ML17284A177

Technical Specification Bases Manual

ML17284A177
Person / Time
Site:	Susquehanna
Issue date:	10/02/2017
From:	Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML17284A177 (42)

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• MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2017-18793 USER INFORMATION:

GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address : NUCSA2 Phone#: 542-3194 TRANSMITTAL INFORMATION:

TO: GERLACH*ROSEY M 10/02/2017 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY_OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE"DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS .

TENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no

• C will be issued with the updated material.

TSBl - TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 09/27/2017 ADD MANUAL TABLE OF CONTENTS DATE: 09/29/2017 CATEGORY: DOCUMENTS TYPE: TSBl ID: TEXT 3.6.3.2 REMOVE: REV: 2 ADD: REV: 3

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• CATEGORY: DOCUMENTS ID: TEXT 3.6.3.3 REMOVE: REV: 2 TYPE: TSBl ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TSBl ID: TEXT LOES REMOVE: REV:l27 ADD: REV: 128 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3171 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE. MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX .

SSES MANUAL Manual Name~ TSBl

~anual

Title:

TECHNICJl...L SPECIFICATION BASES UNIT l MANUAL Table Of Contents Issue Date: 09/29/2017 Procedure Name Rev Issue Date Change ID Change Number TEXT LOEB 128 09/29/2017

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 23 07/02/2014

Title:

TABLE OF CONTENTS TEXT 2 .1.1 6 01/22/2015

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2 .1.2 1 TEXT 3.0

• ~

TEXT 3 .1.1 TEXT 3 .1.2 11/16/2016 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 .! of 8 Report Date: 10/02/17

SSES MANUAL Manual Name: TSBl Manual

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 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (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)

TEXT 3.3.1.1 7 11/16/2016

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 3 11/16/2016

Title:

INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.l 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.l 3 11/16/2016 Page~

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) of 8 INSTRUMENTATION Report Date: 10/02/17

SSES MANUAL Manual Na1t1.e~ 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

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

~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 Pagel of 8 Report Date: 10/02/17

SSES MANUAL Manual Name: TSBl Manual

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:

REACTOR COOLANT 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 SHUTDOWN 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 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_! of 8 Report Date: 10/02/17

SSES MANUAL Manual Na.me: TSBl

~anual

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 3.6.1.4 2 11/16/2016

Title:

CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 2 11/16/2016

Title:

CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURE TEXT 3.6.1.6 1 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 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 2 of 8 Report Date: 10/02/17

SSES MANUAL Manual Name: TSBl rranual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL 04/19/2017 TEXT 3.6.4.2 12

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:

PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ULTIMATE HEAT SINK (UHS)

TEXT 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

'l'EXT 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 3 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:

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 Page §_

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN of 8 Report Date: 10/02/17

SSES MANUAL Manual Name: TSBl

~anual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 5 11/16/2016

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 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

~EXT 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 J_ of 8 Report Date: 10/02/17

SSES MANUAL Manual Name: TSBl Manual

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:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 1 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

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: 10/02/17

r SUSQUEHANNA STEAM ELECTRIC STATION

• LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section TOC 82.0 Title Revision Table of Contents ...............................................................................................23 SAFETY LIMITS BASES 82.1.1 Reactor Core SLs ............................................................................................... 6 82.1.2 Reactor Coolant System (RCS) Pressure SL.. .................................................... 1 8 3.0 LCO AND SR APPLICABILITY BASES .............................................................. 3 B 3.1 REACTIVITY CONTROL BASES 83.1.1 Shutdown Margin (SOM) ..................................................................................... 2 83.1.2 Reactivity Anornalies .......................................................................................... 1 83.1.3 Control Rod OPERABILITY ................................................................................ 3 83.1.4 Control Rod Scram Times ................................................................................... 5 83.1.5 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 Average Planar Linear Heat Generation Rate (APLHGR) ................................... 3 83.2.2 Minimum Critical Power Ratio (MCPR) ............................................................... 4 83.2.3 Linear Heat Generation Rate (LHGR) ................................................................. 3 B 3.3 INSTRUMENTATION 83.3.1.1 Reactor Protection System (RPS) Instrumentation ............................................. 7 83.3.1.2 Source Range Monitor (SRM) Instrumentation ................................................... 3 83.3.2.1 Control Rod Block Instrumentation ..................................................................... 5 83.3.2.2 Feedwater- Main Turbine High Water Level Trip Instrumentation ...................... 3 83.3.3.1 Post Accident Monitoring (PAM) Instrumentation ............................................... 1O 83.3.3.2 Remote Shutdown System ................................................................................. 2 83.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation .................... 3 83.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (AlWS-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 83.3.6.2 Secondary Containment Isolation Instrumentation .............................................. 5 83.3.7.1 Control Room Emergency Outside Air Supply (CREOAS) ................................. 3 83.3.8.1 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 128

