ML18197A079
| ML18197A079 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/09/2018 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18197A079 (22) | |
Text
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~U..1..U MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2018-12267 USER INFORMATION:
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SSES MANUAL Manual Name:
TSBl
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Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:
07/06/2018 Procedure Name T.EXT LOES*
Rev 133
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 23
Title:
TABLE OF CONTENTS TEXT 2.1.1 6
Issue Date 07/05/2_01?
07 /1}2/2014 01/22/2015 Change ID
Title:
SAFETY LIMITS (SLS) REACTOR CORE SLS 10/04/2007
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SAFETY LIMITS (SLS) REACTOR COOLANT $:YSTEif'*(RCS') /PRESSURE S TEXT 2.1.2 1
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REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3
Title:
TEXT 3.1.4 1,
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,/ 3 11/16/2016 SYSTEMS CONTROL ROD OPERABILITY 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
Change NUIDber Report Date: 07/06/18
r, SSES MANUAL Manual Name:
TSBl Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7 4
11/16/2016
Title:
REAC+IVITY 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 4
01/23/2018
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 5
11/16/2016
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3:3.2.2 3
11/16/2016
Title:
INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 10 11/16/2016
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 2
11/16/2016
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 3
11/16/2016
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION
- Page J of 8
Report Date: 07/06/18
SSES MANUAL Manual Name:
TSBl
- **. Manual
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) INST~BMENTATION 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 TEXT 3.3.7.1 3
11/16/2016
Title:
INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 3
11/16/2016
Title:
INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 1
11/16/2016
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 5
11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 4
11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) JET PUMPS TEXT 3.4.3 3
01/13/2012
Title:
REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVS TEXT 3.4.4 1
11/16/2016
Title:
REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Page}.
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Report Date: 07/06/18
SSES MANUAL Manual Nameg TSBl
-- Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 2
04/13/2016
Title:
REACTOR (RCS)
I (PIV)
COOLANT SYSTEM RCS PRESSURE ISOLATION VALVE LEAKAGE TEXT 3.4.6 5
11/16/2016 Titleg 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 1_
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Report Date: 07/06/18 t
SSES MANUAL Manual Name:
TSBl Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.3 14 04/24/2018
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
~
TEXT 3.6.2.2 1
11/16/2016
Title:
CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL TEXT 3.6.2.3 2
11/16/2016
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING TEXT 3.6.2.4 1
11/16/2016
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 2
06/13/2006
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 3
09/29/2017
Title:
CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 3
09/29/2017
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3.6.4.1 14 07/05/2018
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~
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Report Date: 07/06/18
SSES MANUAL Manual Name:
TSBl Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 13 04/24/2018
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.G:.4.3 6
09/15/~017
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
- ~** TEXT 3. 7. 4 1
11/16/2016
Title:
PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 2
11/16/2016
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3.7.6 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 3.8.1 9
02/27/2018
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING TEXT 3.8.2 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN Page.£ of 8
Report Date: 07/06/18
SSES MANUAL Manual Name:
TSBl Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 6
12/14/2017
Title:
ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 4
11/16/2016
Title:
ELECTRICAL POWER SYSTEMS DC SOURCES -
OPERATING TEXT 3.8.5 1
12/14/2006
Title:
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 TEXT 3.8.8 1
11/16/2016
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -
SHUTDOWN TEXT 3.9.1 1
11/16/2016
Title:
REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 2
11/16/2016
Title:
REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 1
11/16/2016
Title:
REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0
11/15/2002
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 2 of 8
Report Date: 07/06/18
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: 07/06/18
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOG Table of Contents................................................................................................. 23 B 2.0 SAFETY LIMITS BASES B2.1.1 Reactor Core SLs................................................................................................. 6 B2.1.2 Reactor Coolant System (RCS) Pressure SL....................................................... 1 B 3.0 LCO AND SR APPLICABILITY BASES............................................................... 3 8 3.1 REACTIVITY CONTROL BASES 83.1.1 Shutdown Margin (SDM)...................................................................................... 2 83.1.2 Reactivity Anomalies............................................................................................ 1 83.1.3 Control Rod OPERABILITY.................................................................................. 3 B3.1.4 Control Rod Scram Times.................................................................................... 5 B3.1.5 Control Rod Scram Accumulat.ors........................................................................ 2 B3.1.6 Rod Pattern Control.............................................................................................. 4 83.1.7 Standby Liquid Control (SLC) System.................................................................. 4 83.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves..................................... 4 B 3.2 POWER DISTRIBUTION LIMITS BASES 83.2.1 83.2.2 Average Planar Linear Heat Generation Rate (APLHGR)................................... 3 Minimum Critical Power Ratio (MCPR)................................................................ 4 B3.2.3 Linear Heat Generation Rate (LHGR).................................................................. 3 B 3.3 INSTRUMENTATION B3.3.1.1 Reactor Protection System (RPS) Instrumentation.............................................. 7 B3.3.1.2 Source Range Monitor (SRM) Instrumentation.................................................... 4 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) lnstrumentation................................................ 10 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 (ATWS-RPT) Instrumentation............................................................. 1 B3.3.5.1 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 133
