ML18093B484

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Proposed Tech Spec Pages for Inclusion in License Change Request 88-02,dtd 880912
ML18093B484
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/03/1989
From:
Public Service Enterprise Group
To:
Shared Package
ML18093B480 List:
References
NUDOCS 8903140570
Download: ML18093B484 (41)
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Text

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1 DEFINITIONS SECTION 1.0 DEFINITIONS DEFINED TERMS ACTION AXIAL FLUX DIFFERENCE CHANNEL CALIBRATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY CONTROLLED LEAKAGE CORE ALTERATION QOSE EQUIVALENT I-131 E-AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE RESPONSE TIME FREQUENCY NOTATION FULLY WITHDRAWN GASEOUS RADWASTE TREATMENT SYSTEM IDENTIFIED LEAKAGE MEMBER(S) OF THE PUBLIC OFFSITE DOSE CALCUIATION MANUAL (ODCM)

OPERABLE - OPERABILITY OPERATIONAL MODE PHYSICS TESTS PRESSURE BOUNDARY LEAKAGE PROCESS CONTROL PROGRAM (PCP)

PURGE-PURGING QUADRANT POWER TILT RATIO RATED THERMAL POWER REACTOR TRIP SYSTEM RESPONSE TIME REPORTABLE OCCURRENCE SHUTDOWN MARGIN SITE BOUNDARY SOLIDIFICATION SOURCE CHECK STAGGERED TEST BASIS THERMAL POWER UNIDENTIFIED LEAKAGE UNRESTRICTED AREA VENTIIATION EXHAUST TREATMENT SYSTEM VENTING a90314057o e~gg&~72

~DR ADOCK 0 PDR SALEM - UNIT 1

\\

I I

1-1 1-1 1-1 1-1 1-1 1-1 1-2 1-2 1-2 1-2 1-3 1-3 1-3 1-3 1-3 1-3 1-4 1-4 1-4 1-4 1-5 1-5 1-5 1-5 1-5 1-5 1-6 1-6 1-6 1-6 l.-6 1-6 1-6 1-7 1-7 1-7 1-7 1-7 Amendment No. 59

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION 2.1 SAFETY LIMITS Reactor Core Reactor Coolant System-Pressure 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Trip System Instrumentation Setpoints BASES SECTION 2.1 SAFETY LIMITS Reactor Core Reactor Coolant System Pressure 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Trip System Instrumentation Setpoints SALEM - UNIT 1 II 2-1 2-1 2-4 B 2-1 B 2-2 B 2-3 Amendment No. 59

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.0 APPLICABILITY 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T

> 200°F Shutdown Margin - Tavg < 200°F Boron Dilution avg -

Moderator Temperature Coefficient Minimum Temperature for Criticality 3/4.1.2 BORATION SYSTEMS Flow Paths - Shutdown Flow Paths - Operating Charging Pump - Shutdown Charging Pump - Operating Boric Acid Transfer Pumps - Shutdown Boric Acid Transfer Pumps - Operating Borated Water Sources - Shutdown Borated Water Sources - Operating 3/4.1. 3 MOVABLE CONTROL ASSEMBLIES Group Height Position Indicating System - Operating Position Indicating Systems - Shutdown Rod Drop Time Shutdown Rod Insertion Limit Control Rod Insertion Limits SALEM - UNIT 1 III 3/4 0-1 3/4 1-1 3/4 1-3 3/4 1-4 3/4 1-5 3/4 1-6 3/4 1-7 3/4 1-8 3/4 1-10 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-16 3/4 1-18 3/4 1-19 3/4 1-20 3/4 1-21 3/4 1-22 3/4 1-23 Amendment No. 59

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LiMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4.2.4 QUADRANT POWER TILT RATIO 3/4.2.5 DNB PARAMETERS 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation Movable Incore Detectors Seismic Instrumentation Meteorological Instrumentation Remote Shutdown Instrumentation Fire Detection Instrumentation Accident Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation SALEM - UNIT 1 IV 3/4 2-1 3/4 2-5 3/4 2-9 3/4 2-11 3/4 2-13 3/4 3-1 3/4 3-14 3/4 3-35 3/4 3-39 3/4 3-40 3/4 3-43 3/4 3-46 3/4 3-49 3/4 3-53 3/4 3-58 3/4 3-64 Amendment No. 59

