ML18033A331
| ML18033A331 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/24/2018 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2018-1636 | |
| Download: ML18033A331 (22) | |
Text
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SSES MANUAL Manual Name~ TSBl
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TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 01/23/2018 Procedure Name Rev Issue Date Change ID Change Number TEXT LOEB 130 01/23/2018
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LIST OF EFFECTIVE SECTIONS TEXT TOC 23 07/02/2014 ,,i':--:=<,)
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TABLE OF CONTENTS "'\,, }
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REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)
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REACTIVITY CONIT'ROL, SYSTE:'iJis REACTIVITY ANOMALIES I \ '\ \ .,
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Title:
REACTIVITi \
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SYSTEMS CONTROL ROD OPERABILITY TEXT 3 .1.4 5 11/16/2016
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3 .1. 5 2 11/16/2016
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3 .1. 6 4 11/16/2016
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Page .1. of 8 Report Date: 01/23/18
SSES MANUAL Manual Name: TSBl
- ,_anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3 .1. 7 4 11/16/2016
Title:
REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 4 11/16/2016
Title:
REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 3 11/16/2016 Title~ POWER DISTRIBUTION LIMITS AVEP~~GE PLn~~AR LINEAR HEAT GENER..~TIQN R..~TE (APLHGR) 4 11/16/2016
Title:
POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
TEXT 3.2.3 3 11/16/2016
Title:
POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)
- " .*'EXT 3 . 3 . 1 . 1 7 11/16/2016
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 4 01/23/2018
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 5 11/16/2016
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 3 11/16/2016
Title:
INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.l 10 11/16/2016
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 2 11/16/2016
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 3 11/16/2016
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION
- Page~ of 8 Report Date: 01/23/18
SSES MANUAL Manual Name: TSBl
~*anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.2 1 11/16/2016
Title:
INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 4 11/16/2016
Title:
INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM .(ECCS) INSTRUMENTATION TEXT 3.3.5.2 1 11/16/2016 Tit.le: INSTRT.JMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION" 8 11/16/2016
Title:
INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 5 11/16/2016
Title:
INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION
~'EXT 3.3.7.1 3 11/16/2016
Title:
INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 3 11/16/2016
Title:
INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 1 11/16/2016
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 5 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 4 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) JET PUMPS TEXT 3.4.3 3 01/13/2012
Title:
REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVS TEXT 3.4.4 1 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Page .l of 8 Report Date: 01/23/18
SSES MANUAL Manual Name: TSB1
- *anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 2 04/13/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 5 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 3 11/16/2016 Title; RE;.~CTOR COOIJl.. .NT SYSTEM (RCS) RCS SPECIFIC ACTIVITY 3 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM
- HOT SHUTDOWN TEXT 3.4.9 2 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL {RHR) SHUTDOWN COOLING SYSTEM
- COLD SHUTDOWN
- C_*,+/-~lEXT 3 .4 .10 5 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 1 11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 5 11/16/2016
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - OPERATING TEXT 3.5.2 1 11/16/2016
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 5 05/31/2017
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM RCIC SYSTEM TEXT 3.6.1.1 6 11/16/2016
Title:
PRIMARY CONTAINMENT TEXT 3.6.1.2 2 11/16/2016
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page i of 8 Report Date: 01/23/18
SSES MANUAL Manual Na.me: TSBl
~ianual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.3 13 11/16/2016
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)
TEXT 3.6.l.4 2 11/16/2016
Title:
CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 2 11/16/2016 Title~ CONTAINMENT SYSTEMS DRYWELL }1,.IR TEMPEP-ll.TURE
".L 11/16/2016
Title:
CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 3 11/16/2016
Title:
CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE
.'EXT 3.6.2.2 1 11/16/2016
Title:
CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL TEXT 3.6.2.3 2 11/16/2016
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING TEXT 3.6.2.4 1 11/16/2016
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 2 06/13/2006
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 3 09/29/2017
Title:
CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM LDCN 5296 TEXT 3.6.3.3 3 09/29/2017
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3.6.4.1 13 04/19/2017
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~ of 8 Report Date: 01/23/18
SSES MANUAL Manual Name: TSB1
. ~~anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 12 04/19/2017
