ML24191A320

Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Table of Contents

ML24191A320
Person / Time
Site:	Callaway
Issue date:	05/06/2024
From:	Ameren Missouri, Union Electric Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML24191A265	List: ML24191A194 ML24191A195 ML24191A196 ML24191A198 ML24191A199 ML24191A200 ML24191A201 ML24191A202 ML24191A203 ML24191A204 ML24191A205 ML24191A206 ML24191A207 ML24191A209 ML24191A210 ML24191A211 ML24191A212 ML24191A213 ML24191A214 ML24191A215 ML24191A216 ML24191A217 ML24191A218 ML24191A219 ML24191A220 ML24191A221 ML24191A222 ML24191A223 ML24191A224 ML24191A225 ML24191A226 ML24191A227 ML24191A228 ML24191A229 ML24191A230 ML24191A231 ML24191A232 ML24191A233 ML24191A234 ML24191A235 ML24191A236 ML24191A273 ML24191A274 ML24191A275 ML24191A276 ML24191A277 ML24191A278 ML24191A279 ... further results
References
ULNRC-06877
Download: ML24191A320 (1)

Text

CALLAWAY PLANT 1

Amendment 202 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....................3.0-4 3.1 REACTIVITY CONTROL SYSTEMS.....................................................3.1-1 3.1.1 SHUTDOWN MARGIN (SDM)........................................................3.1-1 3.1.2 Core Reactivity...............................................................................3.1-2 3.1.3 Moderator Temperature Coefficient (MTC)......................................3.1-4 3.1.4 Rod Group Alignment Limits............................................................3.1-7 3.1.5 Shutdown Bank Insertion Limits.....................................................3.1-11 3.1.6 Control Bank Insertion Limits...........................................................3.1-13 3.1.7 Rod Position Indication....................................................................3.1-16 3.1.8 PHYSICS TESTS Exceptions - MODE 2........................................3.1-19 3.1.9 RCS Boron Limitations < 500°F.......................................................3.1-22 3.2 POWER DISTRIBUTION LIMITS.........................................................3.2-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))(FQ Methodology)................3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( ).................................3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)..................................................3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR)...................................3.2-10 3.3 INSTRUMENTATION............................................................................3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation...................................3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation..........................................................................3.3-27 3.3.3 Post Accident Monitoring (PAM) Instrumentation............................3.3-51 3.3.4 Remote Shutdown System.............................................................3.3-56

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued)

CALLAWAY PLANT 2

Amendment 229 l 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation..........................................................................3.3-59 3.3.6 Containment Purge Isolation Instrumentation.................................3.3-62 3.3.7 Control Room Emergency Ventilation System (CREVS)

Actuation Instrumentation.........................................................3.3-68 3.3.8 Emergency Exhaust System (EES) Actuation Instrumentation......3.3-74 3.3.9 Boron Dilution Mitigation System (BDMS)......................................3.3-80 3.4 REACTOR COOLANT SYSTEM (RCS)................................................3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits...................................................3.4-1 3.4.2 RCS Minimum Temperature for Criticality.......................................3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits..................................3.4-4 3.4.4 RCS Loops - MODES 1 and 2.........................................................3.4-6 3.4.5 RCS Loops - MODE 3.....................................................................3.4-7 3.4.6 RCS Loops - MODE 4.....................................................................3.4-10 3.4.7 RCS Loops - MODE 5, Loops Filled................................................3.4-13 3.4.8 RCS Loops - MODE 5, Loops Not Filled.........................................3.4-16 3.4.9 Pressurizer.......................................................................................3.4-18 3.4.10 Pressurizer Safety Valves................................................................3.4-20 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)......................3.4-22 3.4.12 Cold Overpressure Mitigation System (COMS)...............................3.4-26 3.4.13 RCS Operational LEAKAGE............................................................3.4-31 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage................................3.4-33 3.4.15 RCS Leakage Detection Instrumentation........................................3.4-37 3.4.16 RCS Specific Activity.......................................................................3.4-41 3.4.17 Steam Generator (SG) Tube Integrity.............................................3.4-44 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)...........................3.5-1 3.5.1 Accumulators...................................................................................3.5-1 3.5.2 ECCS - Operating...........................................................................3.5-4 3.5.3 ECCS - Shutdown............................................................................3.5-7 3.5.4 Refueling Water Storage Tank (RWST).........................................3.5-9 3.5.5 Seal Injection Flow...........................................................................3.5-11 3.6 CONTAINMENT SYSTEMS..................................................................3.6-1 3.6.1 Containment...................................................................................3.6-1 3.6.2 Containment Air Locks.....................................................................3.6-3 3.6.3 Containment Isolation Valves.........................................................3.6-7

