 3.8.4-2........... 146 ....137 5.4-1 ..............146 ... 137 3.5.1-1........... 162 ... 155 3.7.3-1 ...........146.... 137 3.8.4-3........... 146 ....137 5.5-1 ..............160 ... 152 3.5.1-2........... 146 ... 137 3.7.3-2 ...........146.... 137 3.8.4-4........... 146 ....137 5.5-2 ..............156 ... 148 3.5.2-1........... 146 ... 137 3.7.4-1 ...........146.... 137 3.8.5-1........... 146 ....137 5.5-3 ..............146 ... 137 3.5.2-2........... 146 ... 137 3.7.4-2 ...........146.... 137 3.8.5-2........... 146 ....137 5.5-4 ..............146 ... 137 3.5.2-3........... 146 ... 137 3.7.5-1 ...........146.... 137 3.8.6-1........... 146 ....137 5.5-5 ..............163 ... 156 3.5.3-1........... 146 ... 137 3.7.5-2 ...........146.... 137 3.8.6-2........... 146 ....137 5.5-6 ..............163 ... 156 3.5.3-2........... 146 ... 137 3.7.5-3 ...........146.... 137 3.8.6-3........... 146 ....137 5.5-7 ..............163 ... 156 3.5.3-3........... 146 ... 137 3.7.6-1 ...........146.... 137 3.8.6-4........... 146 ....137 5.5-8 ..............166 ... 158 3.5.4-1........... 146 ... 137 3.7.7-1 ...........146.... 137 3.8.7-1........... 146 ....137 5.5-9 ..............166 ... 158 3.5.4-2........... 146 ... 137 3.7.7-2 ...........146.... 137 3.8.7-2........... 146 ....137 5.5-10 ............163 ... 156 3.5.5-1........... 146 ... 137 3.7.8-1 ...........146.... 137 3.8.8-1........... 146 ....137 5.5-11 ............163 ... 156 3.5.5-2........... 146 ... 137 3.7.8-2 ...........146.... 137 3.8.8-2........... 146 ....137 5.5-12 ............163 ... 156 3.5.5-3........... 146 ... 137 3.7.9-1 ...........146.... 137 3.8.9-1........... 146 ....137 5.5-13 ............163 ... 156 3.5.6-1........... 146 ... 137 3.7.10-1 .........166.... 158 3.8.9-2........... 146 ....137 5.5-14 ............166 ... 158 3.7.10-2 .........166.... 158 3.8.10-1......... 146 ....137 5.5-15 ............166 ... 158 Section 3.6 Tab 3.7.10-3 .........166.... 158 3.8.10-2......... 146 ....137 3.7.10-4 .........166.... 158 5.6-1 ..............168 ... 160 3.6.1-1........... 146 ... 137 3.7.11-1 .........146.... 137 Section 3.9 Tab 5.6-2 ..............168 ... 160 3.6.1-2........... 146 ... 137 3.7.11-2 .........146.... 137 5.6-3 ..............151 ... 143 3.6.2-1........... 146 ... 137 3.7.12-1 .........161.... 154 3.9.1-1........... 146 ....137 5.6-4 ..............151 ... 143 3.6.2-2........... 146 ... 137 3.7.12-2 .........161.... 154 3.9.2-1........... 146 ....137 5.6-5 ..............151 ... 143 3.6.2-3........... 146 ... 137 3.7.13-1 .........146.... 137 3.9.2-2........... 146 ....137 5.6-6 ..............163 ... 156 3.6.2-4........... 146 ... 137 3.7.14-1 .........146.... 137 3.9.3-1........... 165 ....157 5.7-1 ..............146 ... 137 3.6.2-5........... 146 ... 137 3.7.15-1 .........146.... 137 3.9.3-2........... 165 ....157 5.7-2 ..............146 ... 137 3.6.3-1........... 146 ... 137 3.7.15-2 .........146.... 137 3.9.4-1........... 146 ....137 3.6.3-2........... 146 ... 137 3.7.16-1 .........146.... 137 3.9.4-2........... 146 ....137 3.6.3-3........... 146 ... 137 3.9.5-1........... 146 ....137 3.6.3-4........... 146 ... 137 Section 3.8 Tab 3.9.5-2........... 146 ....137 3.6.3-5........... 146 ... 137 3.9.5-3........... 146 ....137 3.6.3-6........... 146 ... 137 3.8.1-1 ...........146.... 137 3.9.6-1........... 146 ....137 3.6.4-1........... 146 ... 137 3.8.1-2 ...........146.... 137 3.6.5-1........... 146 ... 137 3.8.1-3 ...........146.... 137 Section 4.0 Tab 3.6.6-1........... 146 ... 137 3.8.1-4 ...........146.... 137 3.6.6-2........... 146 ... 137 3.8.1-5 ...........146.... 137 4.0-1.............. 146 ....137 3.6.6-3........... 146 ... 137 3.8.1-6 ...........146.... 137 4.0-2.............. 146 ....137 3.6.7-1........... 167 ... 159 3.8.1-7 ...........146.... 137 4.0-3.............. 146 ....137 3.8.1-8 ...........146.... 137 4.0-4.............. 146 ....137 3.6.8-1........... 146 ... 137 3.8.1-9 ...........146.... 137 4.0-5.............. 146 ....137 3.6.8-2........... 146 ... 137 3.8.1-10 .........146.... 137 4.0-6.............. 146 ....137 3.6.9-1........... 146 ... 137 3.8.1-11 .........146.... 137 4.0-7.............. 146 ....137 3.8.1-12 .........146.... 137 4.0-8.............. 146 ....137 Section 3.7 Tab 3.8.1-13 .........146.... 137 4.0-9.............. 146 ....137 3.8.1-14 .........146.... 137 3.7.1-1........... 146 ... 137 3.8.2-1 ...........146.... 137 Section 5.0 Tab 3.7.1-2........... 146 ... 137 3.8.2-2 ...........146.... 137 3.7.1-3........... 146 ... 137 3.8.2-3 ...........146.... 137 5.1-1.............. 146 ....137 3.7.1-4........... 146 ... 137 3.8.3-1 ...........146.... 137 5.2-1.............. 146 ....137 3.8.3-2 ...........146.... 137 5.2-2.............. 146 ....137 3.8.3-3 ...........146.... 137 5.2-3.............. 146 ....137 Amendment No. 168 (Unit 1)

Amendment No. 160 (Unit 2)

TABLE OF CONTENTS 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 ............................. 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS ..................................................... 3.1.1-1 3.1.1 SHUTDOWN MARGIN (SDM)........................................................ 3.1.1-1 3.1.2 Core Reactivity............................................................................... 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC)..................................... 3.1.3-1 3.1.4 Rod Group Alignment Limits .......................................................... 3.1.4-1 3.1.5 Shutdown Bank Insertion Limits ..................................................... 3.1.5-1 3.1.6 Control Bank Insertion Limits ......................................................... 3.1.6-1 3.1.7 Rod Position Indication................................................................... 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions MODE 2 ..................................... 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS........................................................... 3.2.1-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ............................................ 3.2.1-1 N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FH )........................... 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD) ................................................ 3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR) ................................... 3.2.4-1 3.3 INSTRUMENTATION ............................................................................ 3.3.1-1 3.3.1 Reactor Trip System (RTS) Instrumentation................................... 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ........................................................................ 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation ........................... 3.3.3-1 3.3.4 Remote Shutdown System ............................................................. 3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ........................................................................ 3.3.5-1 3.3.6 Containment Purge and Exhaust Isolation Instrumentation ........................................................................ 3.3.6-1 3.3.7 Control Room Emergency Filtration/Pressurization System (CREFS) Actuation Instrumentation ......................................... 3.3.7-1 3.3.8 Penetration Room Filtration (PRF) System Actuation Instrumentation ........................................................................ 3.3.8-1 Farley Units 1 and 2 i Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

TABLE OF CONTENTS 3.4 REACTOR COOLANT SYSTEM (RCS) .................................................. 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................................................... 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality ....................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits .................................. 3.4.3-1 3.4.4 RCS Loops MODES 1 and 2 ....................................................... 3.4.4-1 3.4.5 RCS Loops MODE 3.................................................................... 3.4.5-1 3.4.6 RCS Loops MODE 4.................................................................... 3.4.6-1 3.4.7 RCS Loops MODE 5, Loops Filled .............................................. 3.4.7-1 3.4.8 RCS Loops MODE 5, Loops Not Filled........................................ 3.4.8-1 3.4.9 Pressurizer....................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves................................................................ 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ...................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ........... 3.4.12-1 3.4.13 RCS Operational LEAKAGE............................................................ 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................. 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ........................................ 3.4.15-1 3.4.16 RCS Specific Activity ....................................................................... 3.4.16-1 3.4.17 Steam Generator (SG) Tube Integrity.............................................. 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ............................. 3.5.1-1 3.5.1 Accumulators ................................................................................... 3.5.1-1 3.5.2 ECCS Operating .......................................................................... 3.5.2-1 3.5.3 ECCS Shutdown .......................................................................... 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) .......................................... 3.5.4-1 3.5.5 Seal Injection Flow........................................................................... 3.5.5-1 3.5.6 ECCS Recirculation Fluid pH Control System ................................. 3.5.6-1 3.6 CONTAINMENT SYSTEMS .................................................................... 3.6.1-1 3.6.1 Containment .................................................................................... 3.6.1-1 3.6.2 Containment Air Locks..................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves .......................................................... 3.6.3-1 3.6.4 Containment Pressure ..................................................................... 3.6.4-1 3.6.5 Containment Air Temperature ......................................................... 3.6.5-1 3.6.6 Containment Spray and Cooling Systems ....................................... 3.6.6-1 3.6.7 Deleted ...........................................................................................3.6.7-1 3.6.8 Hydrogen Mixing System (HMS)...................................................... 3.6.8-1 3.6.9 Reactor Cavity Hydrogen Dilution System....................................... 3.6.9-1 3.7 PLANT SYSTEMS ................................................................................... 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) ............................................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ............................................. 3.7.2-1 Farley Units 1 and 2 ii Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2)

TABLE OF CONTENTS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves................................................. 3.7.3-1 3.7.4 Atmospheric Relief Valves (ARVs) ................................................. 3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System................................................ 3.7.5-1 3.7.6 Condensate Storage Tank (CST) ................................................... 3.7.6-1 3.7.7 Component Cooling Water (CCW) System .................................... 3.7.7-1 3.7.8 Service Water System (SWS) ........................................................ 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)............................................................... 3.7.9-1 3.7.10 Control Room Emergency Filtration/Pressurization System (CREFS)...................................................................... 3.7.10-1 3.7.11 Control Room Air Conditioning System (CRACS)........................... 3.7.11-1 3.7.12 Penetration Room Filtration (PRF) System..................................... 3.7.12-1 3.7.13 Fuel Storage Pool Water Level ...................................................... 3.7.13-1 3.7.14 Fuel Storage Pool Boron Concentration ......................................... 3.7.14-1 3.7.15 Spent Fuel Assembly Storage ........................................................ 3.7.15-1 3.7.16 Secondary Specific Activity ............................................................ 3.7.16-1 3.8 ELECTRICAL POWER SYSTEMS ........................................................ 3.8.1-1 3.8.1 AC Sources Operating ............................................................... 3.8.1-1 3.8.2 AC Sources Shutdown ............................................................... 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ...................................... 3.8.3-1 3.8.4 DC Sources Operating ............................................................... 3.8.4-1 3.8.5 DC Sources Shutdown ............................................................... 3.8.5-1 3.8.6 Battery Cell Parameters ................................................................. 3.8.6-1 3.8.7 Inverters Operating..................................................................... 3.8.7-1 3.8.8 Inverters Shutdown .................................................................... 3.8.8-1 3.8.9 Distribution Systems Operating .................................................. 3.8.9-1 3.8.10 Distribution Systems Shutdown .................................................. 3.8.10-1 3.9 REFUELING OPERATIONS .................................................................. 3.9.1-1 3.9.1 Boron Concentration ...................................................................... 3.9.1-1 3.9.2 Nuclear Instrumentation ................................................................. 3.9.2-1 3.9.3 Containment Penetrations.............................................................. 3.9.3-1 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation High Water Level ................................................ 3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation Low Water Level ................................................. 3.9.5-1 3.9.6 Refueling Cavity Water Level ......................................................... 3.9.6-1 4.0 DESIGN FEATURES..................................................................................... 4.0-1 4.1 Site Location ......................................................................................... 4.0-1 4.2 Reactor Core ......................................................................................... 4.0-1 Farley Units 1 and 2 iii Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

TABLE OF CONTENTS 4.3 Fuel Storage .......................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS.................................................................... 5.1-1 5.1 Responsibility......................................................................................... 5.1-1 5.2 Organization .......................................................................................... 5.2-1 5.3 Unit Staff Qualifications.......................................................................... 5.3-1 5.4 Procedures ............................................................................................ 5.4-1 5.5 Programs and Manuals .......................................................................... 5.5-1 5.6 Reporting Requirements ........................................................................ 5.6-1 5.7 High Radiation Area............................................................................... 5.7-1 Farley Units 1 and 2 iv Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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, 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.

Farley Units 1 and 2 1.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Definitions 1.1 1.1 Definitions 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, 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 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 current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Unit 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.

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.

Farley Units 1 and 2 1.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Definitions 1.1 1.1 Definitions 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.

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 (SG) to the Secondary System;

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

Farley Units 1 and 2 1.1-3 Amendment No. 149 (Unit 1)

Amendment No. 141 (Unit 2)

Definitions 1.1 1.1 Definitions LEAKAGE c. Pressure Boundary LEAKAGE (continued)

LEAKAGE (except SG 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.

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).

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 Tests and Operation, of the FSAR;

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

c. Otherwise approved by the Nuclear Regulatory Commission.

Farley Units 1 and 2 1.1-4 Amendment No. 149 (Unit 1)

Amendment No. 141 (Unit 2)

Definitions 1.1 1.1 Definitions PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) 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 5.6.6. Plant operation within these operating limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits."

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 2775 MWt.

REACTOR TRIP The RTS RESPONSE TIME shall be that time interval from SYSTEM (RTS) RESPONSE when the monitored parameter exceeds its RTS trip setpoint TIME 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 (continued)

Farley Units 1 and 2 1.1-5 Amendment No. 149 (Unit 1)

Amendment No. 141 (Unit 2)

Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM)

(continued) b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the hot zero power temperatures.

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.

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) 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.

Farley Units 1 and 2 1.1-6 Amendment No. 149 (Unit 1)

Amendment No. 141 (Unit 2)

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

MODES MODE TITLE REACTIVITY % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT (keff) POWER(a) TEMPERATURE

(°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.

Farley Units 1 and 2 1.1-7 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

Farley Units 1 and 2 1.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-1 (continued)

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)

Farley Units 1 and 2 1.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

Farley Units 1 and 2 1.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

However, when a subsequent train, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within (continued)

Farley Units 1 and 2 1.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Completion Times 1.3 1.3 Completion Times DESCRIPTION limits, the Completion Time(s) may be extended. To apply this (continued) 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.

Farley Units 1 and 2 1.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Completion Times 1.3 1.3 Completion Times 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)

Farley Units 1 and 2 1.3-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 also 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.

(continued)

Farley Units 1 and 2 1.3-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

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.

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)

Farley Units 1 and 2 1.3-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X train train to OPERABLE AND inoperable. status.

10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y train train to OPERABLE AND inoperable. status.

10 days from discovery of failure to meet the LCO C. One C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X Function X train train to OPERABLE inoperable. status.

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

(continued)

Farley Units 1 and 2 1.3-6 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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)

Farley Units 1 and 2 1.3-7 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable. 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 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)

Farley Units 1 and 2 1.3-8 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 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 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.

(continued)

Farley Units 1 and 2 1.3-9 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

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.

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 Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. SR 3.x.x.x.

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

(continued)

Farley Units 1 and 2 1.3-10 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

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)

Farley Units 1 and 2 1.3-11 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem inoperable. 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to 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 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 (continued)

Farley Units 1 and 2 1.3-12 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

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.

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

Farley Units 1 and 2 1.3-13 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

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.

(continued)

Farley Units 1 and 2 1.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

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 stated 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)

Farley Units 1 and 2 1.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 25% 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)

Farley Units 1 and 2 1.4-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 (plus the extension allowed by SR 3.0.2) interval, 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.

Farley Units 1 and 2 1.4-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2, the departure from nucleate boiling ratio (DNBR) shall be maintained within the 95/95 DNB criterion correlation specified in the COLR.

2.1.1.2 In MODES 1 and 2, the peak fuel centerline temperature shall be Maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU.

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.

Farley Units 1 and 2 2.0-1 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

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 and 3.0.7.

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 not be made except 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.

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

Exceptions to this Specification are stated in the individual specifications.

Farley Units 1 and 2 3.0-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LCO Applicability 3.0 3.0 LCO APPLICABILITY 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, an evaluation shall be performed in accordance with specification 5.5.15, "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.

LCO 3.0.7 Test Exception LCO 3.1.8 allows 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.

Farley Units 1 and 2 3.0-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LCO 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.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS.

Farley Units 1 and 2 3.0-3 Amendment No. 153 (Unit 1)

Amendment No. 145 (Unit 2)

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be within the limits provided in the COLR.