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.6.4.3 6 09/15/2017
Title:
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 5 11/16/2016 Title~ PLP..NT SYSTEMS RESIDUAL HEltT REMOV:AT. SERVICE WATER (RHRSW) SYSTEM AND THE Ul.JT.LlVL~TJ:!i HEAT SINK (UHS) 3 11/=1:.6/2016
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM TEXT 3.7.3 3 09/15/2017
Title:
PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 1 11/16/2016
Title:
PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 2 11/16/2016
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3.7.6 3 11/16/2016
Title:
PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEX'.!' 3. 7. 7 2 11/16/2016
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.7.8 1 11/16/2016
Title:
PLANT SYSTEMS TEXT 3.8.l 8 11/16/2016
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING TEXT 3.8.2 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN Page _§_ of 8 Report Date: 01/23/18
SSES MANUAL Manual Name: TSBl
~*anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 6 12/14/2017
Title:
ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 4 11/16/2016
Title:
ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING TEXT 3.8.5 1 12/14/2006
Title:
ET."RC'l'RTf'AT, POWER SYSTEMS DC SOURCES - ShTUTDOWN TEXT 3.8.6 2 11/16/2016
Title:
ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 2 11/16/2016
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - OPERATING
~\~XT 3.8.8 1 11/16/2016
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 1 11/16/2016
Title:
REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 2 11/16/2016
Title:
REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 1 11/16/2016
Title:
REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002.
Title:
REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 1 11/16/2016
Title:
REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.6 2 11/16/2016
Title:
REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page ']_ of 8 Report Date: 01/23/18
SSES MANUAL Manual Name: TSBl
.. ~anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 1 11/16/2016
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH WATER LEVEL TEXT 3.9.8 1 11/16/2016
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1 1 01/23/2008
Title:
SPECI!-.L OPEP-Il.TIONS INSERVICE LEAK l--..ND HYDROSTATIC TESTING OPEP~Il.TION
".L 11/16/2016
Title:
SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 1 11/16/2016
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN
- 'EXT 3 . 10 . 4 1 11/16/2016
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 1 11/16/2016
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING TEXT 3.10.6 1 11/16/2016
Title:
SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 1 04/18/2006
Title:
SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 2 11/16/2016
Title:
SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Page _§. of 8 Report Date: 01/23/18
SUSQUEHANNA STEAM ELECTRIC STATION
- LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section TOG Table of Contents ............................................................... , ............................... 23 Revision B 2.0 SAFETY LIMITS BASES B2.1.1 Reactor Core SLs ............................................................................................... 6 82.1.2 Reactor Coolant System (RCS) Pressure SL.. .................................................... *1 B 3.0 LCO AND SR APPLICABILITY BASES .............................................................. 3 B 3.1 REACTIVITY CONTROL BASES B3.1.1 Shutdown Margin (SOM) ..................................................................................... 2 B3.1.2 Reactivity Anomalies .......................................................................................... 1 B3.1.3 Control Rod OPERABILITY ................................................................................ 3 B3.1.4 Control Rod Scram Times ................................................................................... 5 B3.1.5 Control Rod Scram Accumulators ....................................................................... 2 83.1.6 Rod Pattern Control ............................................................................................ 4 83.1.7 Standby Liquid Control (SLC) System ................................................................. 4 83.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ..................................... 4 B 3.2 POWER DISTRIBUTION LIMITS BASES
- 83.2.1 83.2.2 83.2.3 B 3.3 Average Planar Linear Heat Generation Rate (APLHGR) ................................... 3 Minimum Critical Power Ratio (MCPR) ............................................................... 4 Linear Heat Generation Rate (LHGR) ................................................................. 3 INSTRUMENTATION 83.3.1.1 Reactor Protection System (RPS) instrumentation ............................................. 7 83.3.1.2 Sou rco Range l\.,1onifr.r rc:::0*1,ll)
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B3.3.2.1 Control Rod Block Instrumentation ..................................................................... 5 83.3.2.2 Feedv.rater - Main Turbine High Water Level Trip Instrumentation ...................... 3
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!:i,:),.:i . .5. I Post .1\ccident Monitoring (PAJVi) instlurnentation ............................................... 1O 83.3.3.2 Remote Shutdown Sys tern ................................................................................. 2
