ML18128A202

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Revision to Technical Specifications Bases Manual
ML18128A202
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 04/25/2018
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Document Control Desk, Office of Nuclear Reactor Regulation
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  • MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2018-8427 USER INFORMATION:

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

TO: GERLACH*ROSEY M 04/25/2018 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

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

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

  • C will be issued with the updated material.

TSB2 - TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 04/19/2018 ADD MANUAL TABLE OF CONTENTS DATE: 04/24/2018 CATEGORY: DOCUMENTS TYPE: TSB2 ID: TEXT 3.6.4.2 ADD: REV: 13 REMOVE: REV:12

Page 2 of 2

  • CATEGORY: DOCUMENTS ID: TEXT LOES REMOVE: REV:135 TYPE: TSB2 ADD: REV: 136 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3107 OR X3171 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX .

SSES MANUAL Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date: 04/24/2018 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 136 04/24/2018

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 23 03/01/2017

Title:

TABLE OF CONTENTS TEXT 2 .1.1 5 01/22/2015

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2 .1.2 1 10/04/2007

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Title:

SAFETY LIMITS (SLS) REACTOR COOLANT ~YSTEW (Rcsf>~RESSURE SL

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TEXT 3.0 3 08/20/200\.. ,

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Title:

LIMITING CONDITION FOR OPERATJ:ON- *(,L<W) *,A*PPLICABILITY TEXT 3 .1.1 1/

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Title:

REACTIVITY CONTROL SYST~_MtSillY.I?DO~ MARGIN (SDM)

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Title:

REACTIVITY CONTROr>sYSTEMS' .r --...... . " "

REACTIVITY ANOMALIES

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  • , I TEXT 3 .1.3 ---- .\, *. ---*' / 3 11/16/2016

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Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY

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TEXT 3 .1.4 5 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3 .1.5 2 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3 .1. 6 4 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL

  • Pagel of 8 Report Date: 04/24/18

SSES MANUAL Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3 .1. 7 4 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3 .1.8 4 11/16/2016

Title:

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

Title:

POWER DISTRIBUTION LIMITS AVERAGE 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 6 11/16/2016

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 4 01/23/2018

Title:

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

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 3 11/16/2016

Title:

INSTRUMENTATION FEEDWATER - MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 9 11/16/2016

Title:

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

Title:

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

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION Page I of 8 Report Date: 04/24/18

SSES MANUAL Manual Name: TSB2

  • ._:* Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.4.2 1 11/16/2016

Title:

INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 6 11/16/2016

Title:

INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 1 11/16/2016

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 8 11/16/2016

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 11/16/2016

.f 5

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 4 11/16/2016

Title:

INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 1 11/16/2016 Title~ INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 5 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 4 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) JET PUMPS TEXT 3.4.3 3 01/13/2012

Title:

REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)

TEXT 3.4.4 1 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Pagel of .§. Report Date: 04/24/18

SSES MANUAL Manual Name: TSB2 Manual

Title:

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

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 5 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 3 11/16/2016

Title:

REACTOR 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 3 11/16/2016

Title:

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

SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 5 05/31/2017

Title:

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

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

Title:

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

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page i of 8 Report Date: 04/24/18

SSES MANUAL

  • :::::: :::~: ::::ICAL SPECIFICATIONS BASES LillIT 2 ~AL TEXT 3.6.1.3 16 04/19/2017

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

TEXT 3.6.1.4 2 11/16/2016

Title:

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

Title:

CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURE TEXT 3 . 6 . 1. 6 1 11/16/2016

Title:

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

Title:

CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE

. " 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 INTENTIONALLY LEFT BLANK TEXT 3.6.3.2 3 09/29/2017

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 3 09/29/2017

Title:

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

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~ of .§. Report Date: 04/24/18

SSES MANUAL Manual Name: TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.4.2 13 04/24/2018

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

LDCN 5277 TEXT 3.6.4.3 6 09/15/2017

Title:

CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 7 03/01/2017

Title:

PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM 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 4 11/16/2016

Title:

PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 3.7.7 2 11/16/2016

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.7.8 1 11/16/2016

Title:

MAINE TURBINE PRESSURE REGULATION SYSTEM TEXT 3.8.1 11 02/27/2018

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING TEXT 3.8.2 0 11/18/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN Page .§_ of 8 Report Date: 04/24/18

SSES MANUAL Manual Name: TSB2

  • - *. Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.3 6 12/14/2017

Title:

ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL LUBE OIL AND STARTING AIR TEXT 3.8.4 4 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING TEXT 3.8.5 1 12/14/2006

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - SHUTDOWN TEXT 3.8.6 2 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 6 03/01/2017

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - OPERATING

  • - TEXT 3.8.8 1 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 1 11/16/2016

Title:

REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 2 11/16/2016

Title:

REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 1 11/16/2016

Title:

REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/18/2002

Title:

REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 1 11/16/2016

Title:

REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.6 2 11/16/2016

Title:

REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Pagel of 8 Report Date: 04/24/18

- --1 SSES MANUAL Manual Name: TSB2

  • Manual

Title:

TECHNICAL SPECIFICATIONS BASES UliIT 2 MANUAL TEXT 3.9.7 1 11/16/2016

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH WATER LEVEL TEXT 3.9.8 1 11/16/2016

Title:

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

Title:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 1 11/16/2016

Title:

SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 1 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN 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 03/24/2005

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 3 11/16/2016

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Page Q. of 8 Report Date: 04/24/18

SUSQUEHANNA STEAM ELECTRIC STATION

  • LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section TOC Title Revision Table of Contents ............... ." ................................................................................ 23 B 2.0 SAFETY LIMITS (SLs)

B2.'i.1 Reactor Core SLs ................................................................................................. 5 B2.1.2 Reactor Coolant System (RCS) Pressure SL ....................................................... 1 B 3.0 LCO AND SR APPLICABILITY BASES ............................................................... 3 B 3.1 REACTIVITY CONTROL SYSTEMS 83.1.1 Shutdown Margin (SOM) ...................................................................................... 2 83.*l.2 Reactivity Anomalies ............................................................................................ 1 83.'l.3 Control Rod OPERABILITY .................................................................................. 3 83.'l .4 Control Rod Scram Times .................................................................................... 5 83.'l.5 Control Rod Scram Accumulators ........................................................................ 2 B3.'l.6 Rod Pattern Control. ............................................................................................. 4 83.1.7 Standby Liquid Control (SLC) System .................................................................. 3 83.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ..................................... 4

  • B 3.2 83.2.1 83.2.2 83.2.3 POWER DISTRIBUTION LIMITS Average Planar Linear Heat Generation Rate (APLHGR) ................................... 5 Minimum Critical Power Ratio (MCPR) ................................................................ 4 Linear Heat Generation Rate (LHGR) ................................... :.............................. 3 B 3.3 INSTRUMENTATION 83.3.1.1 Reactor Protection System (RPS) Instrumentation .............................................. 6 B3.3.1.2 Source Range Monitor (SRM) Instrumentation .................................................... 4 B3.3.2.1 Control Rod Block Instrumentation ....................................................................... 4 B3.3.2.2 Feedwater- Main Turbine High Water Level Trip Instrumentation ..................... 3 B3.3.3.1 Post Accident Monitoring. (PAM) Instrumentation ................................................. 9 B3.3.3.2 Remote Shutdown System ................................................................................... 2 83.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation ................... 2 83.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ............................................................. 1 83.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation ................................. 6 83.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ........................ 1 83.3.6.1 Primary Containment Isolation Instrumentation ................................................... 8 83.3.6.2 Secondary Containment Isolation Instrumentation ............................................... 5 83.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)

System Instrumentation ........................................................................................ 3 B3.3.8.1 Loss of Power (LOP) Instrumentation .................................................................. 4 83.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring .............................. 1

