ML17118A075
| ML17118A075 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/20/2017 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17118A075 (35) | |
Text
{{#Wiki_filter:Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2017-5968 USER INFORMATION: GERLACH*ROSEY M EMPL#: 028401 CA#: 0363 Address: NUCSA2 Phone#: 542-3194 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 04/20/2017 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
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TECHNICAL SPECIFICATION BASES UNIT l MANUAL Table Of Contents Issue Date: 04/19/2017 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 125 04/19/2017
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LIMITING CONDITION FOR OPERATIO::Y-{LG:O')".lIBPLICABILITY
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REACTIVITY\CONTR0L SYSTEMS CONTROL ROD OPERABILITY
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REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3 .1.5 2 11/16/2016
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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: 04/19/17
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TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL
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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)
.. *: 't'EXT 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 3.3.2.1 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.l 3 11/16/2016
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION Pagel of 8 Report Date: 04/19/17
SSES MANUAL J Manual Name: TSBl
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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: 04/19/17
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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
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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.l 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 4 11/16/2016
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM RCIC SYSTEM LDCN 5307 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: 04/19/17
SSES MANUAL Manual Name: TSBl [anual
Title:
TECHNICAL SPECIFICATION BASES UNIT l MANUAL TEXT 3.6.l.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
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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 2 11/16/2016
Title:
CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 2 11/16/2016
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3.6.4.1 13 04/19/2017
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~ of 8 Report Date: 04/19/17
SSES MANUAL I Manual Name: TSBl
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Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 12 04/19/2017
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS) LDCN 5240 TEXT 3.6.4.3 5 11/16/2016
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 2 11/16/2016
Title:
PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM "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 l 11/16/2016
Title:
PLANT SYSTEMS TEXT 3.8.l 8 11/16/2016
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING TEXT 3.8.2 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN Page .§. of 8 Report Date: 04/19/17
SSES MANUAL I 'l' Manual Name: TSBl ranual
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 o'PERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 2 11/16/2016
Title:
REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 1 11/16/2016
Title:
REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 1 11/16/2016
Title:
REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.6 2 11/16/2016
Title:
REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page']_ of 8 Report Date: 04/19/17
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.l 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
'i:'EXT 3.10.4 1 11/16/2016 ~iJ*L:-
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 Tit.le: 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: 04/19/17
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) Section Title Revision TOC Table of Contents .................................................................................................23 B 2.0 SAFETY LIMITS BASES 82.1.1 Reactor Core SLs ................................................................................................. 6 82.1.2 Reactor Coolant System. (RCS) Pressure SL.. ..................................................... 1 B 3.0 LCO AND SR APPLICABILITY BASES ............................................................... 3 B 3.1 REACTIVITY CONTROL BASES 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 .................................................................. 4 83.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ..................................... 4 8 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 8 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) 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) lnstrumentation ............................................................. 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 8 LOES-1 Revision 125
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) Section Title Revision B 3.4 REACTOR COOLANT SYSTEM BASES 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 83.4.5 RCS Pressure Isolation Valve (PIV) Leakage ...................................................... 2 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 83.5 ECCS AND RCIC BASES 83.5.1 ECCS - Operating ................................................................................................ 5 83.5.2 ECCS - Shutdown ............................................................................................... 1 83.5.3 RCIC System ........................................................................................................ 4 83.6 CONTAINMENT SYSTEMS BASES 83.6.1.1 Primary Containment. ........................................................................................... 6 83.6.1.2 Primary Containment Air Lock .............................................................................. 2 83.6.1.3 Primary Containment Isolation Valves (PCIVs) ................................................... 13 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 ....................................................................................... 2 83.6.3.3 Primary Containment Oxygen Concentration ....................................................... 2 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 ............................................................... 5 SUSQUEHANNA - UNIT 1 TS I B LOES-2 Revision 125