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS (continued)

CALLAWAY PLANT 3

Amendment 228 3.6.4 Containment Pressure.....................................................................3.6-16 3.6.5 Containment Air Temperature.........................................................3.6-17 3.6.6 Containment Spray and Cooling Systems......................................3.6-18 3.6.7 Recirculation Fluid pH Control (RFPC) System...............................3.6-22 3.6.8 Containment Sumps........................................................................3.6-24 3.7 PLANT SYSTEMS.................................................................................3.7-1 3.7.1 Main Steam Safety Valves (MSSVs)...............................................3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs), Main Steam Isolation Valve Bypass Valves (MSIVBVs), and Main Steam Low Point Drain Isolation Valves (MSLPDIVs).................................3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Main Feedwater Regulating Valve Bypass Valves (MFRVBVs)..............................................3.7-9 3.7.4 Atmospheric Steam Dump Valves (ASDs)......................................3.7-12 3.7.5 Auxiliary Feedwater (AFW) System.................................................3.7-15 3.7.6 Condensate Storage Tank (CST)....................................................3.7-19 3.7.7 Component Cooling Water (CCW) System.....................................3.7-21 3.7.8 Essential Service Water System (ESW)..........................................3.7-23 3.7.9 Ultimate Heat Sink (UHS)................................................................3.7-26 3.7.10 Control Room Emergency Ventilation System (CREVS).................3.7-28 3.7.11 Control Room Air Conditioning System (CRACS)...........................3.7-32 3.7.12 Not Used..........................................................................................3.7-35 3.7.13 Emergency Exhaust System (EES).................................................3.7-36 3.7.14 Not Used..........................................................................................3.7-39 3.7.15 Fuel Storage Pool Water Level........................................................3.7-40 3.7.16 Fuel Storage Pool Boron Concentration..........................................3.7-41 3.7.17 Spent Fuel Assembly Storage.........................................................3.7-43 3.7.18 Secondary Specific Activity..............................................................3.7-45 3.7.19 Secondary System Isolation Valves (SSIVs)...................................3.7-46 3.7.20 Class 1E Electrical Equipment Air Conditioning (A/C) System........3.7-48 3.8 ELECTRICAL POWER SYSTEMS........................................................3.8-1 3.8.1 AC Sources - Operating...................................................................3.8-1 3.8.2 AC Sources - Shutdown..................................................................3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air.......................................3.8-22 3.8.4 DC Sources - Operating..................................................................3.8-25 3.8.5 DC Sources - Shutdown..................................................................3.8-28 3.8.6 Battery Cell Parameters...................................................................3.8-30 3.8.7 Inverters - Operating........................................................................3.8-34 3.8.8 Inverters - Shutdown........................................................................3.8-36 3.8.9 Distribution Systems - Operating.....................................................3.8-38

TABLE OF CONTENTS 3.8 ELECTRICAL POWER SYSTEMS (continued)

CALLAWAY PLANT 4

Amendment 229 l 3.8.10 Distribution Systems - Shutdown.....................................................3.8-40 3.9 REFUELING OPERATIONS.................................................................3.9-1 3.9.1 Boron Concentration........................................................................3.9-1 3.9.2 Unborated Water Source Isolation Valves.......................................3.9-3 3.9.3 Nuclear Instrumentation...................................................................3.9-5 3.9.4 Containment Penetrations...............................................................3.9-7 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level...................................................3.9-9 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level....................................................3.9-11 3.9.7 Refueling Pool Water Level.............................................................3.9-14 4.0 DESIGN FEATURES...............................................................................4.0-1 4.1 Site Location....................................................................................4.0-1 4.2 Reactor Core...................................................................................4.0-1 4.3 Fuel Storage....................................................................................4.0-1 5.0 ADMINISTRATIVE CONTROLS...........................................................5.0-1 5.1 Responsibility...................................................................................5.0-1 5.2 Organization....................................................................................5.0-2 5.3 Unit Staff Qualifications...................................................................5.0-4 5.4 Procedures......................................................................................5.0-5 5.5 Programs and Manuals.....................................................................5.0-6 5.6 Reporting Requirements..................................................................5.0-25 5.7 High Radiation Area.........................................................................5.0-30