ML19011A060
| ML19011A060 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/04/2019 |
| From: | Susquehanna |
| To: | Gerlach R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19011A060 (42) | |
Text
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L.V..J.....J MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2019-326 USER INFORMATION:
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SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0
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PLANT SYSTEMS EMERGENCY *SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0
11/18/2002
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PLANT SYSTEMS ULTIMATE HEAT SINK (URS) AND GROUND WATER LEVEL TEXT 3.7.3.1 4
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PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3
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PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS 05/16/2016 I
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04/16/2009
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08/31/1998
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11/19/2002.
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11/19/2002
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11/09/2007
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11/09/2007
Title:
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11/19/2002
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11/19/2002
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04/26/2006
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PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0
11/19/2002
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09/27/2012
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PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0
11/19/2002
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0
11/19/2002
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PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0
11/19/2002
Title:
PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 4
06/04/2013
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PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2
01/31/2008
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.8 4
01/31/2014
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12/08/2011
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PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 2
11/01/2018
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STRUCTURAL INTEGRITY TEXT B3.8.1 2
03/10/2010
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11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD-PROTECTION -
CONTINUOUS TEXT B3.8.2.2 1
09/17/2004
Title:
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.AUTOMATIC TEXT B3.8.3 0
11/19/2002
Title:
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11/19/2002
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ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1
. 11/14/2013
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ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 2
12/08/2011
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ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2
06/04/2013
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BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 16 Report Date: 01/07/19
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11/19/2002
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REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 0
11/19/2002
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REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.l 0
11/19/2002
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MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1
03/31/2006
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MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS.INSTRUMENTATION TEXT B3.10.3 0
11/19/2002
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MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3.10.4 1
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SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 1.0 1.1 2.0 2.1 2.2 3.0 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3.
3.1.4 3.2 3.2.1 3.3 3.3.1 3.3.2 3.3.3
- 3.3.4 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 PAGE USE AND APPLICATION.................................................................................. 1.0-1 Definitions.................................................................................................... 1.0-1 PLANT PROGRAMS AND SETPOINTS........................................................... 2.0-1 Plant Programs............................................................................................ 2.0-1 Instrument Trip Setpoint Table.................................................................... 2.0-5 APPLICABILITY................................................................................................ 3.0-1 Technical Requirement for Operation (TRO) Applicability........................... 3.0-1 Technical Requirement Surveillance (TRS) Applicability............................ 3.0-3 REACTIVITY CONTROL SYSTEMS................................................................. 3.1-1 Anticipated Transient Without Scram Alternate Rod Injection (ATWS ARI) Instrumentation......................................................... 3.1-1 Control Rod Drive (CRD) Housing Support................................................. 3.1-4 Control Rod Block Instrumentation.............................................................. 3.1-5 Control Rod Scram Accumulators Instrumentation and Check Valve................................................................................................ 3.1-9 CORE OPERATING LIMITS REPORT............................................................. 3.2-1 Core Operating Limits Report...................................................................... 3.2-1 INSTRUMENTATION........................................................................................ 3.3-1 Radiation Monitoring Instrumentation.......................................................... 