  • SUSQUEHANNA - UNIT 2 TS I B LOES-1 Revision 136

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

Section Title Revision 8 3.4 REACTOR COOLANT SYSTEM (RCS) 83.4.1 Recirculation Loops Operating ............................................................................. 5 83.4.2 Jet Pumps ......................................................................................................... 4 83.4.3 Safety/Relief Valves (S/RVs) ................................................................................ 4 83.4.4 RCS Operational LEAKAGE ................................................................................ 1 83.4.5 RCS Pressure Isolation Valve (PIV) Leakage ...................................................... 4 83.4.6 RCS Leakage Detection Instrumentation ............................................................. 5 83.4.7 RCS Specific Activity ............................................................................................ 3 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ....................................................................................... 3 B3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ......................................................... '. ........................... 2 83.4.10 RCS Pressure and Temperature (PIT) Limits ...................................................... 5 83.4.11 Reactor Steam Dome Pressure ........................................................................... 1 8 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM B3.5.1 ECCS -Operating ................................................................................................ 5 83.5.2 ECCS - Shutdown ............................................................................................... 3 83.5.3 RCIC System ..................................... *************************:***************************************** 5 8 3.6 CONTAINMENT SYSTEMS 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) ................................................... 16 83.6.1.4 Containment Pressure .......................................................................................... 2 83.6.1.5 Drywell Air Temperature ....................................................................................... 2 83.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ........................................... 1 83.6.2.1 Suppression Pool Average Temperature ............................................................. 3 83.6.2.2 Suppression Pool \J\/ater Level ............................................................................. 1 83.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .................................. 2 83.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ..................................... 1 83.6.3.1 Not Used ......................................................................................................... 2 83.6.3.2 Drywell Air. Flow System ....................................................................................... 3 B3.6.3.3 Primary Containment Oxygen Concentration ....................................................... 3 B3.6.4.1 Secondary Containment ...................................................................................... 14 B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .............................................. 13 B3.6.4.3 Standby Gas Treatment (SGT) System .............................................................. 6

  • SUSQUEHANNA - UNIT 2 TS I B LOES-2 Revision 136

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

Section Title Revision B 3.7 PLANT SYSTEMS B3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ........................................................................ 7 B3.7.2 Emergency Service Water (ESW) System ........................................................... 3 B3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ............................................................................................... 3 83.7.4 Control Room Floor Cooling System .................................................................... 1 83.7.5 Main Condenser Offgas ....................................................................................... 2 B3.7.6 Main Turbine Bypass System ............................................................................... 4 B3.7.7 Spent Fuel Storage Pool Water Level .................................................................. 2 83.7.8 Main Turbine Pressure Regulation System .......................................................... 1 B 3.8 ELECTRICAL POWER SYSTEM B3.8.1 AC Sources - Operating ..................................................................................... 11 B3.8.2 AC Sources - Shutdown ............................... ,...................................................... 0 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ............................................................ 6 B3.8.4 DC Sources - Operating ...................................................................................... 4 83.8.5 DC Sources - Shutdown ...................................................................................... 1 83.8.6 Battery Cell Parameters ....................................................................................... 2 83.8.7 Distribution Systems - Operating ......................................................................... 6 83.8.8 Distribution Systems - Shutdown ......................................................................... 1 B 3.9 REFUELING OPERATIONS 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 ............................................................................ 0 B3.9.5 Control Rod OPERABILITY - Refueling .............................................................. 1 B3.9.6 Reactor Pressure Vessel (RPV) Water Level. ...................................................... 2 B3.9.7 Residual Heat Removal (RHR) - High Water Level ............................................. 1 B3.9.8 Residual Heat Removal (RHR) - Low Water Level. ............................................. 1 B 3.10 SPECIAL OPERATIONS 83.10.1 lnservice Leak and Hydrostatic Testing Operation ............................................... 1 83.10.2 Reactor Mode Switch Interlock Testing ................................................................ 1 B3.10.3 Single Control Rod Withdrawal - Hot Shutdown .................................................. 1 83.10.4 Single Control Rod Withdrawal - Cold Shutdown ................................................ 1 83.10.5 Single Control Rod Drive (CRD) Removal - Refueling ........................................ 1 B3.10.6 Multiple Control Rod Withdrawal - Refueling ....................................................... 1 83.10.7 Control Rod Testing - Operating .......................................................................... 1 83.10.8 SHUTDOWN MARGIN (SOM) Test - Refueling .................................................. 3

  • SUSQUEHANNA - UNIT 2 TS I B LOES-3 Revision 136

Rev. 13 SCIVs B 3.6.4.2 B 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 during 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 DBA 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 the ANALYSES 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

  • SUSQUEHANNA - UNIT 2 TS I B 3.6-90 (continued)

Revision 3

Rev. 13 SCIVs 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 before ANALYSES 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 configuration 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 B3.6.4.2-2. Penetrations closed with sealants are considered part of the secondary containment boundary and are not considered 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 Bases 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 .