APPLICABILITY: MODE 2 with keff < 1.0, MODES 3, 4, and 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Farley Units 1 & 2 3.1.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Core Reactivity 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 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 and 7 days not within limit. safety analysis, and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days 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.

Farley Units 1 and 2 3.1.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------------------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 each refueling AND

NOTE--------

Only required after 60 EFPD 31 EFPD thereafter Farley Units 1 and 2 3.1.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the beginning of cycle life (BOL) limit and the end of cycle life (EOL) limit specified in the COLR. The maximum upper limit shall be 0.7 x 10-4 k/k/°F for power levels up to 70%

THERMAL POWER with a linear ramp to 0 k/k/°F at 100% THERMAL POWER.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within BOL 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 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.

C. MTC not within EOL limit. C.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Farley Units 1 and 2 3.1.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within BOL limit. Once prior to entering MODE 1 after each refueling SR 3.1.3.2 ----------------------------NOTES--------------------------------

1. 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.

2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of 100 ppm is less negative than the 100 ppm Surveillance limit specified in the COLR.

Verify MTC is within EOL limit. Once each cycle Farley Units 1 and 2 3.1.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 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 to be within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months untrippable. the limits provided in the COLR.

OR A.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore 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 to be within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the limits provided in the COLR.

OR (continued)

Farley Units 1 and 2 3.1.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore SDM to within limit.

AND 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 to be within Once per the limits provided in the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months COLR.

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.

Farley Units 1 and 2 3.1.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. More than one rod not D.1.1 Verify SDM to be within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within alignment limit. the limits provided in the COLR.

OR D.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore 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 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment limit. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.1.4.2 Verify rod freedom of movement (trippability) by 92 days moving each rod not fully inserted in the core 10 steps in either direction.

SR 3.1.4.3 Verify rod drop time of each rod, from the fully Prior to reactor withdrawn position, is 2.7 seconds from the criticality after beginning of decay of stationary gripper coil voltage each removal of to dashpot entry, with: the reactor head

a. Tavg 541°F; and

b. All reactor coolant pumps operating.

Farley Units 1 and 2 3.1.4-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 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 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.1.1 Verify SDM to be within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months banks not within limits. the limits provided in the COLR.

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

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

Farley Units 1 and 2 3.1.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Shutdown Bank Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 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.

Farley Units 1 and 2 3.1.5-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 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 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.1.1 Verify SDM to be within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits not met. the limits provided in the COLR.

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

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

Farley Units 1 and 2 3.1.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Control Bank Insertion Limits 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence or B.1.1 Verify SDM to be within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months overlap limits not met. the limits provided in the COLR.

OR B.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore 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 3.1.6.1 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 the limits specified in the COLR. prior to achieving criticality Farley Units 1 and 2 3.1.6-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.2 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.

SR 3.1.6.3 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.

Farley Units 1 and 2 3.1.6-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Digital Rod Position Indication (DRPI) 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 digital rod position indicator and each demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One DRPI per group 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 inoperable for one or more rods with inoperable groups. DRPIs indirectly by using movable incore detectors.

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. More than one DRPI per B.1 Place the control rods Immediately group inoperable. under manual control.

AND B.2 Monitor and Record Once per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RCS Tavg.

AND (continued)

Farley Units 1 and 2 3.1.7-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Verify the position of the Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rods with inoperable position indicators indirectly using the movable incore detectors.

AND B.4 Restore the inoperable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable.

C. One or more rods with C.1.1 Initiate action to verify Immediately inoperable DRPIs have the position of the rods been moved in excess of with inoperable DRPIs 24 steps in one direction indirectly by using since the last determination movable incore of the rod's position. detectors.

AND (continued)

Farley Units 1 and 2 3.1.7-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.1.2 Complete rod position 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months verification started in Required Action C.1.1.

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

D. One demand position D.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 DRPIs for the inoperable for one or more affected banks are banks. OPERABLE.

AND D.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 12 steps apart.

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

E. 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.

Farley Units 1 and 2 3.1.7-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each DRPI agrees within 12 steps of the group Once prior to demand position for the full indicated range of rod criticality after each travel. removal of the reactor head.

Farley Units 1 and 2 3.1.7-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

PHYSICS TESTS Exceptions MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";

LCO 3.1.4, "Rod Group Alignment Limits";

LCO 3.1.5, "Shutdown Bank Insertion Limits";

LCO 3.1.6, "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended, provided:

a. THERMAL POWER is 5% RTP;

b. SDM is within the limits provided in the COLR; and

c. RCS lowest loop average temperature is 531°F.

APPLICABILITY: MODE 2 during PHYSICS TESTS.

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

Farley Units 1 and 2 3.1.8-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

PHYSICS TESTS Exceptions MODE 2 3.1.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. RCS lowest loop average C.1 Restore RCS lowest 15 minutes temperature not within loop average limit. 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 3.1.8.1 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 3.1.8.2 Verify the RCS lowest loop average temperature is 30 minutes 531°F.

SR 3.1.8.3 Verify THERMAL POWER is 5% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.1.8.4 Verify SDM to be within the limits provided in the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

Farley Units 1 and 2 3.1.8-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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) shall be within the steady state and transient limits specified in the COLR.

APPLICABILITY: MODE 1.

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

AND A.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux High trip setpoints 1% for each 1% FQ(Z) exceeds steady state 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% FQ(Z) exceeds steady state limit.

AND (continued)

Farley Units 1 and 2 3.2.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

FQ(Z) 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Perform SR 3.2.1.1. Prior to increasing THERMAL POWER above the limit of Required Action A.1 B. FQ(Z) not within transient B.1 Reduce AFD limits 1% 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits. for each 1% FQ(Z) exceeds transient limit and control AFD within reduced limits.

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.

Farley Units 1 and 2 3.2.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 FQ(Z) is within steady state limit. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once after achieving equilibrium conditions after exceeding, by 20% RTP, the THERMAL POWER at which FQ(Z) was last verified AND 31 EFPD thereafter Farley Units 1 and 2 3.2.1-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 -------------------------------NOTE-------------------------------

If measurements indicate FQ(Z) maximum over K(Z) has increased since the previous evaluation of FQ(Z):

a. Increase FQ(Z) by the appropriate penalty factor specified in the COLR and reverify that this value is within the transient limits; or

b. Repeat SR 3.2.1.2 once per 7 EFPD until either "a." above is met or two successive flux maps indicate FQ(Z) maximum over K(Z) has not increased.

Verify FQ(Z) is within the transient limit. Once after each refueling prior to THERMAL POWER exceeding 75%

RTP AND (continued)

Farley Units 1 and 2 3.2.1-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued) Once after achieving equilibrium conditions after exceeding, by 20% RTP, the THERMAL POWER at which FQ(Z) was last verified AND 31 EFPD thereafter Farley Units 1 and 2 3.2.1-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

N FH 3.2.2 3.2 POWER DISTRIBUTION LIMITS N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FH )

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

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME N

A. -------------NOTE-------------- A.1.1 Restore FH to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Actions A.2 limit.

and A.3 must be completed whenever OR Condition A is 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux High 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)

Farley Units 1 and 2 3.2.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

N FH 3.2.2 SURVEILLANCE REQUIREMENTS 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.

Farley Units 1 and 2 3.2.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

N FH 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY N

SR 3.2.2.1 Verify FH is within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter Farley Units 1 and 2 3.2.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

Farley Units 1 and 2 3.2.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Limit THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each POWER to 3% below QPTR determination RTP for each 1% of QPTR > 1.00.

AND A.2 Determine QPTR. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 after SR 3.2.2.1. achieving equilibrium conditions with THERMAL POWER limited by Required Action A.1 AND Once per 7 days thereafter AND (continued)

Farley Units 1 and 2 3.2.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 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 A.5 ----------NOTES-----------

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

2. Required Action A.6 shall be completed if Required Action A.5 is performed.

Normalize excore Prior to increasing detectors to restore THERMAL POWER QPTR to within limits. above the limit of Required Action A.1 AND (continued)

Farley Units 1 and 2 3.2.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.6 -----------NOTE------------

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

Perform SR 3.2.1.1 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after SR 3.2.2.1. achieving equilibrium conditions at 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.

Farley Units 1 and 2 3.2.4-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

1. 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.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by calculation.

7 days SR 3.2.4.2 ------------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER

> 75% RTP.

Confirm that the normalized symmetric power 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months distribution is consistent with QPTR.

Farley Units 1 and 2 3.2.4-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 A.1 Enter the Condition Immediately with 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 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months Farley Units 1 and 2 3.3.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 ACTIONS 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 channel inoperable. The inoperable channel 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 and setpoint adjustment of other channels.

D.1.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.1.2 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months POWER to 75% RTP.

OR D.2.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND (continued)

Farley Units 1 and 2 3.3.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.2.2 -----------NOTE------------

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

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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. One channel inoperable. ------------------NOTE------------------

The inoperable channel 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 of other channels.

E.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR E.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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.

Farley Units 1 and 2 3.3.1-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 to Range Neutron Flux > P-6 channels inoperable.

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

J. Two Source Range J.1 Open RTBs. Immediately Neutron Flux channels inoperable.

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

inoperable.

OR K.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months Farley Units 1 and 2 3.3.1-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 M. One channel inoperable. -----------------NOTE-------------------

The inoperable channel 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 of other channels.

M.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR M.2 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months POWER to < P-7.

Farley Units 1 and 2 3.3.1-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME N. One Reactor Coolant N.1 Restore channel to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Pump Breaker Position OPERABLE status.

channel inoperable.

OR N.2 Reduce THERMAL 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months POWER to < P-8.

O. One Low Auto Stop Oil ------------------NOTE------------------

Pressure channel The inoperable channel may be inoperable. bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

O.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR O.2 Reduce THERMAL 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months POWER to < P-9.

P. One, two, or three Turbine P.1 Place channel(s) in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Throttle Valve Closure channel(s) inoperable. OR P.2 Reduce THERMAL 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months POWER to < P-9.

Farley Units 1 and 2 3.3.1-6 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Q. 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.

Q.1 Restore train to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

OR Q.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months R. One RTB train inoperable. ----------------NOTE-------------------

One train may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided the other train is OPERABLE.

R.1 Restore train to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

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 or more channels S.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 conditions.

OR S.2 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ACTIONS Farley Units 1 and 2 3.3.1-7 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME T. One or more channels T.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 conditions.

OR T.2 Be in MODE 2. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months U. One trip mechanism ----------------NOTE-------------------

inoperable for one RTB. One RTB may be bypassed for maintenance on an undervoltage or shunt trip mechanism, provided the other RTB train is OPERABLE.

U.1 Restore inoperable trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months mechanism to OPERABLE status.

OR U.2 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months V. Two RTS trains inoperable. V.1 Enter LCO 3.0.3. Immediately Farley Units 1 and 2 3.3.1-8 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 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 ----------------------------NOTE--------------------------------

Not required to be performed for source range instrumentation until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is < P-6.

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 calorimetric calculated power exceeds NIS indicated power by more than +2% RTP.

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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.

SR 3.3.1.3 ----------------------------NOTES------------------------------

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

2. Not required to be performed until 7 days after THERMAL POWER is 50% RTP.

3. Performance of SR 3.3.1.9 satisfies this SR.

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

Farley Units 1 and 2 3.3.1-9 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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. 31 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.1.6 Perform TADOT. 92 days SR 3.3.1.7 ----------------------------NOTE------------------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

Perform COT. 92 days Farley Units 1 and 2 3.3.1-10 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.8 -----------------------------NOTE---------------------------------

This Surveillance shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT. --------NOTE--------

Only required when not performed within previous 92 days Prior to reactor startup AND Four hours after reducing power below P-10 for power range and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 92 days thereafter Farley Units 1 and 2 3.3.1-11 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.9 ----------------------------NOTES------------------------------

1. Neutron detectors are excluded from the calibration.

2. Not required to be performed until 7 days after THERMAL POWER is 50% RTP.

Calibrate excore channels to agree with incore 18 months detector measurements.

SR 3.3.1.10 ------------------------------NOTES------------------------------

1. Neutron detectors are excluded from CHANNEL CALIBRATION.

2. 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 Perform COT. 18 months AND

NOTE------

Only required when not performed within previous 92 days.

Prior to reactor startup Farley Units 1 and 2 3.3.1-12 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.12 ----------------------------NOTE--------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.1.13 ----------------------------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 3.3.1.14 ------------------------------NOTE--------------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits. 18 months on a STAGGERED TEST BASIS Farley Units 1 and 2 3.3.1-13 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 8)

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

1. Manual Reactor 1,2 2 B SR 3.3.1.12 NA NA Trip 3 (a) , 4 (a) , 5 (a) 2 C SR 3.3.1.12 NA NA

2. Power Range Neutron Flux

a. High 1,2 4 D SR 3.3.1.1 109.4% RTP 109%

SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.14

b. Low 1(b),2 4 E SR 3.3.1.1 25.4% RTP 25% RTP SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.14

3. Power Range Neutron Flux Rate

a. High Positive 1,2 4 D SR 3.3.1.7 5.4% RTP 5% RTP Rate SR 3.3.1.10 with time with time constant constant 2 sec 2 sec

b. High Negative 1,2 4 D SR 3.3.1.7 5.4% RTP 5% RTP Rate SR 3.3.1.10 with time with time constant constant 2 sec 2 sec

4. Intermediate 1(b), 2(c) 2 F,G SR 3.3.1.1 40% RTP 35% RTP Range Neutron SR 3.3.1.8 Flux SR 3.3.1.10 2(d) 2 H SR 3.3.1.1 40% RTP 35% RTP SR 3.3.1.8 SR 3.3.1.10 (a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

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

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

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

Farley Units 1 and 2 3.3.1-14 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 8)

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

5. Source Range 2(d)

Neutron Flux 2 I,J SR 3.3.1.1 1.3 E5 cps 1.0 E5 cps SR 3.3.1.8 SR 3.3.1.10 3(a), 4(a), 5(a) 2 J,K SR 3.3.1.1 1.3 E5 cps 1.0 E5 cps SR 3.3.1.7 SR 3.3.1.10 3(e), 4(e),5(e) 1 L SR 3.3.1.1 N/A N/A SR 3.3.1.10

6. Overtemperature 1,2 3 E SR 3.3.1.1 Refer to Refer to T SR 3.3.1.3 Note 1 (Page Note 1 (Page SR 3.3.1.7 3.3.1-20) 3.3.1-20)

SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.14

7. Overpower T 1,2 3 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.7 Note 2 (Page Note 2 (Page SR 3.3.1.10 3.3.1-21) 3.3.1-21)

SR 3.3.1.14 (a) With RTBs closed and Rod Control System capable of rod withdrawal.

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

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

Farley Units 1 and 2 3.3.1-15 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 8)

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

8. Pressurizer Pressure

a. Low 1 (f) 3 M SR 3.3.1.1 1862 psig 1865 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.14

b. High 1,2 3 E SR 3.3.1.1 2388 psig 2385 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.14

9. Pressurizer Water 1 (f) 3 M SR 3.3.1.1 92.4% 92%

Level High SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant 1(f) 3 per loop M SR 3.3.1.1 89.7% 90%

Flow Low SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.14 (f) Above the P-7 (Low Power Reactor Trips Block) interlock.

Farley Units 1 and 2 3.3.1-16 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 8)

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

11. Reactor Coolant Pump (RCP)

Breaker Position

a. Single Loop 1(g) 1 per RCP N SR 3.3.1.12 NA NA

b. Two Loops 1(h) 1 per RCP M SR 3.3.1.12 NA NA 1(f)

12. Undervoltage 3 M SR 3.3.1.6 2640 V 2680 V RCPs SR 3.3.1.10 1(f)

13. Underfrequency 3 M SR 3.3.1.6 56.9 Hz 57 Hz RCPs SR 3.3.1.10

14. Steam 1,2 3 per SG E SR 3.3.1.1 27.6% 28%

Generator (SG) SR 3.3.1.7 Water Level SR 3.3.1.10 Low Low SR 3.3.1.14 (f) Above the P-7 (Low Power Reactor Trips Block) interlock.

(g) Above the P-8 (Power Range Neutron Flux) interlock.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) i n t er lock.