3.3-1 Seismic Monitoring Instrumentation............................................................ 3.3-4 Meteorological Monitoring Instrumentation.................................................. 3.3-7 TRM Post-Accident Monitoring Instrumentation.......................................... 3.3-9 Section Not Used......................................................................................... 3.3-12 TRM Isolation Actuation Instrumentation..................................................... 3.3-13 Main Turbine Overspeed Protection System............................................... 3.3-17 Section Not Used......................................................................................... 3.3-19 OPRM Instrumentation Configuration.......................................................... 3.3-22 Reactor Recirculation Pump MG Set Stops................................................ 3.3-23 MVP Isolation Instrumentation..................................................................... 3.3-25 Water Monitoring Instrumentation........................................ ;...................... 3.3-27 REACTOR COOLANT SYSTEM....................................................................... 3.4-1 Reactor Coolant System Chemistry............................................................ 3.4-1 Not Used....................................................................................................... 3.4-6 High/Low Pressure Interface Leakage Monitors.................................... 3.4-9 Reactor Recirculation Flow and Rod Line Limit........................................... 3.4-12 Reactor Vessel Materials............................................................................. 3.4-13 Reactor Recirculation Single Loop Operation (SLO)
Flow Rate Restriction................................................................................. 3.4-14 SUSQUEHANNA - UNIT 1 TOC-1
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 3.5 3.5.1 3.5.2 3.5.3 3.6 3.6.1 3.6.2 3.6.3 3.6.4 3.7 3.7.1 3.7.2 3.7.3 3.7.3.1 3.7.3.2 3.7.3.3 3.7.3.4 3.7.3.5 3.7.3.6 3.7.3.7 3.7.3.8 3.7.4 3.7.5 3.7.5.1 3.7.5.2 3.7.5.3 3.7.6 3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 PAGE EMERGENCY CORE COOLING AND RCIC.................................................... 3.5-1 ADS Manual Inhibit...................................................................................... 3.5-1 ECCS and RCIC System Monitoring Instrumentation................................. 3.5-3 Long Term Nitrogen Supply to ADS............................................................ 3.5-6 CONTAINMENT..................................................................................... :.......... 3.6-1 Venting or Purging............................................... *......................................... 3.6-1 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication..................................................................................................... 3.6-2 Suppression Pool Alarm Instrumentation.................................................... 3.6-3 Primary Containment Closed System Boundaries...................................... 3.6-6 PLANT SYSTEMS................ :............................................................................ 3.7-1 Emergency Service Water System (ESW) Shutdown................................. 3.7-1 Ultimate Heat Sink (UHS) and Ground Water Level.................................... 3.7-3 Fire Protection............................................................................................. 3.7-4 Fire Suppression Water Supply System...................................................... 3. 7-4 Spray and Sprinkler Systems...................................................................... 3. 7-8 CO2 Systems.................................................... ;..............................,.......... 3.7-12 Halon Systems............................................................................................ 3.7-16 Fire Hose Stations........................................,............................................... 3.7-18 Yard Fire Hydrants and Hydrant Hose Houses........................................... 3.7-22 Fire Rated Assemblies................................................................................ 3.7-24 Fire Detection Instrumentation.................................................................... 3. 7-26 Solid Radwaste System................................................................................ 3. 7-35 Explosive Gas and Storage Tank Radioactivity Monitoring Program..................................................................................... 3. 7-38 Main Condenser Offgas Hydrogen Monitor................................................. 3.7-38 Main Condenser Offgas Explosive Gas Mixture.......................................... 3.7-39 Liquid Holdup Tanks.................................................................................... 3.7-40 ESSW Pumphouse Ventilation.................................................................... 3. 7-41 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation.......................................................................... 3.7-42 Snubbers..................................................................................................... 3. 7-44 c*ontrol Structure HVAC.............................................................................. 3.7-50 Spent Fuel Storage Pools (SFSPs)............................................................. 3.7-52 Structural Integrity............,.......................................................................... 3.7-55 SUSQUEHANNA - UNIT 1 TOC-2
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 3.8 3.8.1 3.8.2 3.8.2.1 3.8.2.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.9 3.9.1 3.9.2 3.9.3 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.11 3.11.1 3.11.1.1 3.11.1.2 3.11.1.3 3.11.1.4 3.11.1.5 3.11.2 3.11.2.1 3.11.2.2 3.11.2.3 3.11.2.4 3.11.2.5 3.11.2.6 3.11.3 3.11.4 3.11.4.1 3.11.4.2 3.11.4.3 PAGE ELECTRICAL POWER...................................................................................... 3.8-1 Primary Containment Penetration Conductor Overcurrent Protective Devices........................................................................................ 3.8-1 Motor Operated Valves Thermal Overload Protection................................. 3.8-5 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous.................................................................................................. 3.8-5 Motor Operated Valves (MOV) Thermal Overload Protection -