SUSQUEHANNA STEAM ELECTRIC STATION

• LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section B 3.4 Title REACTOR COOLANT SYSTEM BASES Revision 83.4.1 Recirculation Loops Operating ............................................................................ 5 83.4.2 Jet Pumps ....................................................................................................... 4 83.4.3 Safety/Relief Valves (S/RVs) ................................................ ;............................. 3 83.4.4 RCS Operational LEAKAGE .............................................................................. 1 B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ..................................................... 2 83.4.6 RCS Leakage Detection Instrumentation ............................................................ 5 B3.4.7 RCS Specific Activity .......................................................................................... 3 83.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................................................................... 3 83.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.................................................................................... 2 83.4.10 RCS Pressure and Temperature (PIT) Limits ...................................................... 5 83.4.11 Reactor Steam Dome Pressure .......................................................................... 1 83.5 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 83.6.1.2 83.6.1.3 CONTAINMENT SYSTEMS BASES Primary Containment .......................................................................................... 6 Primary Containment Air Loci< ............................................................................ 2 Primary Containment Isolation Valves (PCIVs) .................................................. 13 B3.6.1.4 Containment Pressure ........................................................................................ 2 B3.6.1.5 Drywell Air Temperature ..................................................................................... 2 83.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers .......................................... 1 83.6.2.1 Suppression Pool Average Temperature ............................................................ 3 83.6.2.2 Suppression Pool Water Level. ........................................................................... 1 B3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ................................. 2 B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .................................... 1 83.6.3.1 Not Used ....................................................................................................... 2 B3.6.3.2 Drywell Air Flow System ..................................................................................... 3 83.6.3.3 Primary Containment Oxygen Concentration ...................................................... 3 83.6.4.1 Secondary Containment .................................................................................... 13 83.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................................. 12 83.6.4.3 Standby Gas Treatment (SGT) System .............................................................. 6

• SUSQUEHANNA - UNIT 1 TS/ B LOES-2 Revision 128

SUSQUEHANNA STEAM ELECTRIC STATION

• LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision 83.7 PLANT SYSTEMS BASES 83.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................................................... 5 83.7.2 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 83.7.8 Main Turbine Pressure Regulation System ......................................................... 1 83.8 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 ........................................................... 5 B3.8.4 DC Sources- Operating ..................................................................................... 4 83.8.5 DC Sources- Shutdown........................ :............................................................ 1 B3.8.6 Battery Cell Parameters ...................................................................................... 2 83.8.7 Distribution Systems - Operating ........................................................................ 2

• 83.8.8 83.9 83.9.1 B3.9.2 Distribution Systems - Shutdown ....................................................................... 1 REFUELING OPERATIONS BASES Refueling Equipment Interlocks .......................................................................... 1 Refuel Position One-Rod-Out Interlock .................................... :.......................... 1 83.9.3 Control Rod Position ........................................................................................... 1 83.9.4 Control Rod Position Indication ........................................................................... O 83.9.5 Control Rod OPERABILITY - Refueling ............................................................. 1 83.9.6 Reactor Pressure Vessel (RPV) Water Level. ..................................................... 2 83.9.7 Residual Heat Removal (RHR) - High Water Level ............................................ 1 83.9.8 Residual Heat Removal (RHR) - Low Water Level. ............................................ 1 83.10 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 B3.10.4 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 (SDM) Test - Refueling .......................................................... 2

• SUSQUEHANNA - UNIT 1 TS I B LOES-3 Revision 128

Rev. 3 Orywell Air Flow System

• 83.6 B 3.6.3.2 CONTAINMENT SYSTEMS Drywell Air Flow System B 3.6.3.2 BASES BACKGROUND The Drywell Cooling fans in low speed ensure a uniformly mixed post accident primary containment atmosphere (Ref. 1), thereby minimizing the potential for local hydrogen burns due to a pocket of hydrogen above the flammable concentration.

The Drywell Cooling fans are an Engineered Safety Feature and are designed to withstand a loss of coolant accident (LOCA) in post accident environments without loss of function. The system consists of three required pairs of fans with each pair consisting of two independent fans.

The three required Drywell Cooling fan pairs are as follows:

a. Drywell Unit Cooler fans 1V414Af1V414B;

b. Drywell Unit Cooler fans 1V416A/1V416B;

c. Recirculation fan 1V418Af1V418B .