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation Hot Standby Hot Shutdown Cold Shutdown 3/4.4.2.1 SAFETY VALVES - SHUTDOWN 3/4.4.2.2 SAFETY VALVES - OPERATING 3/4.4.3 RELIEF VALVES 3/4.4.4 PRESSURIZER 3/4.4.5 STEAM GENERATORS 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection System Operational Leakage Pressure Isolation Valves 3/4.4.7 CHEMISTRY 3/4.4.8 SPECIFIC ACTIVITY 3/4.4.9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System Pressurizer Overpressure Protection Systems 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2, and 3 Components 3/4.4.11 INTENTIONALLY BLANK 3/4.4.12 HEAD VENTS SALEM - UNIT 1 v

3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-3b 3/4 4-4 3/4 4-4a 3/4 4-5 3/4 4-6 3/4 4-7 3/4 4-14 3/4 4-15 3/4 4-16a 3/4 4-17 3/4 4-20 3/4 4-24 3/4 4-29 3/4 4-30 3/4 4-32 3/4 4-34 3/4 4-35 Amendment No. 59

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMUIATORS 3/4.5.2 3/4.5.3 ECCS SUBSYSTEMS - T 350°F avg -

ECCS SUBSYSTEMS - T

< 350°F avg 3/4.5.4 DELETED 3/4.5.5 REFUELING WATER STORAGE TANK 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity Containment Leakage Containment Air Locks Internal Pressure Air Temperature Containment Structural Integrity Containment Ventilation System 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.3 Containment Spray System Spray Additive System Containment Cooling System CONTAINMENT ISOIATION VALVES 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers Electric Hydrogen Recombiners SALEM - UNIT 1 VI 3/4 5-1 3/4 5-3 3/4 5-6 3/4 5-6a 3/4 5-9 3/4 6-1 3/4 6-2 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-8a 3/4 6-9 3/4 6-10 3/4 6-11 3/4 6-12 3/4 6-18 3/4 6-19 Amendment No. 59

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves Auxiliary Feedwater System Auxiliary Feed Storage Tank Activity Main Steam Line Isolation Valves 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION 3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4.7.4 SERVICE WATER SYSTEM 3/4.7.5 FLOOD PROTECTION 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM 3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM 3/4.7.8 SEALED SOURCE CONTAMINATION 3/4.7.9 SNUBBERS 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System Spray and/or Sprinkler System Low Pressure co2 Systems Fire Hose Stations 3/4.7.11 PENETRATION FIRE BARRIERS SALEM - UNIT 1 VII 3/4 7-1 3/4 7-5 3/4 7-7 3/4 7-8 3/4 7-10 3/4 7-14 3/4 7-15 3/4 7-16 3/4 7-17 3/4 7-18 3/4 7-22 3/4 7-26 3/4 7-28 3/4 7-34 3/4 7-37 3/4 7-39 3/4 7-40 3/4 7-42 Amendment No. 59

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES Operating Shutdown 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating A.C. Distribution - Shutdown 125-Volt D.C. Distribution - Operating 125-Volt D.C. Distribution - Shutdown 28-Volt D.C. Distribution - Operating 28-Volt D.C. Distribution - Shutdown SALEM - UNIT 1 VII 3/4 8-1 3/4 8-5 3/4 8-6 3/4 8-7 3/4 8-8 3/4 8-10 3/4 8-11 3/4 8-13 Amendment No. 59

INDEX e

' LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/4 9-1 3/4.9.2 INSTRUMENTATION 3/4 9-2 3/4.9.3 DECAY TIME 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4 9-4 3/4.9.5 COMMUNICATIONS 3/4 9-5 3/4.9.6 MANIPULATOR CRANE 3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING AREA 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels 3/4 9-8 Low Water Level 3/4 9-8a 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-10 3/4.9.11 STORAGE POOL WATER LEVEL 3/4 9-11 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM 3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.l SHUTDOWN MARGIN 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 3/4 10-2 3/4.10.3 PHYSICS TESTS 3/4 10-3 3/4.10.4 NO FLOW TESTS 3/4 10-4 SALEM - UNIT 1 IX Amendment No. 59

