ML18033A334

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Technical Specifications Bases Manual
ML18033A334
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 01/24/2018
From:
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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L.V..LU MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2018-1836 USER INFORMATION:

GERLACH*ROSEY M Address: NUCSA2 Phone#:

542-3194 EMPL#: 028401 CA#:

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TENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no C will be issued with the updated material.

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TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 01/04/2018 ADD MANUAL TABLE OF CONTENTS DATE: 01/23/2018 CATEGORY: DOCUMENTS TYPE: TSB2 ID:

TEXT 3.3.1.2 ADD:

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TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date:

01/23/2018 Procedure Name TEXT LOES Rev 134

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LIST OF EFFECTIVE SECTIONS Issue Date 01/23/2018 Change ID Change Number

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01/22/2015 Title; SAFETY LIMITS (SLS) REACTOR CORE SLS

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REACTIVITY CONTROL SYS!I'EMS REACTIVITY ANOMALIES

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REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY

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11/16/2016

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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:

TSB2

:,: Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 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 5

11/16/2016 Title; POWER DISTRIBUTION LIMITS AVERAGE PL_/:\\NAR LINE~..R HEAT GENEP~~TION R.~TE (APLHGR)

TEXT 3.2.2 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 6

11/16/2016 t~<= ':f TEXT 3. 3. 1. 1

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 4

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 9

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 2

11/16/2016

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION

  • Page~

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Report Date: 01/23/18

SSES MANUAL Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 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 6

11/16/2016

Title:

INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 1

11/16/2016

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 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

.i TEXT 3.3.7.1 3

11/16/2016

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 4

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 Pagel of 8

Report Date: 01/23/18

SSES MANUAL Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.5 3

03/10/2010

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; REACTOR COOL_A_NT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 3

11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM HOT SHLJTDO~"'N TEXT 3.4.9 2

11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM COLD SHUTDOWN TEXT 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 3

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!

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TSB2

- -*-* Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3. 6. 1. 3 16 04/19/2017

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

TEXT 3. 6. 1. 4 2

11/16/2016

Title:

CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3. 6. 1. 5 2

11/16/2016

Title:

CONTAINMENT SYSTEMS DRYWELL AIR TEMPER.~TURE TEX'r 3. 6. 1. 6 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

.#TEXT 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

Title:

CONTAINMENT SYSTEMS TEXT 3.6.3.2 2

3 06/13/2006 INTENTIONALLY LEFT BLANK 09/29/2017

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM LDCN TEXT 3.6.3.3 3

09/29/2017

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3.6.4.1 14 04/19/2017

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT 5297 Page~

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Report Date: 01/23/18

SSES MANUAL Manual Name:

TSB2

,;"' Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 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 7

03/01/2017

Title:

PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM ~.ND THE ULTIMATE HEAT SINK (UHS)

'I'EX'l' 3. 7. 2 3

11/16/2016

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 TEXT 3.7.4 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 4

11/16/2016

Title:

PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 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:

MAINE TURBINE PRESSURE REGULATION SYSTEM TEXT 3.8.1 10 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

OPERATING TEXT 3.8.2 0

11/18/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

SHUTDOWN Page_§_

of 8

Report Date: 01/23/18

  • .j SSES MANUAL Manual Name:

TSB2

.. : *Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 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:

ELECTRICAL POWER SYSTEMS DC SOURCES -

SHUTDOWN

'l'EXT 3. 8. 6 2

11/16/2016

Title:

ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 6

03/01/2017

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -

OPERATING TEXT 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

11/18/2002

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:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 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 Titleg REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -

LOW WATER LEVEL TEXT 3.10.1 1

01/23/2008

Title:

SPECIAL OPERATIONS INSERVICE LE~_K AND HYDROSTATIC TESTING OPER.~TION

'l'EX.'l' 3.10. 2 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

/ TEXT 3.10. 4 1

11/16/2016 Titleg 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

03/24/2005

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING -

OPERATING TEXT 3.10.8 3

11/16/2016

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST -

REFUELING Page.§_

of

.§_

Report Date: 01/23/18

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision TOC B 2.0 B2.1.1 82.1.2 B 3.0 B 3.1 83.1.1 83.1.2 83.1.3 83.1.4 83.1.5 83.1.6 83.1.7 83.1.8 8 3.2 83.2.1 83.2.2 83.2.3 8 3.3 Table of Contents.............................................................................................. 23 SAFETY LIMITS (SLs)