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision B 3.4 B3.4.1 B3.4.2 83.4.3 83.4.4 83.4.5 83.4.6 83.4.7 83.4.8 B3.4.9 83.4.10 83.4.11 83.5 83.5.1 83.5.2 83.5.3 83.6 83.6.1.1 83.6.1.2 83.6.1.3 B3.6.1.4 83.6.1.5 83.6.1.6 83.6.2.1 83.6.2.2 83.6.2.3 83.6.2.4 83.q.3.1 83.6.3.2 83.6.3.3 83.6.4.1 83.6.4.2 83.6.4.3 REACTOR COOLANT SYSTEM BASES Recirculation Loops Operating............................................................................. 5 Jet Pumps
......................................................................................................... 4 Safety/Relief Valves (S/RVs)................................................................................ 3 RCS Operational LEAKAGE............................................................................... 1 RCS Pressure Isolation Valve (PIV) Leakage...................................................... 2 RCS Leakage Detection Instrumentation............................................................. 5 RCS Specific Activity............................................................................................ 3 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown....................................................................................... 3 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown..................................................................................... 2 RCS Pressure and Temperature (PIT) Limits...................................................... 5 Reactor Steam Dome Pressure........................................................................... 1 ECCS AND RCIC BASES ECCS - Operating................................................................................................ 5 ECCS - Shutdown............................................................................................... 1 RCIC System........................................................................................................ 5 CONTAINMENT SYSTEMS BASES Primary Containment............................................................................................ 6 Primary Containment Air Lock.............................................................................. 2 Primary Containment Isolation Valves (PCIVs)................................................... 14 Containment Pressure.......................................................................................... 2 Drywell Air Temperature....................................................................................... 2 Suppression Chamber-to-Drywell Vacuum Breakers........................................... 1 Suppression Pool Average Temperature............................................................. 3 Suppression Pool Water Level............................................................................. 1 Residual Heat Removal (RHR) Suppression Pool Cooling................................. 2 Residual Heat Removal (RHR) Suppression Pool Spray..................................... 1 Not Used
......................................................................................................... 2 Drywell Air Flow System....................................................................................... 3 Primary Containment Oxygen Concentration....................................................... 3 Secondary Containment...................................................................................... 14 Secondary Containment Isolation Valves (SCIVs).............................................. 13 Standby Gas Treatment (SGT) System............................................................... 6 SUSQUEHANNA - UNIT 1 TS I B LOES-2 Revision 133
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 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 83.7.6 Main Turbine Bypass System..................... :......................................................... 3 83.7.7 Spent Fuel Storage Pool Water Level.................................................................. 2 B3.7.8 Main Turbine Pressure Regulation System.......................................................... 1 B3.8 ELECTRICAL POWER SYSTEMS BASES B3.8.1 AC Sources - Operating...................................................................................... 9 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 83.8.5 DC Sources - Shutdown...................................................................................... 1 83.8.6 Battery Cell Parameters....................................................................................... 2 83.8.7 83.8.8 Distribution Systems - Operating......................................................................... 2 Distribution Systems - Shutdown.......................................................................... 1 83.9 REFUELING OPERATIONS BASES 83.9.1 Refueling Equipment Interlocks............................................................................ 1 83.9.2 Refuel Position One-Rod-Out Interlock................................................................ 1 B3.9.3 Control Rod Position............................................................................................ 1 83.9.4 Control Rod Position Indication............................................................................ O B3.9.5 Control Rod OPERABILITY-Refueling.............................................................. 1 83.9.6 Reactor Pressure Vessel (RPV) Water Level....................................................... 2
)
B3.9.7 Residual Heat Removal (RHR) - High Water Level............................................. 1 83.9.8 Residual Heat Removal (RHR) - Low Water Level................ :............................. 1 B3.10 SPECIAL OPERATIONS BASES 83.10.1 lnservice Leak and Hydrostatic Testing Operation............................................... 1 83.10.2 Reactor Mode Switch Interlock Testing................................................................ 1 83.10.3 Single Control Rod Withdrawal - Hot Shutdown.................................................. 1 83.10.4 Single Control Rod Withdrawal - Cold Shutdown................................................ 1 B3.10.5 Single Control Rod Drive (CRD) Removal - Refueling........................................ 1 B3.10.6 Multiple Control Rod Withdrawal - Refueling....................................................... 1 83.10.7 Control Rod Testing - Operating.......................................................................... 1 83.10.8 Shutdown Margin (SOM) Test - Refueling........................................................... 2 SUSQUEHANNA - UNIT 1 TS I 8 LOES-3 Revision 133
B 3.6 B 3.6.4.1 BASES CONTAINMENT SYSTEMS Secondary Containment Rev. 14 Secondary Containment B 3.6.