INDEX e

)*.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration 3/4 11-1 Dose 3/4 11-5 Liquid Radwaste Treatment 3/4 11-6 Liquid Holdup Tanks 3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS Dose Rate 3/4 11-8 Dose-Noble Gases 3/4 11-12 Dose-Iodine-131, Tritium, and Radionuclides in Particulate Form 3/4 11-13 Gaseous Radwaste Treatment 3/4 11-14 Explosive Gas Mixture 3/4 11-15 3/4.11.3 SOLID RADIOACTIVE WASTE 3/4 11-17 3/4.11.4 TOTAL DOSE 3/4 11-18 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4 12-1 3/4.12.2 LAND USE CENSUS 3/4 12-11 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 3/4 12-13 SALEM - UNIT 1 x

Amendment No. 59

r~

INDEX

)

BASES SECTION PAGE 3/4.0 APPLICABILITY B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL B 3/4 1-1 3/4.1.2 BORATION SYSTEMS B 3/4 1-3 3/4.1. 3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE B 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR and AND 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO B 3/4 2-6 3/4.2.5 DNB PARAMETERS B 3/4 2-6 SALEM - UNIT 1 XI Amendment No. 59

INDEX 4

BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION B 3/4 4-1 3/4.4.2 SAFETY VALVES B 3/4 4-la 3/4.4.3 RELIEF VALVES B 3/4 4-la 3/4.4.4 PRESSURIZER B 3/4 4-2 3/4.4.5 STEAM GENERATORS B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-3 3/4.4.7 CHEMISTRY B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY B 3/4 4-5 3/4.4.9 PRESSURE/TEMPERATURE LIMITS B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-11 SALEM - UNIT 1 XII Amendment No. 59

~

BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS 3/4. 5.2 and ECCS SUBSYSTEMS 3/4.5.3 3/4.5.4 DELETED 3/4.5.5 REFUELING WATER STORAGE TANK (RWST) 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4.6.4 COMBUSTIBLE GAS CONTROL SALEM - UNIT 1 XIII B 3/4 5-1 B 3/4 5-1 B 3/4 5-2 B 3/4 6-1 B 3/4 6-3 B 3/4 6-3 B 3/4 6-4 Amendment No. 59

INDEX

.BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-4 3/4.7.5 FLOOD PROTECTION B 3/4 7-5 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM B 3/4 7-5 3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM B 3/4 7-5 3/4.7.8 SEALED SOURCE CONTAMINATION B 3/4 7-5 3/4.7.9 SNUB BERS B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS B 3/4 7-7 3/4.7.11 PENETRATION FIRE BARRIERS B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.l A. C. SOURCES and AND 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 SALEM - UNIT 1 XIV Amendment No. 59

INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-3 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM B 3/4 9-3 3/4.9.10 WATER LEVEL - REACTOR VESSEL and AND 3/4.9.11 STORAGE POOL B 3/4 9-3 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS

  • 3/4.10.1 SHUTDOWN MARGIN B 3/4 10-1 1/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PHYSICS TESTS B 3/4 10-1 3/4.10.4 NO FLOW TESTS B 3/4 10-1 SALEM - UNIT 1 xv Amendment No. 59

INDEX

,PASES SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS B 3/4 11-3 3/4.11. 3 SOLID RADIOACTIVE WASTE B 3/4 11-6 3/4.11.4 TOTAL DOSE B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12-1 3/4.12.2 LAND USE CENSUS B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/4 12-2 SALEM - UNIT 1 XVI Amendment No. 59

DESIGN FEATURES SECTION 5.1 SITE Exclusion Area Low Population Zone 5.2 CONTAINMENT Configuration Design Pressure and Temperature 5.3 REACTOR CORE Fuel Assemblies Control Rod Assemblies 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature Volume 5.5 METEOROLOGICAL TOWER LOCATION 5.6 FUEL STORAGE Criticality Drainage Capacity 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT SALEM - UNIT 1 XVII 5-1 5-1 5-1 5-4 5-4 5-4 5-4 5-5 5-5 5-5 5-5 5-5 5-6 Amendment No. 59