Reactor Core SLs............................................................................................... 5 Reactor Coolant System (RCS) Pressure SL...................................................... 1 LCO AND SR APPLICABILITY BASES.............................................................. 3 REACTIVITY CONTROL SYSTEMS Shutdown Margin (SDM)........................................................... ;......................... 2 Reactivity Anomalies.......................................................................................... 1 Control Rod OPERABILITY............................................................. :.................. 3 Control Rod Scram Times................................................................................... 5 Control Rod Scram Accumulators....................................................................... 2 Rod Pattern Control............................................................................................ 4 Standby Liquid Control (SLC) System................................................................. 3 Scram Discharge Volume (SDV) Vent and Drain Valves.....................................4 POWER DISTRIBUTION LIMITS Average Planar Linear Heat Generation Rate (APLHGR)................................... 5 Minimum Critical Power Ratio (MCPR)............................................................... 4 Linear Heat Generation Rate (LHGR)................................................................. 3 INSTRUMENTATION 83.3. i. i Reactor PiOtection System (RPS) Instrumentation............................................. 6 83.3.1.2 Source Range Monitor (SRM) Instrumentation...................................................4 83.3.2.1 B3.3.2.2 83.3.3.1 83.3.3.2 83.3.4.1 83.3.4.2 83.3.5.1 83.3.5.2 83.3.6.1 83.3.6.2 83.3.7.1 83.3.8.1 83.3.8.2 Control Rod Block Instrumentation..................................................................... 4 Feedwater - Main Turbine High vVater Level Trip Instrumentation.........'............ 3 Post Accident Monitoring (PAM) Instrumentation................................................ 9 Remote Shutdown System................................................................................. 2 End of Cycle Recirculation Pump Trip (EOC~RPD Instrumentation................... 2 Anticipated Transient Without Scram Recirculation Pump Trip (A iWS-RPD Instrumentation............................................................ 1 Emergency Core Cooling System (ECCS) Instrumentation................................. 6 Reactor Core Isolation Cooling (RCIC) System Instrumentation........................ 1 Primary Containment Isolation Instrumentation................................................... 8 Secondary Containment Isolation Instrumentation.............................................. 5 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation...................................................................................... 3 Loss of Power (LOP) Instrumentation................................................................. 4 Reactor Protection System (RPS) Elec~ric Power Monitoring.... :......................... 1 SUSQUEHANNA - UNIT 2 TS I 8 LOES-1 Revision 134

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision B 3.4 83.4.1 83.4.2 83.4.3 83.4.4 83.4.5 83.4.6 83.4.7 83.4.8 83.4.9 83.4.10 83.4.11 B 3.5 83.5.1 83.5.2 83.5.3 8 3.6 83.6.1.1 83.6.1.2 83.6.1.3 REACTOR COOLANT SYSTEM (RCS)

Recirculation Loops Operating............................................................................ 5 Jet Pumps

....................................................................................................... 4 Safety/Relief Valves (S/RVs).............................................................................. 4 RCS Operational LEAKAGE............................................................................... 1 RCS Pressure Isolation Valve (PIV) Leakage..................................................... 4 RCS Leakage Detection Instrumentation............................................................ 5 RCS Specific Activity.......................................................................................... 3 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown..................................................................................... 3 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................................................................... 2 RCS Pressure and Temperature (PIT) Limits...................................................... 5 Reactor Steam Dome Pressure.......................................................................... 1 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS - Operating.............................................................................................. 5 ECCS - Shutdown.............................................................................................. 3 RCIC System...................................................................................................... 5 CONTAINMENT SYSTEMS Primary Containn1ent.......................................................................................... 6 Primary Containment Air Lock............................................................................ 2 Primary Containment Isolation Valves (PCiVs).................................................. 16 83.6.1.4 Containment Pressure.................... u*****aa****************u****************************************u 2 83.6.1.5 Drywell Air Temperature..................................................................................... 2 83.6.1.6 83.6.2.i 83.6.2.2 B3.6.2.3 B3.6.2.4 83.6.3.1 83.6.3.2 B3.6.3.3 83.6.4.1 83.6.4.2 83.6.4.3 Suppression Chamber-to-Drywe!! Vacuum Breakers.......................................... 1 Suppression Pool Average Temperature............................................................ 3 Suppression Poo! Water Leve!............................................................................ 1 Residual Heat Rernovai (RHR) Suppression Pooi Cooling.................................. 2 Residual Heat Removal (RHR) Suppression Pool Spray.................................... 1 Not Used