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) Section Title Revision B3.7 PLANT SYSTEMS BASES B3.7.1 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 ...................... 2 B3.7.4 Control Room Floor Cooling System .................................................................... 1 B3.7.5 Main Condenser Offgas ....................................................................................... 2 B3.7.6 Main Turbine Bypass System ............................................................................... 3 B3.7.7 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 ...................................................................................... 8 B3.8.2 AC Sources - Shutdown ...................................................................................... O B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ............................................................ 5 B3.8.4 DC Sources - Operating ...................................................................................... 4 B3.8.5 DC Sources - Shutdown ....................................... ,.............................................. 1 B3.8.6 Battery Cell Parameters ....................................................................................... 2 83.8.7 Distribution Systems - Operating ......................................................................... 2 B3.8.8 Distribution Systems - Shutdown ......................................................................... 1 B3.9 REFUELING OPERATIONS BASES 83.9.1 Refueling Equipment Interlocks ............................................................................ 1 83.9.2 Refuel Position One-Rod-Out Interlock ................................................................ 1 83.9.3 Control Rod Position ............................................................................................ 1 B3.9.4 Control Rod Position Indication ............................................................................ 0 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 B3.10 SPECIAL OPERATIONS BASES 83.10.1 lnservice Leak and Hydrostatic Testing Operation ............................................... 1 83.10.2 Reactor Mode Switch Interlock Testing ................................................................ 1 83.10.3 Single Control Rod Withdrawal - Hot Shutdown .................................................. 1 83.10.4 Single Control Rod Withdrawal. - Cold Shutdown ................................................ 1 83.10.5 Single Control Rod Drive (CRD) Removal - Refueling ........................................ 1 83.10.6 Multiple Control Rod Withdrawal - Refueling ....................................................... 1 83.10.7 Control Rod Testing - Operating .......................................................................... 1 83.10.8 Shutdown Margin (SOM) Test - Refueling ........................................................... 2 SUSQUEHANNA - UNIT 1 TS I B LOES-3 Revision 125
Rev. 13 Secondary Containment B 3.6.4.1 B 3.6 CONTAINMENT SYSTEMS B 3.6.4.1 Secondary Containment BASES 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
Rev. 13 Secondary Containment B 3.6.4.1 BASES BACKGROUND To prevent ground level exfiltration while allowing the secondary containment (continued) 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). APPLICABLE There are two principal accidents for which credit is taken for secondary SAFETY containment OPERABILITY. These are a loss of coolant accident (LOCA) ANALYSES (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). LCO 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 I B 3.6-85 Revision 2
Rev. 13 Secondary Containment B 3.6.4.1 BASES (continued) APPLICABILITY 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. ACTIONS A.1 If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours. The 4 hour 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 hours) with an "OR" connector. The Temporary Completion Time is 48 hours and applies to the replacement of the Reactor Building Recirculating Fan Damper Motors. The Temporary Completion Time of 48 hours 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 hours and to MODE 4 within 36 hours. 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 _ _J
Rev. 13 Secondary Containment B 3.6.4.1 BASES ACTIONS C.1, C.2, and C.3 (continued) 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. SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude exfiltration under expected wind conditions. Expected wind conditions are defined as sustained wind speeds of less than or equal to 16 mph at the 60m meteorological tower or less than or equal to 11 mph at the 1Om meteorological tower if the 60m tower wind speed is not available. Changes in indicated reactor building differential pressure observed during periods of short-term wind speed gusts above these sustained speeds do not by themselves impact secondary containment integrity. However, if secondary containment integrity is known to be compromised, the LCO must" be entered regardless of wind speed. (continued) SUSQUEHANNA - UNIT 1 TS I B 3.6-87 Revision 2
Rev. 13 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.1 (continued) REQUIREMENTS 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 secondaf"Y 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 4
Rev. 13 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 1 TS I B 3.6-88a Revision 4
Rev. 13 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 hour at less than or equal to the maximum flow rate permitted for the secondary containment configuration that is operable. The 1 hour 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 :;;; 300 Seconds :5:5400 CFM Railroad Bay aligned to (Zones I, II, and Ill) (From Zones I, II, and Ill) Secondary Containment). Zones I and Ill (Unit 1 Railroad ::; 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 :;;; 300 Seconds ::;5300 CFM Railroad Bay not aligned to (Zones I, II, and Ill) (From Zones I, II, and Ill) Secondary Containment). Zones I and Ill (Unit 1 Railroad :;;; 300 Seconds :5:3800 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
Rev. 13 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 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
Rev. 13 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 Surveillance 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 1 TS I B 3.6-90a Revision 1
Rev. 12 SCI Vs B 3.6.4.2 3.6 CONTAINMENT SYSTEMS B 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) BASES BACKGROUND The function of the SCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Ref. 1). Secondary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that fission products that leak from primary containment into secondary containment following a OBA, or that are released duling certain operations when primary containment is not required to be OPERABLE or take place outside primary containment, are maintained within the secondary containment boundary.
- The OPERABILITY requirements for SCIVs help ensure that an adequate secondary containment boundary is maintained during and after an accident by minimizing potential paths to the environment. These isolation devices consist of either passive devices or active (automatic) devices. Manual valves or dampers, de-activated automatic valves or dampers secured in their closed position (including check valves with flow through the valve secured), and blind flanges are considered passive devices.