Automatic..................................................................................................... 3.8-11 Diesel Generator (DG) Maintenance Activities............................................ 3.8-13 24 voe Electrical Power Subsystem.......................................................... 3.8-15 Degraded Voltage Protection...................................................................... 3.8-21 Emergency Switchgear Room Cooling........................................................ 3.8-24 Battery Monitoring and Maintenance Program............................................ 3.8-26 REFUELING OPERATIONS............................................................................. 3.9-1 Decay Time................................................................................................. 3.9-1 Communications...................... :................................................................... 3.9-2 Refueling Platform..................................................................,.................... 3.9-3 MISCELLANEOUS............................................................................................. 3.10-1 Sealed Source Contamination..................................................................... 3.10-1 Shutdown Margin Test RPS Instrumentation.....,........................................ 3.10-4 Independent Spent Fuel Storage Installation (ISFSI).................................. 3.10-7 Section Not Used........................................................................... 3.10.8 RADIOACTIVE EFFLUENTS............................................................................ 3.11-1 Liquid Effluents............................................................................................ 3.11-1 Liquid Effluents Concentration..................................................................... 3.11-1 Liquid Effluents Dose................................................................................... 3. 11-4 Liquid Waste Treatment System................................................................. 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation................................. 3.11-8 Radioactive Liquid Process Monitoring Instrumentation.............................. 3.11-13 Gaseous Effluents....................................................................................... 3.11-17 Dose Rate.................................................................................................... 3.11-17 Dose - Noble Gases.................................................................................... 3.11-20 Dose - Iodine, Tritium, and Radionuclides in Particulate Form.......................................................................................... 3.11-21 Gaseous Radwaste Treatment System....................................................... 3.11-22 Ventilation Exhaust Treatment System....................................................... 3.11-23 Radioactive Gaseous Effluent Monitoring Instrumentation............................................................................................ 3.11-25 Total Dose.................................................................... :.............................. 3.11-33 Radiological Environmental Monitoring....................................................... 3.11-35 Monitoring Program..................................................................................... 3.11-35 Land Use Census........................................................................................ 3.11-45 lnterlaboratory Comparison Program.......................................................... 3.11-47 SUSQUEHANNA - UNIT 1 TOC-3
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 3.12 3.12.1 3.12.2 3.12.3 4.0 4.1 4.2 4.3 4.4 4.5 4.5.1 4.5.2 4.5.3 4.6 4.7 PAGE LOADS CONTROL PROGRAM........................................................................ 3.12-1 Crane Travel - Spent Fuel Storage Pool..................................................... 3.12-1 Heavy Loads Requirements........................................................................ 3.12-3 Light Loads Requirements........................................................................... 3.12-5 ADMINISTRATIVE CONTROLS....................................................................... 4.0-1 Organization................................................................................................ 4.0-1 Reportable Event Action.............................................................................. 4.0-2 Safety Limit Violation................................................................................... 4.0-3 Procedures and Programs........................................................................... 4.0-4 Reporting Requirements.............................................................................. 4.0-5 Startup Reports........................................................................................... 4.0-5 Annual Reports............................................................................................. 4.0-6 Special Reports........................................................................................... 4.0-6 Radiation Protection Program..................................................................... 4.0-7 Training........................................................................................................ 4.0-8 SUSQUEHANNA - UNIT 1 TOC-4
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION B 3.0 B 3.0 B 3.1.1