....................................................................................................... 2 Drywell Air Flow System..................................................................................... 3 Primary Containment Oxygen Concentration...................................................... 3 Secondary Containment.................................................................................... 14 Secondary Containment Isolation Valves (SCIVs)............................................. 12 Standby Gas Treatment (SGT) System............................................................. 6 SUSQUEHANNA - UNIT 2 TS/B LOES-2 Revision 134

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision B 3.7 83.7.1 B3.7.2 83.7.3 B3.7.4 B3.7.5 83.7.6 83.7.7 83.7.8 B 3.8 83.8.1 B3.8.2 83.8.3 83.8.4 83.8.5 83.8.6 83.8.7 83.8.8 8 3.9 83.9.1 83.9.2 83.9.3 83.9.5 83.9.6 83.9.7 83.9.8 83.10 83.10.1 83.10.2 B3.10.3 83.10.4 83.10.5 83.10.6 83.10.7 83.10.8 PLANT SYSTEMS Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS)...................................................................... 7 Emergency Service Water (ESW) System.......................................................... 3 Control Room Emergency Outside Air Supply (CREOAS) System............................................................................................. 3 Control Room Floor Cooling System................................................................... 1 Main Condenser Offgas...................................................................................... 2 Main Turbine Bypass System............................................................................. 4 Spent Fuel Storage Pool Water Level................................................................. 2 Main Turbine Pressure Regulation System......................................................... 1 ELECTRICAL POWER SYSTEM AC Sources - Operating.................................................................................... 10 AC Sources - Shutdown..................................................................................... 0 Diesel Fuel Oil, Lube Oil, and Starting Air........................................................... 6 DC Sources - Operating..................................................................................... 4 DC Sources-Shutdown.:................................................................................... 1 Battery Cell Parameters...................................................................................... 2 Distribution Systems - Operating........................................................................ 6 Distribution Systems - Shutdown....................................................................... 1 REFUELING OPERATIONS Refueling Equipment Interlocks.......................................................................... 1 Refuel Position One-Rod-Out Interlock............................................................... 1 Control Rod Position........................................................................................... 1 Control Rod Position Indication........................................................................... 0 Control Rod OPERABILITY - Refueling............................................................. 1 Reactor Pressure Vessel (RPV) Water Leve!...................................................... 2

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!.. g,, "-""' !-.VVV!............................................ I Residual Heat Remova! (RHR) - Low Water Leve!............................................. 1 SPECIAL OPERATIONS lnseNice Leak and Hydrostatic Testing Operation.............................................. 1 Reactor Mode Switch Interlock Testing............................................................... 1 Single Control Rod Withdrawal - Hot Shutdown................................................. 1 Single Control Rod Withdrawal - Cold Shutdown............................................... 1 Single Control Rod Drive (CRD) Removal - Refueling........................................ 1 Multiple Control Rod Withdrawal - Refueling...................................................... 1 Control Rod Testing - Operating........................................................................ 1 SHUTDOWN MARGIN (SOM) Test - Refueling.................................................. 3 SUSQUEHANNA - UNIT 2 TS/ B LOES-3 Revision 134

Rev. 4 SRM Instrumentation B 3.3.1.2 B 3.3 INSTRUMENTATION B 3.3.1.2 Source Range Monitor (SRM) Instrumentation BASES BACKGROUND APPLICABLE SAFETY ANALYSES 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), when 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, shutdown, and !ow 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 snd give the control room operator eariy indication of unexpected subcritical multiplication that could be indicative of an approach to criticaiity~

Prevention and mitigation of prompt reactivity excursions during refueling and low power operation is provided by LCO 3.9.1, "Refueling Equipment Interlocks"; LCO 3.1.1, "SHUTDOWN MARGIN (SOM)": LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation"; IRM Neutron Flux-High and Average Power Range Monitor (APRM) Neutron Flux-High (continued)

SUSQUEHANNA - UNIT 2 TS/ B 3.3-35 Revision 2

BASES APPLICABLE SAFETY ANALYSES (continued)

LCO Rev. 4 SRM Instrumentation B 3.3.1.2 (Setdown) Functions; and LCO 3.3.2.1, "Control Rod Block Instrumentation."