Automatic SCIVs close on a secondary containment isolation signal to establish a boundary for untreated radioactive material within secondary containment following a OBA or other accidents. Other non-sealed penetrations which cross a secondary containment boundary are isolated by the use of valves in the closed position or blind flanges. APPLICABLE The SCIVs must be OPERABLE to ensure the secondary containment barrier SAFETY to fission product releases is established. The principal accidents for which ANALYSES the secondary containment boundary is required are a loss of coolant accident (Ref. 1) and a fuel handling accident inside secondary containment (Ref. 2). The secondary containment performs no active function in response to either of these limiting events, but the boundary (continued) SUSQUEHANNA'- UNIT 1 TS I B 3.6-91 Revision*3
Rev.12 SCI Vs B 3.6.4.2 BASES APPLICABLE established by SCIVs is required to ensure that leakage from the primary SAFETY containment is processed by the Standby Gas Treatment (SGT) System ANALYSES before being released to the environment. (continued) Maintaining SCIVs OPERABLE with isolation times within limits ensures that fission products will remain trapped inside secondary containment so that they can be treated by the SGT System prior to discharge to the environment. SCIVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 3) . LCO . SCIVs that form a part of the secondary containment boundary are required to be OPERABLE. Depending on the configu~ation of the secondary containment only specific SCIVs are required. The SCIV safety function is related to control of offsite radiation releases resulting from DBAs. The automatic isolation valves are considered OPERABLE when their isolation times are within limits and the valves actuate on an automatic isolation. signal. The valves covered by this LCO, along with their associated stroke times, are listed in Table B 3.6.4.2-1. The normally closed isolation valves or blind flanges are considered OPERABLE when manual valves are closed or open in accordance with appropriate administrative controls, automatic SCIVs are deactivated and secured in their closed position, or blind flanges are in place. These passive isolation valves or devices are listed-in Table 83.6.4.2-2. Penetrations closed with sealants are considered part of the secondary containment boundary and are not COf!Sidered penetration flow paths. 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. When the SOHR and temporary chiller system piping is connected and full of water, the piping forms the secondary containment boundary and the passive devices in TS BasE!S Table 83.6.4.2-2 are no longer required for these systems since the piping forms the barrier. During certain plant evolutions, piping systems may be drained and breached within secondary containment. During the pipe breach, system isolation valves can be used to provide secondary containment isolation. The isolation valve alignment will be controlled when the piping system is breached. (continued) SUSQUEHANNA - UNIT 1 TS/ B 3.6-92 Revision 3
Rev. 12 SCIVs B 3.6.4.2 BASES (continued) APPLICABILITY In MODES 1, 2, and :?. a OBA could lead to a fission product release to the primary containment that leaks to the secondary containment. Therefore, the OPERABILITY of SCIVs is required. In MODES 4 and 5, the probability and consequences.of these events are reduced due to pressure and temperature limitation~ in these MODES. Therefore, maintaining SCIVs OPERABLE is not required in MODE 4 or 5, except for other situations under which significant radioactive releases 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. Moving irradiated fuel assemblies in the secondary containment may also occur in MODES 1, 2, and 3. ACTIONS The ACTIONS are modified by three Notes. The first Note allows penetration flow paths to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated 9perator, who is in continuous communication with the control room, at the controls of the isolation device. In this way, the penetration can be rapidly isolated when a need for secondary containment isolation is indicated. The second Note provides clarification that for the purpose of this LCO separate Condition entry is allowed for each penetration flow path. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable SCIV. Complying with the Reql!irecj
- Actions may allow for continued operation, and subsequent inoperable SCIVs are governed by subsequent Condition entry and application of associated Required Actions.
The third Note ensures appropriate remedial actions are taken, if necessary, if the affected system(s) are rendered inoperable by an inoperable SCIV. A.1 and A.2 In the event that there are one or more required penetration flow paths with one required SCIV inoper~ble, the affected penetration flow path(s) must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic SCIV, a closed manual valve, and a blind flange. For penetrations isolated in (continued) SUSQUEHANNA - UNIT 1 TS I B 3.6-93 Revision 2
Rev. 12 SCI Vs B 3.6.4;2 BASES ACTIONS A.1 and A.2 (continued) accordance with Required Action A.1, the device used to isolate the penetration should be the closest available device to secondary containment. The Required Action must be completed within the 8 hour Completion Time. The specified time period is reasonable considering the time required to isolate the penetration, and the probability of a OBA, which requires the SCJVs to close, occurring during this short time is very low. For affected penetrations that have been isolated in accordance with Required Action A.1, the affected penetration must be verified to be isolated on a periodic _basis. This is necessary to ensure that secondary containment penetrations required to be isolated following an accident, but no longer capable of being automatically isolated, will be in the isolation position should an event occur. The Completion Time of once per 31* days is appropriate because the valves are operated under administrative controls and the probability of their misalignment is low. This Required Action does not require any testing or device manipulation. Rather, it involves verification that the affected penetration remains isolated. Condition A is modified by a Note indicating that this Condition is only applicable to those penetration flow paths with two SCIVs. For penetration flow paths with one SCIV, Condition C provides the appropriate Required Actions. Required Action A.2 is modified by a Note that applies to devices located in high radiation areas and allows them to be verified closed by use of
- administrative controls. Allowing verification by administrative controls is considered acceptable, since access to these areas is typically restricted.