The fans are initiated manually since flammability limits would not be reached until several days after a LOCA. Each fan in a pair is powered from a separate emergency power supply. Since one fan in each pair can provide 100% of the mixing requirements, the system will provide its design function with a worst case single active failure.

APPLICABLE The Drywell Cooling fans provide the capability_ for reducing the local SAFETY hydrogen concentration to approximately the bulk average concentration ANALYSES following a Design Basis Accident (OBA).

Reference 2 no longer defines a design basis hydrogen source term and therefore no design basis calculates hydrogen generation as a function of time. See Reference 3 for a detailed discussion for hydrogen generation.

(continued)

• SUSQUEHANNA- UNIT 1 TS I B 3.6-76 Revision 1

Rev. 3 Drywall Air Flow System

• BASES APPLICABLE 8 3.6.3.2 SAFETY Although natural circulation phenomena reduces the gradient ANALYSES concentration differences in containment, a containment mixing system (continued) provides further means of preventing local hydrogen gas buildups in containment post-accident.

The Drywell Cooling fans satisfy Criterion 3 of the NRC Policy Statement.

(Ref. 4)

LCO Three required Drywell Cooling fan pairs must be OPERABLE in low speed to ensure operation of at least one fan in each of the required pairs in the event of a worst case single active failure. The three required Drywell Cooling fan pairs are as follows:

a. Drywell Unit Cooler fans 1V414A/1V414B;

b. Drywall Unit Cooler fans 1V416A/1V416B;

c. Recirculation fan 1V418A/1V418B .

Operation with at least one fan in each required pair provides the capability of controlling the bulk hydrogen concentration in primary containment without exceeding the flammability limit.

APPLICABILITY In MODES 1 and 2, the three Drywall Cooling fan pairs ensure the capability to prevent localized hydrogen concentrations above the flammability limit of 4.0 v/o in drywell, assuming a worst case single active failure.

(continued)

• SUSQUEHANNA- UNIT 1 TS I B 3.6-77 Revision 1

Rev. 3 Drywell Air Flow System B 3.6.3.2 BASES APPLICABILITY In MODE 3, both the hydrogen production rate and the total hydrogen (continued) produced after a LOCA would be less than that calculated for the OBA LOCA. Also, because of the limited time in this MODE, the probability of an accident requiring the Drywall Cooling fans is low. Therefore, the Drywell Cooling fans are not required in MODE 3.

In MODES 4 and 5, the probability and consequences of a LOCA are reduced due to the pressure and temperature limitations in these MODES.

Therefore, the Drywell Cooling fans are not required in these MODES.

ACTIONS With one required Drywell Cooling fan in one or more pairs inoperable, the inoperable fan must be restored to OPERABLE status within 30 days. In this Condition, the remaining OPERABLE fan is adequate to perform the hydrogen mixing function. However, the overall reliability is reduced because a single failure in the OPERABLE fan could result in reduced hydrogen mixing capability. The 30 day Completion Time is based on the availability of the second fan, the low probability of the occurrence of a LOCA that would generate hydrogen in amounts capable of exceeding the flammability limit, the amount of time available after the event for operator action to prevent exceeding this limit, and the availability of the Primary Containment Hydrogen Recombiner System.

(continued)

• SUSQUEHANNA - UNIT 1 TS/ B 3.6-78 Revision 1

Rev. 3 Drywell Air Flow System

• BASES ACTIONS B.1 and B .. 2 8 3.6.3.2 (continued)

With two required Drywell Cooling fans in one or more pairs inoperable, the ability to perform the hydrogen control function via alternate capabilities must be verified by administrative means within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The alternate hydrogen control capabilities are provided by the containment nitrogen purge system. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time allows a reasonable period of time to verify that a loss of hydrogen control function does not exist. In .addition, the alternate hydrogen control system capability must be verified once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter to ensure its continued availability. Both the initial verification and all subsequent verifications may be performed as an administrative check by examining logs or other information to determine the availability of the alternate hydrogen control system. It does not mean to perform the Surveillances needed to demonstrate OPERABILITY of the alternate hydrogen control system. If the ability to perform the hydrogen control function is maintained, continued operation is permitted with two Drywell Cooling fans in one or more pairs inoperable for up to 7 days. Seven days is a reasonable time to allow two Drywell Cooling fans in one or more pairs to be inoperable because the hydrogen control function is maintained and because of the low probability of the occurrence of a LOCA that would generate hydrogen ,.

in amounts capable of exceeding the flammability limit.