  • SUSQUEHANNA - UNIT 2 TS I B 3.6-91 (continued)

Revision 3

Rev. 13 SCIVs

  • BASES (continued)

APPLICABILITY In MODES 1, 2, and 3, a OBA could lead to a fission product release to the B 3.6.4.2 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 limitations 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 operator, 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 Required Actions may allow for continued operation, and subsequent inoperable SC IVs 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 inoperable, 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

  • SUSQUEHANNA - UNIT 2 TS I B 3.6-92

( continued)

Revision 2

Rev. 13 SCIVs 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 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time.

The specified time period is reasonable considering the time required to isolate the penetration, and the probability of P OBA, which requires the SC IVs 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The method of isolation must

  • SUSQUEHANNA - UNIT 2 TS I B 3.6-93 (continued)

Revision 1

Rev. 13 SCIVs 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is reasonable considering the time required to isolate the penetration and the probability of a DBA, 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 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 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time.

The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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

  • SUSQUEHANNA - UNIT 2 TS I B 3.6-94 (continued)

Revision 1

Rev. 13 SCIVs 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 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.

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 activities shall not preclude completion of movement of 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 .

  • SUSQUEHANNA - UNIT 2 TS I B 3.6-95 (continued)

Revision 1

Rev. 13 SCIVs 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, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.

SURVEILLANCE SR 3.6.4.2.1 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 being 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 SC IVs, 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 SCIVs are open .

    • SUSQUEHANNA - UNIT 2 TS I B 3.6-96 (continued)

Revision 3

Rev. 13 SCIVs

  • BASES SURVEILLANCE SR 3.6.4.2.2 B 3.6.4.2 REQUIREMENTS (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 will isolate in a time period less 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 2 TS I B 3.6-97 Revision 2

Rev. 13 SCIVs

Maximum Reactor Valve Number Valve Description Type of Valve Isolation Building Time Zone (Seconds)

I HD-17586A&B Supply System Dampers Automatic Isolation Damper 10.0 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 Damper 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-17564 A&B Supply System Dampers Automatic Isolation Damper 14.0 Ill HD-17514A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 Ill HD-17502 A&B Unfiltered Exhaust System Dampers Automatic Isolation Damper 6.0 Ill HD-27564 A&B Supply System Dampers Automatic Isolation Damper 14.0 Ill 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 NIA HD-17534A Zone 3 Airlock 1-606 Automatic Isolation Damper NIA NIA HD-175348 Zone 3 Airlock 1-611 Automatic Isolation Damper NIA NIA HD-17534D Zone 3 Airlock 1-803 Automatic Isolation Damper NIA NIA HD-17534E Zone 3 Airlock 1-805 Automatic Isolation Damper NIA NIA HD-17534F Zone 3 Airlock 1-617 Automatic Isolation Damper NIA NIA HD-17534H Zone 3 Airlock 1-618 Automatic Isolation Damper NIA N/A HD-27534A Zone 3 Airlock 11-606 Automatic Isolation Damper NIA NIA HD-27534D Zone 3 Airlock 11-803 Automatic Isolation Damper NIA N/A HD-27534E Zone 3 Airlock 11-805 Automatic Isolation Damper NIA NIA HD-27534G Zone 3 Airlock C-806 Automatic Isolation Damper N/A NIA HD-27534H Zone 3 Airlock 11-618 Automatic Isolation Damper NIA NIA HD-275341 Zone 3 Airlock 11-609 Automatic Isolation Damper NIA SUSQUEHANNA - UNIT 2 TS I B 3.6-98 Revision 2

Rev. 13 SCIVs B 3.6.4.2 Table B 3.6.4.2Q2 Secondary Containment Ventilation System Passive Isolation Valves or Devices

{Page 1 of 4)