- B 3.1.2 B 3.1.3 B 3.1.4 B 3.2.1 B 3.3.1 B 3.3.2 B 3.3.3 B 3.3.4 B 3.3.5 B 3.3.6 B 3.3.7 B 3.3.8 B 3.3.9 B 3.3.10 B 3.3.11 B 3.3.12 B 3.4.1 B 3.4.2 B 3.4.3 B 3.4.4 B 3.4.5 B 3.4.6 B 3.5.1 B 3.5.2 B 3.5.3 PAGE Technical Requirement for Operation (TRO) Applicability........................... B 3.0-1 Technical Requirement Surveillance (TRS) Applicability............................ B 3.0-9 Anticipated Transient Without SCRAM Alternate Rod Injection (ATWS-ARI) Instrumentation....................................................................... B 3.1-1 Control Rod Drive (CRD) Housing Support................................................. B 3.1-4 Control Rod Block Instrumentation.............................................................. B 3.1-5 Control Rod Scram Accumulators Instrumentation and Check Valve.................................................................... :........................... 8 3.1-8 Core Operating Limits Report (COLR)........................................................ B 3.2-1 Radiation Monitoring Instrumentation.......................................................... B 3.3-1 Seismic Monitoring Instrumentation............................................................ B 3.3-2 Meteorological Monitoring Instrumentation.................................................. B 3.3-3 TRM Post-Accident Monitoring Instrumentation.......................................... B 3.3-4 Section Not Used...................................................,...................................... B 3.3-9 TRM Isolation Actuation Instrumentation...............................,...................... B 3.3-10 Main Turbine Overspeed Protection System.......... ~.................................... B 3.3-14 Section Not Used......................................................................................... B 3.3-15 OPRM Instrumentation................................................................................ B 3.3-17 Reactor Recirculation Pump MG Set Stops................................................ B 3.3-18 MVP Isolation Instrumentation..................................................................... B 3.3-20 Water Monitoring Instrumentation.............................................................. B 3.3-22 Reactor Coolant System Chemistry............................................................ B 3.4-1 Not Used...................................................................................................... B 3.4-2 High/Low Pressure lntelface 1,.eakage Monitors...............,........................... B 3.4-4 Reactor Recirculation Flow and Rod Line Limit........................................... B 3.4-5 Reactor Vessel Materials............................................................................. B 3.4-6 Reactor Recirculation Single Loop Operation (SLO)
Flow Rate Restriction................................................................................. B 3.4-7 ADS Manual Inhibit.,..................................................................................... B 3.5-1 ECCS and RCIC System Monitoring Instrumentation................................. B 3.5-3 Long Term Nitrogen Supply to ADS............................................................ B 3.5,.4 SUSQUEHANNA - UNIT 1 TOC-5
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 8 3.6.1 8 3.6.2 8 3.6.3 8 3.6.4 8 3.7.1 8 3.7.2 8 3.7.3.1 8 3.7.3.2 8 3.7.3.3 8 3.7.3.4 8 3.7.3.5 8 3.7.3.6 8 3.7.3.7 8 3.7.3.8 8 3.7.4 8 3.7.5.1 8 3.7.5.2 8 3.7.5.3 8 3.7.6 8 3.7.7 8 3.7.8 8 3.7.9 8 3.7.10 8 3.7.11 8 3.8.1 8 3.8.2.1 8 3.8.2.2 8 3.8.3 8 3.8.4 8 3.8.5 8 3.8.6 8 3.8.7 8.3.9.1 8 3.9.2 PAGE Venting or Purging....................................................................................... 8 3.6-1 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication..................................................................................................... 8 3.6-3 Suppression Pool Alarm Instrumentation.................................................... 8 3.6-4 Primary Containment Closed System Boundaries...................................... 8 3.6-6 Emergency Service Water System (Shutdown).......................................... 8 3.7-1 Ultimate Heat Sink (UHS) Ground Water Level........................................... 8 3.7-2 Fire Suppression Water Supply System...................................................... B 3.7-3 Spray and Sprinkler Systems...................................................................... B 3. 7-5 CO2 systems............................................................................................... 8 3. 7-7 Halon Systems............................................................................................ 8 3. 7-8 Fire Hose Stations....................................................................................... 8 3.7-10 Yard Fire Hydrants and Hydrant Hose Houses........................................... 8 3.7-11 Fire Rated Assemblies................................................................................ 8 3.7-12 Fire Detection Instrumentation.................................................................... 8 3.7-14 Solid Radwaste System............................................................................... 8 3.7-15 Main Condenser Offgas Hydrogen Monitor................................................. B 3.7-17 Main Condenser Offgas Explosive Gas Mixture.......................................... 8 3.7-19 Liquid Holdup Tanks.................................................................................... 8 3.7-20 ESSW Pumphouse Ventilation.................................................................... 8 3. 7-21 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation.......................................................................... B 3.7-22 Snubbers..................................................................................................... B 3.7-24 Control Structure HVAC.............................................................................. 8 3.7-31 Spent Fuel Storage Pools............................................................................ 8 3.7-33 Structural Integrity....................................................................................... 8 3.7-36 Primary Containment Penetration Conductor Overcurrent Protective Devices....................................................................................... 8 3.8-1 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous.................................................................................................. 8 3.8-3 Motor Operated Valves (MOV) Thermal Overload Protection "".