If any Required Action and associated Completion Time cannot be met, the plant must be brought to a MODE in which the LCO does not apply.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 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 MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.3.2.1 REQUIREMENTS Operating each required Drywell Cooling fan in low speed from the control room for~ '15 minutes ensures that each (continued)

• SUSQUEHANNA - UNIT 1 TS I B 3.6-79 Revision 0

Rev. 3 Drywell Air Flow System

• BASES SURVEILLANCE SR 3.6.3.2.1 (continued)

B3.6.3.2 REQUIREMENTS subsystem is OPERABLE and that all associated controls are functioning properly. Since required fans are operated at high speed during normal operations this SR ensures the low speed motor circuits operate. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR 9.4.5

2. Regulatory Guide 1.7, Revision 3.

3. FSAR, Section 6.2.5.

4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132) .

• SUSQUEHANNA- UNIT 1 TS I B 3.6-80 Revision 1

Rev.3 Primary Containment Oxygen Concentration

• B 3.6 B 3.6.3.3 CONTAINMENT SYSTEMS Primary Containment Oxygen Concentration 8 3.6.3.3 BASES BACKGROUND All nuclear reactors must be designed to withstand events that generate hydrogen either due to the zirconium metal water reaction in the core or due to radiolysis. The primary method to control hydrogen is to inert the primary containment. With the primary containment inert, that is, oxygen concentration < 4.0 volume percent (v/o), a combustible mixture cannot be present in the primary containment for any hydrogen concentration. An event that rapidly generates hydrogen from zirconium metal waterreaction will result in excessive hydrogen in primary containment, but oxygen

-concentration will remain < 4.0 v/o and no combustion can occur. This LCO ensures that oxygen concentration does not exceed 4.0 v/o during operation in the applicable conditions.

APPLICABLE The Reference 1 calculations assume that the primary containment is SAFETY inerted when a Design Basis Accident loss of coolant accident occurs .

ANALYSES Thus, the hydrogen assumed to be released to the primary containment as a result of metal water reaction in the reactor core will not produce combustible gas mixtures in the primary containment.

Primary containment oxygen concentration satisfies Criterion 2 of the NRC Policy Statement. (Ref. 2)

(continued)

SUSQUEHANNA- UNIT 1 TS I B 3.6-81 Revision 2

Rev.3 Primary Containment Oxygen Concentration

• BASES (continued)

B 3.6.3.3 LCO The primary containment oxygen concentration is maintained< 4.0 v/o to ensure that an event that produces any amount of hydrogen does not result in a combustible mixture inside primary containment.

APPLICABILITY The primary containment oxygen concentration must be within the specified limit when primary containment is inerted, except as allowed by the* relaxations during startup and shutdown addressed below. The primary containment must be inert in MODE 1, since this is the condition with the highest probability of an event that could produce hydrogen.

lnerting the primary containment is an operational problem because it prevents containment access without an appropriate breathing apparatus.

Therefore, the primary containment is inerted as late as possible in the plant startup and de-inerted as soon as possible in the plant shutdown.

As long as reactor power is< 15% RTP, the potential for an event that generates significant hydrogen is low and the primary containment need not be inert. Furthermore, the probability of an event that generates hydrogen occurring within the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a startup, or within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before a shutdown, is low enough that these "windows," when the primary containment is not inerted, are also justified. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period is a reasonable amount of time to allow plant personnel to perform inerting or de-inerting.

ACTIONS A.1 If oxygen concentration is ~ 4.0 v/o at any time while operating in MODE 1, with the exception of the relaxations allowed during startup and shutdown, oxygen concentration must be restored to < 4.0 v/o within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is allowed when oxygen concentration is;;:: 4.0 v/o because of the low probability and long duration of an event that would generate significant amounts of hydrogen occurring during this period.

(continued)

SUSQUEHANNA - UNIT 1 TS I B 3.6-82 Revision 1

Rev. 3 Primary Containment Oxygen Concentration B 3.6.3.3 BASES ACTIONS B.1 (continued)

If oxygen concentration cannot be restored to within limits within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, power must be reduced to ~ 15% RTP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is reasonable, based on operating experience, to reduce reactor power from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.3.3.1 REQUIREMENTS The primary containment must be determined to be inert by verifying that oxygen concentration is < 4.0 v/o. The Surveillance Frequency is controlled under the Surveillance Frequency Control. Program.

REFERENCES 1. FSAR, Section 6.2.5 .

• 2. Final Policy Statement on Technical Specifications Improvements July 22, 1993 (58 FR 39132) .