Farley Units 1 and 2 3.3.1-17 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 8)

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

15. Turbine Trip

a. Low Auto Stop 1 (i) 3 O SR 3.3.1.10 43 psig 45 psig Oil Pressure SR 3.3.1.13

b. Turbine Throttle 1 (i) 4 P SR 3.3.1.10 NA NA Valve Closure SR 3.3.1.13

16. Safety Injection (SI) 1,2 2 trains Q SR 3.3.1.12 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)

17. Reactor Trip System Interlocks

a. Intermediate 2 (d) 2 S SR 3.3.1.10 6E-11 amp 1E-10 Range Neutron SR 3.3.1.11 amp Flux, P-6

b. Low Power 1 1 per train T NA NA NA Reactor Trips Block, P-7

c. Power Range 1 4 T SR 3.3.1.10 30.4% RTP 30% RTP Neutron Flux, SR 3.3.1.11 P-8

d. Power Range 1 4 T SR 3.3.1.10 50.4% RTP 50% RTP Neutron Flux, SR 3.3.1.11 P-9

e. Power Range 1,2 4 S SR 3.3.1.10 7.6% RTP 8% RTP Neutron Flux, SR 3.3.1.11 and and P-10 10.4% RTP 10% RTP

f. Turbine Impulse 1 2 T SR 3.3.1.1 11% 10%

Pressure, P-13 SR 3.3.1.10 turbine turbine SR 3.3.1.11 power power (d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

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

Farley Units 1 and 2 3.3.1-18 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 8)

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

18. Reactor Trip 1,2 2 trains R, V SR 3.3.1.4 NA NA Breakers (j) 3 (a) , 4 (a) , 5 (a) 2 trains C, V SR 3.3.1.4 NA NA

19. Reactor Trip 1,2 1 each per U SR 3.3.1.4 NA NA Breaker RTB Undervoltage and 3 (a) , 4 (a) , 5 (a) C SR 3.3.1.4 NA NA Shunt Trip 1 each per Mechanisms RTB

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

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

Farley Units 1 and 2 3.3.1-19 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 8)

Reactor Trip System Instrumentation Note 1: Overtemperature T The Overtemperature T Function Allowable Value shall not exceed the following Trip Setpoint by more than 0.4% of T span.

(1 + 4s ) (1 + 1s ) 1 T TO K1 - K 2 T - T + K 3 (P - P ) - f 1 ( I)

(1 + 5s ) (1 + 2s ) (1 + 6s )

Where: T is measured loop T, °F.

T0 is the indicated loop T at RTP and reference Tavg, °F.

s is the Laplace transform operator, sec-1.

T is the measured loop average temperature, °F.

T' is the reference Tavg at RTP, * °F.

P is the measured pressurizer pressure, psig.

P' is the nominal pressurizer operating pressure =

psig.

K1 =

K2 = */°F K3 = */psi 1

sec 2

sec 4 =

sec 5

sec 6

sec f1(I) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

f1(I) = *{* + (qt - qb)} when (qt - qb) * % RTP

% of RTP when *% RTP < (qt - qb) *% RTP

{(qt - qb) - *} when (qt - qb)> *% 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.

as specified in the COLR Farley Units 1 and 2 3.3.1-20 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 8 of 8)

Reactor Trip System Instrumentation Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following Trip Setpoint by more than 0.4% of T span.

T (1 + 4s )

TO K 4 - K5 3s 1 T - K T 1 - T" - f ( I) 6 2 (1 + 5s ) 1 + 3s 1 + 6s 1 + 6s Where: T is measured loop T, °F.

T0 is the indicated loop T at RTP and reference Tavg, °F.

s is the Laplace transform operator, sec-1.

T is the measured loop average temperature, °F.

T is the reference Tavg at RTP, * °F.

K4 =

K5 = */°F for increasing Tavg K6 = */°F when T > T

K5 = */°F for decreasing Tavg K6 = */°F when T T

3

sec 4 =

sec 5

sec 6

sec f2(I) = *% RTP for all I.

as specified in the COLR Farley Units 1 and 2 3.3.1-21 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

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 A.1 Enter the Condition Immediately with 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 Farley Units 1 and 2 3.3.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 ACTIONS 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

OR C.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND C.2.2 Be in MODE 5. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months D. One channel inoperable. D.1 -------------NOTE-----------

The inoperable channel 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 of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months Farley Units 1 and 2 3.3.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment E.1 -----------NOTE-------------

Pressure channel One additional channel inoperable. 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.

Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months bypass.

OR E.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND E.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 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 Farley Units 1 and 2 3.3.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 ACTIONS 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

OR G.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND G.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

OR H.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Farley Units 1 and 2 3.3.2-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I. One channel inoperable. I.1 -----------NOTE-------------

The inoperable channel 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 of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR I.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months J. One or more Main J.1 Restore channel(s) to Prior to next required Feedwater Pump trip OPERABLE status. TADOT channels inoperable on one or more Main Feedwater Pumps.

K. Two channels inoperable. K.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 condition.

OR K.2.1 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND K.2.2 Be in MODE 4. 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months L. One train inoperable. L.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 condition.

OR (continued)

Farley Units 1 and 2 3.3.2-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 CONDITION REQUIRED ACTION COMPLETION TIME L. (continued) L.2 ------------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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

OR L.3.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND L.3.2 Be in MODE 5 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months 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. 31 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.2.4 Perform COT. 92 days SR 3.3.2.5 Perform TADOT. 92 days Farley Units 1 and 2 3.3.2-6 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.6 -------------------------------NOTE-------------------------------

Verification of setpoint not required.

Perform TADOT. 18 months SR 3.3.2.7 -------------------------------NOTE-------------------------------

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

Perform CHANNEL CALIBRATION. 18 months SR 3.3.2.8 Perform SLAVE RELAY TEST 18 months SR 3.3.2.9 -------------------------------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 SG pressure is 1005 psig.

Verify ESFAS RESPONSE TIMES are within limit. 18 months on a STAGGERED TEST BASIS SR 3.3.2.10 -------------------------------NOTE------------------------------- ------------NOTE----------

Verification of setpoint not required. Only required when not

performed within previous 92 days.

Perform TADOT. Prior to reactor startup Farley Units 1 and 2 3.3.2-7 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER 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 3.3.2.6 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 3.3.2.8 Relays

c. Containment 1,2,3 3 D SR 3.3.2.1 4.5 psig 4.0 psig Pressure SR 3.3.2.4 High 1 SR 3.3.2.7 SR 3.3.2.9

d. Pressurizer 1,2,3(a) 3 D SR 3.3.2.1 1847 psig 1850 psig Pressure Low SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9

e. Steam Line Pressure (1) Low 1,2,3(b) 1 per steam D SR 3.3.2.1 575(c) psig 585(c) psig line SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9 (2) High 1,2,3 3 per steam D SR 3.3.2.1 112 psig 100 psig Differential line SR 3.3.2.4 Pressure SR 3.3.2.7 Between SR 3.3.2.9 Steam Lines (a) Above the P-11 (Pressurizer Pressure) interlock.

(b) Above the P-12 (Tavg - Low Low) interlock.

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

Farley Units 1 and 2 3.3.2-8 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 4)

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

2. Containment Spray

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.6 NA NA

b. Automatic Actuation 1,2,3,4 2 trains C SR 3.3.2.2 NA NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.8

c. Containment 1,2,3 4 E SR 3.3.2.1 28.3 psig 27 psig Pressure SR 3.3.2.4 High - 3 SR 3.3.2.7 SR 3.3.2.9

3. Containment Isolation

a. Phase A Isolation (1) Manual 1,2,3,4 2 B SR 3.3.2.6 NA NA Initiation (2) 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 3.3.2.8 Relays (3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

b. Phase B Isolation (1) Manual 1,2,3,4 2 B SR 3.3.2.6 NA NA Initiation (2) 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 3.3.2.8 Relays (3) Containment 1,2,3 4 E SR 3.3.2.1 28.3 psig 27 psig Pressure SR 3.3.2.4 High - 3 SR 3.3.2.7 SR 3.3.2.9 Farley Units 1 and 2 3.3.2-9 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 4)

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

4. Steam Line Isolation

a. Manual 1 per steam Initiation 1,2(d),3(d) line F SR 3.3.2.6 NA NA

b. Automatic 1,2(d),3(d) 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.8 Relays

c. Containment 1,2(d), 3(d) 3 D SR 3.3.2.1 17.5 psig 16.2 psig Pressure - High SR 3.3.2.4 2 SR 3.3.2.7 SR 3.3.2.9

d. Steam Line 1,2(d),3(b)(d) 1 per steam D SR 3.3.2.1 575(c) psig 585(c) psig Pressure Low line SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9

e. High Steam 1,2(d),3(d) 2 per steam D SR 3.3.2.1 (e) (f)

Flow line SR 3.3.2.4 in Two Steam SR 3.3.2.7 Lines Coincident with 1,2(d),3(d) 1 per loop D SR 3.3.2.1 542.6°F 543°F Tavg - Low Low SR 3.3.2.4 SR 3.3.2.7 (b) Above the P-12 (Tavg - Low Low) interlock.

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

(d) Except when one MSIV is closed in each steam line.

(e) Less than or equal to a function defined as P corresponding to 40.3% full steam flow below 20% load, P increasing linearly from 40.3% full steam flow at 20% load to 110.3% full steam flow at 100% load.

(f) Less than or equal to a function defined as P corresponding to 40% full steam flow between 0% and 20% load and then a P increasing linearly from 40% steam flow at 20% load to 110% full steam flow at 100% load.

Farley Units 1 and 2 3.3.2-10 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

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

5. Turbine Trip and Feedwater Isolation 1,2 2 trains H SR 3.3.2.2 NA NA

a. Automatic Actuation Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.8

b. SG Water Level - 1,2 3 per SG I SR 3.3.2.1 82.4% 82%

High High (P-14) SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9

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

6. Auxiliary Feedwater 1,2,3 2 trains G SR 3.3.2.2 NA NA

a. Automatic Actuation SR 3.3.2.3 Logic and Actuation SR 3.3.2.8 Relays

b. SG Water Level - 1,2,3 3 per SG D SR 3.3.2.1 27.6% 28%

Low Low SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9(g)

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

d. Undervoltage 1,2 3 I SR 3.3.2.5 2640 volts 2680 Reactor Coolant SR 3.3.2.7 volts Pump SR 3.3.2.9

e. Trip of all Main 1 2 per pump J SR 3.3.2.10 NA NA Feedwater Pumps

7. ESFAS Interlocks 1,2,3 2 trains L SR 3.3.2.2 NA NA

a. Automatic Actuation Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.8

b. Reactor Trip, P-4 1,2,3 1 per train, 2 C SR 3.3.2.6 NA NA trains

c. Pressurizer 1,2,3 3 K SR 3.3.2.4 2003 psig 2000 psig Pressure, P-11 SR 3.3.2.7

d. Tavg - Low Low, P-12 1,2,3 1 per loop K SR 3.3.2.4 542.6°F 543°F (Decreasing) SR 3.3.2.7 545.4°F 545°F (Increasing)

(g) Applicable to MDAFW pumps only.

Farley Units 1 and 2 3.3.2-11 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTES--------------------------------------------------------

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status.

channel inoperable.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.8.

not met.

C. One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status.

channels inoperable.

Farley Units 1 and 2 3.3.3-1 Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2)

PAM Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met. 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 AND Table 3.3.3-1.

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 accordance with referenced in Specification 5.6.8.

Table 3.3.3-1.

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 Perform CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 3.3.3-2 Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2)

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

Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED REQUIRED FUNCTION CHANNELS ACTION D.1

1. RCS Hot Leg Temperature (Wide Range) 2 E

2. RCS Cold Leg Temperature (Wide Range) 2 E

3. RCS Pressure (Wide Range) 2 E

4. Steam Generator (SG) Water Level (Wide or 2/SG E Narrow Range)

5. Refueling Water Storage Tank Level 2 E

6. Containment Pressure (Narrow Range) 2 E

7. Pressurizer Water Level 2 E

8. Steam Line Pressure 2/SG E

9. Auxiliary Feedwater Flow Rate 2 E

10. RCS Subcooling Margin Monitor 2 E

11. Containment Water Level (Wide Range) 2 E

12. Core Exit Temperature - Quadrant 1 2 (a) E

13. Core Exit Temperature - Quadrant 2 2(a) E

14. Core Exit Temperature - Quadrant 3 2(a) E

15. Core Exit Temperature - Quadrant 4 2(a) E

16. Reactor Vessel Level Indicating System 2 F

17. Condensate Storage Tank Level 2 E

18. Deleted

19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples.

Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2)

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

NOTES--------------------------------------------------------

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable. to OPERABLE status.

B. ------------NOTE------------ B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Not applicable to Source Range Neutron AND Flux function.

B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action and associated Completion Time not met.

Farley Units 1 and 2 3.3.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Remote Shutdown System 3.3.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Submit a report to the 14 days associated Completion NRC outlining the Time not met for Source preplanned alternate Range Neutron Flux method of ensuring the function. reactor remains shutdown in the event of a control room evacuation, the cause of the inoperability, and the plans and schedule for restoring the Source Range Neutron Flux monitor to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days monitoring 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 monitoring instrumentation channel.

Farley Units 1 and 2 3.3.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 CHANNELS MONITORING INSTRUMENTATION

1. Steam Generator Wide Range Level 1/SG

2. Steam Generator Pressure 1/SG

3. Pressurizer Water Level 1

4. Pressurizer Pressure 1

5. RCS Hot Leg Temperature (Loop A) 1

6. RCS Cold Leg Temperature (Loop A) 1

7. Source Range Neutron Flux (Gammametrics) 1

8. Condensate Storage Tank Level 1 TRANSFER AND CONTROL CIRCUITS

9. Reactivity Control

a. Boric Acid Transfer System 1

10. RCS Pressure

a. Pressurizer Heater Control 1

11. RCS Inventory

a. Charging System 1

b. Letdown Orifice Isolation Valves 1

12. Decay Heat Removal

a. Auxiliary Feedwater System 1

b. SG Atmospheric Relief Valves 1

13. Safety Grade Support Systems Required For 1 Functions Listed Above Farley Units 1 and 2 3.3.4-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 instrumentation for each Function in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. ----------NOTE----------- A.1 -------------NOTE------------

Only applicable to The inoperable channel Functions 1 and 2. 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 of other channels.

One or more functions with one channel per train inoperable.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. ----------NOTE----------- B.1 Restore all but one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to channel per train to Functions 1 and 2. OPERABLE status.

One or more Functions with two or more channels per train inoperable.

C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Required Time of Condition A or Action(s) for the B not met. associated DG made inoperable by LOP DG start instrumentation.

Farley Units 1 and 2 3.3.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LOP DG Start Instrumentation 3.3.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. ----------NOTE----------- D.1 Verify voltage on Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to associated bus is 3850 Function 3. volts.

One Alarm Function channel inoperable on one or more trains.

E. Required Action and E.1 Restore bus voltage to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion 3850 volts.

Time of Condition D not met.

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 E AND not met.

F.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 3.3.5.1 ---------------------------NOTES--------------------------------

1. TADOT shall exclude actuation of the final trip actuation relay for LOP Functions 1 and 2.

2. Setpoint verification not required.

Perform TADOT. 31 days Farley Units 1 and 2 3.3.5-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LOP DG Start Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.2 -------------------------------NOTE-----------------------------

CHANNEL CALIBRATION shall exclude actuation of the final trip actuation relay for Functions 1 and 2.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.5.3 -------------------------------Note-------------------------------

Response time testing shall include actuation of the final trip actuation relay.

Verify ESF RESPONSE TIME within limit. 18 months on a STAGGERED TEST BASIS Farley Units 1 and 2 3.3.5-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)

Loss of Power Diesel Generator Start Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE ALLOWABLE TRIP MODES OR CHANNELS REQUIREMENTS VALUE SETPOINT OTHER PER TRAIN SPECIFIED CONDITIONS

1. 4.16 kV Emergency Bus 1,2,3,4, (a) 3 SR 3.3.5.1 3222 V 3255 V Loss of Voltage DG Start SR 3.3.5.2 and SR 3.3.5.3 3418 V

2. 4.16 kV Emergency Bus 1,2,3,4, (a) 3 SR 3.3.5.1 3638 V 3675 V Degraded Grid Voltage SR 3.3.5.2 and Actuation SR 3.3.5.3 3749 V

3. 4.16 kV Emergency Bus 1,2,3,4 1 SR 3.3.5.1 Degraged Grid Voltage SR 3.3.5.2 3835 V 3850 V Alarm (a) When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources - Shutdown."

Farley Units 1 and 2 3.3.5-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Purge and Exhaust Isolation Instrumentation LCO 3.3.6 The Containment Purge and Exhaust Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One Required radiation A.1 Restore the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months monitoring channel channel to OPERABLE inoperable. status.

B. ------------NOTE------------ B.1 Enter applicable Immediately Only applicable in Conditions and Required MODE 1, 2, 3, or 4. Actions of LCO 3.6.3,

"Containment Isolation Valves," for containment One or more Functions purge and exhaust with one or more isolation valves made manual or automatic inoperable by isolation actuation trains instrumentation.

inoperable.

OR Required Action and associated Completion Time of Condition A not met.

Farley Units 1 and 2 3.3.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Place and maintain Immediately Only applicable during containment purge and CORE ALTERATIONS exhaust valves in closed or movement of position.

irradiated fuel assemblies within OR containment.

C.2 Enter applicable Immediately Conditions and Required One or more manual Actions of LCO 3.9.3, channel(s) inoperable. "Containment Penetrations," for OR containment purge and exhaust isolation valves Two radiation made inoperable by monitoring channels isolation instrumentation.

inoperable.

OR Required Action and associated Completion Time for Condition A not met.