Automatic..................................................................................................... 8 3.8-4 Diesel Generator (DG) Maintenance Activities............................................ 8 3.8-5 24 VDC Electrical Power Subsystem.......................................................... B 3.8-6 Degraded Voltage Protection...................................................................... 8 3.8-16 Emergency Switchgear Room Cooling........................................................ 8 3.8-17 Battery Monitoring and Maintenance Program............................................ 8 3.8-18 Decay Time................................................................................................. 8 3.9-1 Communications.......................................................................................... 8 3.9-2 SUSQUEHANNA - UNIT 1 TOC-6
SUSQUEHANNA STEAM ELECTRIC STATION Rev.26 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION B 3.9.3 B 3.10.1 B 3.10.2 B 3.10.3 B 3.11.1.1 B 3.11.1.2 B 3.11.1.3 B 3.11.1.4 B 3.11.1.5 B 3.11.2.1 B 3.11.2.2 B 3.11.2.3 B 3.11.2.4 B 3.11.2.5 B 3.11.2.6 B 3.11.3 B 3.11.4.1 B 3.11.4.2 B 3.11.4.3 B.3.12.1 B.3.12.2 B.3.12.3 PAGE
.Refueling Platform....................................................................................... B 3.9-3 Sealed Source Contamination..................................................................... B 3.10-1 Shutdown Margin Test RPS Instrumentation...................................... ;....... B 3.10-2 Independent Spent Fuel Storage Installation (ISFSI).................................. B 3.10-4 Liquid Effluents Concentration..................................................................... B 3.11-1 Liquid Effluents Dose................................................................................... B 3.11-4 Liquid Waste Treatment System................................................................. B 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation................................. B 3.11-7 Radioactive Liquid Process Monitoring Instrumentation.............................. B 3.11-10 Dose Rate.................................................................................................... B 3.11-12 Dose - Noble Gases.................................................................................... B 3.11-16 Dose - Iodine, Tritium, and Radionuclides in Particulates Form........................................................................................ B 3.11-18 Gaseous Radwaste Treatment System....................................................... B 3.11-20 Ventilation Exhaust Treatment System*....................................................... B 3.11-21 Radioactive Gaseous Effluent Monitoring Instrumentation............................................................................................ B 3.11-24 Total Dose................................................................................................... B 3.11-26 Monitoring Program..................................................................................... B 3.11-28 Land Use Census........................................................................................ B 3.11-34 lnterlaboratory Comparison Program.......................................................... B 3.1-1-36 Crane Travel - Spent Fuel Storage Pool.................................................... B 3.12-1 Heavy Loads Requirements..................................................................... :.. B 3.12-2 Light Loads Requirements........................................................................... B 3.12-3 SUSQUEHANNA - UNIT 1 TOC-7
Suppression Chamber-to-Drywell Vacuum Breaker Position Indication Rev. 3 3.6.2 3.6 Containment 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication TRO 3.6.2 The Suppression Chamber-to-Drywell Vacuum Breaker Position Indication shall be OPERABLE APPLICABILITY:
MODES 1, 2, and 3 ACTIONS
~----~--------------------------------~------------NOTE-----------------------------------------*--------------
Separate condition entry is allowed for each instrument.
CONDl1ION A. One or more position indicators of any suppression chamber -
drywell vacuum breaker inoperable SUSQUEHANNA - UNIT 1 REQUIRED ACTION COMPLETION TIME A.1.1 Verify that the associated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> suppression chamber - drywell vacuum breaker is closed.
AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR thereafter A.1.2 Enter CONDITION B of LCO 3.6.1.6 3.6-2 Immediately
( continued)
Rev.3 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication 3.6.2 ACTIONS (continued)
CONDITION REQUIRED ACTION A.2 Restore the suppression chamber - drywell vacuum breaker indication to OPERABLE status.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> At the next outage with containment entry, not to exceed the next refueling outage for in-accessible containment components.
FREQUENCY TRS 3.6.2.1 Observe-expected actuation of both valve position indicators during the Technical Specification Functional cycling.
As required by SR 3.6.1.6.2 TRS 3.6.2.2 Perform a CHANNEL CALIBRATION on each 24 months vacuum breaker position indicator.