• SUSQUEHANNA - UNIT 1 TS I B 3.6-83 Revision O

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SSES MANUAL Manual Name: TSB2

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-1 SSES MANUAL Manual Name: TSB2 Manual

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TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7 4 11/16/2016

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REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3 .1. 8 4 11/16/2016

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REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 5 11/16/2016

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POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

TEXT 3.2.2 4 11/16/2016

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POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 3 11/16/2016

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POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR TEXT 3.3.1.1 6 11/16/2016

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INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3. 3 .1. 2 3 11/16/2016

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INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 4 11/16/2016

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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 3.3.3.1 9 11/16/2016

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 2 11/16/2016

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INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 2 11/16/2016 Page~

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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

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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.l 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)

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Title:

REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE I

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TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.5 3 03/10/2010

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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 COOLANT 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

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

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REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 1 11/16/2016

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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

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EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM RCIC SYSTEM TEXT 3 . 6 . 1. 1 6 11/16/2016

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PRIMARY CONTAINMENT TEXT 3 . 6 . 1. 2 2 11/16/2016

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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page_! of 8 Report Date: 10/02/17

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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

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CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 2 11/16/2016

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CONTAINMENT SYSTEMS DRYWELL AI-R TEMPERATURE TEXT 3.6.1.6 1 11/16/2016

Title:

CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 3 11/16/2016

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CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE

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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

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CONTAINMENT SYSTEMS RESIDUAL. HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 2 06/13/2006

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CONTAINMENT SYSTEMS INTENTIONALLY LEFT BLANK TEXT 3.6.3.2 3 09/29/2017

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CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM LDCN 5297 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 Page E_

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CONTAINMENT SYSTEMS SECONDARY CONTAINMENT of 8 Report Date: 10/02/17

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CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

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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 AND THE ULTIMATE HEAT SINK (UHS)

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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 11/18/2002 TEXT 3.8.2 0

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ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN

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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 TEXT 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

~EXT 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

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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

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1 1 01/23/2008

Title:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 1 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

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SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL TEXT 3.10.5 1 11/16/2016

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SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING TEXT 3.10.6 1 11/16/2016

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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 8 Report Date: 10/02/17

SUSQUEHANNA STEAM ELECTRIC STATION

• LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section TOC Revision Table of Contents ..............................................................................................23 B2.0 SAFETY LIMITS (SLs) 82.1.1 Reactor Core SLs ............................................................................................... 5 82.1.2 Reactor Coolant System (RCS) Pressure SL ...................................................... 1 B3.0 LCO AND SR APPLICABILITY BASES .............................................................. 3 B 3.1 REACTIVITY CONTROL SYSTEMS 83.1.1 Shutdown Margin (SOM) ..................................................................................... 2 83.1.2 Reactivity Anomalies .......................................................................................... 1 83.1.3 Control Rod OPERABILITY ................................................................................ 3 83.1.4 Control Rod Scram Times ................................................................................... 5 83.1.5 Control Rod Scram Accumulators ....................................................................... 2 83.1.6 Rod Pattern Control ............................................................................................ 4 83.1.7 Standby Liquid Control (SLC) System ................................................................. 3 83.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves..................................... 4

• s 3.2 83.2.1 83.2.2 83.2.3 POWER DISTRIBUTION LIMITS Average Planar Linear Heat Generation Rate (APLHGR) ................................... 5 Minimum Critical Power Ratio (MCPR) ............................................................... 4 Linear Heat Generation Rate (LHGR) .......................-.......................................... 3 8 3.3 INSTRUMENTATION 83.3.1.1 Reactor Protection System (RPS) Instrumentation ............................................. 6 83.3.1.2 Source Range Monitor (SRM) Instrumentation ................................................... 3 83.3.2.1 Control Rod Block Instrumentation ..................................................................... 4 83.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation ..................... 3 83.3.3.1 Post Accident Monitoring (PAM) Instrumentation ................................................ 9 83.3.3.2 Remote Shutdown System ................................................................................. 2 83.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation ................... 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 ................................. 6 83.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ........................ 1 83.3.6.1 Primary Containment Isolation Instrumentation ................................................... 8 83.3.6.2 Secondary Containment Isolation Instrumentation .............................................. 5 83.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation ...................................................................................... 3 83.3.8.1 Loss of Power (LOP) Instrumentation ................................................................. 4 83.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ................. : ............ 1