-I

,ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY 6.2 ORGANIZATION Off site Facility Staff Shift Technical Advisor 6.3 FACILITY STAFF QUALIFICATION 6.4 TRAINING 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE 6.5.2 Function Composition Alternates Meeting Frequency Quorum Responsibilities Review Process Authority Record NUCLEAR SAFETY REVIEW Function Composition Consultants Off-Site Review Group Review Audits On-Site Safety Review Group Responsibilities Authority SALEM - UNIT 1 XVIII 6-1 6-1 6-1 6-6 6-6 6-6 6-7 6-7 6-7 6-7 6-7 6-8 6-9 6-9 6-9 6-9 6-9 6-9a 6-9a 6-9a 6-10 6-11 6-11 6-11 Amendment No. 62

,ADMINISTRATIVE CONTROLS SECTION 6.5.3 TECHNICAL REVIEW AND CONTROL 6.6 REPORTABLE EVENT ACTION 6.7 SAFETY LIMIT VIOLATION 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6.9.2 SPECIAL REPORTS 6.10 RECORD RETENTION 6.11 RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA 6.13 PROCESS CONTROL PROGRAM 6.14 OFFSITE DOSE CALCULATION MANUAL 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.16 ENVIRONMENTAL QUALIFICATION SALEM - UNIT 1 XIX 6-12 6-12a 6-12a 6-13 6-15 6-21 6-21 6-23 6-23 6-24 6-24 6-25 6-26 Amendment No. 62

,DEFINITIONS SECTION 1.0 DEFINITIONS DEFINED TERMS.............................................. 1-1 ACTION...*.....................*.*.*.*..........*.......... 1-1 AXIAL FLUX DIFFERENCE....................*...........*..... 1-1 CHANNEL CALIBRATION.................*...........*.......... 1-1 CHANNEL CHECK.........................................*.... 1-1 CHANNEL FUNCTIONAL TEST.................................... 1-1 CONTAINMENT INTEGRITY...................................... 1-2 CONTROLLED LEAKAGE......................................... 1-2 CORE ALTERATION............................................ 1-2 Q.OSE EQUIVALENT I-131 *..................................... 1-2 E-AVERAGE DISINTEGRATION ENERGY............................ 1-3 ENGINEERED SAFETY FEATURE RESPONSE TIME.................... 1-3 FREQUENCY NOTATION......................................... 1-3 FULLY WITHDRAWN............................................. 1-3 GASEOUS RADWASTE. TREATMENT SYSTEM.......................... 1-3 IDENTIFIED LEAKAGE......................................... 1-3 MEMBER(S) OF THE PUBLIC.................................... 1-4 OFFSITE DOSE CALCUIATION MANUAL (ODCM)..................... 1-4 OPERABLE -

OPERABILITY..................................... 1-4 OPERATIONAL MODE..................*........................ 1-4 PHYSICS T~STS.............................................. 1-5 PRESSURE BOUNDARY LEAKAGE.................................. 1-5 PROCESS CONTROL PROGRAM (PCP).............................. 1-5 PURGE-PURGING.............................................. 1-5 QUADRANT POWER TILT RATIO.................................. 1-5 RATED THERMAL POWER........................................ 1-5 REACTOR TRIP SYSTEM RESPONSE TIME.......................... 1-6 REPORTABLE OCCURRENCE...................................... 1-6 SHUTDOWN MARGIN............................................ 1-6 SITE BOUNDARY................................. *............. 1-6 SOLIDIFICATION............................................. 1-6 SOURCE CHECK............................................... 1-6 STAGGERED TEST BASIS....................................... 1-6 THERMAL POWER...................................*.......... 1-7 UNIDENTIFIED LEAKAGE..................*................*... 1-7 UNRESTRICTED AREA.......................................... 1-7 VENTIIATION EXHAUST TREATMENT SYSTEM....................... 1-7 VENTING.................................................... 1-7 SALEM -