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83.3.4.1 vy,.*v~:; :,~'!.....B\.,Uh-:.JUll I 111p \ , ' - - --,-.... I 11* ,., LI 1:. ..**.*..*....*.*.*. '2 83.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ............................................................ 1 83.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation ................................. 4 83.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ......................... 1 83.3.6.1 Primary Containment Isolation Instrumentation ................................................... 8
- B3.3.6.2 Secondary Containment Isolation Instrumentation .............................................. 5 83.3.7.1 Control Room Emergency Outside Air Supply (CREOAS) ................................. 3 B3.3.8.1 Loss of Power (LOP) Instrumentation ................................................................. 3 83.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring .............................. 1
- SUSQUEHANNA - UNIT 1 TS I B LOES-1 Revision 130
SUSQUEHANNA STEAM ELECTRIC STATION
- LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section 8 3.4 Title REACTOR COOLANT SYSTEM BASES Revision 83.4.1 Recirculation Loops Operating ............................................................................ 5 B3.4.2 Jet Pumps ....................................................................................................... 4 83.4.3 Safety/Relief Valves (S/RVs) .............................................................................. 3 83.4.4 RCS Operational LEAKAGE .............................................................................. 1 83.4.5 RCS Pressure Isolation Valve (PIV) Leakage ..................................................... 2 83.4.6 RCS Leakage Detection Instrumentation ............................................................ 5 B3.4.7 RCS Specific Activity .......................................................................................... 3 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................................................................... 3 83.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................................................................... 2 B3.4.10 RCS Pressure and Temperature (PIT) Limits ..................................................'.... 5 B3.4.11 Reactor Steam Dome Pressure ............................................................:............. 1 B3.5 ECCS AND RCIC BASES 83.5.1 ECCS - Operating .............................................................................................. 5 83.5.2 ECCS = Shutdown .............................................................................................. 1 83.5.3 RCIC System ...................................................................................................... 5
- 83.6 83.6.1.1 B3.6.1.2 83.6.1.3 CONTAINMENT SYSTEMS BASES Primary Containment .......................................................................................... 6 Primary Containment Air Loci< ............................................................................ 2 Primary Containment Isolation Valves (PCIVs) .................................................. 13 83.6.1.4 Containment Pressure ........................................................................................ 2 83.6.1.5 Dryv.ieil /\it Temperature ............... u ............................................. u .. ,, . . . . . . . . . . . . . . . . . . . 2 83.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers .......................................... 1 83.6.2.1 Suppression Pool Average Temperature ............................................................ 3 8~.6.~.~ Suppression Pool \t\later Leve! ..................................... u ******************* u **************** 1 83.6.2.3 Residual Heat Removai (RHR) Suppression Pool Cooling ................................. 2 83.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spiay .................................... 1 B3.6.3.1 Not Used ....................................................................................................... 2 B3.6.3.2 Drywall Air Flow System ..................................................................................... 3 83.6.3.3 Primary Containment Oxygen Concentration ...................................................... 3 83.6.4.1 Secondary Containment .................................................................................... 13 B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................................. 12 83.6.4.3 Standby Gas Treatment (SGT) System .............................................................. 6
- SUSQUEHANNA - UNIT 1 TS I B LOES-2 Revision 130
SUSQUEHANNA STEAM ELECTRIC STATION
- LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section 83.7 Title PLANT SYSTEMS BASES Revision 83.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink {UHS) ...................................................................... 5 B3.7.2 Emergency Service Water (ESW) System .......................................................... 3 83.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ..................... 3 83.7.4 Control Room Floor Cooling System ................................................................... 1 83.7.5 Main Condenser Offgas ...................................................................................... 2 83.7.6 Main Turbine Bypass System ............................................................................. 3 83.7.7 Spent Fuel Storage Pool Water Level. ................................................................ 