ML18197A078
| ML18197A078 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/09/2018 |
| From: | Gerlach R Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18197A078 (18) | |
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- MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2018-12387 USER INFORMATION:
GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 542-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSEY M 07/09/2018 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 RORS.
TENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no
- C will be issued with the updated material.
TSB2 - TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 05/22/2018 ADD MANUAL TABLE OF CONTENTS DATE: 07/06/2018 CATEGORY: DOCUMENTS TYPE: TSB2 ID: TEXT 3.6.4.1 REMOVE: REV: 14 ADD: REV: 15
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- CATEGORY: DOCUMENTS ID: TEXT LOES REMOVE: REV:136 TYPE: TSB2 ADD: REV: 137 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: TSB2
~anual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date: 07/06/2018 Procedure Name Rev Issue Date Change ID Change Number TEXT LOEB 137 07/05/2018
Title:
LIST OF EFFECTIVE SECTIONS TEXT !!'OC
- 23 03/01/2017
Title:
TABLE OF CONTENTS TEXT 2 .1.1 5 01/22/2015
Title:
SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2 .1.2 1
-EXT 3.0
Title:
LIMITING CONDITION TEXT 3.1.1 TEXT 3 .1.2 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 Pagel of 8 Report Date: 07/06/18
SSES MANUAL J'
\.
Manual Name: TSB2
- anual
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 li/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 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
'EXT 3 . 3 . 1 . 1 6 11/16/2016
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 4 01/23/2018
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 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 3.3.3.1 .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? of 8 Report Date: 07/06/18
SSES MANUAL Manual Name : TSB2
.ranual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.4.2 l 11/16/2016
Title:
INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.l 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
.'.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 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
- Tit~e; REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Page .l of 8 Report Date: 07/06/18
SSES MANUAL Manual Name: TSB2
'anual
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 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
/EXT 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_! of 8 Report Date: 07/06/18
SSES MANUAL Manual Name: TSB2
- anual
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 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 INTENTIONALLY LEFT BLANK TEXT 3.6.3.2 3 09/29/2017
Title:
CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 3 09/29/2017
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3 6 4 1 15 07/05/2018
- . Ti t~e; ~ONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~ of 8 Report Date: 07/06/18
SSES MANUAL Manual Name: TSB2
- . ~anual Title~ TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.4.2 13 04/24/2018 Title~ CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.6.4.3 6 09/15/2017 Title~ CONTAINMENT SYSTEMS STAl"\TDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.l 7 03/01/2017
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 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 11 02/27/2018
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: 07/06/18
SSES MANUAL Manual Name: TSB2
.;anual
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 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
Title:
REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page 2 of 8 Report Date: 07/06/18
SSES MANUAL Manual Name: TSB2
- . *:-~anual
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
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 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 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 8 Report Date: 07/06/18
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC Table of Contents ................................................................................................23 B 2.0 SAFETY LIMITS (SLs)
B2.1.1 Reactor Core SLs ................................................................................................. 5 B2.1.2 Reactor Coolant System (RCS) Pressure SL ....................................................... 1 B 3.0 LCO AND SR APPLICABILITY BASES ............................................................... 3 B 3.1 REACTIVITY CONTROL SYSTEMS B3.1.1 Shutdown Margin (SOM) ...................................................................................... 2 B3.1.2 Reactivity Anomalies ............................................................................................ 1 B3.1.3 Control Rod OPERABILITY .................................................................................. 3 B3.1.4 Control Rod Scram Times ............................................ :....................................... 5 B3.1.5 Control Rod Scram Accumulators ........................................................................ 2 83.1.6 Rod Pattern Control. ..................................................................................*........... 4 B3.1.7 Standby Liquid Control (SLC) System ........ :......................................................... 3 B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ..................................... 4 B 3.2 POWER DISTRIBUTION LIMITS 83.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ................................... 5 83.2.2 Minimum Critical Power Ratio (MCPR) ................................................................ 4 B3.2.3 Linear Heat Generation Rate (LHGR) .................................................................. 3 B 3.3 INSTRUMENTATION 83.3.1.1 Reactor Protection System (RPS) Instrumentation .............................................. 6 B3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................................... 4 B3.3.2.1 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 B3.3.5.1 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 Revisipn 137
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision 8 3.4 REACTOR COOLANT SYSTEM (RCS) 83.4.1 Recirculation Loops Operating ............................................................................. 5 B3.4.2 Jet Pumps ......................................................................................................... 4 83.4.3 Safety/Relief Valves (S/RVs) ................................................................................ 4 B3.4.4 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 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ....................................................................................... 3 B3.4.9 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 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM B3.5.1 ECCS - Operating ................................................................................................ 5 B3.5.2 ECCS - Shutdown ............................................................................................... 3 B3.5.3 RCIC System ........................................................................................................ 5 B 3.6 CONTAINMENT SYSTEMS B3.6.1.1 Primary Containment. ........................................................................................... 6 83.6.1.2 Primary Containment Air Lock .............................................................................. 2 B3.6.1.3 Primary Containment Isolation Valves (PCIVs) ..... :............................................. 16 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 B3.6.2.1 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 B3.6.3.2 Drywell Air Flow System ....................................................................................... 3 B3.6.3.3 Primary Containment Oxygen Concentration ....................................................... 3 B3.6.4.1 Secondary Containment. ..................................................................................... 15 B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .............................................. 13 83.6.4.3 Standby Gas Treatment (SGT) System .............................................................. 6 SUSQUEHANNA- UNIT 2 TS I B LOES-2 Revision 137