Therefore, the probability of misalignment, once they have been verified to be in the proper position, is low. With two SCIVs in one or more penetration flow paths inoperable, the affected penetration flow path must be isolated within 4 hours. The method of isolation must (continued) SUSQUEHANNA - UNIT 1 TS I B 3.6-94 Revision 1
Rev.12 SC IVs B 3.6.4.2 BASES ACTIONS B.1 (continued) include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de..:activated automatic valve, a closed manual valve, and a blind flange. The 4 hour Completion Time is reasonable considering the time required to isolate the penetration and the probability of a OBA, which requires the SCIVs to close, occurring during this short time, is very low. The Condition has been modified by a Note stating that Condition B is only applicable to penetration flow paths with two isolation valves. For penetration flow paths with one SCIV, Condition C provides the appropriate Required Actions. C.1 and C.2 With one or more required penetration flow paths with one required SCIV inoperable, the inoperable valve must be restored to OPERABLE status or the affected penetration flow path must be isolated. The method of isolatior:i must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. A check valve may not be used to isolate the affected penetration. Required Action C.1 must be completed within the 4 hour Completion Time. The Completion Time of 4 hours is reasonable considering the relative stability of the system {hence, reliability) to act as a penetration isolation boundary and the relative importance of supporting secondary containment OPERABILITY during MODES 1, 2, and 3. In the event the affected penetration flow path is isolated in accordance with Required Action C.1, the affected penetration must be verified to be isolated on a periodic basis. This is necessary to ensure that secondary containment penetrations required to be isolated following an accident are isolated. The Completion Time of once per 31 days for verifying each affected penetration is isolated is appropriate because the (continued) SUSQUEHANNA- UNIT 1 TS I B 3.6-95 Revision 1
Rev. 12 SCI Vs B 3.6.4.2 BASES . ACTIONS C.1 and C.2 (continued) valves are operated under administrative controls and the probability of their misalignment is low. Condition C is modified by a Note indicating that this Condition is only . applicable to penetration flow paths with only one SCIV. For penetration flow paths with two SCIVs, Conditions A and B provide the appropriate Required Actions.
- Required Action C.2 is modified by a Note that applies to valves and blind flanges located in high radiation areas and allows them to be verified by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted.
Therefore, the probability of misalignment of these valves, once they have been verified to be in the proper position, is low. D.1 and D.2 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 hours and to MODE 4 within 36 hours. 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 chal!enging plant systems. E.1, E.2. and E.3.
*if any Required Action and associated Completion Time are not met, the plant must be placed in a condition in which the LCO does not apply. If applicable, CORE ALTERATIONS and the movement of irradiated fuel assemblies in the secondary containment must be immediately suspended. Suspension of these of activities shall not preclude completion of movement a component to a safe position. Also, if applicable, actions must be immediately initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and the subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.
(continued) SUSQUEHANNA - UNIT 1 TS /:B 3.6-96 Revision 1
Rev. 12 SCI Vs B 3.6.4.2 BASES ACTIONS E.1. E.2. and E.3 (continued) Required Action E.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 fuel while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, iri either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.6.4.2.1 REQUIREMENTS ...* . This SR verifies that each secondary containment manual isolation valve and blind flange that is required to be closed during accident conditions is closed. The SR helps to ensure that post accident leakage of radioactive fluids or gases outside of the secondary containment boundary is within design limits. This SR does not require any testing or valve manipulation. Rather, it involves verification (typically visual) that those required SCIVs in secondary containment that are capable of be!ng mispositioned are in the correct position. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Two Notes have been added to this SR. The first Note applies to valves and blind flanges located in high radiation areas and allows them to be verified by use of administrative controls. Allowing verification by administrative controls is considered acceptable, since access to these areas is typically restricted during MODES 1, 2, and 3 for ALARA reasons. Therefore, the probability of misalignment of these SCIVs, once they have been verified to be in the* proper position, is low. A second Note has been included to clarify that SCIVs that are open under administrative controls are not required to meet the SR during the time the r SCIVs are open. (continued) SUSQUEHANNA- UNIT 1 TS I B 3.6-97 Revision 3
Rev. 12 SCI Vs B 3.6.4.2 BASES SURVEILLANCE SR 3.6.4.2.2 REQUfREMENTS (continued) SCIVs with maximum isolation times specified in Table B 3.6.2.4-1 are tested to verify that the isolation time is within limits to demonstrate*
*OPERABILITY. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Automatic SCIVs without maximum isolation times specified in Table B 3.6.4.2-1 are tested under the requirements of SR 3.6.4.2.3. The isolation time test ensures that the SCIV wili isolate in a time period Jess than or equal to that assumed in the safety analyses.