UNIT 2 I

Amendment No. 28

.. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION 2.1 SAFETY LIMITS Reactor Core............................................... 2 -1 Reactor Coolant System Pressure............................ 2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Trip System Instrumentation Setpoints.............. 2-4 BASES SECTION 2.1 SAFETY LIMITS Reactor Core............................................... B 2-*l Reactor Coolant System Pressure............................ B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Trip System Instrumentation Setpoints.............. B 2-3 SALEM - UNIT 2 II Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4. 0 APPLICABILITY......................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T

> 200 °F....................... 3/4 1-1 Shutdown Margin - Tavg 200 °F....................... 3/4 1-3 Moderator Temperatu~Xgc~efficient..................... 3/4 1-4 Minimum Temperature for Criticality................... 3/4 1-6 3/4.1. 2 BORATION SYSTEMS Flow Paths - Shutdown................................. 3/4 1-7 Flow Paths - Operating................................ 3/4 1-8 Charging Pump - Shutdown.............................. 3/4 1-9 Charging Pump - Operating............................. 3/4 1-10 Borated Water Sources - Shutdown...................... 3/4 1-11 Borated Water Sources - Operating..................... 3/4 1-12 3/4.1. 3 MOVABLE CONTROL ASSEMBLIES Group Height.......................................... 3/4 1-13 Position Indicating Systems - Operating............... 3/4 1-16 Position Indicating Systems - Shutdown................ 3/4 1-17 Rod Drop Time......................................... 3/4 1-18 Shutdown Rod Insertion Limit.......................... 3/4 1-19 Control Rod Insertion Limits.......................... 3/4 1-20 SALEM - UNIT 2 III Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................................. 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.......................... 3/4 2-5 3/4.2.3 RCS FLOW RATE AND R................................... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO............................. 3/4 2-13 3/4.2.5 DNB PARAMETERS........................................ 3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION....................................... 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.................. 3/4 3-38 Movable Incore Detectors.............................. 3/4 3-42 Remote Shutdown Instrumentation....................... 3/4 3-43 Fire Detection Instrumentation........................ 3/4 3-46 Accident Monitoring Instrumentation................... 3/4 3-50 Radioactive Liquid Effluent Monitoring Instrumentation....................................... 3/4 3-53 Radioactive Gaseous Effluent Monitoring Instrumentation....................................... 3/4 3-59 3/4.3.4 TURBINE OVERSPEED PROTECTION.......................... 3/4 3-65 SALEM - UNIT 2 IV Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation........................... 3/4 4-1 Hot Standby........................................... 3/4 4-2 Hot Shutdown.......................................... 3/4 4-3 Cold Shutdown......................................... 3/4 4-4a 3/4.4.2 SAFETY VALVES - SHUTDOWN.............................. 3/4 4-5 3/4.4.3 SAFETY VALVES - OPERATING............................. 3/4 4-6 3/4.4.4 PRESSURIZER........................................... 3/4 4-7 3/4.4.5 RELIEF VALVES......................................... 3/4 4-8 3/4.4.6 STEAM GENERATORS...................................... 3/4 4-9 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection System.............................. 3/4 4-16 Operational Leakage................................... 3/4 4-17 3/4.4.8 CHEMISTRY.....,....................................... 3/4 4-20 3/4.4.9 SPECIFIC ACTIVITY..................................... 3/4 4-23 3/4.4.10 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System................................ 3/4 4-27 Pressurizer........................................... 3/4 4-30 Overpressure Protection Systems....................... 3/4 4-31 3/4.4.11 STRUCTURAL INTEGRITY ASME Code Class 1, 2, and 3 Components................ 3/4 4-33 SALEM - UNIT 2 v

Amendment No. 28

SECTION 3/4.5 3/4.5.l 3/4.5.2 3/4.5.3 3/4.5.4 3/4.5.5 3/4.6 3/4.6.1 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS EMERGENCY CORE COOLING SYSTEMS (ECCS)

ACCUMULATORS.......................................... 3/4 5-1 ECCS SUBSYSTEMS - T 350°F........................ 3/4 5-3 avg -