Farley Units 1 and 2 3.3.6-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Exhaust 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 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT. 92 days SR 3.3.6.5 Perform SLAVE RELAY TEST. 18 months 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 SR 3.3.6.8 Verify ESF RESPONSE TIME within limit. 18 months on a STAGGERED TEST BASIS Farley Units 1 and 2 3.3.6-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Purge and Exhaust Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Purge and Exhaust Isolation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP SETPOINT MODES OR OTHER CHANNELS REQUIREMENTS SPECIFIED CONDITIONS

1. Manual Initiation 1,2,3,4, (a), (b) 2 SR 3.3.6.6 NA

2. Automatic Actuation Logic 1,2,3,4 2 trains SR 3.3.6.2 NA and Actuation Relays SR 3.3.6.3 SR 3.3.6.5 SR 3.3.6.8

3. Containment Radiation 1,2,3,4 1 SR 3.3.6.1 -2 2.27 X 10 µCi/cc Gaseous (R-24A, B) (a), (b) 2 SR 3.3.6.4 (c)(d)

SR 3.3.6.7 -3 4.54 X 10 µCi/cc (c)(e)

-3 2.27 X 10 µCi/cc (c)(f)

4. Containment Isolation - Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and Phase A requirements.

(a) During CORE ALTERATIONS.

(b) During movement of irradiated fuel assemblies within containment.

(c) Above background with no flow.

(d) With mini-purge in operation.

(e) With slow speed main purge in operation.

(f) With fast speed main purge in operation.

Farley Units 1 and 2 3.3.6-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CREFS Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Emergency Filtration/Pressurization System (CREFS) Actuation Instrumentation LCO 3.3.7 The CREFS actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.7-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place one CREFS train in 7 days with one required emergency recirculation channel or train mode.

inoperable.

B. One or more Functions B.1.1 Place one CREFS train in Immediately with two required emergency recirculation channels or two trains mode.

inoperable.

AND B.1.2 Enter applicable Immediately Conditions and Required Actions of LCO 3.7.10, "CREFS" for one CREFS train made inoperable by inoperable CREFS actuation instrumentation.

OR (continued)

Farley Units 1 and 2 3.3.7-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CREFS Actuation Instrumentation 3.3.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place both CREFS trains Immediately in emergency recirculation 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 AND or B 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 CORE Immediately associated Completion ALTERATIONS.

Time for Condition A or B not met during AND movement of irradiated fuel assemblies or D.2 Suspend movement of Immediately during CORE irradiated fuel assemblies.

ALTERATIONS.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.7-1 to determine which SRs apply for each CREFS 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 Farley Units 1 and 2 3.3.7-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CREFS Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.3 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.7.4 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.7.5 Perform SLAVE RELAY TEST. 18 months SR 3.3.7.6 ----------------------------NOTE---------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.7.7 Perform CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 3.3.7-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CREFS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CREFS Actuation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP SETPOINT MODES OR OTHER CHANNELS REQUIREMENTS SPECIFIED CONDITIONS

1. Manual Initiation 1,2,3,4, (a), (b) 2 trains SR 3.3.7.6 NA

2. Automatic Actuation Logic 1,2,3,4 2 trains SR 3.3.7.3 NA and Actuation Relays SR 3.3.7.4 SR 3.3.7.5

3. Control Room Radiation 1,2,3,4 1 SR 3.3.7.1 800 cpm Control Room Air Intake (a), (b) 2 SR 3.3.7.2 (R-35A, B) SR 3.3.7.7

4. Containment Isolation - Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and Phase A requirements.

(a) During CORE ALTERATIONS.

(b) During movement of irradiated fuel assemblies.

Farley Units 1 and 2 3.3.7-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

PRF Actuation Instrumentation 3.3.8 3.3 INSTRUMENTATION 3.3.8 Penetration Room Filtration (PRF) System Actuation Instrumentation LCO 3.3.8 The PRF 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 A.1 Place one PRF train in 7 days with one channel or operation.

train inoperable.

B. One or more Functions B.1.1 Place one PRF train in Immediately with two channels or operation.

two trains inoperable.

AND B.1.2 Enter applicable Immediately Conditions and Required Actions of LCO 3.7.12, "PRF System," for one train made inoperable by inoperable actuation instrumentation.

OR B.2 Place both PRF trains in Immediately operation.

Farley Units 1 and 2 3.3.8-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

PRF Actuation Instrumentation 3.3.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. ----------NOTE------------- C.1 Suspend movement of Immediately Only applicable to irradiated fuel assemblies Functions required in the spent fuel pool OPERABLE by Table room.

3.3.8-1 during movement of irradiated fuel assemblies in the spent fuel pool room.

Required Action and associated Completion Time for Condition A or B not met during movement of irradiated fuel assemblies in the spent fuel pool room.

D. ----------NOTE------------- D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Only applicable to Functions required AND OPERABLE by Table 3.3.8-1 in MODES 1-4. D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and associated Completion Time for Condition A or B not met in MODE 1, 2, 3, or 4.

Farley Units 1 and 2 3.3.8-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

PRF Actuation Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8-1 to determine which SRs apply for each PRF Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.8.2 Perform COT. 92 days SR 3.3.8.3 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.8.4 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.8.5 Perform SLAVE RELAY TEST. 18 months SR 3.3.8.6 ------------------------------NOTE--------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.8.7 Perform CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 3.3.8-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

PRF Actuation Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)

PRF Actuation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP SETPOINT MODES OR OTHER CHANNELS REQUIREMENTS SPECIFIED CONDITIONS

1. Manual Initiation 1,2,3,4, (a) 2 trains SR 3.3.8.6 NA

2. Automatic Actuation Logic 1,2,3,4 2 trains SR 3.3.8.3 NA and Actuation Relays SR 3.3.8.4 SR 3.3.8.5

3. Spent Fuel Pool Room (a) 2 SR 3.3.8.1 8.73 x 10-3 µCi/cc (b)

Radiation Gaseous SR 3.3.8.2 (R-25A, B) SR 3.3.8.7

4. Spent Fuel Pool Room (a) 2 SR 3.3.8.6 NA Ventilation Differential SR 3.3.8.7 Pressure (PDSL-3989A and B)

5. Containment Isolation - Refer to LCO 3.3.2, "ESFAS Instrumentation" Function 3.b, for all initiation Functions and Phase B requirements.

(a) During movement of irradiated fuel assemblies in the spent fuel pool room.

(b) Above background with no flow.

Farley Units 1 and 2 3.3.8-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 in the COLR. The minimum RCS total flow rate shall be 263,400 GPM when using the precision heat balance method, 264,200 GPM when using the elbow tap method, and the limit specified in the COLR.

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 parameter(s) to within limits. 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.

Farley Units 1 and 2 3.4.1-1 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is within the limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR.

SR 3.4.1.2 Verify RCS average temperature is within the limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR.

SR 3.4.1.3 Verify RCS total flow rate is within the limits. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.4 -------------------------------NOTE-------------------------

Not required to be performed until 7 days after 90% RTP.

Verify by measurement that RCS total flow rate is 18 months within the limits.

Farley Units 1 and 2 3.4.1-2 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

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 541°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 541°F. --------NOTE--------

Only required if low low Tavg alarm not reset and any RCS loop Tavg

< 547°F 30 minutes thereafter Farley Units 1 and 2 3.4.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Requirements of LCO not acceptable for continued met in MODE 1, 2, 3, or 4. operation.

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.

Farley Units 1 and 2 3.4.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS P/T Limits 3.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------- C.1 Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within be completed whenever limits.

this Condition is entered.

AND Requirements of LCO not C.2 Determine RCS is Prior to entering met any time in other acceptable for continued MODE 4 than MODE 1, 2, 3, or 4. operation.

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months heatup and cooldown rates are within the limits specified in the PTLR.

Farley Units 1 and 2 3.4.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Three 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 Farley Units 1 and 2 3.4.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 not be in 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:

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.

Farley Units 1 and 2 3.4.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS Loops MODE 3 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One required RCS loop C.1 Restore required RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not in operation, and loop to operation.

reactor trip breakers closed and Rod Control OR System capable of 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. Two required RCS loops D.1 De-energize all CRDMs. Immediately inoperable.

AND OR D.2 Suspend all operations Immediately No RCS loop in involving a reduction of operation. 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 30% (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.

Farley Units 1 and 2 3.4.5-2 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

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 consisting of any combination of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.

NOTES---------------------------------------

1. All reactor coolant pumps (RCPs) and RHR pumps may not be in operation for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-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.

2. No RCP shall be started with any RCS cold leg temperature 325°F unless:

a. The secondary side water temperature of each steam generator (SG) is < 50°F above each of the RCS cold leg temperatures; or

b. The pressurizer water volume is less than 770 cubic feet (24%

of wide range, cold, pressurizer level indication).

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Initiate action to restore a Immediately inoperable. second loop to OPERABLE status.

AND Two RHR loops inoperable.

Farley Units 1 and 2 3.4.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS Loops MODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 Two required RCS loops inoperable.

C. Required RCS or RHR C.1 Suspend all operations Immediately loops inoperable. involving a reduction of RCS boron concentration.

OR AND No RCS or RHR loop in operation. C.2 Initiate action to restore Immediately one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify SG secondary side water levels are 75% 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (wide range) for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

Farley Units 1 and 2 3.4.6-2 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

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 75% (wide range).

NOTES---------------------------------------

1. The RHR pump of the loop in operation may not be in operation for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-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.

2. One required 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.

3. No reactor coolant pump shall be started with one or more RCS cold leg temperatures 325°F unless:

a. The secondary side water temperature of each SG is < 50°F above each of the RCS cold leg temperatures; or

b. The pressurizer water volume is less than 770 cubic feet (24%

of wide range, cold, pressurizer level indication).

4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

5. The number of operating Reactor Coolant Pumps is limited to one at RCS temperatures < 110°F with the exception that a second pump may be started for the purpose of maintaining continuous flow while taking the operating pump out of service.

Farley Units 1 and 2 3.4.7-1 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

RCS Loops MODE 5, Loops Filled

3.4.7 APPLICABILITY

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop A.1 Initiate action to restore a Immediately inoperable. second RHR loop to OPERABLE status.

AND OR Required SGs secondary side water levels not A.2 Initiate action to restore Immediately within limits. required SG secondary side water levels to within limits.

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 75% (wide 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months range) in required SGs.

Farley Units 1 and 2 3.4.7-2 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

RCS Loops MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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.

Farley Units 1 and 2 3.4.7-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

NOTES-----------------------------------------

1. All RHR pumps may not be in operation 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 A.1 Initiate action to restore Immediately inoperable. RHR loop to OPERABLE status.

Farley Units 1 and 2 3.4.8-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS Loops MODE 5, Loops Not Filled 3.4.8 ACTIONS 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.

Farley Units 1 and 2 3.4.8-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 63.5% indicated; and

b. Two groups of pressurizer heaters OPERABLE with the capacity of each group 125 kW and capable of being powered from an emergency power supply.

APPLICABILITY: MODES 1, 2, and 3.

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

Pressurizer water level 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. Pressurizer water level A.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months not 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 Farley Units 1 and 2 3.4.9-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 63.5% indicated. 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 125 kW.

SR 3.4.9.3 Verify required pressurizer heaters are capable of 18 months being powered from an emergency power supply.

Farley Units 1 and 2 3.4.9-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 2460 psig and 2510 psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > 325°F.

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

The lift settings are not required to be within the LCO limits during MODES 3 and 4 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 Two or more pressurizer temperatures 325°F.

safety valves inoperable.

Farley Units 1 and 2 3.4.10-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Following testing, lift settings shall be within +/- 1%. Testing Program Farley Units 1 and 2 3.4.10-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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

NOTES---------------------------------------------------------

1. Separate Condition entry is allowed for each PORV.

2. LCO 3.0.4 is not applicable.

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 being manually cycled. block 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.

Farley Units 1 and 2 3.4.11-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. 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, AND or C 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 E.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 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 Farley Units 1 and 2 3.4.11-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. More than one block valve F.1 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. PORVs 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.

AND F.3 Restore remaining 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months block valve to OPERABLE status.

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 -------------------------------NOTES-----------------------------

1. Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.

2. Not required to be performed prior to entry into MODE 3.

3. Not required to be performed for Unit 2 for the remainder of operating cycle 16 for block valve Q2B31MOV8000B.

Perform a complete cycle of each block valve. 92 days Farley Units 1 and 2 3.4.11-3 Amendment No. 146 (Unit 1)

Amendment No. 151 (Unit 2)

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.2 ----------------------------NOTE---------------------------------

Not required to be performed prior to entry into MODE 3.

Perform a complete cycle of each PORV during 18 months MODE 3 or 4.

SR 3.4.11.3 Perform a complete cycle of each PORV using the 18 months backup PORV control system.

SR 3.4.11.4 ----------------------------NOTE---------------------------------

Required to be performed only for Unit 2 for the remainder of operating cycle 16.

Check power available to the Unit Two PORV block 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months valve Q2B31MOV8000B.

Farley Units 1 and 2 3.4.11-4 Amendment No. 146 (Unit 1)

Amendment No. 151 (Unit 2)

LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of one charging pump capable of injecting into the RCS and the accumulators isolated and either a or b below.

a. Two residual heat removal (RHR) suction relief valves with setpoints 450 psig.

b. The RCS depressurized and an RCS vent of 2.85 square inches.

APPLICABILITY: MODE 4 when the temperature of one or more RCS cold legs is 325°F, MODE 5, MODE 6 when the reactor vessel head is on.

NOTES----------------------------------------------

1. The requirement to have only one charging pump capable of injecting into the RCS is only applicable when one or more of the RCS cold legs is 180°F; however, while in this condition, two charging pumps may be capable of injecting into the RCS during pump swap operations for a period of no more than 15 minutes provided that the RCS is in a non-water solid condition and both RHR relief valves are OPERABLE or the RCS is vented via an opening of no less than 5.7 square inches in area.

2. Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

3. LCO 3.0.4 is not applicable.

Farley Units 1 and 2 3.4.12-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two or more charging A.1 ----------- NOTE-----------

pumps capable of Two charging pumps injecting into the may be capable of RCS. injecting into the RCS during pump swap operation for 15 minutes.

Initiate action to verify a Immediately maximum of one charging pump is capable of injecting into the RCS.

B. An accumulator not B.1 Isolate affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

C. Required Action and C.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 > 325°F.

Time of Condition B not OR met.

C.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.

Farley Units 1 and 2 3.4.12-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One required RHR relief D.1 Reduce pressurizer level 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months valve inoperable. to 30% (cold calibrated).

AND D.2 Assign a dedicated 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months operator for RCS pressure monitoring and control.

AND D.3 Restore required RHR 7 days relief valve to OPERABLE status.

E. Two required RHR relief E.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 of 2.85 square inches.

OR Required Action and associated Completion Time of Condition A, C, or D not met.

OR LTOP System inoperable for any reason other than Condition A, B, C, or D.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of one charging pump is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months capable of injecting into the RCS.

Farley Units 1 and 2 3.4.12-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.2 Verify each accumulator is isolated. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.3 Verify RHR suction isolation valves are open for each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months required RHR suction relief valve.

SR 3.4.12.4 -----------------------------NOTE--------------------------------

Only required to be performed when complying with LCO 3.4.12.b.

Verify RCS vent 2.85 square inches open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for unlocked, unsealed, or unsecured open vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s)

SR 3.4.12.5 Verify each required RHR suction relief valve In accordance with setpoint. the Inservice Testing Program AND Every 18 months on a STAGGERED TEST BASIS Farley Units 1 and 2 3.4.12-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits within limits.

for reasons 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 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 Pressure boundary LEAKAGE exists.

OR Primary to secondary LEAKAGE not within limit.

Farley Units 1 and 2 3.4.13-1 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ----------------------------NOTES-------------------------------- -------NOTE--------

1. Not required to be performed in MODE 3 or 4 Only required to until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation. be performed during steady

2. Not applicable to primary to secondary LEAKAGE. state operation Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 150 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months gallons per day through any one SG.

Farley Units 1 and 2 3.4.13-2 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

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

with leakage from one or Each valve used to satisfy more RCS PIVs not Required Action A.1 and Required within limit. Action A.2 must be verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary or the high pressure portion of the system.

(continued)

Farley Units 1 and 2 3.4.14-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 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 A.2 Isolate the high 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressure portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

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 C. RHR System C.1 Place the affected valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months autoclosure or open in the closed position and permissive interlock maintain closed under function inoperable. administrative control.

Farley Units 1 and 2 3.4.14-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -----------------------------NOTES-----------------------------

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 18 months, prior 0.5 gpm per nominal inch of valve size up to a to entering maximum of 5 gpm at an RCS pressure 2215 psig MODE 2 and 2255 psig.

AND Following valve actuation due to automatic or manual action or flow through the valve (except for RCS PIVs located in the RHR flow path)

SR 3.4.14.2 --------------------------------NOTE------------------------------

Not required to be met when the RHR System valves are required open in accordance with SR 3.4.12.3.

Verify RHR System autoclosure interlock 18 months causes the valves to close automatically with a simulated or actual RCS pressure signal 700 psig and 750 psig.

Farley Units 1 and 2 3.4.14-3 Amendment No. 155 (Unit 1)

Amendment No. 147 (Unit 2)

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SR 3.4.14.3 -------------------------- NOTE----------------------------------

Not required to be met when the RHR System valves valves are required open in accordance with SR 3.4.12.3.

Verify RHR System open permissive interlock 18 months prevents the valves from being opened with a simulated or actual RCS pressure signal 295 psig and 415 psig.