2 B3.7.8 Main Turbine Pressure Regulation System ......................................................... 1 B3.8 ELECTRICAL POWER SYSTEMS BASES 83.8.1 AC Sources - Operating ..................................................................................... 8 83.8.2 AC Sources-Shutdown ..................................................................................... 0 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ........................................................... 6 83.8.4 DC Sources - Operating ..................................................................................... 4 83.8.5 DC Sources - Shutdown..................................................................................... 1 83.8.6 Battery Cell Parameters ...................................................................................... 2 B3.8.7 Distribution Systems - Operating ........................................................................ 2
- 83.8.8 83.9 83.9.1 83.9.2 Distribution Systems - Shutdown ....................................................................... 1 REFUELING OPERATIONS BASES Refueling Equipment Interlocks .......................................................................... 1 Refuel Position One-Rod-Out Interlock ............................................................... 1 B3.9.3 Control Rod Position ........................................................................................... 1 83.9.4 Control Red Position indication ........................................... :............................... O 83.9.5 Control Rod OPERABILITY - Refueling ............................................................. 1 83.9.6 Reactor Pressure Vessel (RP\/) Water Level. ..................................................... 2
.,..,.,,.., n ""'7 t:i.:'.l.:::i./ Residua! Heat Rernovai (RHR)- High VVat..er Leve! ................... u ....................... *1 83.9.8 Residual Heat Removal (RHR) - Low Water Level. ............................................ 1 B3.10 SPECIAL OPERATIONS BASES 83.10.1 lnservice Leak and Hydrostatic Testing Operation .............................................. 1 83.10.2 Reactor Mode Switch Interlock Testing ............................................................... 1 83.10.3 Single Control Rod Withdrawal - Hot Shutdown ................................................. 1 83.10.4 Single Control Rod Withdrawal-Cold Shutdown ............................... ;........... ;... 1 83.10.5 Single Control Rod Drive (CRD) Removal - Refueling ........................................ 1 83.10.6 Multiple Control Rod Withdrawal - Refueling ...................................................... 1 83.10.7 Control Rod Testing - Operating ........................................................................ 1 83.10.8 Shutdown Margin (SOM) Test - Refueling .......................................................... 2
- SUSQUEHANNA - UNIT 1 TS I B LOES-3 Revision 130
Rev.4 SRM Instrumentation
- B 3.3 INSTRUMENTATION 8 3.3.1.2 Source Range Monitor (SRM) Instrumentation B 3.3.1.2 BASES BACKGROUND The SRMs provide the operator with information relative to the neutron flux level at startup and low flux levels in the core. As such, the SRM indication is used by the operator to monitor the approach to criticality and determine when criticality is achieved. The SRMs are not fully withdrawn from the core until the SRM to intermediate range monitor (IRM) overlap is demonstrated (as required by SR 3.3.1.1.6), wl1en the SRMs are normally fully withdrawn from the core.
The SRM subsystem of the Neutron Monitoring System (NMS) consists of four channels. Each of the SRM channels can be bypassed, but only one at any given time, by the operation of a bypass switch. Each channel includes one detector that can be physically positioned in the core. Each detector assembly consists of a miniature fission chamber with associated cabling, signal conditioning equipment, and electronics associated with the various SRM functions. The signal conditioning equipment converts the current pulses from the fission'chamber to analog
- DC currents that correspond to the count rate. Each channel also includes indication, alarm, and control rod blocks. However, this LCO specifies OPERABILITY requirements only for the monitoring and indication functions of the SRMs.
During refueling, shutdovm, and low power operations, the primary indication of neutron flux levels is provided by the SRMs or special movable detectors connected to the normal SRM circuits. The SRMs provide monitoring of reactivity changes during fuel or control rod movement and give the control room operator early indication of unexpected subcriticai muiiip!ication that couid be indicative of an approach to crit1caHty.
APPLICABLE Prevention and mitigation of prompt reactivity excursions during SAFETY refueling and low power operation is provided by LCO 3.9.1, "Refueling ANALYSES Equipment Interlocks"; LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";
LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation"; IRM Neutron Flux-High and Average Power Range Monitor (APRM)
Neutron Flux-High
- SUSQUEHANNA- UNIT 1 TS/ B 3.3-35 (continued)
Revision 2
Rev. 4 SRM Instrumentation
- BASES APPLICABLE (Setdown) Functions; and LCO 3.3.2.1, "Control Rod Blocl<
B 3.3.1.2 SAFETY Instrumentation."
ANALYSES (continued) The SRMs have no safety function and are not assumed to function during any FSAR design basis accident or transient analysis. However, the SRMs provide the only on-scale monitoring of neutron flux levels during startup and refueling. Therefore, they are being retained in Technical Specifications.