SR 3.6.4.2.3 Verifying that each automatic required SCIV closes on a secondary containment isolation signal is required to prevent leakage of radioactive material from secondary containment following a OBA or other accidents. This SR ensures that each automatic SCIV will actuate to the isolation position on a secondary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. REFERENCES 1. FSAR, Section 6.2.
- 2. . FSAR, Section 15.
- 3. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
SUSQUEHANNA- UNIT 1 TS/ B 3.6-98 Revision 2
Rev.12 SCIVs. B 3.6.4.2 Table B 3.6.4.2-1 Secondary Containment Ventilation System Automatic Isolation Dampers (P~ge 1of1) Maximum Reactor Valve Number Valve Description Type of Valve Isolation Building Time Zone (Seconds) I HD-17586 A&B Supply System Dampers Automatic Isolation Damper 1.0.0 I HD-17524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0* I HD-17576A&B Unfiltered Exhaust System Dampers . Automatic Isolation Damper 10.0 II HD-27586 A&B Supply System Dampers Automatic Isolation Darriper 10.0 II HD-27524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0 II HD-27576 A&B Unfiltered Exhaust System Dampers Automatic Isolation Damper 10.0 Ill HD-17564A&B Supply System Dampers Automatic Isolation Damper 14.0 Ill HD-17514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 Ill HD-17502A&B Unfiltered Exhaust System Dampers Automatic Isolation Damper 6.0 Ill HD-27564 A&B Supply System Dampers Automatic Isolation Damper 14.0 lll HD-27514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 Ill HD-27502 A&B Unfiltered Exhaust System Dampers Automatic Isolation Damper 6.0 N/A HD-17534A Zone 3 Airlock 1-606 Automatic Isolation Damper N/A N/A HD-175348 Zone 3 Airlock 1-611 Automatic Isolation Damper NIA N/A HD-175340 Zone 3 Airlock 1-803 Automatic Isolation Damper N/A N/A HD-17534E Zone 3 Airlock 1-805 Automatic lsolatioi:i Damper N/A N/A HD-17534F . Zone 3Airlock1-617 Automatic Isolation Damper N/A N/A HD-17534H Zone 3 Airlock l-61 B Automatic Isolation Damper N/A NIA HD-27534A Zone 3 Airlock 11-606 Automatic Isolation Damper NIA NIA HD-275340 Zone 3 Airlock 11-803 Automatic Isolation Damp.er NIA N/A HD-27534E Zone 3 Airlock 11-805 Automatic Isolation Damper NIA N/A HD-275348 Zone 3 Airlock C-806 Automatic Isolation Damper N/A NIA HD-27534H Zone 3 Airlock 11-618 Automatic Isolation Damper NIA N/A HD-275341 Zone 3 Airlock 11-609 Automatic Isolation Damper N/A SUSQUEHANNA- UNIT 1 TSJ B 3.6-99 Revision 2
Rev.12 SCI Vs B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System Passive Jsolation Valves or Devices *-
. (Page 1 of 4)
Device Device Description Area/Elev. Required Position I Notes Number X-29-2-44 SOHR Svstem to Fuel Pool Cooling Yard/670 Blind Flanged I Note 1 X-29-2-45 SOHR Svstem to Fuel Pool Coolina Yard/670 Blind Flanaed I Note 1 110176 SDHR Suoolv Drain Viv 29/670 Closed Manuar Isa Valve/ Note 1 110186 SOHR Discharae Drain Viv 29/670 Closed Manual Isa Valve I Nole 1 110180 SOHR Suoolv Vent Viv 29/749 Closed Manual Isa Valve I Note 1 110181 SOHR Discharae RI! Viv 27/749 Closed Manual Isa Valve I Note 1 110182 SOHR Discharge Vent Viv 27/749 Closed Manuaf Isa Valve I Note 1 110187 SOHR Supply Fill Viv 29/749 Closed Manual lso Valve I Note 1 210186 SOHR Supply Drain Viv 33/749 Closed Manual Isa Valve I Nole 1 210187 SDHR Supply Vent Viv 33/749 Closed Manual Isa Valve I Note 1 210191 SOHR Discharge Vent Viv 30/749 Closed Manual Isa Valve I Note 1 210192 SOHR Dlscharae Drain Viv 301749 Closed Manual lso Valve I Note 1 210193 SOHR Discharae Vent Viv 331749 Closed Manual lso Valve I Note 1 X-29-2-46 TemooraryChillerto RBCW Yard/670 Blind Flanoed I Note 2 X-29-2-47 