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.

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 ALTERATIONS 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 aH in a singie fueled region containing at !east one OPER/\\BLE SRM is met. Spiral reioading and offloading encompass reioading or offloading a ceil on the edge of a continuous fueled region (the ceii 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 (continued)

SUSQUEHANNA - UNIT 2 TS/ B 3.3-36 Revision 2

BASES LCO (continued)

APPLICABILITY ACTIONS Rev. 4 SRM Instrumentation B 3.3.1.2 the quadrant of tl1e reactor core where CORE AL TERA TIONS are being performed, and the other SRM to be OPERABLE in an adjacent quadrant 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 t11e 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.

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 provide adequate monitoring and the SRMs are not required.

A.1 and 8.1 in MODE 2, with the iRivis on Range 2 or beicw, SRfvis provide the means of monitoring core reactivity and criticality. With any number of the required SRMs inoperabie, the abiiity to monitor neutron fiux is degraded. Therefore, a limited time is allowed to restore the inoperable 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 2 TS/ B 3.3-37 Revision 1

'*{\\:**. -:

BASES ACTIONS A.1 and B.1 (continued)

Rev.4 SRM Instrumentation 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 applies 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 fuily inserted, the core is in its least reactive state with the most margin to criticality. The aHovved Compietion 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 en operating experience, to reach MODE 3 from fuil power conditions in an orderly manner and without chaiienging piant systems.

0.1 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 2 TS/ B 3.3-38 Revision 1

BASES ACTIONS SURVEILLANCE REQUIREMENTS D.1 and D.2 (continued)

Rev.4 SRM Instrumentation 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 takes 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 ALTERATIONS 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 AL TERA 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 AL TERA TIONS shall not preclude completion of the movement of a component to a safe, conservative position.

\\~-::::r~

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.

The SRs for each SRM Applicable MODE or other specified conditions 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 2 TS I B 3.3-39 Revision 2

BASES SURVEILLANCE REQUIREMENTS SR 3.3.1.2.1 and SR 3.3.1.2.3 (continued)

Rev.4 SRM Instrumentation 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 this 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.

SR 3.3.1.2.2 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 AL TERA TIONS are being performed, and the other OPERABLE SRM must be in an adjacent quadrant containing fuel. However, in accordance with Table 3.3.1.2~1, 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 ALTERATIONS. It is not required to be met at other times in MODE 5 since core reactivity changes are not occurring. This Sunisiiiancg consists of a revie\\v of piant iogs to ensure that SRfv1s required to be OPERABLE for given CORE AL TERA TlONS are, in fact, OPERABLE. in the event that only one SRM is required to be OPERABLE, peiTable 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 2 TS/ B 3.3-40 Revision 2

BASES SURVEILLANCE REQUIREMENTS SR 3.3.1.2.4 Rev. 4 SRM Instrumentation B 3.3.1.2 This Surveillance consists of a verification of the SRM instrument 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 assE?mblies 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.3.1.2.5 and SR 3.3.1.2.6 Performance of a CHANNEL FUNCTIONAL TEST demonstrates the associated charmei wiii function properly. SR 3.3. i.2.5 is (continued)

SUSQUEHANNA - UNIT 2 TS/ B 3.3-41 Revision 2

BASES SURVEILLANCE REQUIREMENTS SR 3.3.1.2.5 and SR 3.3.1.2.6 (continued)

Rev.4 SRM Instrumentation 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 tl1e 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 E::f<<

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 pm.var 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 OPER/;BLE (Le., satisfactorily performing the CHAr-Jr~EL CHECK) and the time required to perform the Surveiiiances.

(continued)

SUSQUEHANNA - UNIT 2 TS I B 3.3-42 Revision 3

BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.1.2.7 Rev. 4 SRM Instrumentation B 3.3.1.2 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 timeof 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.

1.

General Electric Service Information Letter (SIL) 478 "SRM tviinimum Count Ratet dated December 161 1988.

SUSQUEHANNA - UNIT 2 TS I B 3.3-43 Revision 2

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