ECCS SUBSYSTEMS - T

< 350°F........................ 3/4 5-7 avg DELETED REFUELING WATER STORAGE TANK.......................... 3/4 5-9 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Containment Integrity................................. 3/4 6-1 Containment Leakage................................... 3/4 6-2 Containment Air Locks................................. 3/4 6-4 Internal Pressure..................................... 3/4 6-6 Air Temperature....................................... 3/4 6-7 Containment Structural Integrity...................... 3/4 6-8 Containment Ventilation System........................ 3/4 6-9 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.............................. 3/4 6-10 Spray Additive System................................. 3/4 6-11 Containment Cooling System............................ 3/4 6-12 3/4.6.3 CONTAINMENT ISOLATION VALVES........................... 3/4 6-14 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers.................................... 3/4 6-21 Electric Hydrogen Recombiners......................... 3/4 6-22 SALEM - UNIT 2 VI Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves......................................... 3/4 7-1 Auxiliary Feedwater System............................ 3/4 7-5 Auxiliary Feed Storage Tank........................... 3/4 7-7 Activity.............................................. 3/4 7-8 Main Steam Line Isolation Valves...................... 3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION............................................ 3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................ 3/4 7-12 3/4.7.4 SERVICE WATER SYSTEM.................................. 3/4 7-13 3/4. 7. 5 FLOOD PROTECTION...................................... 3/4 7-14 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM................................... 3/4 7-15 3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM..................................... 3/4 7-18 3/4.7.8 SEALED SOURCE CONTAMINATION........................... 3/4 7-21

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3/4. 7. 9 SNUBBERS.............................................. 3/4 7-23 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System......................... 3/4 7-31 Spray and/or Sprinkler System......................... 3/4 7-34 Low Pressure co2 Systems.............................. 3/4 7-36 Fire Hose Stations.................................... 3/4 7-37 3/4.7.11 PENETRATION FIRE BARRIERS............................. 3/4 7-39 SALEM - UNIT 2 VII Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.l A. C. SOURCES Operating............................................. 3/4 8-1 Shutdown.............................................. 3/4 8-7 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating......................... 3/4 8-8 A.C. Distribution - Shutdown.......................... 3/4 8-9 125-Volt D.C. Distribution - Operating................ 3/4 8-10 125-Volt D.C. Distribution - Shutdown................. 3/4 8-12 28-Volt D.C. Distribution - Operating................. 3/4 8-13 28-Volt D.C. Distribution - Shutdown.................. 3/4 8-15 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices.................................... 3/4 8-16 SALEM - UNIT 2 VIII Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4. 9.1 BORON CONCENTRATION................................... 3/4 9-1 3/4.9.2 INSTRUMENTATION....................................... 3/4 9-2 3/4. 9. 3 DECAY TIME................... :........................ 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..................... 3/4 9-4 3/4. 9. 5 COMMUNICATIONS........................................ 3/4 9-5 3/4.9.6 MANIPULATOR CRANE..................................... 3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING AREA..................... 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels................... ;.................. 3/4 9-8 Low Water Level....................................... 3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM............................... 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL.......................... 3/4 9-11 3/4.9.11 STORAGE POOL WATER LEVEL.............................. 3/4 9-12 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM................. 3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS................................... 3/4 10-2 3/4.10. 3 PHYSICS TESTS......................................... 3/4 10-4 3/4.10.4 NO FLOW TESTS......................................... 3/4 10-5 SALEM - UNIT 2 IX Amendment No. 28

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration......................................... 3/4 11-1 Dose.................................................. 3/4 11-5 Liquid Radwaste Treatment............................. 3/4 11-6 Liquid Holdup Tanks................................... 3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS Dose Rate............................................. 3/4 11-8 Dose-Noble Gases...................................... 3/4 11-12 Dose-Iodine-131, Tritium, and Radionuclides in Particulate Form.................... 3/4 11-13 Gaseous Radwaste Treatment............................ 3/4 11-14 Explosive Gas Mixture................................. 3/4 11-15 3/4.11.3 SOLID RADIOACTIVE WASTE............................... 3/4 11-17 3/4.11.4 TOTAL DOSE............................................ 3/4 11-19 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.................................... 3/4 12-1 3/4.12. 2 LAND USE CENSUS....................................... 3/4 12-11 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.................... 3/4 12-13 SALEM - UNIT 2 x