Temoorary Chiller to RBCW Yard/670 Blind Flanoed I Note 2 X-29-5-95 Temoorary Chiller to Unit 1 RBCW 29/149 Bl!nd Flanged I Note 2 X-29-5-96 Temoorarv Chiller to Unit 1 RBCW 29/749 Blind Ranged I Note 2 X-29-5-91 Temoorarv Chiller to Unit 2 RBCW 33/749 Blind Flanged I Note 2 X-29-5-92 Temnorary Chiller to Unit 2 RBCW 33/749 Blind Flanoed I Note 2 187388 RBCW Temp Chiller Discharge Jso Viv 29/670 Closed Manual lso Valve I Note 2 187389 RBCW Temo Chiller Supply !so Viv 29/670 Closed Manual lso Valve I Note 2 187390 RBCW Temo Chiller Supply Drain Viv 29/670 Closed Manual [so Valve I Note 2 187391 RBCW Temo Chnler Discharae Drain Viv 29/670 Closed Manual lso Valve I Note 2 X-28-2-3000 Utmtv Penetration to Unit 1 East Stairwell Yard/670 Blind Flanged I Note 3 X-29-2-48 Utilitv Penetration to Unit 1 RR Bav Yard/670 Canned I Note 5 X-33-2-3000 Utilitv Penetration to Unit 2 East Stairwell Yard/670 Blind Flanged I Note 4 X-28-2-3000 UHlitv Penetration to Unit 1 East Stairwell 28/670 Blind Flanaed I Note 3 X-29-2-48 Utility Penetration to Unit 1 RR Bav 29/670 Caooed I Note 5 X-33-2-3000 Ulilitv Penetration to Unit 2 East Stairwell 33/670 Blind Ftanged I Note 4 X-29-3-54 Utilllv Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanaed I Note 6 X-29-3-55 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged I Note 6 X-29-5-97 Utility Penetration from Unit 1 RR Bav to Unit 2 Elev. 749 331749 Canned X-27-6-92 Instrument Tubing Stubs 27/779' Canned X-29-7-4 1" Soare Conduit Threaded Plua 29/818' Installed X-30-6-72 Instrument Tubino Stubs 30/779' Canoed X-30-6-1002 . Stairwell #214 Rupture Disc 30/779' Installed Intact X-30-6-1003 Airlock 11-609 Rupture Disc 30/779' Installed Intact SUSQUEHANNA - UNIT 1 TS I B 3.6-100 Revision 7
Rev.12 SCI Vs B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System
- Passive Isolation Valves or Devices (Page 2 of 4)
Device Device Description Area/Elev. Required Position I Notes Number X-25-6-1008 Airlock 1-606 Rupture Disc 25/779' Installed Intact X-29-4-01-B Penetration at Door 4330 291719' Blind Flanoe Installed X-29-4-01-A Penetration at Door 4330 291719' Blind Flanoe Installed X-29-4-01-B Penetration at Door 404 33/719' Blind Flanoe Installed X-29-4-01-A Penetration at Door 404 33/719' Blind Flanoe Installed HD17534C Airlock 1-707 Bllnd Flanae 28/799' Bltnd Flanoe Installed HD27534C Airlock 11-707 Blind Flanae 33/799' Blfnd Flange Installed XD-17513 Isolation damper for Railroad Bay Zone Ill HVAC Supply 29/799' Position is dependent on Railroad Bay alii:mment XD-17514 Isolation damper for Railroad Bay Zone Ill HVAC Exhaust 291719' Position is dependent on Railroad Bay alianment XD-12301 PASS Air Flow Damper 11/729' Closed Damper XD-22301 PASS Air Flow Damper 22/729' Closed Damper 161827 HPCl Blowout Steam Vent Drain Valve 25/645' Closed Manual lso Valve I Note 3 161828 RCIC Blowout Steam Vent Drain Valve 28/645' Closed Manual Isa Valve I Note 3 161829 'A'. RHR Blowout Steam Vent Drain Valve 29/645' Closed Manual lso Valve I Note 3 161830 'B' RHR Blowout Steam Vent Drain Valve 28/645' Closed Manual lso Valve I Note 3 261820 RCIC Blowout Steam Vent Drain Valve 33/645' Closed Manual Isa Valve I Note 4 261821 'A' RHR Blowout Steam Vent Drain Valve 34/645' Closed Manual lso Valve I Note 4 261822 'B' RHR Blowout Steam Vent Drain Valve 33/645' Closed Manual lso Valve I Note 4 1LRWl810U Zone Ill Floor Drain 29-818 Pluooed I Note 7 1LRWl810V Zone Ill Floor Drain 29-818 Plu~med I Note 7 1LRW1810W Zone Ill Floor Drain 29-818 Pluaaed I Note 7 1LRWl810X Zone Ill Floor Drain 29-818 Pluaaed I Note 7 1LRW1810Y Zone Ill Floor Drain 29-818 Plu1:10ed I Note 7 1LRWl810Z Zone 111 Floor Drain 29-818 