4.1 BACKGROUND
The secondary containment structure completely encloses the primary containment structure such that a dual-containment design is utilized to limit the spread of radioactivity to the environment to within limits. The function of the secondary containment is to contain, dilute, and hold up fission products that may leak from primary containment into secondary containment following a Design Basis Accident (OBA). In conjunction with operation of the Standby Gas Treatment (SGT) System and closure of certain valves whose lines penetrate the secondary containment, the secondary containment is designed to reduce the activity level of the fission products prior to release to the environment and to isolate and contain fission products that are released during certain operations that take place inside primary containment, when primary containment is not required to be OPERABLE, or that take place outside primary containment (Ref. 1).
The secondary containment is a structure that completely encloses the primary containment and reactor coolant pressure boundary components.
This structure forms a control volume that serves to hold up and dilute the fission products. It is possible for the pressure in the control volume to rise relative to the environmental pressure (e.g., due to pump and motor heat load additions).
The secondary containment boundary consists of the reactor building structure and associated removable walls and panels, hatches, doors, dampers, sealed penetrations and valves. Certain plant piping systems (e.g.,
Service Water, RHR Service Water, Emergency Service Water, Feedwater, etc.) penetrate the secondary containment boundary. The intact piping within secondary containment provides a passive barrier which maintains secondary containment requirements. Breaches of these piping systems within secondary containment will be controlled to maintain secondary containment requirements. The secondary containment is divided into Zone I, Zone II and Zone Ill, each of which must be OPERABLE depending on plant status and the alignment of the secondary containment boundary.
Specifically, the Unit 1 secondary containment boundary can be modified to exclude Zone II. Similarly, the Unit 2 secondary containment boundary can be modified to exclude Zone I. Secondary containment may consist of only Zone Ill when in MODE 4 or 5 during CORE ALTERATIONS, or during handling of irradiated fuel within the Zone Ill secondary containment boundary.
(continued)
SUSQUEHANNA - UNIT 1 TS I B 3.6-84 Revision 4
BASES BACKGROUND (continued)
APPLICABLE SAFETY ANALYSES LCO Rev. 14 Secondary Containment B 3.6.4.1 To prevent ground level exfiltration while allowing the secondary containment to be designed as a conventional structure, the secondary containment requires support systems to maintain the control volume pressure at less than the external pressure. Requirements for the safety related systems are specified separately in LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)," and LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."
When one or more zones are excluded from secondary containment, the specific requirements for support systems will also change (e.g., required secondary containment isolation valves).
There are two principal accidents for which credit is taken for secondary containment OPERABILITY. These are a loss of coolant accident (LOCA)
(Ref. 2) and a fuel handling accident inside secondary containment (Ref. 3).
The secondary containment performs no active function in response to either of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from the primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the SGT System prior to discharge to the environment.
Secondary containment satisfies Criterion 3 of the NRC Policy Statement (Ref. 4).
An OPERABLE secondary containment provides a control volume into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondary containment, can be diluted and processed prior to release to the environment. For the secondary containment to be considered OPERABLE, it must have adequate leak tightness to ensure that the required vacuum can be established and maintained. The leak tightness of secondary containment must also ensure that the release of radioactive materials to the environment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis. For example, secondary containment bypass leakage must be restricted to the leakage rate required by LCO 3.6.1.3. The secondary containment boundary required to be OPERABLE is dependent on the operating status of both units, as well as the configuration of walls, doors, hatches, SCIVs, and available flow paths to the SGT System.