Device Number Device Description Area/Elev. Required Position / Notes X-29-2-44 SDHR System to Fuel Pool Coolinq Yard/670 Blind Flanqed / Note 1 X-29-2-45 SOHR System to Fuel Pool Coolinq Yard/670 Blind Flanqed / Note 1 110176 SDHR Supply Drain Viv 29/670 Closed Manual lso Valve / Note 1 110186 SDHR Discharqe Drain Viv 29/670 Closed Manual lso Valve/ Note 1 110180 SDHR Supply Vent Viv 29/749 Closed Manual lso Valve / Note 1 110181 SDHR Discharqe Fill Viv 27/749 Closed Manual lso Valve / Note 1 110182 SOHR Discharqe Vent Viv 27/749 Closed Manual Jso Valve / Note 1 110187 SOHR Supply Fill Viv 29/749 Closed Manual Jso Valve/ Note 1 210186 SDHR Suoolv Drain Viv 33/749 Closed Manual lso Valve/ Note 1 210187 SOHR Supply Vent Viv 33/749 Closed Manual lso Valve/ Note 1 210191 SDHR Discharqe Vent Viv 30/749 Closed Manual Jso Valve/ Note 1 210192 SOHR Discharqe Drain Viv 30/749 Closed Manual lso Valve/ Note 1 210193 SOHR Discharqe Vent Viv 33/749 Closed Manual lso Valve/ Note 1 X-29-2-46 Temporary Chiller to RBCW Yard/670 Blind Flanqed / Note 2 X-29-2-47 Temporary Chiller to RBCW Yard/670 Blind Flanged / Note 2 X-29-5-95 Temporary Chiller to Unit 1 RBCW 29/749 Blind Flanged / Note 2 X-29-5-96 Temporary Chiller to Unit 1 RBCW 29/749 Blind Flanged / Note 2 X-29-5-91 Temporary Chiller to Unit 2 RBCW 33/749 Blind Flanged / Note 2 X-29-5-92 Temporary Chiller to Unit 2 RBCW 33/749 Blind Flanged / Note 2 187388 RBCWTemp Chiller Discharge lso Viv 29/670 Closed Manual Jso Valve/ Note 2 187389 RBCWTemp Chiller Supply lso Viv 29/670 Closed Manual lso Valve/ Note 2 187390 RBCW Temp Chiller Suoplv Drain Viv 29/670 Closed Manual Jso Valve / Note 2 187391 RBCWTemo Chiller Discharqe Drain Viv 29/670 Closed Manual Jso Valve/ Note 2 X-28-2-3000 Utility Penetration to Unit 1 East Stairwell Yard/670 Blind Flanqed / Note 3 X-29-2-48 Utility Penetration to Unit 1 RR Bay Yard/670 Capped / Note 5 X-33-2-3000 Utility Penetration to Unit 2 East Stairwell Yard/670 Blind Flanaed / Note 4 X-28-2-3000 Utility Penetration to Unit 1 East Stairwell 28/670 Blind Flanqed / Note 3 X-29-2-48 Utility Penetration to Unit 1 RR Bav 29/670 Capped/ Note 5 X-33-2-3000 Utilitv Penetration to Unit 2 East Stairwell 33/670 Blind Flanged / Note 4 X-29-3-54 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged / Note 6 X-29-3-55 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanaed / Note 6 Utility Penetration from Unit 1 RR Bay to Unit 2 X-29-5-97 33/749 Capped Elev. 749 X-27-6-92 Instrument Tubing Stubs 27/779' Capped X-29-7-4 1" Soare Conduit Threaded Plug 29/818' Installed X-30-6-72 Instrument Tubing Stubs 30/779' Capped 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 X-25-6-1008 Airlock 1-606 Rupture Disc 25/779' Installed Intact X-29-4-D1-B Penetration at Door 4330 29/719' Blind Flange Installed X-29-4-D1-A Penetration at Door 4330 29/719' Blind Flange Installed X-29-4-D1-B Penetration at Door 404 33/719' Blind Flange Installed X-29-4-D1-A Penetration at Door 404 33/719' Blind Flange Installed SUSQUEHANNA - UNIT 2 TS I B 3.6-99 Revision 8