Farley Units 1 and 2 3.4.14-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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:

a. One containment atmosphere particulate radioactivity monitor; and

b. One containment air cooler condensate level monitor or one containment atmosphere gaseous radioactivity monitor.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

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

LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Containment atmosphere A.1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months particulate radioactivity the containment monitor inoperable. atmosphere.

OR A.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 A.2 Restore the containment 30 days atmosphere particulate radioactivity monitor to OPERABLE status.

Farley Units 1 and 2 3.4.15-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 gaseous the containment radioactivity monitor atmosphere.

inoperable.

OR AND 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 Required containment air cooler condensate level monitor inoperable. AND B.2 Restore at least one 30 days required monitor 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 D. All required monitors D.1 Enter LCO 3.0.3. Immediately inoperable.

Farley Units 1 and 2 3.4.15-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS Leakage Detection Instrumentation 3.4.15 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 radioactivity monitor.

SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere radioactivity monitor.

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere radioactivity monitor.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required 18 months containment air cooler condensate level monitor.

Farley Units 1 and 2 3.4.15-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 --------------------Note----------------

I-131 > 0.5 µCi/gm. LCO 3.0.4 is not 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 within the acceptable region of Figure 3.4.16-1.

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 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months reactor coolant not within Tavg < 500°F.

limit.

Farley Units 1 and 2 3.4.16-1 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

RCS Specific Activity 3.4.16 ACTIONS 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 in the unacceptable region of Figure 3.4.16-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity 7 days 100/ µCi/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 0.5 µCi/gm.

AND Between 2 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 Farley Units 1 and 2 3.4.16-2 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

RCS Specific Activity 3.4.16 SURVIELLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.3 ---------------------------------NOTE-----------------------------

Not required to be performed until 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 .

Farley Units 1 and 2 3.4.16-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS Specific Activity 3.4.16 Figure 3.4.16-1 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.5 µCi/gm DOSE EQUIVALENT I-131.

Farley Units 1 and 2 3.4.16-4 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

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 repair criteria shall be plugged 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 repair affected tube(s) is criteria and not plugged maintained until the next in accordance with the inspection.

Steam Generator AND Program.

A.2 Plug the affected tube(s) Prior to entering in accordance with the MODE 4 following 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 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 SG tube integrity not maintained.

Farley Units 1 and 2 3.4.17-1 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the In accordance with 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 repair criteria is plugged in accordance with the MODE 4 following Steam Generator Program. a SG tube inspection Farley Units 1 and 2 3.4.17-2 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Three ECCS accumulators shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS pressure > 1000 psig.

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

In MODE 3, with RCS pressure > 1000 psig, the accumulators may be inoperable for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to perform pressure isolation valve testing per SR 3.4.14.1.

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 OPERABLE status.

other 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 RCS pressure to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1000 psig.

D. Two or more D.1 Enter LCO 3.0.3. Immediately accumulators inoperable.

Farley Units 1 and 2 3.5.1-1 Amendment No. 162 (Unit 1)

Amendment No. 155 (Unit 2)

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 7555 gallons (31.4%) and 7780 gallons (58.4%).

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 601 psig and 649 psig.

SR 3.5.1.4 Verify boron concentration in each accumulator is 31 days 2200 ppm and 2500 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 12%

level, indicated, 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 RCS pressure is 2000 psig.

Farley Units 1 and 2 3.5.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

NOTES---------------------------------------------

1. In MODE 3, the Residual Heat Removal or the Centrifugal Charging 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. Upon entry into MODE 3 from MODE 4, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be locked open for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from MODE 4 requirements.

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 Farley Units 1 and 2 3.5.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ECCS Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 ----------------------------NOTE---------------------------------

Only required to be performed for valves 8132A and 8132B when Centrifugal Charging Pump A is inoperable.

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 8884, 8886 Closed Centrifugal Charging Pump to RCS Hot Leg 8132A, 8132B Open Centrifugal Charging Pump discharge isolation 8889 Closed RHR to RCS Hot Leg Injection 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 each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.5.2.4 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.

Farley Units 1 and 2 3.5.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ECCS Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each ECCS pump starts automatically on an 18 months actual or simulated actuation signal.

SR 3.5.2.6 Verify, for each ECCS throttle valve listed below, 18 months each position stop is in the correct position.

Valve Number CVC-V-8991 A/B/C CVC-V-8989 A/B/C CVC-V-8996 A/B/C CVC-V-8994 A/B/C RHR-HV 603 A/B SR 3.5.2.7 Verify, by visual inspection, each ECCS train 18 months containment sump suction inlet is not restricted by debris and the suction inlet trash racks, screens, and inner cages are properly installed and show no evidence of structural distress or abnormal corrosion.

Farley Units 1 and 2 3.5.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

NOTES-----------------------------------------------

1. 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.

2. Upon entry into MODE 4 from MODE 3, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be closed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from MODE 3 requirements.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS centrifugal B.1 Restore required ECCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months charging subsystem centrifugal charging inoperable. subsystem to OPERABLE status.

AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.

Farley Units 1 and 2 3.5.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ECCS Shutdown 3.5.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required ECCS C.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months centrifugal charging centrifugal charging subsystem inoperable. subsystem to OPERABLE status.

D. Required Action and D.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 or C not met.

AND At least one RHR subsystem OPERABLE.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all equipment In accordance with required to be OPERABLE: applicable SRs SR 3.5.2.2 SR 3.5.2.6 SR 3.5.2.3 SR 3.5.2.7 Farley Units 1 and 2 3.5.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ECCS Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.2 Verify the following valves are in the listed position 31 days with power to the valve operator removed.

Number Position Function 8706A, Closed RHR pump discharge 8706B to centrifugal charging pump suction 8884, Closed Centrifugal charging 8886 pump discharge to RCS hot legs Farley Units 1 and 2 3.5.3-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 A.1 Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

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 Farley Units 1 and 2 3.5.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -----------------------------NOTE------------------------------

Only required to be performed when ambient air temperature is < 35ºF.

Verify RWST borated water temperature is 35ºF. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.5.4.2 Verify RWST borated water volume is 471,000 7 days gallons.

SR 3.5.4.3 Verify RWST boron concentration is 2300 ppm and 7 days 2500 ppm.

Farley Units 1 and 2 3.5.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 within limits.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow not A.1 Adjust manual seal 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months within limit. injection throttle valves in accordance with SR 3.5.5.1.

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 Farley Units 1 and 2 3.5.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Seal Injection Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 --------------------------------NOTE-----------------------------

Not required to be performed until 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 the limits of Figure 3.5.5-1 with the seal water injection flow control valve full open.

Farley Units 1 and 2 3.5.5-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Seal Injection Flow 3.5.5 Figure 3.5.5-1 Seal Injection Flow Limits Farley Units 1 and 2 3.5.5-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ECCS Recirculation Fluid pH Control System 3.5.6 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 ECCS Recirculation Fluid pH Control System LCO 3.5.6 The ECCS Recirculation Fluid pH Control System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ECCS Recirculation Fluid A.1 Restore system to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pH Control System OPERABLE status.

inoperable.

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. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.6.1 Perform a visual inspection of the ECCS 18 months Recirculation Fluid pH Control System and verify the following:

a. Three (3) storage baskets are in place, and

b. Have maintained their integrity, and

c. Each basket is filled with trisodium phosphate compound such that the level is between the indicated fill marks on the baskets.

Farley Units 1 and 2 3.5.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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. Structural integrity of the A.1 Restore the structural 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months containment not integrity to within limits.

conforming to the requirements of SR 3.6.1.2.

B. Containment inoperable B.1 Restore containment to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for 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 Farley Units 1 and 2 3.6.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment 3.6.1 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.

SR 3.6.1.2 Verify containment structural integrity in accordance In accordance with with the Containment Tendon Surveillance Program. the Containment Tendon Surveillance Program Farley Units 1 and 2 3.6.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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)

Farley Units 1 and 2 3.6.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

Farley Units 1 and 2 3.6.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One or more containment ------------------NOTES------------------

air locks with 1. Required Actions B.1, B.2, containment air lock and B.3 are not applicable if interlock mechanism both doors in the same air inoperable. 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door 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.

Farley Units 1 and 2 3.6.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Air Locks 3.6.2 ACTIONS 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 Farley Units 1 and 2 3.6.2-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Verify only one door in the air lock can be opened at 24 months a time.

Farley Units 1 and 2 3.6.2-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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. The 8-inch containment mini-purge supply and exhaust isolation valves may be open for safety-related reasons.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES--------------------------------------------------------

1. Penetration flow path(s) except for 48-inch purge valve flow paths 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.

Farley Units 1 and 2 3.6.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Isolation Valves 3.6.3 ACTIONS 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 use of at least one closed with two containment and de-activated isolation 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 AND for purge valve penetration leakage not A.2 -------------NOTE-------------

within limit. Isolation devices in high radiation areas 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 Farley Units 1 and 2 3.6.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Isolation Valves 3.6.3 ACTIONS 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 use of at least one closed with two containment and de-activated isolation 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 penetration leakage not within limit.

C. ------------NOTE------------ C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with only one and de-activated containment isolation automatic valve, closed valve and a closed manual valve, or blind system. flange.

AND One or more penetration flow paths with one C.2 -------------NOTE------------

containment isolation Isolation devices in high valve inoperable. radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

Farley Units 1 and 2 3.6.3-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months flow paths containing penetration flow path by containment purge use of at least one valves, with penetration closed and de-activated leakage such that the automatic valve, closed sum of the leakage for all manual valve, or blind Type B and C tests is not flange.

within limits.

AND D.2 ------------NOTE-------------

Isolation devices in high radiation areas 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 AND D.3 Perform SR 3.6.3.5 for Once per 92 days the penetrations containing resilient seal purge valves closed to comply with Required Action D.1.

Farley Units 1 and 2 3.6.3-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. 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 of Condition A, B, AND C, or D not met.

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. One or more penetration F.1 Reduce leakage to within Prior to entering flow paths containing limit. MODE 4 from MODE containment purge 5 if the existing valves, with penetration leakage is determined leakage not within the during quarterly penetration limits. testing per SR 3.6.3.5 OR Prior to entering MODE 4 if excess leakage is determined during MODE 5 per SR 3.6.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 48 inch purge valve is sealed closed, 31 days except for one purge valve in a penetration flow path while in Condition D of this LCO.

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 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.

Farley Units 1 and 2 3.6.3-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.3 ----------------------------NOTES--------------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. The blind flange on the fuel transfer canal flange is only required to be verified closed after each draining of the canal.

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days SR 3.6.3.4 Verify the isolation time of each power operated or In accordance with automatic containment isolation valve in the IST the Inservice Program is within limits. Testing Program SR 3.6.3.5 Perform leakage rate testing for containment 184 days penetrations containing containment purge 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.

Farley Units 1 and 2 3.6.3-6 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be -1.5 psig and +3.0 psig.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not 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 Farley Units 1 and 2 3.6.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 120°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 limit. to 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 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit.

Farley Units 1 and 2 3.6.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

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. AND 10 days from discovery of failure to meet the LCO 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. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months C. One containment cooling C.1 Restore containment 7 days train inoperable. cooling train to OPERABLE status. AND 10 days from discovery of failure to meet the LCO Farley Units 1 and 2 3.6.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Spray and Cooling Systems 3.6.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Two containment cooling D.1 Restore one containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trains inoperable. cooling train to OPERABLE status.

E. 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 of Condition C or D AND not met.

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Two containment spray F.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

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 Operate each required containment cooling train fan 31 days unit for 15 minutes.

SR 3.6.6.3 Verify each containment cooling train cooling water 31 days flow rate is 1600 gpm.

Farley Units 1 and 2 3.6.6-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.4 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal to the Inservice the required developed head. Testing Program SR 3.6.6.5 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 3.6.6.6 Verify each containment spray pump starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.7 Verify each containment cooling train starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.8 Verify each spray nozzle is unobstructed. 10 years Farley Units 1 and 2 3.6.6-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Hydrogen Recombiners 3.6.7 DELETED Additional page deleted:

3.6.7-2 Farley Units 1 and 2 3.6.7-1 Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2)

HMS 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Mixing 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 A.1 ------------NOTE-------------

inoperable. LCO 3.0.4 is not applicable.

Restore HMS train to 30 days OPERABLE status.

B. Two HMS trains B.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. means that the hydrogen control function is AND maintained.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Restore one HMS train to 7 days 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.

Farley Units 1 and 2 3.6.8-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

HMS 3.6.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Operate each HMS train for 15 minutes. 92 days SR 3.6.8.2 Verify each HMS fan speed is 1320 rpm. 18 months SR 3.6.8.3 Verify each HMS train starts on an actual or 18 months simulated actuation signal.

Farley Units 1 and 2 3.6.8-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Reactor Cavity Hydrogen Dilution System 3.6.9 3.6 CONTAINMENT SYSTEMS 3.6.9 Reactor Cavity Hydrogen Dilution System LCO 3.6.9 Two Reactor Cavity Hydrogen Dilution trains shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Reactor Cavity A.1 -------------NOTE-------------

Hydrogen Dilution train LCO 3.0.4 is not inoperable. applicable.

Restore the train to 30 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.9.1 Operate each Reactor Cavity Hydrogen Dilution train 92 days for 15 minutes.

SR 3.6.9.2 Verify each Reactor Cavity Hydrogen Dilution train 18 months starts on an actual or simulated actuation signal.

Farley Units 1 and 2 3.6.9-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 POWER to 87% RTP.

MSSV inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels.

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 POWER to less than or more MSSVs inoperable. equal to the Maximum Allowable % RTP OR specified in Table 3.7.1-1 for the number of One or more steam OPERABLE MSSVs.

generators with one MSSV inoperable and AND the MTC positive at any power level.

(continued)

Farley Units 1 and 2 3.7.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

MSSVs 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 -------------NOTE------------

Only required in MODE 1.

Reduce the Power Range 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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.

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 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR 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 Table In accordance with 3.7.1-2 in accordance with the Inservice Testing the Inservice Program. Following testing, lift setting shall be within Testing Program

+/-1%.

Farley Units 1 and 2 3.7.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 MAXIMUM ALLOWABLE MSSVs PER STEAM GENERATOR POWER (% RTP) 4 60 3 43 2 24 Farley Units 1 and 2 3.7.1-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING (psig +/- 3%)

STEAM GENERATOR

1 #2 #3 Q1(2)N11V010A Q1(2)N11V011A Q1(2)N11V012A 1075 Q1(2)N11V010B Q1(2)N11V011B Q1(2)N11V012B 1088 Q1(2)N11V010C Q1(2)N11V011C Q1(2)N11V012C 1102 Q1(2)N11V010D Q1(2)N11V011D Q1(2)N11V012D 1115 Q1(2)N11V010E Q1(2)N11V011E Q1(2)N11V012E 1129 Farley Units 1 and 2 3.7.1-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Two MSIVs per steam line shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when one MSIV in each steam line is closed.

ACTIONS

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

Separate Condition entry is allowed for each steam line.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam lines A.1 Restore MSIV to OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with one MSIV inoperable status.

in MODE 1.

B. One or more steam lines B.1 Restore one MSIV to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with two MSIVs OPERABLE status in inoperable in MODE 1. affected steam line.

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 of Condition A or B not met.

D. One or more steam lines D.1 Verify one MSIV closed in 7 days with one MSIV affected steam line.

inoperable in MODE 2 or AND 3.

Once per 7 days thereafter Farley Units 1 and 2 3.7.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

MSIVs 3.7.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One or more steam lines E.1 Verify one MSIV closed in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with two MSIVs affected steam line.

inoperable in MODE 2 AND or 3.

Once per 7 days thereafter 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 D or E AND not met.

F.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 3.7.2.1 -------------------------------NOTE-------------------------------

Only required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is 7 seconds. In accordance with the Inservice Testing Program Farley Units 1 and 2 3.7.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve.

ACTIONS

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

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW A.1 Close or isolate Main FW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Stop Valves inoperable. Stop Valve.

AND A.2 Verify Main FW Stop Valve Once per 7 days is closed or 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.

Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV C.1 Close or isolate bypass 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months bypass valves valve.

inoperable.

AND C.2 Verify bypass valve is closed Once per 7 days or isolated.

D. Two valves in the same D.1 Isolate affected flow path. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow path inoperable.

E. 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, In accordance with MFRV, and associated bypass valve is in accordance the Inservice with the time requirement in the Inservice Testing Testing Program.

Plan.

Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ARVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Relief Valves (ARVs)

LCO 3.7.4 Three ARV lines shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ARV line A.1 -------------NOTE-------------

inoperable. LCO 3.0.4 is not applicable.

Restore required ARV line 7 days to OPERABLE status.

B. Two or more required B.1 Restore all but one ARV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ARV lines inoperable. line 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 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months Farley Units 1 and 2 3.7.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ARVs 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ARV. 18 months SR 3.7.4.2 Verify one complete cycle of at least one manual 18 months isolation valve in each ARV Line.

Farley Units 1 and 2 3.7.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore steam supply to 7 days turbine driven AFW OPERABLE status.

pump inoperable. AND 10 days from discovery of failure to meet the LCO B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons OPERABLE status.

other than Condition A. AND 10 days from discovery of failure to meet the LCO 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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two AFW trains inoperable.