Amendment No. 28

,BASES SECTION PAGE 3/4.0 APPLICABILITY......................................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL...................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS...................................... B 3/4 1-3 3/4.1.3 MOVABLE CONTROL ASSEMBLIES............................ B 3/4 1-4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................................. B 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR and 3/4.2.3 RCS FLOW RATE AND R................................... B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO............................. B 3/4 2-5 3/4.2.5 DNB PARAMETERS.................................... *... B 3/4 2-5 SALEM - UNIT 2 XI Amendment No. 28

.BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION............................ B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION....................................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION............................ B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION........................................... B 3/4 4-1 3/4.4.2 and SAFETY VALVES......................................... B 3/4 4-2 3/4.4.3 3/4.4.4 PRESSURIZER........................................... B 3/4 4-2 3/4.4.5 RELIEF VALVES......................................... B 3/4 4-2 3/4.4.6 STEAM GENERATORS...................................... B 3/4 4-3 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE........................ B 3/4 4-4 3/4.4.8 CHEMISTRY............................................. B 3/4 4-5 3/4.4.9 SPECIFIC ACTIVITY..................................... B 3/4 4-6 3/4.4.10 PRESSURE/TEMPERATURE LIMITS........................... B 3/4 4-7 3/4.4.11 STRUCTURAL INTEGRITY............................ '...... B 3/4 4-17 SALEM - UNIT 2 XII Amendment No. 28

-BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMUIATORS.......................................... B 3/4 5-1 3/4.5.2 and ECCS SUBSYSTEMS....................................... B 3 / 4 5 -1 3/4.5.3 3/4.5.4 DELETED 3/4.5.5 REFUELING WATER STORAGE TANK (RWST)................... B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................. B 3/4 6-3 3/4.6.3 CONTAINMENT ISOIATION VALVES.......................... B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTROL............................... B 3/4 6-4 SALEM ;.. UNIT 2 XIII Amendment No. 28

,BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE......................................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION............................................ B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................ B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM.................................. B 3/4 7-4 3/4. 7. 5 FLOOD PROTECTION...................................... B 3/4 7-5 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM................................... B 3/4 7-5

.3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM..................................... B 3/4 7-5 3/4.7.8 SEALED SOURCE CONTAMINATION........................... B 3/4 7-5 3 I 4. 7. 9 SNUBBERS.............................................. B 3 I 4 7 -6 3/4.7.10 FIRE SUPPRESSION SYSTEMS.............................. B 3/4 7-7 3/4.7.11 PENETRATION FIRE BARRIERS............................. B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES and AND 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS..................... B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES............... B 3/4 8-1 SALEM - UNIT 2 XIV Amendment No. 28

  • BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4. 9. 1 BORON CONCENTRATION................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................................... B 3/4 9-1 3/4.9.3 DECAY TIME............................................ B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..................... B 3/4 9-1 3/4. 9. 5 COMMUNICATIONS........................................ B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE..................................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION........................................... B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM............................... B 3/4 9-3 3/4.9.10 WATER LEVEL - REACTOR VESSEL and AND 3/4. 9.11 STORAGE POOL.......................................... B 3/4 9-3 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM................. B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................................... B 3/4 10 "-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS................................... B 3/4 10-1 3/4.10.3 PHYSICS TESTS......................................... B 3/4 10-1 3/4.10.4 NO FLOW TESTS......................................... B 3/4 10-1 3/4.10.5 POSITION INDICATION - SHUTDOWN........................ B 3/4 10-1 SALEM - UNIT 2 xv Amendment No. 28

,BASES SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS...................................... B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS..................................... B 3/4 11-3 3/4.11.3 SOLID RADIOACTIVE WASTE............................... B 3/4 11-6 3/4.11. 4 TOTAL DOSE............................................ B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS....................................... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.................... B 3/4 12-2 SALEM - UNIT 2 XVI Amendment No. 28