• SUSQUEHANNA - UNIT 2 TS I B LOES-1 Revision 132

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

Section Title Revision B 3.4 REACTOR COOLANT SYSTEM (RCS) 83.4.1 Recirculation Loops Operating ............................................................................ 5 83.4.2 Jet Pumps ....................................................................................................... 4 83.4.3 Safety/Relief Valves (S/RVs) .............................................................................. 4 83.4.4 RCS Operational LEAKAGE ............................................................................... 1 83.4.5 RCS Pressure Isolation Valve {PIV) Leakage ..................................................... 4 83.4.6 RCS Leakage Detection Instrumentation ............................................................ 5 83.4.7 RCS Specific Activity .......................................................................................... 3 83.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................................................................... 3 83.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ...........................................................:........................ 2 83.4.10 RCS Pressure and Temperature (PIT) Limits ........................................ ."............. 5 83.4.11 Reactor Steam Dome Pressure .......................................................................... 1 B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 83.5.1 ECCS - Operating .............................................................................................. 5 83.5.2 ECCS - Shutdown .............................................................................................. 3

• 83.5.3 B 3.6 83.6.1.1 83.6.1.2 RCIC System ...................................................................................................... 5 CONTAINMENT SYSTEMS Primary Containment .......................................................................................... 6 Primary Containment Air Lock ............................................................................ 2 83.6.1.3 Primary Containment Isolation Valves (PCIVs) .................................................. 16 83.6.1.4 Containment Pressure ........................................................................................ 2 83.6.1.5 Drywell Air Temperature ..................................................................................... 2 83.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers .......................................... 1 83.6.2.1 Suppression Pool Average Temperature ............................................................ 3 83.6.2.2 Suppression Pool Water Level ............................................................................ 1 83.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .................................. 2 83.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .................................... 1 83.6.3.1 Not Used ....................................................................................................... 2 83.6.3.2 Drywell Air Flow System ..................................................................................... 3 83.6.3.3 Primary Containment Oxygen Concentration ...................................................... 3 83.6.4.1 Secondary Containment ....................................................................................14 83.6.4.2 Secondary Containment Isolation Valves (SCIVs) ............................................. 12 83.6.4.3 Standby Gas Treatment (SGT) System ............................... '. ............................. 6

• SUSQUEHANNA- UNIT 2 TS/ 8 LOES-2 Revision 132

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

Section Revision 8 3.7 PLANT SYSTEMS 83.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................................................... 7 83.7.2 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 ............................................................................. 4 83.7.7 Spent Fuel Storage Pool Water Level. ................................................................ 2 83.7.8 Main Turbine Pressure Regulation System ......................................................... 1 8 3.8 ELECTRICAL POWER SYSTEM 83.8.1 AC Sources - Operating .................................................................................... 10 83.8.2 AC Sources - Shutdown ..................................................................................... 0 83.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ........................................................... 5 83.8.4 DC Sources - Operating ..................................................................................... 4 83.8.5 DC Sources - Shutdown ..................................................................................... 1 83.8.6 Battery Cell Parameters ...................................................................................... 2 83.8.7 Distribution Systems - Operating ........................................................................ 6

• 83.8.8 B 3.9 83.9.1 83.9.2 Distribution Systems - Shutdown ....................................................................... 1 REFUELING OPERATIONS Refueling Equipment Interlocks .......................................................................... 1 Refuel Position One-Rod-Out Interlock ............................................................... 1 83.9.3 Control Rod Position ........................................................................................... 1 83.9.4 Control Rod Position Indication ........................................................................... O 83.9.5 Control Rod OPERABILITY - Refueling ............................................................. 1 83.9.6 Reactor Pressure Vessel (RPV) Water Level. ..................................................... 2 83.9.7 Residual Heat Removal (RHR) - High Water Level ............................................ 1 B3.9.8 Residual Heat Removal (RHR) - Low Water Level. ............................................ 1 B 3.10 SPECIAL OPERATIONS 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 B3.10.6 Multiple Control Rod Withdrawal - Refueling ...................................................... 1 B3.10.7 Control Rod Testing - Operating ........................................................................ 1 83.10.8 SHUTDOWN MARGIN (SOM) Test- Refueling .................................................. 3

• SUSQUEHANNA - UNIT 2 TS I 8 LOES-3 Revision 132

Rev. 3 Drywell Air Flow System

• 8 3.6 83.6.3.2 CONTAINMENT SYSTEMS Drywell Air Flow System 8 3.6.3.2 BASES BACKGROUND The Drywell Cooling fans in low speed ensure a uniformly mixed post accident primary containment atmosphere (Ref. 1), thereby minimizing the potential for local hydrogen burns due to a pocket of hydrogen above the flammable concentration.

The Drywell Cooling fans are an Engineered Safety Feature and are designed to withstand a loss of coolant accident (LOCA) in post accident environments without loss of function. The system consists of three required pairs of fans with each pair consisting of two independent fans.