SUSQUEHANNA - UNIT 1 3.6-2a
ADMINISTRATIVE CONTROLS Rev. 1 4.0 4.2 Reportable Event Action 4.2.1 The following actions shall be taken for REPORTABLE EVENTS:
- a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and,
- b.
Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the Nuclear Safety Review Board (NSRB) and a specified corporate officer.
SUSQUEHANNA - UNIT 1 4.0-2
ADMINISTRATIVE CONTROLS Rev. 1 4.0 4.3 Safety Limit Violation 4.3.1 The following actions shall be taken in the event a Safety Limit is violated:
4.3.1.1 Nuclear Safety Review Board (NSRB) and a specified corporate officer shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.3.1.2 A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC.
4.3.1.3 The Safety Limit Violation Report shall be submitted to the NSRB and a specified corporate officer within 14 days of the violation.
4.3.1.4 Critical operation of the unit shall not be resumed until authorized by the Commission.
SUSQUEHANNA - UNIT 1 4.0-3
Rev.4 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties.
Setpoints and Settings Bases TOL(E)
Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. A range of values is.
provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
1, Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filt~r Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from
- stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
Oscillation Period Lower Time Limit Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.
(continued)
SUSQUEHANNA - UNIT 1 B 3.3-17
ACTIONS LPRMmin This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation.
Amplitude and Growth Rate Based Algorithm Parameters S1 Peak Threshold Setpoint / ABA & GRBA S2 Valley Threshold Setpoint I ABA & GRBA Amplitude Trip Setpoint / ABA Growth Rate Factor Setpoint / GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm. The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients.
The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3.1.1 is then entered, or an alternate method to detect ~nd suppress thermal hydraulic instability oscillations is employed.
(continued)
SUSQUEHANNA - UNIT 1 B 3.3-17a
Note 1 has been provided to modify the ACTIONS related to affected OPRM channels. Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, 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. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into thE? Condition. However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.
Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm.
- The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per ceil parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions.
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.
- Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.
C.1 The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.
( continued)
SUSQUEHANNA - UNIT 1 B 3.3-17b
Rev. 4 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued)
Because the ability of the OPRM Channel to perform its safety function is not affected by these parameter settings, the affected OPRM Channel need not be immediately considered inoperable when these conditions are not met.
These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification.
Since the Amplitude and Growth Rate Based parameters affect only the defens~-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.
This Action is fo be taken if the Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required.
E.1 As directed from Required Action D.1, this. Action provides preemptive protection through Power/Flow Map operating restrictions When operating in Region I of the Power/ Flow map specified in the COLR, or when operating in Region II of the Power/ Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
( continued)
SUSQUEHANNA - UNIT 1 B 3.3-17c
Rev.4 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS F.1
( continued)
As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION.
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, 8, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings.in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
As directed from Required Action D.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 70% rod line is prohibited due to potential instability problems.
(continued)
SUSQUEHANNA - UNIT 1 B 3.3-17d
Rev. 4 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS H.1
( continued)
TRS The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.
TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power
/ Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic instability. The Power/ Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and the operator's inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.
TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.
(continued)
SUSQUEHANNA - UNIT 1 B 3.3-17e
Rev. 4 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRS (continued)
TRS 3.3.9.3 The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18.
REFERENCES
- 1. NED0-31960-A, BWROG Long Term Solution Licensing Methodology
- 2. NED0-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology
- 3. NED0-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications
- 4. Deleted
- 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors
- 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation
- 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984
- 8. Letter, L. A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994
- 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," Novembe~ 1999
- 10. NEDC-3241 OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option Ill Stability Trip Function" SUSQUEHANNA - UNIT 1 B 3.3-17f
Rev.3 Reactor Recirculation Single Loop Operation (SLO) Flow Rate Restriction B 3.4.6 B 3.4.6 Reactor Recirculation Single Loop Operation (SLO) Flow Rate Restriction BASES TRO TRO 3.4.6 requires that the operating loop flow rate be maintained less than or equal to 54.0 Mlbm/hr during single loop operation. Single loop operation includes events that require a recirculation loop to be declared "not in operation" due to Technical Specification 3.4.1 Condition B. Note that the parameter of concern is the 3 minute average recirculation system loop flow (e.g., Plant Process Computer (PPC) point NJF02B and NJF03B) not core flow. This restriction avoids excessive vibration of jet pump components.