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision B 3.7 PLANT SYSTEMS B3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ........................................................................ 7 B3.7.2 Emergency Service Water (ESW) System ........................................................... 3 B3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ............................................................................................... 3 B3.7.4 Control Room Floor Cooling System .................................................................... 1 B3.7.5 Main Condenser Offgas ....................................................................................... 2 B3.7.6 Main Turbine Bypass System ............................................................................... 4 B3.7.7 Spent Fuel Storage Pool Water Level .................................................................. 2 B3.7.8 Main Turbine Pressure Regulation System .......................................................... 1 B 3.8 ELECTRICAL POWER SYSTEM B3.8.1 AC Sources - Operating ..................................................................................... 11 B3.8.2 AC Sources - Shutdown ...................................................................................... 0 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ............................................................ 6 B3.8.4 DC Sources - Operating ...................................................................................... 4 B3.8.5 DC Sources - Shutdown ...................................................................................... 1 B3.8.6 Battery Cell Parameters ....................................................................................... 2 B3.8.7 Distribution Systems - Operating ......................................................................... 6 B3.8.8 Distribution Systems - Shutdown ......................................................................... 1 B 3.9 REFUELING OPERATIONS B3.9.1 Refueling Equipment Interlocks ............................................................................ 1 B3.9.2 Refuel Position One-Rod-Out Interlock ................................................................ 1 B3.9.3 Control Rod Position ............................................................................................ 1 B3.9.4 Control Rod Position Indication ............................................................................ 0 B3.9.5 Control Rod OPERABILITY- Refueling .............................................................. 1 B3.9.6 Reactor Pressure Vessel (RPV) Water Level. ...................................................... 2 B3.9.7 Residual Heat Removal (RHR) - High Water Level ............................................. 1 B3.9.8 Residual Heat Removal (RHR) - Low Water Level. ............................................. 1 B 3.10 SPECIAL OPERATIONS B3.10.1 lnservice Leak and Hydrostatic Testing Operation ............................................... 1 B3.10.2 Reactor Mode Switch Interlock Testing ................................................................ 1 B3.10.3 Single Control Rod Withdrawal - Hot Shutdown .................................................. 1 B3.10.4 Single Control Rod Withdrawal - Cold Shutdown ................................................ 1 B3.10.5 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 B3.10.8 SHUTDOWN MARGIN (SOM) Test- Refueling ............. :.................................... 3 SUSQUEHANNA - UNIT 2 TS I B LOES-3 Revision 137
Rev. 15 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.1 (continued)
REQUIREMENTS The analysis should consider the actual conditions (equipment configuration, temperature, atmospheric pressure, wind conditions, measured secondary containment vacuum, etc.) to determine whether, if an accident requiring secondary containment to be OPERABLE were to occur, one train of SGT could establish the assumed secondary containment vacuum within the time assumed in the accident analysis. If so, the SR may be considered met for a period up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit is based on the expected should duration of the situation when the Note would be applied.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.6.4.1.2 and SR 3.6.4.1.3 Verifying that secondary containment equipment hatches, removable walls and one access door in each access opening required to be closed are closed ensures that the infiltration of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur.
Verifying that all such openings are closed also provides adequate assurance that exfiltration from the secondary containment will not occur.
In this application, the term "sealed" has no connotation of leak tightness.
An access opening typically contains one inner and one outer door.
Maintaining secondary containment OPERABILITY requires verifying one door in each access opening to secondary containment zones is closed.
In some cases (e.g., railroad bay), secondary containment access openings are shared such that a secondary containment barrier may have multiple inner or multiple outer doors. The intent is to maintain the secondary containment barrier intact, which is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, brief, inadvertent, simultaneous opening of the inner and outer secondary containment doors for personnel entry and exit is allowed. Intentional or extended opening of both doors simultaneously, even for personnel entry and exit, is not permitted and will result in Secondary Containment being declared INOPERABLE. All secondary containment access doors are normally kept closed, except when the access opening is being used for entry and exit or when maintenance is being performed on an access opening.
(continued)
SUSQUEHANNA - UNIT 2 TS I B 3.6-87 Revision 5
Rev. 15 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)
REQUIREMENTS When the railroad bay door (No. 101) is closed; all Zone I and Ill hatches, removable walls, dampers, and one door in each access opening connected to the railroad access bay are closed; or, only Zone I removable walls and/or doors are open to the railroad access shaft; or, only Zone Ill hatches and/or dampers are open to the railroad access shaft. When the railroad bay door (No. 101) is open; all Zone I and Ill hatches, removable walls, dampers, and one door in each access opening connected to the railroad access bay are closed. The truck bay hatch is closed and the truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and Ill.