Pluaaed I Note 7 1LRWl810FF Zone Ill Floor Drain 29-818 Pluooed I Note 7 1LRWl810GG Zone Ill Floor Drain 29-818 Pluooed I Note 7 1LRW1810HH Zone Ill Floor Drain 29-818 Pluooed I Note 7 1LRW1810JJ Zone Ill Floor Drain 29-818 Pluaaed I Note 7 1LRWl810KK Zone Ill Floor Drain 29-818 Pluaaed/ Note 7 1LRWl615A Zone I, Zone Ill, or No Zone Floor Drain 29-779 Pluaaed I Note 7 1LRWl100A Zone I, Zone Ill, or No Zone Floor Drain 29-670 Plum1ed I Note 7 1LRWl100B Zone I, Zone Ill, or No Zone Floor Drain 29-670 Plugged I Note! 7 1LRWl100C Zone I, Zone Ill, or No Zone Floor Drain 29-670 Pluaaed I Note 7 1LRWl100D Zone I. Zone Ill, or No Zone Floor Drain 29-670 Pluaaed I Note 7 1LRW110DE Zone l, Zone Ill, or No Zone Floor Drain 29-670 Pluaaed I Note 7 1LRWl100F Zone I, Zone Ill, or No Zone Floor Drain 29-670 Pluaaed I Nole 7 1LRW1100G Zone I, Zone Hf, or No Zone Floor Drain 29-670 Plum:ied I Note 7 SUSQUEHANNA - UNIT 1 TS I B 3.6-100a Revision 6
- Rev. 12 SCI Vs B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System Passive Isolation Valves or Devices (Page 3of4)
Device Device Description Area/Elev. Required Position I Notes Number - 2LRWl810L Zone Ill Floor Drain 34-818 Pluaaed I Note 7 2LRWl810M Zone Ill Floor Drain 34-818 Pluaaed I Note 7 2LRWl81QN Zone Ill Floor Drain 34-818 Pluaaed I Note 7 2LRWl810R Zone Ill Floor Drain 34-818 Pluaaed I Note 7 2LRWl810S Zone 111 Floor Drain 34-818 Pluaaed I Note 7 2LRWl703A Zone II Floor Drain 34-799 Pluaaed I Nole 7 2LRWl615A Zone II Floor Drain 34-779 Pluaaed I Note 7 2LRWl100A Zone II Floor Drain 34-670 Pluaaed I Note 7 2LRW1100B Zone II Floor Drain 34-670 Pluaaed I Note 7 2LRWl100C Zone If Floor Drain 34-670 Pluaaed I Note 7 2LRW1100D Zone II Floor Drain 34-670 Pluaaed I Note 7 2LRW1100E Zone II Floor Drain 34-670 Ph 1aned I Note 7 2LRWl100F Zone II Floor Drain 34-670 Pluaaed I Note 7 2LRWl100G Zone II Floor Drain 34-670 Pluaaed I Note 7 2573280R HCVS Rupture Disc Burst Connection Isolation Valves 21/686' Closed Manual lso Valve I Note 4 257336 SUSQUEHANNA - UNIT 1 TS I B 3.6-100b Revision 5
Rev.12 SC IVs B 3.6.4.2 Table s 3.6.4.2-2 Secondary Containment Ventilation System Passive Isolation Valves or Devices (Page 4 of 4) Note 1: The two blind flanges on the SOHR penetrations (blind flanges for device number X-29-2-44 and X-29-2-45) and all the closed manual valves for the SOHR system (110176, 110186, 110180, 110181, 110182, 110187, 210186, 210187, 210191, 210192, 210193) can each be considered as a separate secondary containment Isolation device for the SDHR penetrations. If one or both of the blind flanges is removed and all the above Identified manual valves for the SOHR system are closed, the appropriate LCO should be entered for one inoperable SCIV in a penetration flow path with two SCIVs. With the blind flange removed, the manual valves could be opened intermittently under administrative* controls per the Technical Specification Note. When both SOHR blind flanges are installed, opening of the manual valves for the SOHR system will be controlled to prevent cross connecting ventilation zones. When the manual valves for the SDHR system are open in this coriditlon, the ap'propriate LCD should be entered for one inoperable SCIV in a penetration fiow path with two SC IVs. When the SDHR system piping is connected and full of water, the piping forms the secondary containment boundary and the above listed SCIVs in Table B3.6.4.2-2 are no longer requlred for this system since the piping forms the barrier. Note 2: Due to the multiple alignments of the RBCW temporary chiller, different devices will perform the SCIV function depending on the RBCW configuration. There are three