LCO During startup in MODE 2, three of the four SRM channels are required to be OPERABLE to monitor the reactor flux level prior to and during control rod withdrawal, subcritical multiplication and reactor criticality, and neutron flux level and reactor period until the flux level is sufficient to maintain the IRMs on Range 3 or above. All but one of the channels are required in order to provide a representation of the overall core response during those periods when reactivity changes are occurring throughout the core.
In MODES 3 and 4, with the reactor shut down, two SRM channels provide redundant monitoring of flux levels in the core.
In MODE 5, during a spiral offload or reload, an SRM outside the fueled region will no longer be required to be OPERABLE, since it is not capable of monitoring neutron flux in the fueled region of the core. Fueled region is a continuous area with fuel. Thus, CORE ALTERAT!ONS are allowed in a quadrant with no OPERABLE SRM in an adjacent quadrant provided the Table 3.3.1.2-1, footnote (b), requirement that the bundles being spiral reloaded or spiral offloaded are all in a single fueled region containing at least one OPERi\BLE: SR.tvi is met. Spiral reloading and offloading encompass reioading or offloading a ceii on the edge of a continuous fueled region (the cell can be reloaded or offloaded in any sequence).
In nonspiral routine operations, two SRMs are required to be OPERABLE to provide redundant monitoring of reactivity changes occurring in the reactor core. Because of the local nature of reactivity changes during refueling, adequate coverage is provided by requiring one SRM to be OPERABLE in
- SUSQUEHANNA- UNIT 1 TS/ B 3.3-36 (continued)
Revision 2
Rev.4 SRM Instrumentation
- BASES LCO the quadrant of the reactor core where CORE ALTERATIONS are being performed, and the other SRM to be OPERABLE in an adjacent quadrant B 3.3.1.2 (continued) containing fuel. These requirements ensure that the reactivity of the core will be continuously monitored during CORE ALTERATIONS.
Special movable detectors, according to footnote (c) of Table 3.3.1.2-1, may be used during CORE ALTERATIONS in place of the normal SRM nuclear detectors. These special detectors must be connected to the normal SRM circuits in the NMS, such that the applicable neutron flux indication can be generated. These special detectors provide more flexibility in monitoring reactivity changes during fuel loading, since they can be positioned anywhere within the core during refueling. They must still meet the location requirements of SR 3.3.1.2.2 and all other required SRs for SRMs.
For an SRM channel to be considered OPERABLE, it must be providing neutron flux monitoring indication.
APPLICABILITY The SRMs are required to be OPERABLE in MODES 2, 3, 4, and 5 prior to the IRMs being on scale on Range 3 to provide for neutron monitoring.
In MODE 1, the APRMs provide adequate monitoring of reactivity changes in the core; therefore, the SRMs are not required. In MODE 2, with IRMs on Range 3 or above, the IRMs p*rovide adequate monitoring and the SRMs are not required.
ACTIONS A.1 and B.1 means cf monitoring core reactivity and criticaiity. itVith any number of the iequired SRMs inoperabie, the ability to monitor neutron flux is degraded. Therefore, a iimited time ls ailowed to restore the inoperabie channels to OPERABLE status.
Provided at least one SRM remains OPERABLE, Required Action A.1 allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore the required SRMs to OPERABLE status. This time is reasonable because there is adequate capability remaining to monitor the core, there is (continued)
SUSQUEHANNA - UNIT 1 TS I B 3.3-37 Revision 1
Rev.4 SRM Instrumentation
- BASES ACTIONS A.1 and B.1 (continued)
B 3.3.1.2 limited risk of an event during this time, and there is sufficient time to take corrective actions to restore the required SRMs to OPERABLE status or to establish alternate IRM monitoring capability. During this time, control rod withdrawal and power increase is not precluded by this Required Action. Having the ability to monitor the core with at least one SRM, proceeding to IRM Range 3 or greater (with overlap required by SR 3.3.1.1.6), and thereby exiting the Applicability of this LCO, is acceptable for ensuring adequate core monitoring and allowing continued operation.
With three required SRMs inoperable, Required Action B.1 allows no positive changes in reactivity (control rod withdrawal must be immediately suspended) due to inability to monitor the changes. Required Action A.1 still applfes and allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore monitoring capability prior to requiring control rod insertion. This allowance is based on the limited risk of an event during this time, provided that no control rod withdrawals are allowed, and the desire to concentrate efforts on repair, rather than to immediately shut down, with no SRMs OPERABLE .