(continued)
SUSQUEHANNA - UNIT 1 TS/ B 3.6-85 Revision 2
BASES (continued)
APPLICABILITY ACTIONS Rev. 14 Secondary Containment B 3.6.4.1 In MODES 1, 2, and 3, a LOCA could lead to a fission product release to primary containment that leaks to secondary containment. Therefore, secondary containment OPERABILITY is required during the same operating conditions that require primary containment OPERABILITY.
In MODES 4 and 5, the probability and consequences of the LOCA are reduced due to the pressure and temperature limitations in these MODES.
Therefore, maintaining secondary containment OPERABLE is not required in MODE 4 or 5 to ensure a control volume, except for other situations for which significant releases of radioactive material can be postulated, such as during operations with a potential for draining the reactor vessel (OPDRVs), during CORE ALTERATIONS, or during movement of irradiated fuel assemblies in the secondary containment.
If secondary containment is inoperable, it must be restored to OPERABLE status within 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 /> Completion Time provides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary containment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.
A temporary (one-time) Completion Time is connected to the Completion Time Requirements above (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) with an "OR" connector. The Temporary Completion Time is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and applies to the replacement of the Reactor Building Recirculating Fan Damper Motors. The Temporary Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may only be used once, and expires on December 31, 2005.
B.1 and B.2 If secondary containment cannot be restored to OPERABLE status within the required Completion Time, 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 /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
(continued)
SUSQUEHANNA - UNIT 1 TS I B 3.6-86 Revision 4
BASES ACTIONS (continued)
SURVEILLANCE REQUIREMENTS C.1, C.2, and C.3 Rev. 14 Secondary Containment B 3.6.4.1 Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.
Suspension of these activities shall not preclude completing an action that
. involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until OPDRVs are suspended.
Required Action C.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.
SR 3.6.4.1.1 This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude exfiltration under expected wind conditions.
The SR is modified by a Note which states the SR is not required to be met for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if an analysis demonstrates that one SGT subsystem remains capable of establishing the required secondary containment vacuum. Use of the Note is expected to be infrequent but may be necessitated by situations in which secondary containment vacuum may be less than the required containment vacuum, such as, but not limited to, wind gusts or failure or change of operating normal ventilation subsystems. These conditions do not indicate any change in the leak tightness of the secondary containment boundary.
(continued)
SUSQUEHANNA - UNIT 1 TS I B 3.6-87 Revision 3
- ~
BASES Rev. 14 Secondary Containment B 3.6.4.1 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 1 TS I B 3.6-88 Revision 5
BASES Rev. 14 Secondary Containment B 3.6.4.1 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 1 TS I B 3.6-88a Revision 4
BASES SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 REQUIREMENTS Rev. 14 Secondary Containment B 3.6.4.1 (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 2:: 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 2:: 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)
Group 1 Zones I, II and Ill (Unit 1
- s; 300 Seconds
- 5400 CFM Railroad Bay aligned to (Zones I, II, and 111)
(From Zones I, II, and Ill)
Zones I and Ill (Unit 1 Railroad
- s; 300 Seconds
- 3900 CFM Bay aligned to Secondary (Zones I and Ill)
(From Zones I and Ill)
Containment).
Group 2 Zones I, II and Ill (Unit 1
- s; 300 Seconds
- 5300 CFM Railroad Bay not aligned to (Zones I, II, and Ill)
(From Zones I, II, and 111)
Secondarv Containment).
Zones I and Ill (Unit 1 Railroad
- s; 300 Seconds
- 3800 CFM Bay not aligned to Secondary (Zones I and 111)
(From Zones I and Ill)
Containment).
Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.
(continued)
SUSQUEHANNA - UNIT 1 TS I B 3.6-89 Revision 6
BASES Rev. 14 Secondary Containment B 3.6.4.1 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 performed with each division on a STAGGERED TEST BASIS.
Two zone testing (Zones I 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 II fans 2V202A&B, 2V205A&B and 2V206A&B) should not be in operation.
Additionally, a controlled opening of adequate size should be maintained in Zone II 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 secondary 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 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 aligning the Railroad Bay to either Zone I or Ill is acceptable since either zone is part of secondary containment.
(continued)
SUSQUEHANNA - UNIT 1 TS I B 3.6-90 Revision 4
BASES Rev. 14 Secondary Containment B 3.6.4.1 SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)
REQUIREMENTS REFERENCES The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
- 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 1 TS I B 3.6-90a Revision 1