devices/equipment that can perfonn the SCIV function forthe RBCW temporary chiller supply penetration. The first SCIV for the RBCW temporary chil!er supply penetration is the Installed blind flange on penetration X-29-2-47. The second SCIV for the RBCW temporary chiller supply penetration is Isolation valve 187389. The third SCIV for the temporary RBCW chiller supply penetration Is closed draln valve 187390 and an installed blind flange on penetrations X-29-5-92 and X-29-5-96. Since there are effectively three SCJVs, any two can be used to satisfy the SCIV requirements for the penetration. Removal of one of the two required SCIVs requires entry into the appropriate LCD for one inoperable SQIV in a penetration flow path with two SCIVs. Opening of drain valve 187390 and operation of blank flanges X-29-5-96 and X-29-5-92 will be controlled to prevent cross connecting ventilation zones. These three SCIVs prevent air leakage. The isolation of the penetration per the Technical Specification .requirement is to assure that one of the above SCIVs is closed so that there Is no air leakage. There are three devices/equipment that can perform the SClV function for the RBCW temporary chiller return penetration. The first SCIV for the RBCW temporary chiller return penetration is the Installed blind flange on penetration X-29-2-46. The second SCIV for the RBCW temporary chiller return penetration is isolation valve 187388. The third SCIV for the temporary RBCW chiller return penetration is closed drain valve 187391 and an installed blind flange on penetrations X-29-5-91 and X-29-5-95. Since there are effectively three SCIVs, any two can be used to define the SCIV for the penetration. Removal of one of the two required SCIVs requires entry into the appropriate LCO for one Inoperable SCIV in a penetration flow path with two SC IVs. Opening of drain valve 187391 and operation of blank flanges X-29-5-91 and X-29-5-95 wlll be controlled to prevent cross connecting ventilation zones. These three SCIVs prevent air leakage. The isolation of the penetration per the Technical Specification requirement is to assure that one of the above SCIVs is closed so that there is no air leakage. When the RBCW temporary chiller piping Is connected and full of water, the piping inside secondary containment forms the secondary containment boundary and the above listed SCIVs in Table B3.6.4.2-2 are no longer required for this system. Note 3: These penetrations connect Secondary Containment Zone I to a No-Zone. When Secondary Containment Zone I is isolated from the recirculation plenum, the above listed SCIVs In Table 83.6.4.2-2 are no longer required. Note 4: TheSe penetrations connect Secondary Containment Zone II to a No-Zone. When Secondary Containment Zone II is isolated from the recirculation plenum, the above listed SCIVs in Table B3.6.4.2-2 are no longer required. Note 5: These penetrations connect the Railroad Bay to a No-Zone. When the Railroad Bay ls a No-Zone, the above listed SCIVs In Table B3.6.4.2-2 are no longer required. Note 6: These penetrations connect Secondary Containment Zone I to the Railroad Bay. Tlie above listed SGIVs in Table 83.6.4.2-2 are not required if the RaUroad Bay is a No-Zone and Zone I is isolated from the recirculation plenum OR if the Railroad Bay is aligned to Zo.ne I. Note 7: Due to a drain header containing multiple floor drains in different ventilation zones, drain plugs were installed in all of the drain header floor drains. To provide the passive Secondary Containment boundary only drain plugs In one ventilation zone are required to be installeCl. SUSQUEHANNA - UNIT 1- TS I B 3.6-1 OOc
- Revision 0}}