Rev. 13 SCIVs 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 Number Device Description Area/Elev. Required Position/ Notes HD17534C Airlock 1-707 Blind Flanae 28ll99' Blind Flange Installed HD27534C Airlock 11-707 Blind Flanae 33ll99' Blind Flange Installed XD-17513 Isolation damper for Railroad Bay Zone Ill HVAC 29/799' Position is dependent on Railroad Supply Bav alignment XD-17514 Isolation damper for Railroad Bay Zone Ill HVAC 29/719' Position is dependent on Railroad Exhaust Bay alignment XD-12301 PASS Air Flow Damper 11n29' Closed Damper XD-22301 PASS Air Flow Damper 22n29' Closed Damper 161827 HPCI Blowout Steam Vent Drain Valve 25/645' Closed Manual Isa Valve / Note 3 161828 RCIC Blowout Steam Vent Drain Valve 28/645' Closed Manual Isa Valve / Note 3 161829 'A' RHR Blowout Steam Vent Drain Valve 29/645' Closed Manual Isa Valve / Note 3 161830 'B' RHR Blowout Steam Vent Drain Valve 28/645' Closed Manual Isa Valve / Note 3 261820 RCIC Blowout Steam Vent Drain Valve 33/645' Closed Manual Isa Valve / Note 4 261821 'A' RHR Blowout Steam Vent Drain Valve 34/645' Closed Manual Isa Valve / Note 4 261822 'B' RHR Blowout Steam Vent Drain Valve 33/645' Closed Manual Isa Valve/ Note 4 2LRWl810L Zone Ill Floor Drain 34-818 Plugged/ Note 7 2LRWl810M Zone Ill Floor Drain 34-818 Plugged / Note 7 2LRWl810N Zone Ill Floor Drain 34-818 Pluaoed / Note 7 2LRWl810R Zone Ill Floor Drain 34-818 Pluaoed / Note 7 2LRWl810S Zone Ill Floor Drain 34-818 Pluaoed / Note 7 2LRWl703A Zone Floor Drain 34-799 Plum1ed / Note 7 2LRWl615A Zone Floor Drain 34-779 Plugged / Note 7 2LRWJ100A Zone Floor Drain 34-670 Plugged/ Note 7 2LRWl100B Zone Floor Drain 34-670 Plurrned / Note 7 2LRWl100C Zone Floor Drain 34-670 Plugged / Note 7 2LRWl100D Zone Floor Drain 34-670 Plugged / Note 7 2LRWl100E Zone Floor Drain 34-670 Plugged / Note 7 2LRWl100F Zone Floor Drain 34-670 Pluaaed / Note 7 2LRWl100G Zone Floor Drain 34-670 Pluaaed / Note 7 SUSQUEHANNA - UNIT 2 TS I B 3.6-99a Revision 6

Rev. 13 SCIVs

  • B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System Passive Isolation Valves or Devices (Page 3 of 4)

Device Number Device Description Area/Elev. Required Position/ Notes 1LRVVl810U Zone Ill Floor Drain 29-818 Pluooed / Note 7 1LRVVl1810V Zone Ill Floor Drain 29-818 Pluooed / Note 7 1LRVVl1810W Zone Ill Floor Drain 29-818 Pluqoed / Note 7 1LRWl810X Zone Ill Floor Drain 29-818 Pluqqed / Note 7 1LRWl810Y Zone Ill Floor Drain 29-818 Pluqqed / Note 7 1LRW1810Z Zone Ill Floor Drain 29-818 Plugged / Note 7 1LRWl810FF Zone Ill Floor Drain 29-818 Pluaaed / Note 7 1LRWl810GG Zone Ill Floor Drain 29-818 Pluqaed / Note 7 1LRWl810HH Zone Ill Floor Drain 29-818 Pluooed / Note 7 1LRWl810JJ Zone Ill Floor Drain 29-818 PIU!=JQed / Note 7 1LRWl810KK Zone Ill Floor Drain 29-818 Pluaaed / Note 7 1LRWl615A Zone Zone Ill, or No Zone Floor Drain 29-779 Pluooed / Note 7 1LRWl100A Zone Zone Ill, or No Zone Floor Drain 29-670 Pluooed / Note 7 1LRWl100B Zone Zone Ill, or No Zone Floor Drain 29-670 Pluqqed / Note 7 1LRWl100C Zone Zone Ill, or No Zone Floor Drain 29-670 Pluqqed / Note 7 1LRWl100D Zone Zone Ill, or No Zone Floor Drain 29-670 Pluqqed / Note 7