Farley Units 1 and 2 3.7.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AFW System 3.7.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Three AFW trains D.1 --------------NOTE---------------

inoperable. LCO 3.0.3 and all other 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -------------------------------NOTE-------------------------------

Not required to be performed for the AFW flow control valves when 10% RTP or when the AFW system is not in automatic control.

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.

Farley Units 1 and 2 3.7.5-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 1005 psig in the steam generator.

Verify the developed head of each AFW pump at the In accordance flow test point is greater than or equal to the required with the Inservice developed head. Testing Program.

SR 3.7.5.3 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----------------------------------

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 1005 psig in the steam generator.

Verify each AFW pump starts automatically on an 18 months actual or simulated actuation signal.

SR 3.7.5.5 Verify the turbine driven AFW pump steam admission 18 months valves open when air is supplied from their respective air accumulators.

Farley Units 1 and 2 3.7.5-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)

LCO 3.7.6 The CST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CST inoperable. A.1 Verify by administrative 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months means OPERABILITY of backup water supply. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore CST 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 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is 150,000 gal. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Farley Units 1 and 2 3.7.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 ------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops MODE 4,"

for residual heat removal loops made inoperable by CCW.

Restore CCW 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 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 Farley Units 1 and 2 3.7.7-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CCW System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 ------------------------------NOTE--------------------------------

Isolation of CCW flow to individual components does not render the CCW System inoperable.

Verify each accessible CCW manual, power 31 days operated, and 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 3.7.7.2 Verify each CCW 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 3.7.7.3 Verify each CCW pump starts automatically on an 18 months actual or simulated actuation signal.

Farley Units 1 and 2 3.7.7-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

SWS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water System (SWS)

LCO 3.7.8 Two SWS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SWS 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 SWS.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops MODE 4,"

for residual heat removal loops made inoperable by SWS.

Restore SWS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. One SWS automatic B.1 Restore both inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months turbine building isolation turbine building isolation valve inoperable in each valves to OPERABLE SWS train. status.

Farley Units 1 and 2 3.7.8-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

SWS 3.7.8 ACTIONS 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.

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 3.7.8.1 ------------------------------NOTE--------------------------------

Isolation of SWS flow to individual components does not render the SWS inoperable.

Verify each accessible SWS manual, power 31 days operated, and 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 SWS 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 SWS pump starts automatically on an 18 months actual or simulated actuation signal.

SR 3.7.8.4 Verify the integrity of the SWS buried piping by visual 18 months inspection of the ground area.

Farley Units 1 and 2 3.7.8-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS (Service Water Pond) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS water level or A.1 Be in MODE 4. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months temperature not within the required limit(s). AND A.2 Be in MODE 5. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is 184 ft 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mean sea level.

SR 3.7.9.2 Verify water temperature of 95°F at the discharge 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the Service Water Pumps Farley Units 1 and 2 3.7.9-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Control Room 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room LCO 3.7.10 Two Control Room Emergency Filtration/Pressurization System (CREFS) trains and the Control Room Envelope (CRE) shall be OPERABLE.

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

The CRE may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies, During CORE ALTERATIONS.

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

B. CRE inoperable. B.1 Initiate mitigating actions. Immediately AND B.2.1 Restore CRE to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR B.2.2.1 Verify General Design 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Criteria (GDC) 19 met using mitigating actions in B.1.

AND B.2.2.2 Restore CRE to 30 days OPERABLE status.

Farley Units 1 and 2 3.7.10-1 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

Control Room 3.7.10 ACTIONS 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. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.2 Be in MODE 5.

OR Two CREFS trains inoperable in MODE 1, 2, 3, or 4.

D. Required Action and D.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A not recirculation mode.

met during movement of OR irradiated fuel assemblies or during CORE ALTERATIONS. D.2.1 Suspend CORE Immediately ALTERATIONS.

AND D.2.2 Suspend movement of Immediately irradiated fuel assemblies.

Farley Units 1 and 2 3.7.10-2 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

Control Room 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Suspend CORE Immediately associated Completion ALTERATIONS.

Time of Condition B not met during movement of AND irradiated fuel assemblies or during CORE E.2 Suspend movement of Immediately ALTERATIONS. irradiated fuel assemblies.

OR Two CREFS trains inoperable during movement of irradiated fuel assemblies or during CORE ALTERATIONS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREFS Pressurization train with the 31 days heaters operating and each CREFS Recirculation and Filtration train for 15 minutes.

SR 3.7.10.2 Perform required CREFS filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). VFTP SR 3.7.10.3 ----------------------------NOTE---------------------------------

Not required to be performed in MODES 5 and 6.

Verify each CREFS train actuates on an actual or 18 months simulated actuation signal.

Farley Units 1 and 2 3.7.10-3 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

CRACS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRACS)

LCO 3.7.11 Two CRACS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies, During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRACS train A.1 Restore CRACS train to 30 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 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 CRACS train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies or during CORE C.2.1 Suspend CORE Immediately ALTERATIONS. ALTERATIONS.

AND C.2.2 Suspend movement of Immediately irradiated fuel assemblies.

Farley Units 1 and 2 3.7.11-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CRACS 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Two CRACS trains D.1 Suspend CORE Immediately inoperable during ALTERATIONS.

movement of irradiated fuel assemblies or during AND CORE ALTERATIONS.

D.2 Suspend movement of Immediately irradiated fuel assemblies.

E. Two CRACS trains E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CRACS train has the capability to 18 months remove the assumed heat load.

Farley Units 1 and 2 3.7.11-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Control Room 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.4 Verify CRE p within limits in the Control Room Integrity 24 months on a Program (CRIP). STAGGERED TEST BASIS SR 3.7.10.5 Verify CRE integrity in accordance with the CRIP. In accordance with the CRIP Farley Units 1 and 2 3.7.10-4 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

PRF 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Penetration Room Filtration (PRF) System LCO 3.7.12 Two PRF trains shall be OPERABLE.

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

The PRF and Spent Fuel Pool Room (SFPR) boundaries may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, and 4 for post LOCA mode of operation, During movement of irradiated fuel assemblies in the SFPR for the fuel handling accident mode of operation.

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

B. Two PRF trains B.1 Restore PRF boundary to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable in MODE 1, 2, OPERABLE status.

3, or 4 due to inoperable PRF boundary.

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 OR Two PRF trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

D. Required Action and D.1 Place OPERABLE PRF Immediately associated Completion train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies in the SFPR. D.2 Suspend movement of Immediately irradiated fuel assemblies in the SFPR.

Farley Units 1 and 2 3.7.12-1 Amendment No. 161 (Unit 1)

Amendment No. 154 (Unit 2)

PRF 3.7.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Two PRF trains inoperable E.1 Suspend movement of Immediately during movement of irradiated fuel irradiated fuel assemblies assemblies in the SFPR.

in the SFPR.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 ----------------------------NOTE----------------------------------

Only required to be performed during movement of irradiated fuel assemblies in the SFPR.

Verify two PRF trains aligned to the SFPR. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.7.12.2 Operate each PRF train for 15 minutes in the 31 days applicable mode of operation (post LOCA and/or refueling accident).

SR 3.7.12.3 Perform required PRF filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.12.4 Verify each PRF train actuates and the normal spent 18 months fuel pool room ventilation system isolates on an actual or simulated actuation signal.

SR 3.7.12.5 Verify one PRF train can maintain a pressure 18 months on a

-0.125 inches water gauge with respect to adjacent STAGGERED areas during the post LOCA mode of operation at a TEST BASIS flow rate 5500 cfm.

SR 3.7.12.6 Verify one PRF train can maintain a slightly negative 18 months on a pressure with respect to adjacent areas during the STAGGERED fuel handling accident mode of operation at a flow TEST BASIS rate 5500 cfm.

Farley Units 1 and 2 3.7.12-2 Amendment No. 161 (Unit 1)

Amendment No. 154 (Unit 2)

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.

Farley Units 1 and 2 3.7.13-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Fuel Storage Pool Boron Concentration 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Fuel Storage Pool Boron Concentration LCO 3.7.14 The fuel storage pool boron concentration shall be 2000 ppm.

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool boron -------------------NOTE--------------------

concentration not within LCO 3.0.3 is not applicable.

limit. -----------------------------------------------

A.1 Suspend movement of fuel Immediately assemblies in the fuel storage pool.

AND A.2 Initiate action to restore Immediately fuel storage pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the fuel storage pool boron concentration is 7 days within limit.

Farley Units 1 and 2 3.7.14-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 in the spent fuel storage pool shall be within the Acceptable Burnup Domain of Figure 3.7.15-1 or 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 A.1 -------------NOTE-------------

LCO not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly to an acceptable storage location.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the initial enrichment Within 7 days and burnup of the fuel assembly is in accordance following the with Figure 3.7.15-1 or Specification 4.3.1.1. relocation or addition of fuel assemblies to the spent fuel storage pool.

Farley Units 1 and 2 3.7.15-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Spent Fuel Assembly Storage 3.7.15 Initial U-235 Enrichment (nominal w/o)

Figure 3.7.15-1 Fuel Assembly Burnup Limit Requirements For All Cell Storage Farley Units 1 and 2 3.7.15-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Secondary Specific Activity 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Secondary Specific Activity LCO 3.7.16 The specific activity of the secondary coolant shall be 0.10 µCi/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 3.7.16.1 Verify the specific activity of the secondary coolant is 31 days 0.10 µCi/gm DOSE EQUIVALENT I-131.

Farley Units 1 and 2 3.7.16-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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. Two diesel generator (DG) sets capable of supplying the onsite Class 1E power distribution subsystem(s); and

c. Automatic load sequencers for Train A and Train B.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. required 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 discovery of no offsite 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)

Farley Units 1 and 2 3.8.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status. AND 13 days from discovery of failure to meet LCO B. One DG set inoperable. ------------------NOTE-------------------

LCO 3.0.4 is not applicable when only one of the three DGs is inoperable.

B.1 Perform SR 3.8.1.1 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months the required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 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 set 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 set is not inoperable due to common cause failure.

OR (continued)

Farley Units 1 and 2 3.8.1-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3.2 Perform SR 3.8.1.6 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG set.

AND B.4 Restore DG set to 10 days OPERABLE status.

AND 13 days from discovery of failure to meet LCO C. Two required offsite C.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from circuits 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 required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months offsite circuit to OPERABLE status.

Farley Units 1 and 2 3.8.1-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One required offsite circuit -----------------NOTE-------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems Operating," when Condition D is One DG set inoperable. entered with no AC power source to any train.

D.1 Restore required offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status.

OR D.2 Restore DG set to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

E. Two DG sets inoperable. E.1 Restore one DG set to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if all three OPERABLE status. DGs are inoperable OR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months if DG 1-2A and DG 1(2)B are inoperable OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if DG 1C and DG 1(2)B are inoperable 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 C or E not met.

Farley Units 1 and 2 3.8.1-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. One automatic load G.1 Restore automatic load 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sequencer inoperable. sequencer to OPERABLE status.

H. Required Action and H.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, D, AND or G not met.

H.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months I. Three or more required AC I.1 Enter LCO 3.0.3. Immediately sources inoperable.

Farley Units 1 and 2 3.8.1-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 required offsite circuit.

SR 3.8.1.2 -----------------------------NOTES-------------------------------

1. Performance of SR 3.8.1.6 satisfies this SR.

2. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

3. 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 3.8.1.6 must be met.

Verify each DG starts from standby conditions and 31 days achieves steady state voltage 3740 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz.

Farley Units 1 and 2 3.8.1-6 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUREMENTS SURVEILLANCE FREQUENCY 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 3.8.1.6.

Verify each DG is synchronized and loaded and 31 days operates for 60 minutes at a load 2700 kW and 2850 kW for the 2850 kW DG and 3875 kW and 4075 kW for the 4075 kW DGs.

SR 3.8.1.4 Verify each day tank contains 900 gal of fuel oil for 31 days the 4075 kW DGs and 700 gal of fuel oil for the 2850 kW DG.

SR 3.8.1.5 Verify the fuel oil transfer system operates to transfer 31 days fuel oil from storage tank to the day tank.

SR 3.8.1.6 ------------------------------NOTE--------------------------------

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and 184 days achieves in 12 seconds, voltage 3952 V and frequency 60 Hz.

Farley Units 1 and 2 3.8.1-7 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.7 ------------------------------NOTE--------------------------------

This Surveillance shall not be performed in MODE 1 or 2.

Verify manual transfer of AC power sources from the 18 months normal offsite circuit to the alternate required offsite circuit.

SR 3.8.1.8 Verify each DG rejects a load greater than or equal to 18 months its associated single largest post-accident load, and:

a. Following load rejection, the speed is 75% of the difference between nominal speed and the overspeed trip setpoint; and

b. Following load rejection, the voltage is 3740 V and 4580 V.

Farley Units 1 and 2 3.8.1-8 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.9 -------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

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 12 seconds,

2. energizes auto-connected shutdown loads through automatic load sequencer,

3. maintains steady state voltage 3740 V and 4580 V,

4. maintains steady state frequency 58.8 Hz and 61.2 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for 5 minutes.

Farley Units 1 and 2 3.8.1-9 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.10 -------------------------------NOTE-------------------------------

All DG starts may be preceded by prelube period.

Verify on an actual or simulated Engineered Safety 18 months Feature (ESF) actuation signal each DG auto-starts from standby condition and:

a. In 12 seconds after auto-start and during tests, achieves voltage 3952 V;

b. In 12 seconds after auto-start and during tests, achieves frequency 60 Hz;

c. Operates for 5 minutes and maintains a steady state generator voltage and frequency of 3740 V and 4580 V and 58.8 Hz and 61.2 Hz;

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

SR 3.8.1.10.d and e shall not be performed in MODE 1 or 2.

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized from the offsite power system.

Farley Units 1 and 2 3.8.1-10 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.11 Verify each DG's automatic trips are bypassed on 18 months actual or simulated loss of voltage signal on the emergency bus and/or an actual or simulated ESF actuation signal except:

a. Engine overspeed;

b. Generator differential current; and

c. Low lube oil pressure.

SR 3.8.1.12 -------------------------------NOTE-------------------------------

Momentary transients below the minimum load specified do not invalidate this test.

Verify each DG operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: 18 months

a. For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 4353 for the 4075 kW DGs and 3100 kW for the 2850 kW DG; and

b. For the remaining hours of the test loaded 4075 kW for the 4075 kW DGs and 2850 kW for the 2850 kW DG.

Farley Units 1 and 2 3.8.1-11 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.13 -------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 10 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 4075 kW for the 4075 kW DGs and 2850 kW for the 2850 kW DG.

Momentary transients below the minimum load specified do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves, in 12 seconds, 18 months voltage 3952 V and frequency 60 Hz.

SR 3.8.1.14 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

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.

Farley Units 1 and 2 3.8.1-12 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.15 Verify, with a DG operating in test mode and 18 months connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by returning DG to ready-to-load operation.

SR 3.8.1.16 Verify interval between each sequenced load block is 18 months within +/- 10% of design interval or 0.5 seconds, whichever is greater, for each emergency load sequencer.

SR 3.8.1.17 -------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

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. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 12 seconds, (continued)

Farley Units 1 and 2 3.8.1-13 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.17 (continued)

2. energizes auto-connected emergency loads through load sequencer,

3. achieves steady state voltage 3740 V and 4580 V,

4. achieves steady state frequency 58.8 Hz and 61.2 Hz, and

5. supplies permanently connected and auto-connected emergency loads for 5 minutes.

SR 3.8.1.18 -------------------------------NOTE------------------------------

Testing of the shared Emergency Diesel Generator (EDG) set (EDG 1-2A or EDG 1C) on either unit may be used to satisfy this surveillance requirement for these EDGs for both units.

Verify each DG does not trip and voltage is 5 years maintained 4990 V and 3330 V during and following a load rejection of 1200 kW and 2400 kW.

SR 3.8.1.19 -------------------------------NOTE-----------------------------

All DG starts may be preceded by an engine prelube period.

Verify when started simultaneously from standby 10 years condition, each DG achieves, in 12 seconds, voltage 3952 V and frequency 60 Hz.

Farley Units 1 and 2 3.8.1-14 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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. One diesel generator (DG) 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 Immediately required feature(s) with no offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND (continued)

Farley Units 1 and 2 3.8.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Immediately suspend 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 Immediately suspend operations involving positive reactivity additions.

AND B.4 Initiate action to restore Immediately required DG to OPERABLE status.

Farley Units 1 and 2 3.8.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

AC Sources Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -------------------------------NOTE-------------------------------

The following SRs are applicable but are not required to be performed: SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.14, and SR 3.8.1.18.

For AC sources required to be OPERABLE, the SRs In accordance with of Specification 3.8.1, "AC Sources Operating," applicable SRs except SR 3.8.1.3, SR 3.8.1.7, SR 3.8.1.10, SR 3.8.1.15, SR 3.8.1.16, SR 3.8.1.17, and SR 3.8.1.19, are applicable. The following SRs are applicable and required to be performed: SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.4, SR 3.8.1.5, and SR 3.8.1.6.