Fatigue usage can be accumulated when loop flow rates are above 54 Mlbm/hr if large gaps are present. Excessive vibration can lead to cracking of the Jet pump riser brace welds. The limitation contained in this TRO will assure jet pump integrity will be maintained and thus the FSAR Chapter 15 analysis assumption of maintaining 2/3 core height will be met. Additionally, these measures will assure asset preservation and avoid lengthy repairs due to potential riser brace cracking. The required action to place the reactor mode switch in shutdown in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> assures the flow rate is established within limits. The time frames are required to avoid excessive vibrations that occur at higher loop flow rates and the subsequent impact on jet pump riser brace.
APPLICABILITY This Requirement is applicable whenever in reactor recirculation single loop operation in Modes 1 and 2. Single loop operation includes events that require a recirculation loop to be declared "not in operation" due to Technical Specification 3.4.1 Condition B.
ACTIONS The Actions assure that excessive jet pump vibration can not occur when in single loop operation.
TRS The required surveillance assures that the maximum loop flow rate is not exceeded.
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SUSQUEHANNA - UNIT 1 B 3.4-7
Rev. 3 Reactor Recirculation Single Loop Operation (SLO) Flow Rate Restriction B 3.4.6 B 3.4.6 Reactor Recirculation Single Loop Operation (SLO) Flow Rate Restriction BASES REFERENCES
- 1.
FSAR Section 15.6
- 2.
GE Report 0000-0144-9821 R1, "Jet Pump 11 and 12 Fatigue Usage Reduction Detailed Analysis" July 2012.
SUSQUEHANNA - UNIT 1 B 3.4-8
Rev. 1 CO2 Systems B 3.7.3.3 B 3.7.3.3 C02Systems BASES TRO ACTIONS The OPERABILITY of the fire suppression CO2 systems is one part of ensuring that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water supply system, spray and sprinkler systems, CO2 systems, Halon systems, fire hose stations, and fire hydrants. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
Removal *of any floor panel in a CO2 protected area can cause the affected CO2 system to become inoperable if the floor panel must be left open and unattended or cannot be immediately closed.
The basis for those systems included within the scope of this TRO includes both Safety Related and Safe Shutdown system protection. The CO2 system is described in the FPRR.
The Actions are defined to ensure proper corrective measures and compensatory actions are taken in response to the inoperable systems or components.
Hourly Firewatch Patrols shall be completed once each clock hour.
Individual zones on the hourly firewatch patrol shall be toured at intervals (i.e. - zone A and back to zone A) of sixty minutes with a margin of fifteen minutes. These are required (Condition C) for areas other than where redundant equipment could be damaged by fire.
A Continuous Firewatch must remain in the specified area at all times and must patrol the required fire zones in the specified area at least once per fifteen minutes with a margin of five minutes. The specified area can be as small as one fire zone or as large as a firewatch can reasonably patrol within the fifteen minute time period. The specified area is limited to two floors of the Control Structure or Reactor Buildings. The floors must be adjacent or served by an operable elevator. These are required (Condition B) for areas where redundant equipment could be damaged by fire.
( continued)
SUSQUEHANNA - UNIT 1 B 3.7-7
Rev. 1 CO2 Systems B 3.7.3.3 B 3.7.3.3 C02Systems ACTIONS (continued)
TRS REFERENCES Areas exist within the plant where the posting of a firewatch does not provide acceptable radiological ALARA practices. For these inaccessible areas, alternate measures should be taken to assure an adequate level of fire protection is maintained.
The TRSs provide assurance that the minimum OPERABILITY requirements of the fire suppression CO2 systems are met.
TRS 3.7.3.3.4 The purpose of the "puff test" is to verify that there are no obstructions/blockages in the CO2 system headers or nozzles. The use of air or nitrogen is acceptable for use in the performance of the puff test.
- 1.
FPRR Section 4.8.
SUSQUEHANNA - UNIT 1 B 3.7-7a