The three required Drywell Cooling fan pafrs are as follows:

a. Drywell Unit Cooler fans 2V414A/2V414B;

b. Drywell Unit Cooler fans 2V416A/21V416B;

• c. Recirculation fan 2V418A/2V418B.

The fans are initiated manually since flammability limits would not be reached until several days after a LOCA. Each fan in a pair is powered from a separate emergency power supply. Since one fan in each pair can

<.:::.:::z:::i-:::

provide 100% of the mixing requirements, the system will provide its design function with a worst case single active failure.

APPLICABLE The Drywell Cooling fans provide the capability for reducing the local SAFETY hydrogen concentration to approximately the bulk average concentration ANALYSES following a Design Basis Accident (OBA).

Reference 2 no longer defines a design basis hydrogen source term and therefore no design basis analysis calculates hydrogen generation as a function of time. See Reference 3 for a detailed discussion for hydrogen generation.

(continued)

SUSQUEHANNA- UNIT 2 TS/ B 3.6-75 Revision 1

Rev.3 Drywell Air Flow System B 3.6.3.2 BASES APPLICABLE SAFETY Although natural circulation phenomena reduces the gradient ANALYSES concentration differences in containment, a containment mixing system (continued) provides further means of preventing local hydrogen gas buildups in containment post~accident.

The Drywell Cooling fans satisfy Criterion 3 of the NRC Policy Statement.

(Ref. 4)

LCO Three required Drywall Cooling fan pairs must be OPERABLE in low speed to ensure operation of at least one fan in each of the required pairs in the event of a worst case single active failure. The three required Drywell Cooling fan pairs are as follows:

a. Drywall Unit Cooler fans 2V414A/2V414B;

b. Drywell Unit Cooler fans 2V416A/2V416B;

c. Recirculation fan 2V418A/2V418B.

Operation with at least one fan in each required pair provides the capability of controlling the bulk hydrogen concentration in primary containment without exceeding the flammability limit.

APPLICABILITY In MODES 1 and 2, the three Drywell Cooling fan pairs ensure the capability to prevent localized hydrogen concentrations above the flammability limit of 4.0 v/o in drywall, assuming a worst case single active failure.

(continued)

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Rev.3 Drywell Air Flow System

• BASES 8 3.6.3.2 APPLICABILITY In MODE 3, both the hydrogen production rate and the total hydrogen (continued) produced after a LOCA would be less than that calculated for the OBA LOCA. Also, because of the limited time in this MODE, the probability of an accident requiring the Drywell Cooling fans is low. Therefore, the Drywell Cooling fans are not required in MODE 3.

In MODES 4 and 5, the probability and consequences of a LOCA are reduced due to the pressure and temperature limitations in these MODES.

Therefore, the Drywell Cooling fans are not required in these MODES.

ACTIONS A.1 With one required Drywell Cooling fan in one or more pairs inoperable, the inoperable fan must be restored to OPERABLE status within 30 days. In this Condition, the remaining OPERABLE fan is adequate to perform the hydrogen mixing function. However, the overall reliability is reduced because a single failure in the OPERABLE fan could result in reduced hydrogen mixing capability. The 30 day Completion Time is based on the availability of the second fan, the low probability of the occurrence of a LOCA that would generate hydrogen in amounts capable of exceeding the flammability limit, the amount of time available after the event for operator action to prevent exceeding this limit, and the availability of the Primary Containment Hydrogen Recombiner System.

(continued)

SUSQUEHANNA - UNIT 2 TS/ B 3.6-77 Revision 1

Rev. 3 Drywell Air Flow System

• BASES B 3.6.3.2 ACTIONS B.1 and B. 2 (continued)

With two required Drywell Cooling fans in one or more pairs inoperable, the ability to perform the hydrogen control function via alternate capabilities must be verified by administrative means within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The alternate hydrogen control capabilities are provided by the containment nitrogen purge system. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time allows a reasonable period of time to verify that a loss of hydrogen control function does not exist. In addition, the alternate hydrogen control system capability must be verified once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter to ensure its continued availability. Both the initial verification and all subsequent verifications may be performed as an administrative check by examining logs or other information to determine the availability of the alternate hydrogen control system. It does not mean to perform the Surveillances needed to demonstrate OPERABILITY of the alternate hydrogen control system. If the ability to perform the hydrogen control function is maintained, continued operation is permitted with two Drywell Cooling fans in one or more pairs inoperable for up to 7 days. Seven days is a reasonable time to allow two Drywell Cooling fans in one or more pairs to be inoperable because the hydrogen control function is maintained and because of the low probability of the occurrence of a LOCA that would generate hydrogen in amounts capable of exceeding the flammability limit.