Farley Units 1 and 2 3.8.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 a A.1 Restore fuel oil level to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months useable fuel level within limits.

< 25,000 gal and

> 21,000 gal in the storage tank.

B. One or more DGs with B.1 Restore lube oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months lube oil inventory < 238 gal inventory to within limits.

and > 204 gal (for DG 1-2A, 1B, and 2B) or < 167 gal and > 143 gal (for DG 1C).

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.

Farley Units 1 and 2 3.8.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. One or more DGs with new D.1 Restore stored fuel oil 30 days fuel oil properties not properties to within within limits. limits.

E. One or more DGs with the E.1 Restore at least one 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months required starting air starting air receiver receiver pressure < 350 pressure per affected psig and 150 psig (for DG to 350 psig (for DG 1-2A, 1B, and 2B), or DG 1-2A, 1B, and 2B) or

< 200 psig and 90 psig 200 psig (for DG 1C).

(for DG 1C).

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 fuel oil storage tank contains 31 days 25,000 gal of useable fuel.

Farley Units 1 and 2 3.8.3-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.2 Verify lubricating oil inventory is 238 gal (for 31 days DG 1-2A, 1B, and 2B) or 167 gal (for DG 1C).

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 has at least one air start receiver with 31 days a pressure 350 psig (for DG 1-2A, 1B, and 2B) and 200 psig (for DG 1C).

Farley Units 1 and 2 3.8.3-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

DC Sources Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources Operating LCO 3.8.4 The Train A and Train B Auxiliary Building and Service Water Intake Structure (SWIS) DC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Auxiliary Building DC A.1 Restore the Auxiliary 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power subsystem Building DC electrical inoperable. power subsystem to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for 1B OPERABLE status. Auxiliary Building DC electrical power subsystem inoperable due to inoperable battery for cycle 19 only B. One Auxiliary Building DC B.1 Restore the battery 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power subsystem connection resistance to with battery connection within limit.

resistance not within limit.

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 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. One required SWIS DC D.1 Restore the battery 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months electrical power connection resistance to subsystem battery within the limit.

connection resistance not within limit.

E. One required SWIS DC E.1 Declare the associated Immediately electrical power Service Water System subsystem inoperable. train inoperable.

OR Required Action and associated Completion Time of Condition D not met.

Farley Units 1 and 2 3.8.4-1 Amendment No. 164 (Unit 1)

Amendment No. 137 (Unit 2)

DC Sources Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 127.8 V on float 7 days charge.

SR 3.8.4.2 Verify no visible corrosion at battery terminals and 92 days connectors.

OR Verify post-to-post battery connection resistance of each cell-to-cell and terminal connection is 150 microhms for the Auxiliary Building batteries and 1500 microhms for the SWIS batteries.

SR 3.8.4.3 Verify battery cells, cell plates, and racks show no 18 months visual indication of physical damage or abnormal deterioration.

SR 3.8.4.4 Remove visible terminal corrosion, verify battery 18 months cell- to-cell and terminal connections are coated with anti-corrosion material.

SR 3.8.4.5 Verify post-to-post battery connection resistance of 18 months each cell-to-cell and terminal connection is 150 microhms for the Auxiliary Building batteries and 1500 microhms for the SWIS batteries.

Farley Units 1 and 2 3.8.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

DC Sources Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.6 -------------------------------NOTE-------------------------------

This Surveillance may be performed in MODE 1, 2, 3, 4, 5, or 6 provided spare or redundant charger(s) placed in service are within surveillance frequency to maintain DC subsystem(s) OPERABLE.

Verify each required Auxiliary Building battery 18 months charger supplies 536 amps at 125 V for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and each required SWIS battery charger supplies 3 amps at 125 V for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SR 3.8.4.7 -----------------------------NOTES-------------------------------

1. The performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 once per 60 months.

2. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test at any time.

3. This Surveillance shall not be performed for the Auxiliary Building batteries in MODE 1, 2, 3, or 4.

Verify battery capacity is adequate to supply, and 18 months maintain in OPERABLE status, the required emergency loads for the design load profile described in the Final Safety Analysis Report, Section 8.3.2, by subjecting the battery to a service test.

Farley Units 1 and 2 3.8.4-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

DC Sources Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.8 -------------------------------NOTE-------------------------------

This Surveillance shall not be performed for the Auxiliary Building batteries in MODE 1, 2, 3, or 4.

Verify battery capacity is 80% of the manufacturer's 60 months rating when subjected to a performance discharge test or a modified performance discharge test. AND 18 months when battery shows degradation or has reached 85% of expected life or 17 years, whichever comes first Farley Units 1 and 2 3.8.4-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

DC Sources Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5 DC electrical power subsystem(s) shall be OPERABLE to support the DC 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 DC A.1 Declare affected Immediately electrical power required feature(s) subsystems 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 Immediately suspend operations involving positive reactivity additions.

AND (continued)

Farley Units 1 and 2 3.8.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

DC Sources Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 -------------------------------NOTE-------------------------------

The following SRs are applicable but are not required to be performed: SR 3.8.4.6, SR 3.8.4.7, and SR 3.8.4.8.

For DC sources required to be OPERABLE, the In accordance with following SRs are applicable: applicable SRs SR 3.8.4.1 SR 3.8.4.4 SR 3.8.4.7 SR 3.8.4.2 SR 3.8.4.5 SR 3.8.4.8.

SR 3.8.4.3 SR 3.8.4.6 Farley Units 1 and 2 3.8.5-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for Train A and Train B Auxiliary Building and Service Water Intake Structure (SWIS) batteries shall be within the limits of Table 3.8.6-1.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Verify pilot cells 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months batteries with one or more electrolyte level and float battery cell parameters not voltage meet within Category A or B Table 3.8.6-1 limits. Category C limits.

AND A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

Farley Units 1 and 2 3.8.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Battery Cell Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion Time battery inoperable.

of Condition A not met.

OR One or more required batteries with average electrolyte temperature of the representative cells

< 60°F for the Auxiliary Building batteries or < 35°F for the SWIS batteries.

OR One or more required batteries with one or more battery cell parameters not within Category C values.

OR

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

Battery terminal voltage of 127.8 volts as measured by SR 3.8.4.1 is equivalent to average cell float voltage of 2.13 volts per cell.

One or more required batteries with the average cell float voltage 2.13 volts.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet Table 3.8.6-1 7 days Category A limits.

Farley Units 1 and 2 3.8.6-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify battery cell parameters meet Table 3.8.6-1 92 days Category B limits.

AND Once within 7 days after a battery discharge

< 110 V AND Once within 7 days after a battery overcharge

> 150 V SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is 60°F for the Auxiliary Building batteries and 35°F for the SWIS batteries.

Farley Units 1 and 2 3.8.6-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameters Requirements PARAMETER CATEGORY A: CATEGORY B: CATEGORY C:

LIMITS FOR EACH LIMITS FOR EACH ALLOWABLE DESIGNATED CONNECTED CELL LIMITS FOR EACH PILOT CELL CONNECTED CELL Electrolyte Level > Minimum level > Minimum level Above top of plates, indication mark, and indication mark, and and not overflowing 1/4 inch above 1/4 inch above maximum level maximum level indication mark(a) indication mark(a)

Float Voltage 2.08 V 2.08 V > 2.02 V Specific Gravity(b) 1.195(c) 1.190 If a cell is < 1.190, then it shall not have AND decreased more than 0.080 from the Average of all previous 92 day test.

connected cells

> 1.195 AND Average of all connected cells 1.190 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature and level. Level correction is not required, however, when battery charging is < 2 amps when on float charge.

(c) Or battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits.

Farley Units 1 and 2 3.8.6-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Inverters Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters Operating LCO 3.8.7 The required Train A and Train B inverters shall be OPERABLE.

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

Two inverters may be disconnected from their associated DC bus for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform an equalizing charge on their associated common battery, provided:

a. The associated AC vital buses are energized from their Class 1E constant voltage source transformers; and

b. All other AC vital buses are energized from their associated OPERABLE inverters.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 ------------NOTE------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - Operating" with any vital bus de-energized.

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

Farley Units 1 and 2 3.8.7-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Inverters Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 3.8.7.1 Verify correct inverter voltage, frequency, and 7 days alignment to required AC vital buses.

Farley Units 1 and 2 3.8.7-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 Immediately inverters inoperable. required feature(s) 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 Immediately suspend operations involving positive reactivity additions.

AND (continued)

Farley Units 1 and 2 3.8.8-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Inverters Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate action to restore Immediately required inverters to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and 7 days alignments to required AC vital buses.

Farley Units 1 and 2 3.8.8-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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, DC, and 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(s) 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 B.1 Restore AC vital bus 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months buses inoperable. subsystem(s) 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 Auxiliary Building DC C.1 Restore Auxiliary 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power distribution Building DC electrical subsystem inoperable. power distribution AND subsystem to 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 Farley Units 1 and 2 3.8.9-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Distribution Systems Operating 3.8.9 ACTIONS 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, B, or AND C 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 Service Water Intake E.1 Declare the associated Immediately Structure (SWIS) DC Service Water train electrical power distribution inoperable.

subsystem inoperable.

F. Two trains with inoperable F.1 Enter LCO 3.0.3. Immediately 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, DC, and AC vital bus electrical power distribution subsystems.

Farley Units 1 and 2 3.8.9-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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, 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 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 Immediately A.2.3 Initiate action to suspend operations involving positive reactivity additions.

AND (continued)

Farley Units 1 and 2 3.8.10-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Distribution Systems Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate actions to restore Immediately required AC, 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, DC, and AC vital bus electrical power distribution subsystems.

Farley Units 1 and 2 3.8.10-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 not A.1 Suspend CORE Immediately 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.

Farley Units 1 and 2 3.9.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors and one channel of audible count rate shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One source range neutron A.1 Suspend CORE Immediately flux monitor inoperable. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

B. Two source range neutron B.1 Initiate action to restore Immediately flux monitors inoperable. one source range neutron flux monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. No audible count rate. C.1. Initiate action to isolate Immediately unborated water sources.

Farley Units 1 and 2 3.9.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 ------------------------------NOTE--------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 3.9.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:

a. The equipment hatch is capable of being closed and held in place by four bolts;

b. One door in each air lock closed; and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend CORE Immediately penetrations not in ALTERATIONS.

required status.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

Farley Units 1 and 2 3.9.3-1 Amendment No. 165 (Unit 1)

Amendment No. 157 (Unit 2)

Containment Penetrations 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required containment penetration is in the 7 days required status.

SR 3.9.3.2 Verify each required containment purge and exhaust 18 months valve actuates to the isolation position on an actual or simulated actuation signal.

SR 3.9.3.3 --------------------------------NOTE----------------------------- 7 days Only required for an open equipment hatch.

Verify the capability to install the equipment hatch.

Farley Units 1 and 2 3.9.3-2 Amendment No. 165 (Unit 1)

Amendment No. 157 (Unit 2)

RHR and Coolant Circulation High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation High Water Level LCO 3.9.4 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 A.1 Suspend operations Immediately not 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)

Farley Units 1 and 2 3.9.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RHR and Coolant Circulation High Water Level 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Close equipment hatch 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and secure with four bolts.

AND A.5 Close one door in each 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months air lock.

AND A.6.1 Close each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR A.6.2 Verify each penetration is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months capable of being closed by an OPERABLE Containment Purge and exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 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 3000 gpm.

Farley Units 1 and 2 3.9.4-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RHR and Coolant Circulation Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation Low Water Level LCO 3.9.5 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

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

One RHR loop may be inoperable and no RHR loop may be in the decay heat removal mode of operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance testing.

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.

OR A.2 Initiate action to Immediately establish 23 ft of water above the top of reactor vessel flange.

B. No RHR loop in operation. B.1 Suspend operations Immediately involving a reduction in reactor coolant boron concentration.

AND (continued)

Farley Units 1 and 2 3.9.5-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RHR and Coolant Circulation Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Initiate action to restore Immediately one RHR loop to operation.

AND B.3 Close equipment hatch 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and secure with four bolts.

AND B.4 Close one door in each 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months air lock.

AND B.5.1 Close each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR B.5.2 Verify each penetration is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

Farley Units 1 and 2 3.9.5-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RHR and Coolant Circulation Low Water Level 3.9.5 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 3000 gpm.

SR 3.9.5.2 Verify correct breaker alignment and indicated power 7 days available to the required RHR pump that is not in operation.

Farley Units 1 and 2 3.9.5-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Refueling Cavity Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Cavity Water Level LCO 3.9.6 Refueling cavity water level shall be maintained 23 ft above the top of reactor vessel flange.

APPLICABILITY: During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water level A.1 Suspend CORE Immediately not within limit. ALTERATIONS.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 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.

Farley Units 1 and 2 3.9.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The site is located in southeast Alabama on the west side of the Chattahoochee River about 6 miles north of the intersection of U.S. Highway No. 84 and State Highway No. 95. It is in the northeastern section of Houston County, Alabama, and about 180 miles south-southwest of Atlanta, Georgia.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 157 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy, zircaloy-4, ZIRLO, or stainless steel filler rods for fuel rods, in accordance with NRC-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 48 control rod assemblies. The control material shall be silver, indium, and cadmium as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum nominal U-235 enrichment of 5.0 weight percent; (continued)

Farley Units 1 and 2 4.0-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.1 (continued)

b. keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 4.3.2.7.2 of the FSAR;

c. keff 0.95 if fully flooded with water borated to 400 ppm, which includes an allowance for uncertainties and biases as described in Section 4.3.2.7.2 of the FSAR;

d. A nominal 10.75 inch center to center distance between fuel assemblies placed in the fuel storage racks;

e. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the "acceptable range" of Figure 3.7.15-1 may be allowed unrestricted storage in the spent fuel storage rack(s) (also shown as the All Cell Storage configuration in Figure 4.3-2);

f. New or partially spent fuel assemblies with a combination of discharge burnup and initial enrichment in the "unacceptable range" of Figure 3.7.15-1 will be stored in compliance with the NRC approved Figures 4.3-1 through 4.3-5. The high enrichment fuel assemblies shown in the Burned/Fresh Storage configuration in Figure 4.3-2, with maximum nominal enrichments > 3.9 weight percent U-235, shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly K 1.455 at 68°F is maintained; and

g. Unit 1 only Damaged fuel assemblies F02, F05, F06, F15, F17, F18, F19, F20, F30, F31, and F32 shall be stored in accordance with Figure 4.3-6.

4.3.1.2 The new fuel pit storage racks are designed and shall be maintained with:

a. Fuel assemblies with Standard Fuel Assembly fuel rod diameters having a maximum nominal U-235 enrichment of 4.25 weight percent; (continued)

Farley Units 1 and 2 4.0-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.2 (continued)

b. Fuel assemblies with Optimized Fuel Assembly fuel rod diameters having a maximum nominal U-235 enrichment of 5.0 weight percent. Fuel assemblies with Optimized Fuel Assembly fuel rod diameters having a maximum nominal U-235 enrichment > 3.9 weight percent shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly K 1.455 at 68°F is maintained;

c. keff 0.95 if fully flooded with unborated water;

d. keff 0.98 if moderated by aqueous foam; and

e. 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 149 ft.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.

Farley Units 1 and 2 4.0-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 45000 40000 35000 ACCEPTABLE 30000 Fuel Assembly Burnup (MWD/MTU) 25000 20000 15000 UNACCEPTABLE 10000 5000 0

1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (nominal w/o)

Figure 4.3-1 Fuel Assembly Burnup Limit Requirements for Low Enrichment (L)

Assembly of the Burned/Fresh Checkerboard Storage (see Figure 4.3-2)

Farley Units 1 and 2 4.0-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 A A A A All Cell Storage C Empty H L Empty C L L 2-out-of-4 Storage Burned/Fresh Storage Note:

A = All Cell Enrichment (Figure 3.7.15-1)

C = 2-out-of-4 Enrichment (No restriction on enrichment or burnup)

L = Low Enrichment of Burned/Fresh (Figure 4.3-1)

H = High Enrichment of Burned/Fresh (See section 4.3.1.1.f for IFBA requirement)

Empty = Empty Cell Figure 4.3-2 Spent Fuel Storage Configurations Farley Units 1 and 2 4.0-5 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 A A A A A A A A A A A A Interface A A A A A A L L L A A A L H L A A A L L L A A A Note:

A = All Cell Enrichment L = Low Enrichment of Burned/Fresh H = High Enrichment of Burned/Fresh Boundary Between All Cell Storage and Burned/Fresh Storage Note:

1. A row of empty cells can be used at the interface to separate the configurations.

2. It is acceptable to replace an assembly with an empty cell.

Figure 4.3-3 Interface Requirements Farley Units 1 and 2 4.0-6 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 A A A A A A A A A A A A Interface A Empty A A A A Empty C Empty A A A C Empty C Empty A A Empty C Empty A A A Note:

A = All Cell Enrichment C = 2-out-of-4 Enrichment Empty = Empty Cell Boundary Between All Cell Storage and 2-out-of-4 Storage Note:

1. A row of empty cells can be used at the interface to separate the configurations.

2. It is acceptable to replace an assembly with an empty cell.

Figure 4.3-4 Interface Requirements Farley Units 1 and 2 4.0-7 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 Empty C Empty C Empty C C Empty C Empty C Empty Interface Empty C Empty C Empty C H Empty H Empty C Empty L L Empty C Empty C H L H Empty C Empty Note:

C = 2-out-of-4 Enrichment L = Low Enrichment of Burned/Fresh H = High Enrichment of Burned/Fresh Empty = Empty Cell Boundary Between 2-out-of-4 Storage and Burned/Fresh Storage Note:

1. A row of empty cells can be used at the interface to separate the configurations.

2. It is acceptable to replace an assembly with an empty cell.

Figure 4.3-5 Interface Requirements Farley Units 1 and 2 4.0-8 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Design Features 4.0 F31 Empty F30 F06 F18 F17 F19 F02 F15 F20 F05 F32 Water Note: All Assemblies are 3.0 w/o 235U nominal enrichment Figure 4.3-6 Damaged Fuel Assembly Configuration (Unit 1 Only)

Farley Units 1 and 2 4.0-9 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The General Manager - Nuclear Plant shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The General Manager - Nuclear Plant 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 A Senior Reactor Operator (SRO) shall be responsible for the control room command function. During any absence of the responsible SRO from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active SRO license shall be designated to assume the control room command function.