- In MODE 2, if the required number of SRMs is not restored to OPERABLE status within the allowed Completion Time, the reactor shall be placed in MODE 3. With all control rods fully inserted, the core is in its least reactive state with the most margin to criticality. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach iv10DE 3 from fuH pov,er conditions !n an orderiy D.1 and D.2 With one or more required SRMs inoperable in MODE 3 or 4, the neutron flux monitoring capability is degraded or nonexistent. The requirement to fully insert all insertable control rods ensures that the reactor will be at its minimum reactivity level while no neutron monitoring capability is available. Placing the reactor mode switch in the shutdown position prevents subsequent control rod withdrawal by (continued)
SUSQUEHANNA - UNIT 1 TS I B 3.3-38 Revision 1
Rev.4 SRM Instrumentation
- BASES ACTIONS D.1 and 0.2 (continued)
B 3.3.1.2 maintaining a control rod block. The allowed Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is sufficient to accomplish the Required Action, and tal<es into account the low probability of an event requiring the SRM occurring during this interval.
E.1 and E.2 With one or more required SRM inoperable in MODE 5, the ability to detect local reactivity changes in the core during refueling is degraded.
CORE ALTERA TIONS must be immediately suspended and action must be immediately initiated to fully insert all insertable control rods in core cells containing one or more fuel assemblies. Suspending CORE ALTERA TIONS prevents the two most probable causes of reactivity changes, fuel loading and control rod withdrawal, from occurring.
Inserting all insertable control rods ensures that the reactor will be at its minimum reactivity given that fuel is present in the core. Suspension of CORE ALTERA TIONS shall not preclude completion of the movement of a component to a safe, conservative position .
Action (once required to be initiated) to insert control rods must continue until all insertable rods in core cells containing one or more fuel assemblies are inserted.
SURVEILLANCE The SRs for each SRM Applicable MODE or other specified conditions REQUIREMENTS are found in the SRs column of Table 3.3.1.2-1.
SR 3.3.1.2.1 and SR 3.3.1.2.3 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it (continued)
SUSQUEHANNA - UNIT 1 TS I B 3.3-39 Revision 2
Rev. 4 SRM Instrumentation
- BASES SURVEILLANCE REQUIREMENTS SR 3.3.1.2. 'I and SR 3.3.1.2.3 (continued)
B 3.3.1.2 is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria which are determined by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support tl1is parameter comparison and include indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit, and does not necessarily indicate the channel is Inoperable.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The CHANNEL CHECK supplements less formal checks of channels during normal operational use of the displays associated with the channels required by the LCO.
- To provide adequate coverage of potential reactivity changes in the core, a maximum of two SRMs are required to be OPERABLE. One SRM is required to be OPERABLE in the quadrant where CORE ALTERATIO NS are being performed, and the other OPERABLE SRM must be in an adjacent quadrant containing fuel. However, in accordance with Table 3.3.1.2-'i, only one SRM is required during a spiral reload until the fueled region is large enough to encompass a second installed SRM. Note 1 states that the SR is required to be met only during CORE ALTERA TIONS. It is not required to be met at other times in MODE 5 since corg reactivity changes are not occurring. This SurveHiance wu11:si:s!.:s ui" d Itivitiw o! t-Jic:1111 ioys i.u 1::11:su1 ti ti ii::!L SRiv'i:s ,1:::yui, tiu i.u Utl OPERABLE for given CORE ALTERATIONS are, in fact, OPERABLE. in the event that only one SRM is required to be OPERABLE, per Table 3.3.1.2-1, footnote (b), only the a. portion of this SR is required.
Note 2 clarifies that more than one of the three requirements can be met by the same OPERABLE SRM. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
SUSQUEHANNA - UNIT 1 TS/ B 3.3-40 Revision 2
Rev. 4 SRM lnstrL1mentation
- BASES SURVEILLANCE REQUIREMENTS B 3.3.1.2 SR 3.3.1.2.4 This Surveillance consists of a verification of the SRM instrL1ment readout to ensure that the SRM reading is greater than a specified minimum count rate, which ensures that the detectors are indicating count rates indicative of neutron flux levels within the core. The signal-to-noise ratio shown in Figure 3.3.1.2-1 is the SRM count rate at which there is a 95%
probability that the SRM signal indicates the presence of neutrons and only a 5% probability that the SRM signal is a result of noise (Ref. 1).