The access openings between secondary containment zones which are not provided with two doors are administratively controlled to maintain secondary containment integrity during exit and entry. This Surveillance is modified by a Note that allows access openings with a single door (i.e., no airlock) within the secondary containment boundary (i.e., between required secondary containment zones) to be opened for entry and exit. Opening of an access door for entry and exit allows sufficient administrative control by individual personnel making the entries and exits to assure the secondary containment function is not degraded. When one of the zones is not a zone required for secondary containment OPERABILITY, the Note allowance would not apply.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
SUSQUEHANNA - UNIT 2 TS I B 3.6-87a Revision 5
Rev. 15 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 REQUIREMENTS (continued) The SGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment. To ensure that all fission products are treated, SR 3.6.4.1.4 verifies that the SGT System will rapidly establish and maintain a pressure in the secondary containment that is less than the pressure external to the secondary containment boundary.
This is confirmed by demonstrating that one SGT subsystem will draw down the secondary containment to ~ 0.25 inches of vacuum water gauge in less than or equal to the maximum time allowed. This cannot be accomplished if the secondary containment boundary is not intact. SR 3.6.4.1.5 demonstrates that one SGT subsystem can maintain ~ 0.25 inches of vacuum water gauge for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at less than or equal to the maximum flow rate permitted for the secondary containment configuration that is operable. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows secondary containment to be in thermal equilibrium at steady state conditions. As noted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits are dependent upon the secondary containment configuration when testing is being performed. The acceptance criteria for the SRs based on secondary containment configuration is defined as follows:
SECONDARY MAXIMUM DRAWDOWN TIME(SEC) MAXIMUM FLOW RATE (CFM)
CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5 TEST CONFIGURATION ACCEPTANCE CRITERIA) . ACCEPTANCE.CRITERIA)
Grouo 1 Zones I, II and Ill (Unit 1 s 300 Seconds s5400CFM Railroad Bay aligned to (Zones I, II, and Ill) (From Zones I, II, and Ill)
Zones II and Ill (Unit 1 s 300 Seconds s4000 CFM Railroad Bay aligned to (Zones II and Ill) (From Zones II and Ill)
Zone Ill).
Group2 Zones I, II and Ill (Unit 1 s 300 Seconds s5300CFM Railroad Bay not aligned to (Zones I, II, and Ill) (From Zones I, II, and Ill)
Zones II and Ill (Unit 1 s 300 Seconds s3900CFM Railroad Bay not aligned to (Zones II and Ill) (From Zones II and Ill)
Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.
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SUSQUEHANNA - UNIT 2 TS I B 3.6-88 Revision 6
Rev. '15 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)
REQUIREMENTS A Note also modifies the Frequency for each SR. This Note identifies that each configuration is to be tested every 60 months. Testing each configuration every 60 months assures that the most limiting configuration is tested every 60 months. The 60 month Frequency is acceptable because operating experience has shown that these components usually pass the Surveillance and all active components are tested more frequently.
Therefore, these tests are used to ensure secondary containment boundary integrity.
The secondary containment testing configurations are discussed in further detail to ensure the appropriate configurations are tested. Three zone testing (Zones, I, II and Ill aligned to the recirculation plenum) should be performed with the Railroad Bay aligned to secondary containment and another test with the Railroad Bay not aligned to secondary containment.
Each test should be perf9rmed with each division on a STAGGERED TEST BASIS.
Two zone testing (Zones II and Ill aligned to the recirculation plenum) should be performed with the Railroad Bay aligned to secondary containment and another test with the Railroad Bay not aligned to secondary containment.
Each test should be performed with each division on a STAGGERED TEST BASIS. The normal operating fans of the non-tested HVAC zone (Zone I fans 1V202A&B, 1V205A&B and 1V206A&B) should not be in operation.
Additionally, a controlled opening of adequate size should be maintained in Zone I Secondary Containment during testing to assure that atmospheric conditions are maintained in that zone.
The Unit 1 Railroad Bay can be aligned as a No Zone (isolated from secondary containment) or as part of seconda1y containment (Zone I or Ill).
Due to the different leakage pathways that exist in the Railroad Bay, the Railroad Bay should be tested when aligned to secondary containment and also not aligned to secondary containment. It is preferred to align the Railroad Bay to Zone Ill when testing with the Railroad Bay aligned to secondary containment since Zone Ill is included in all possible secondary containment isolation alignments. Note that when performing the three zone testing (Zones I, II and Ill aligned to the recirculation plenum) aligning the Railroad Bay to either Zone I or Ill is acceptable since either zone is part of secondary containment. When performing the Zone II & Ill testing with the Railroad Bay aligned to secondary containment, the Unit 1 Railroad Bay must be aligned to Zone Ill.
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SUSQUEHANNA - UNIT 2 TS I B 3.6-89 Revision 4
Rev. 15 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)
REQUIREMENTS The Suiveillance Frequency is controlled under the Surveillance Frequency Control Program.
REFERENCES 1. FSAR, Section 6.2.3.
- 2. FSAR, Section 15.6.
- 3. FSAR, Section 15.7.4.
- 4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
SUSQUEHANNA - UNIT 2 TS I B 3.6-89a Revision 1