During any absence of the responsible SRO 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. A single individual may be responsible for the control room command function for both units.

Farley Units 1 and 2 5.1-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

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 FSAR;

b. The General Manager - Nuclear Plant 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 Vice-President shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. With both units in MODES 5 or 6 or defueled, a total of three non-licensed operators are required.

(continued)

Farley Units 1 and 2 5.2-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room. A single SRO may fill this position for both units.

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.g 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 absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

d. A Health Physics 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.

e. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g., licensed SROs, licensed ROs, health physicists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time;

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period, all excluding shift turnover time; (continued)

Farley Units 1 and 2 5.2-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time;

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines for the minimum shift compliment defined in Specifications 5.2.2.a and b and health physics technicians shall be reviewed and approved by the General Manager - Nuclear Plant, his designee, or by higher levels of management.

Any deviation from the above guidelines for key maintenance personnel shall be reviewed and approved by the Maintenance Manager or his designee.

f. The Assistant General Manager - Plant Operations or the Operations Manager shall hold an SRO license.

g. The Shift Technical Advisor (STA) shall provide advisory technical support to the responsible SRO in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The same individual may fill this position for both units.

Farley Units 1 and 2 5.2-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in 10 CFR 55, except for (1) the senior individual in charge of Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. Personnel who complete an accredited program which has been endorsed by the NRC shall meet the requirements of the accredited program in lieu of the above.

Farley Units 1 and 2 5.3-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 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. Quality assurance for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, February 1979;

c. Fire Protection Program implementation; and

d. All programs specified in Specification 5.5.

Farley Units 1 and 2 5.4-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose 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 Specification 5.6.2 and Specification 5.6.3.

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), and

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 General Manager -

Nuclear Plant; and

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.

Farley Units 1 and 2 5.5-1 Amendment No. 160 (Unit 1)

Amendment No. 152 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 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 recirculation portions of the Containment Spray, Safety Injection, and Chemical and Volume Control Systems, the Waste Gas System, the Reactor Coolant Sampling System, the Residual Heat Removal System, and the Containment Atmosphere Sampling System. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system with the exception of the waste gas system and the containment atmosphere sampling system which are "snoop" tested at refueling cycle intervals or less.

5.5.3 Not Used 5.5.4 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; (continued)

Farley Units 1 and 2 5.5-2 Amendment No. 156 (Unit 1)

Amendment No. 148 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration stated in 10 CFR 20, Appendix B (to paragraphs 20.1001-20.2401),

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 and projected 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;

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;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at and beyond the site boundary as follows:

1. For noble gases: Less than or equal to a dose rate of 500 mrem/year to the total body and less than or equal to a dose rate of 3000 mrem/year to the skin, and

2. For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/year 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; (continued)

Farley Units 1 and 2 5.5-3 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

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 due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Table 5.2-2a, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 2, 1976.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel at least once per 10 years by conducting either:

a. An in-place ultrasonic examination over the volume from the innner bore of the flywheel to the circle of one-half the outer radius: or

b. A surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program.

Farley Units 1 and 2 5.5-4 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Inservice Testing Program 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 specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities 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 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 Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

5.5.9 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 provisions:

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 (continued)

Farley Units 1 and 2 5.5-5 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) inspection results or by other means, prior to the plugging 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 inservice SG tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby and cooldown and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 (3P) 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.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a 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. Accident induced leakage is not to exceed 1 gpm total for all three SGs.

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, RCS Operational LEAKAGE.

(continued)

Farley Units 1 and 2 5.5-6 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator SG Program (continued)

c. Provisions for SG tube 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.

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 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. An assessment of degradation 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 replacement.

2. Inspect 100% of the tubes at sequential periods of 144, 108, 72, and, thereafter, 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. In addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall operate for more than 72 effective full power months or three refueling outages (whichever is less) without being inspected.

3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). 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)

Farley Units 1 and 2 5.5-7 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation. 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 condenser hotwells for evidence of condenser in leakage;

d. Procedures for the recording and management of data;

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.

5.5.11 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 Regulatory Guide 1.52, Revision 3, and in accordance with ASME N510-1989. The FNP Final Safety Analysis Report identifies the relevant surveillance testing requirements.

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 < 0.5% when tested in accordance with ASME N510-1989 at the system flowrate specified below.

ESF Ventilation System Flowrate (CFM)

CREFS Recirculation 2,000 + 10%

CREFS Filtration 1,000 + 10%

CREFS Pressurization 300 + 25% to - 10%

PRF Post LOCA Mode 5,000 + 10%

(continued)

Farley Units 1 and 2 5.5-8 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 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 < 0.5% when tested in accordance with ASME N510-1989 at the system flowrate specified below.

ESF Ventilation System Flowrate (CFM)

CREFS Recirculation 2,000 + 10%

CREFS Filtration 1,000 + 10%

CREFS Pressurization 300 + 25% to - 10%

PRF Post LOCA Mode 5,000 + 10%

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in ASME N510-1989, 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.

ESF Ventilation System Penetration RH CREFS Recirculation 2.5% 70%

CREFS Filtration 2.5% 70%

CREFS Pressurization 0.5% 70%

PRF Post LOCA Mode 5% 95%

NOTE: CREFS Pressurization methyl iodide penetration limit is based on a 6-inch bed depth.

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is less than the value specified below when tested in accordance with ASME N510-1989 at the system flowrate specified below.

Delta P Flowrate ESF Ventilation System (in. water gauge) (CFM)

CREFS Recirculation 2.3 2,000 + 10%

CREFS Filtration 2.9 1,000 + 10%

CREFS Pressurization 2.2 300 + 25% to - 10%

PRF Post LOCA Mode 2.6 5,000 + 10%

(continued)

Farley Units 1 and 2 5.5-9 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)

e. Demonstrate that the heaters for the CREFS Pressurization System dissipate the value specified below when tested in accordance with ASME N510-1989.

ESF Ventilation System Wattage (kW)

CREFS Pressurization 2.5 + 0.5 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas System, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Waste Gas System and a surveillance program to ensure the limits are maintained.

Such limits shall be appropriate to the system's design;

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 10 curies.

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.

(continued)

Farley Units 1 and 2 5.5-10 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 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 emergency diesel generator 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 kinematic viscosity within limits for ASTM 2D fuel oil, and

3. a clear and bright appearance.

b. Fuel oil stored in the emergency diesel generator storage tanks is within limits by verifying that a sample of diesel fuel oil from the storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water, and sediment every 92 days.

c. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program surveillance test frequencies.

5.5.14 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. a change in the TS incorporated in the license; or

2. a change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

(continued)

Farley Units 1 and 2 5.5-11 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Technical Specifications (TS) Bases Control Program (continued)

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 5.5.14b above 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).

5.5.15 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.

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 (continued)

Farley Units 1 and 2 5.5-12 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP) (continued)

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.

5.5.16 Main Steamline Inspection Program The three main steamlines from the rigid anchor points of the containment penetrations downstream to and including the main steam header shall be inspected. The extent of the inservice examinations completed during each inspection interval (IWA 2400, ASME Code, 1974 Edition,Section XI) shall provide 100 percent volumetric examination of circumferential and longitudinal pipe welds to the extent practical. The areas subject to examination are those defined in accordance with examination category C-G for Class 2 piping welds in Table IWC-2520.

5.5.17 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of 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 1.163, Performance-Based Containment Leak-Test Program, dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, Industry Guidelines for Implementing Performance-Based Option of 10 CFR 50, Appendix J:

Section 9.2.3: The next Type A test, after the March 1994 test for Unit 1 and the March 1995 test for Unit 2, shall be performed within 15 years. This is a one time exception.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 43.8 psig.

The maximum allowable containment leakage rate, La, at Pa, is 0.15% of containment air weight per day.

(continued)

Farley Units 1 and 2 5.5-13 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Containment Leakage Rate Testing Program (continued)

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criterion is 1.0 La. During plant startup following testing in accordance with this program, the leakage rate acceptance criteria are 0.60 La for the combined Type B and 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 10 psig.

c. During plant startup following testing in accordance with this program, the leakage rate acceptance criterion for each containment purge penetration flowpath is 0.05 La.

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.

5.5.18 Control Room Integrity Program (CRIP)

A Control Room Integrity Program (CRIP) shall be established and implemented to ensure that the control room integrity is maintained such that a radiological event, hazardous chemicals, or a fire challenge (e.g., fire byproducts, halon, etc.)

will not prevent the control room operators from controlling the reactor during normal or accident conditions. The program shall require testing as outlined below. Testing should be performed when changes are made to structures, systems and components which could impact Control Room Impact (CRE) integrity. These structures, systems and components may be internal or external to the CRE. Testing should also be conducted following a modification or a repair that could affect CRE inleakage. Testing should also be performed if the conditions associated with a particular challenge result in a change in operating mode, system alignment or system response that could result in a new limiting condition. Testing should be commensurate with the type and degree of modification or repair. Testing should be conducted in the alignment that results in the greatest consequence to the operators.

(continued)

Farley Units 1 and 2 5.5-14 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Integrity Program (CRIP) (continued)

A CRIP shall be established to implement the following:

a. Demonstrate, using Regulatory Guide (RG) 1.197 and ASTM E741, that CRE inleakage is less than the below values. The values listed below do not include 10 cfm assumed in accident analysis for ingress / egress.

i) 43 cfm when the control room ventilation systems are aligned in the emergency recirculation mode of operation, ii) 600 cfm when the control room ventilation systems are aligned in the isolation mode of operation, and iii) 2,340 cfm when the control room ventilation systems are aligned in the normal mode of operation;

b. Demonstrate that the leakage characteristics of the CRE will not result in simultaneous loss of reactor control capability from the control room and the hot shutdown panels;

c. Maintain a CRE configuration control and a design and licensing bases control program and a preventative maintenance program. As a minimum, the CRE configuration control program will determine whether the i) CRE differential pressure relative to adjacent areas and ii) the control room ventilation system flow rates, as determined in accordance with ASME N510-1989 or ASTM E2029-99, are consistent with the values measured at the time the ASTM E741 test was performed. If item i or ii has changed, determine how this change has affected the inleakage characteristics of the CRE. If there has been degradation in the inleakage characteristics of the CRE since the E741 test, then a determination should be made whether the licensing basis analyses remain valid. If the licensing basis analyses remain valid, the CRE remains OPERABLE.

d. Test the CRE in accordance with the testing methods and at the frequencies specified in RG 1.197, Revision 0, May 2003.

The provisions of SR 3.0.2 are applicable to the control room inleakage testing frequencies.

Farley Units 1 and 2 5.5-15 Amendment No. 166 (Unit 1)

Amendment No. 158 (Unit 2)

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted.

5.6.2 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.

(continued)

Farley Units 1 and 2 5.6-1 Amendment No. 168 (Unit 1)

Amendment No. 160 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 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 in 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 Part 50, Appendix I, Section IV.B.1.

5.6.4 Deleted.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Reactor Core Safety Limits for THERMAL POWER, Reactor Coolant System highest loop average temperature and pressurizer pressure for Safety Limit 2.1.1,

2. SHUTDOWN MARGIN limit for MODES 2 (with keff < 1), 3, 4, and 5 for LCO 3.1.1,

3. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm and 100 ppm surveillance limits for LCO 3.1.3, (continued)

Farley Units 1 and 2 5.6-2 Amendment No. 168 (Unit 1)

Amendment No. 160 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. Shutdown Bank Insertion Limits for LCO 3.1.5,

5. Control Bank Insertion Limit for LCO 3.1.6,

6. Heat Flux Hot Channel Factor FQRTP limits, K(Z) figure, W(Z) values, and FQ(Z) Penalty Factors for LCO 3.2.1,

7. Nuclear Enthalpy Rise Hot Channel Factor limits, FHRTP, and Power Factor Multiplier, PFH, for LCO 3.2.2.

8. Axial Flux Limits for LCO 3.2.3,

9. Reactor Trip System Instrumentation Overtemperature T (OTT) and Overpower T (OPT) setpoint parameter values for Table 3.3.1-1,

10. Reactor Coolant System pressure, temperature, and flow in LCO 3.4.1,

11. Refueling Operations Boron Concentration for LCO 3.9.1.

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:

1. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985 (W Proprietary).

(Methodology for LCOs 3.1.1 - SHUTDOWN MARGIN, 3.1.3 -

Moderator Temperature Coefficient, 3.1.5 - Shutdown Bank Insertion Limit, 3.1.6 - Control Bank Insertion Limits, 3.2.3 - Axial Flux Difference, 3.2.1 - Heat Flux Hot Channel Factor, 3.2.2 -

Nuclear Enthalpy Rise Hot Channel Factor and 3.9.1 - Boron Concentration)

2. WCAP-10216-P-A, Rev.1A, Relaxation of Constant Axial Offset Control / FQ Surveillance Technical Specification, February 1994 (W Proprietary).

(Methodology for LCOs 3.2.3 - Axial Flux Difference and 3.2.1 -

Heat Flux Hot Channel Factor.)

(continued)

Farley Units 1 and 2 5.6-3 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 3a. WCAP-12945-P-A, Volume 1, Revision 2, and Volumes 2 through 5, Revision 1, Code Qualification Document for Best Estimate LOCA Analysis, March 1998 (W Proprietary).

3b. WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995 (W Proprietary).

(Methodology for LCO 3.2.1 - Heat Flux Hot Channel Factor and LCO 3.4.1-RCS Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)

4. WCAP-8745-P-A, "Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions," September 1986 (Westinghouse Proprietary)

(Methodology for Overpower T and Thermal Overtemperature T Trip Functions)

5. WCAP-14750-P-A Revision 1, "RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop PWRs. (Westinghouse Proprietary)

(Methodology for minimum RCS flow determination using the elbow tap measurement.)

6. WCAP-11596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Methodology for LCO 3.9.1 - Boron Concentration.)

7. WCAP-11397-P-A "Revised Thermal Design Procedure," April 1989 (Methodology for LCO 2.1.1-Reactor Core Safety Limits, LCO 3.4.1-RCS Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)

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.

(continued)

Farley Units 1 and 2 5.6-4 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. The reactor coolant system pressure and temperature limits, including heatup and cooldown rates, shall be established and documented in the PTLR for LCO 3.4.3.

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC letters dated March 31, 1998 and April 3, 1998.

c. The PTLR shall be provided to the NRC upon issuance for each reactor fluence period and for any revision or supplement thereto.

5.6.7 EDG Failure Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures shall be reported within 30 days.

Reports on EDG failures shall include a description of the failures, underlying causes, and corrective actions taken per the Emergency Diesel Generator Reliability Monitoring Program.

5.6.8 PAM Report When a report is required by Condition B or G 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.

5.6.9 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance (continued)

Farley Units 1 and 2 5.6-5 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.9 Tendon Surveillance Report (continued)

Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

5.6.10 Steam Generator (SG) 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 5.5.9, 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 during the inspection outage for each active degradation mechanism,

f. Total number and percentage of tubes plugged to date, and

g. The results of condition monitoring, including the results of tube pulls and in-situ testing.

5.6.11 Alternate AC (AAC) Source Out of Service Report The NRC shall be notified if the AAC source is out of service for greater than 10 days.

Farley Units 1 and 2 5.6-6 Amendment No. 163 (Unit 1)

Amendment No. 156 (Unit 2)

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem/hr but < 1000 mrem/hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics personnel) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the health physics supervision in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas accessible to personnel with radiation levels, as measured at 30 cm from the radiation source or from any surface that the radiation penetrates, such that a major portion of the body could receive in one hour a dose greater than 1000 mrem, shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Shift Foreman on duty or health physics supervision. Doors shall remain locked (continued)

Farley Units 1 and 2 5.7-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued) except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.7.3 For individual high radiation areas with radiation levels, as measured at 30 cm from the radiation source or from any surface that the radiation penetrates, such that a major portion of the body could receive in one hour a dose greater than 1000 mrem, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

Farley Units 1 and 2 5.7-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

ML051440298

Text

3.4.7 APPLICABILITY

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