With few fuel assemblies loaded, the SRMs will not have a high enough count rate to satisfy the SR. Therefore, allowances are made for loading sufficient "source" material, in the form of irradiated fuel assemblies, to establish the minimum count rate.
To accomplish this, the SR is modified by a Note that states that the
- count rate is not required to be met on an SRM that has less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies are in the associated core quadrant. With four or less fuel assemblies loaded around each SRM and no other fuel assemblies in the associated core quadrant, even with a control rod withdrawn, the configuration will not be critical.
The Surveiiiance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.3. i .2.5 and SR 3.3. i .2.6 Performance of a CHANNEL FUNCTIONAL TEST demonstrates the associated channel will function properly. SR 3.3.1.2.5 is (continued)
SUSQUEHANNA - UNIT 1 TS I B 3.3-41 Revision 2
Rev. 4 SRM Instrumentation
- BASES SURVEILLANCE REQUIREMENTS SR 3.3.1.2.5 and SR 3.3.1.2.6 (continued)
B 3.3:1.2 required in MODE 5, and ensures that the channels are OPERABLE while core reactivity changes could be in progress. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.3.1.2.6 is required in MODE 2 with IRMs on Range 2 or below, and in MODES 3 and 4. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
Verification of the signal to noise ratio also ensures that the detectors are inserted to an acceptable operating level. In a fully withdrawn condition, the detectors are sufficiently removed from the fueled region of the core to essentially eliminate neutrons from reaching the detector. Any count rate obtained while the detectors are fully withdrawn is assumed to be "noise" only.
The Note to the Surveillance allows the Surveillance to be delayed until entry into the specified condition of the Applicability (THERMAL POWER
- decreased to IRM Range 2 or below). The SR must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after IRMs are on Range 2 or below. The allowance to enter the Applicability with the Frequency not met is reasonable, based on the limited time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed after entering the Applicability and the inability to perform the Surveillance while at higher power levels.
Although the Surveillance could be performed while on IRM Range 3, the
- .:::;--.. ~-. -:~*
~ .
plant would not be expected to maintain steady state operation at this power level. In this event, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable, based on the SRMs being otherwise verified to be OPERABLE (i.e.,
satisfactorily performing the CH~!\f\Jf'{EL CHECK) and th time required to per iu11 r I ti 1e Sur veii!c:tr 1CeS.
(continued)
-f~~=f SUSQUEHANNA - UNIT 1 TS/ B 3.3-42 Revision 3
Rev. 4 SRM Instrumentation
- BASES SURVEILLANCE REQUIREMENTS SR 3.3.1.2.7 8 3.3.1.2 (continued) Performance of a CHANNEL CALIBRATION verifies the performance of the SRM detectors and associated circuitry. The Frequency considers the plant conditions required to perform the test, the ease of performing the test, and the likelihood of a change in the system or component status. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program,.The neutron detectors are excluded from the CHANNEL CALIBRATION because they cannot readily be adjusted. The detectors are fission chambers that are designed to have a relatively constant sensitivity over the range and with an accuracy specified for a fixed useful life.
Note 2 to the Surveillance allows the Surveillance to be delayed until entry into the specified condition of the Applicability. The SR must be performed in MODE 2 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 with IRMs on Range 2 or below. The allowance to enter the Applicability with the Frequency not met is reasonable, based on the limited time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed after entering the Applicability and the inability to perform the
- Surveillance while at higher power levels. Although the Surveillance could be performed while on IRM Range 3, the plant would not be expected to maintain steady state operation at this power level. In this event, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable, based on the SRMs being otherwise verified to be OPERABLE (i.e., satisfactorily performing the CHANNEL CHECK) and the time required to perform the Surveillances.
REFERENCES 1. General Electric Service Information Letter (SIL) 478 "SRM Minimum Count Rateii dated December 16, 1988~
(continued)
SUSQUEHANNA - UNIT 1 TS I B 3.3-43 Revision 2