J)ESIGN FEATURES SECTION 5.1 SITE Exclusion Area............................................. 5-1 Low Population Zone........................................ 5 -1 5.2 CONTAINMENT Configuration.............................................. 5-1 Design Pressure and Temperature............................ 5-4 5.3 REACTOR CORE Fuel Assemblies............................................ 5-4 Control Rod Assemblies..................................... 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature............................ 5-4 Volume..................................................... 5-4 5.5 METEOROLOGICAL TOWER LOCATION.............................. 5-5 5.6 FUEL STORAGE Criticality................................................ 5-5 Drainage................................................... 5-5 Capacity................................................... 5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-5 SALEM - UNIT 2 XVII Amendment No. 28

1

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~ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Offsite.................................................... 6-1 Facility Staff............................................. 6-1 Shift Technical Advisor.................................... 6 - 6 6.3 FACILITY STAFF QUALIFICATIONS.............................. 6-6 6. 4 TRAINING................................................... 6 - 6 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE Function.............................................. 6-7 Composition........................................... 6-7 Alternates............................................ 6-7 Meeting Frequency..................................... 6-7 Quorum................................................ 6-7 Responsibilities...................................... 6-8 Review Process........................................ 6-9 Authority............................................. 6-9 Records............................................... 6 - 9 6.5.2 NUCLEAR SAFETY REVIEW Function.............................................. 6-9 Composition............................ :.............. 6-9 Consultants........................................... 6-9a Off-Site Review Group................................. 6-9a Review............. *................................... 6-9a Audits................................................ 6-10 On-Site Safety Review Group........................... 6-11 Responsibilities...................................... 6-11 Authority............................................. 6-11 SALEM - UNIT 2 XVIII Amendment No. 33

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~ADMINISTRATIVE CONTROLS SECTION 6.5.3 TECHNICAL REVIEW AND CONTROL............................. 6-12 6.6 REPORTABLE EVENT ACTION.................................... 6-12a

6. 7 SAFETY LIMIT VIOLATION..................................... 6-12a 6.8 PROCEDURES AND PROGRAMS.................................... 6-13 6.9 REPORTING REQUIREMENTS 6. 9. 1 ROUTINE REPORTS....................................... 6 -15
6. 9. 2 SPECIAL REPORTS....................................... 6-21 6.10 RECORD RETENTION........................................... 6-21 6.11 RADIATION PROTECTION PROGRAM............................... 6-23 6.12 HIGH RADIATION AREA........................................ 6-23.

6.13 PROCESS CONTROL PROGRAM.................................... 6-24 6.14 OFFSITE DOSE CALCULATION MANUAL............................ 6-24 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS.......................... 6-25 SALEM - UNIT 2 i

X_I_X __________

Am_e_n_dm-en_t_N_o_._3_3_____

\\'1 SALEM - UNIT 1 SECTION 3/4.4.11 INTENTIONALLY BLANK J/4 4-34

",.'RJ\\\\CTOR COOLANT SYSTEM 3/4.4.12 HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.12 At least one reactor vessel head vent path shall be operable with the vent path closed.

A vent path shall consist of at least two valves in series, powered from vital sources.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the reactor vessel head vent path inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with the valve actuators key locked in the closed position; restore the inoperable vent path to OPERABLE status within 3 days, or, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVRILLANCE REQUIREMENTS 4.4.12 Reactor vessel head vent system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1.

Verifying all manual isolation valves in each vent path are locked in the open position.

2.

Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or refueling.

3.

Verifying flow through the reactor vessel head vent system vent path during venting.

SALEM - UNIT 1 3/4 4-35

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i,rAcTOR COOLANT SYSTEM 3/4.4.12 HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.12 At least one reactor vessel head vent path shall be operable with the vent path closed.

A vent path shall consist of at least two valves in series, powered from vital sources.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the reactor vessel head vent path inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with the valve actuators key locked in the closed position; restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.12 Reactor vessel head vent system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1.

Verifying all manual isolation valves in each vent path are locked in the open position.

2.

Cycling each valve in the vent path through at least one complete cycle of Jull travel from the control room during COLD SHUTDOWN or refueling.

3.

Verifying flow through the reactor vessel head vent system vent path during venting.

SALEM - UNIT 2 3/4 4-34

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