'ILRWl100E Zone Zone Ill, or No Zone Floor Drain 29-670 Pluqged / Note 7

  • ILRWl100F Zone Zone Ill, or No Zone Floor Drain 29-670 Plugged / Note 7 1LRWl100G Zone Zone Ill, or No Zone Floor Drain 29-670 Plugged / Note 7 HCVS Rupture Disc Burst Connection Isolation 257328 OR 257336 21/686' Closed Manual lso Valve/ Note 4 Valves HCVS Rupture Disc Burst Connection Isolation 157328 OR 157336 21/686' Closed Manual lso Valve/ Note 3 Valves
  • SUSQUEHANNA - UNIT 2 TS I B 3.6-99b Revision 6

Rev. 13 SCIVs

  • B 3.6.4.2 Table B 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 SOHR 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 SCJV in a penetration flow path with two SCJVs. 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 SDJ-JR system will be controlled to prevent cross connecting ventilation zones. When the manual valves for the SOHR system are open in this condition, the appropriate LCO should be entered for one inoperable SCIV in a penetration flow path with two SC IVs. When the SOHR system piping is connected and full of water, the piping forms the secondary containment boundary and the above listed SC IVs in Table B3.6.4.2-2 are no longer required 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 SCJV function depending on the RBCW configuration. There are three devices/equipment that can perform the SCJV function for the RBCW temporary chiller supply penetration. The first SCJV for the RBCW temporary chiller supply penetration is the installed blind flange on penetration X-29-2-47. The second SCJV for the RBCW temporary chiller supply penetration is isolation valve 187389. The third SCIV for the temporary RBCW chiller supply penetration is closed drain valve 187390 and an installed blind flange on penetrations X-29-5-92 and/or X-29-5-96. 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 SC IVs requires entry into the appropriate LCO for one inoperable SCIV in a penetration flow path with two SCJVs. Opening of drain valve 187390 and operation of blanl< flanges X-29-5-96 and X-29-5-92 will be controlled to prevent cross connecting ventilation zones. These three SC IVs prevent air inleakage into secondary containment. The isolation of the penetration per the Technical Specification requirement is to assure that one of the above SC IVs is closed so that there is no air in leakage into secondary containment.

There are three devices/equipment that can perform the SCIV 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 SCJV for the RBCW temporary chiller return penetration is isolation valve 187.388. The third SCJV for the temporary RBCW chiller return penetration is closed drain valve 187391 and an installed blind flange on penetrations X-29-5-91 and/or X-29-5-95. Since there are effectively three SCJVs, any two can be used to define the SCIV for the penetration. Removal of one of the two required SCJVs requires entry into the appropriate LCO for one inoperable SCIV in a penetration flow path with two SCJVs. Opening of drain valve 187391 and operation of blank flanges X-29-5-91 and X-29-5-95 will be controlled to prevent cross connecting ventilation zones.

These three SCIVs prevent air in leakage into secondary containment. The isolation of the penetration per the Technical Specification requirement is to assure that one of the above SC IVs is closed so that there is no air in leakage into secondary containment.

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 SCJVs in Table 83.6.4.2-2 are no longer required for this system.

Mote 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 SCJVs 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 SCJVs in Table 83.6.4.2-2 are no longer required.

Note 5: These penetrations connect the Railroad Bay to a No-Zone. When the Railroad Bay is a No-Zone, the above listed SC IVs in Table 83.6.4.2-2 are no longer required.

Note 6: These penetrations connect Secondary Containment Zone I to the Railroad Bay. The above listed SCJVs in Table B3.6.4.2-2 are not required if the Railroad Bay is a No-Zone and Zone I is isolated from the recirculation plenum OR if the Railroad Bay is aligned to Zone I.

Note 7: Due to 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 installed.

SUSQUEHANNA - UNIT 2 TS I B 3.6-99c Revision 0