If any Required Action and associated Completion Time cannot be met, the plant must be brought to a MODE in which the LCO does not apply.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 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 MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE REQUIREMENTS SR 3 *6 *3 *2

• 1 Operating each required Drywell Cooling fan in low speed from the control room for;::: 15 minutes ensures that each (continued)

SUSQUEHANNA - UNIT 2 TS I B 3.6-78 Revision 0

Rev. 3 Drywell Air Flow System

• *BASES 8 3.6.3.2 SURVEILLANCE SR 3.6.3.2.1 (continued)

REQUIREMENTS subsystem is OPERABLE and that all associated controls are functioning properly. Since required fans are operated at high speed during normal operations this SR ensures the low speed motor circuits operate. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR 9.4.5

2. Regulatory Guide 1.7, Revision 3.

3. FSAR, Section 6.2.5.

4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132) .

• SUSQUEHANNA - UNIT 2 TS I B 3.6-79 Revision 2

Rev.3 Primary Containment Oxygen Concentration

• B 3.6 B 3.6.3.3 CONTAINMENT SYSTEMS Primary Containment Oxygen Concentration B 3.6.3.3 BASES BACKGROUND All nuclear reactors must be designed to withstand events that generate hydrogen either due to the zirconium metal water reaction in the core or due to radiolysis. The primary method to control hydrogen is to inert the primary containment. With the primary containment inert, that is, oxygen concentration< 4.0 volume percent (v/o), a combustible mixture cannot be present in the primary containment for any hydrogen concentration. An event that rapidly generates hydrogen from zirconium metal water reaction will result in excessive hydrogen in primary containment, but oxygen concentration will remain < 4.0 v/o and no combustion can occur. This LCO ensures that oxygen concentration does not exceed 4.0 v/o during operation in the applicable conditions.

APPLICABLE The Reference 1 calculations assume that the primary containment is SAFETY inerted when a Design Basis Accident loss of coolant accident occurs .

ANALYSES Thus, the hydrogen assumed to be released to the primary containment as a result of metal water reaction in the reactor core will not produce combustible gas mixtures in the primary containment.

Primary containment oxygen concentration satisfies Criterion 2 of the NRC Policy Statement. (Ref. 2)

• SUSQUEHANNA - UNIT 2 TS I B 3.6-80 (continued)

Revision 2

. Rev.3 Primary Containment Oxygen Concentration

• BASES (continued)

B 3.6.3.3 LCO The primary containment oxygen concentration is maintained < 4.0 v/o to ensure that an event that produces any amount of hydrogen does not result in a combustible mixture inside primary containment.

APPLICABILITY The primary containment oxygen concentration must be within the specified limit when primary containment is inerted, except as allowed by the relaxations during startup and shutdown addressed below. The primary containment must be inert in MODE 1, since this is the condition with the highest probability of an event that could produce hydrogen.

lnerting the primary containment is an operational problem because it prevents containment access without an appropriate breathing apparatus.

Therefore, the primary containment is inerted as late as possible in the plant startup and de-inerted as soon as possible in the plant shutdown.

As long as reactor power is< 15% RTP, the potential for an event that generates significant hydrogen is low and the primary containment need not be inert. Furthermore, the probability of an event that generates hydrogen occurring within the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a startup, or within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before a shutdown, is low enough that these "windows," when the primary containment is not inerted, are also justified. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period is a reasonable amount of time to allow plant personnel to perform inerting or de-inerting.

ACTIONS If oxygen concentration is ;:::: 4.0 v/o at any time while operating in MODE 1, with the exception of the relaxations allowed during startup and shutdown, oxygen concentration must be restored to < 4.0 v/o within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is allowed when oxygen concentration is~ 4.0 v/o because of the low probability and long duration of an event that would generate significant amounts of hydrogen occurring during this period .

• SUSQUEHANNA - UNIT 2 TS I 8 3.6-81 (continued)

Revision 1

Rev.3 Primary Containment Oxygen Concentration

• BASES B 3.6.3.3 ACTIONS B.1 (continued)

If oxygen concentration cannot be restored to within limits within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, power must be reduced to ::;; 15% RTP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is reasonable, based on operating experience, to reduce reactor power from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.3.3.1 REQUIREMENTS The primary containment must be determined to be inert by verifying that oxygen concentration is < 4.0 v/o. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. FSAR, Section 6.2.5 .

• 2. Final Policy Statement on Technical Specifications Improvements July 22, 1993 (58 FR 39132) .

• SUSQUEHANNA- UNIT 2 TS/ B 3.6-82 Revision 1