ML110380433

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Technical Specification Bases Unit 2 Manual, Revision 103
ML110380433
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 01/26/2011
From:
Susquehanna
To: Gerlach R M
Document Control Desk, Office of Nuclear Reactor Regulation
References
2011-4849
Download: ML110380433 (28)
v • d • e


Text

Jan. 26, 2011 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2011-4849 USER INFORMATION:

GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:

TO: GERLACH*ROSE M 01/26/2011 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.ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 01/14/2011 ADD MANUAL TABLE OF CONTENTS DATE: 01/25/2011 CATEGORY:

DOCUMENTS TYPE: TSB2 Adoo/

Jan. 26, 2011 Page 2 of 2 ID: TEXT 3.4.6 REMOVE: REV:2 ADD: REV: 3 CATEGORY: ID: TEXT REMOVE: DOCUMENTS TYPE: TSB2 3.7.6 REV:2 ADD: REV: 3 CATEGORY:

DOCUMENTS TYPE: TSB2 ID: TEXT LOES ADD: REV: 103 REMOVE: REV:102 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 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: 01/25/2011 Procedure Name Rev TEXT LOES 103 Title: LIST OF EFFECTIVE SECTIONS Issue Date 01/25/2011 Change ID Change Number TEXT TOC Title: TABLE OF CONTENTS 18 09/01/2010 TEXT 2. 1.1 4 Title: SAFETY LIMITS (SLS) REACTOR TEXT 2.1.2 1 Title: SAFETY LIMITS (SLS) REACTOR 05/06/2009 CORE SLS 10/04/2007 COOLANT SYSTEM (RCS) PRESSURE SL TEXT 3.0 3 08/20/2009 Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3. 1.1 Title: REACTIVITY TEXT 3.1.2 Title: REACTIVITY TEXT 3.1.3 Title: REACTIVITY TEXT 3.1.4 Title: REACTIVITY TEXT 3.1.5 Title: REACTIVITY TEXT 3.1.6 Title: REACTIVITY 1 CONTROL SYSTEMS 0 CONTROL SYSTEMS 2 CONTROL SYSTEMS 4 CONTROL SYSTEMS 1 CONTROL SYSTEMS 2 CONTROL SYSTEMS 03/24/2005 SHUTDOWN MARGIN (SDM)11/18/2002 REACTIVITY ANOMALIES 01/19/2009 CONTROL ROD OPERABILITY 01/30k2009 CONTROL ROD SCRAM TIMES 07/06/2005 CONTROL ROD SCRAM ACCUMULATORS 03/24/2005 ROD PATTERN CONTROL Pagel of 8 Report Date: 01/25/11 Page 1 of .8 Report Date: 01/25/11 SSES MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7 Title: REACTIVITY CONTROL 3 10/04/2007 SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 3 05/06/2009 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 4 05/06/2009 Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 Title: POWER DISTRIBUTION 3 05/06/2009 LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 05/06/2009 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR TEXT 3.3.1.1 4 05/06/2009 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 Title: INSTRUMENTATION 2 01/19/2009 SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 2 04/09/2007 Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 Title: INSTRUMENTATION TEXT 3.3.3.1 Title: INSTRUMENTATION 1 05/06/2009 FEEDWATER

-MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION 7 10/27/2008 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 Title: INSTRUMENTATION 1 05/06/2009 0 END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATION Page2 of 8 Report Date: 01/25/11 Page 2 of .8 Report Date: 01/25/11 SSES MANUAL* Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.4.2 0 11/18/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 4 08/20/2009 Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 Title: INSTRUMENTATION TEXT 3.3.6.1 Title: INSTRUMENTATION TEXT 3.3.6.2 Title: INSTRUMENTATION TEXT 3.3.7.1 Title: INSTRUMENTATION INSTRUMENTATION TEXT 3.3.8.1 Title: INSTRUMENTATION TEXT 3.3.8.2 Title: INSTRUMENTATION 0 11/18/2002 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION 4 05/06/2009 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION 4 09/01/2010 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 3 12/17/2007 LOSS OF POWER (LOP) INSTRUMENTATION 0 11/18/2002 REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING 4 07/20/2010 SYSTEM (RCS) RECIRCULATION LOOPS OPERATING 2 07/20/2010 SYSTEM (RCS) JET PUMPS 2 05/06/2009 SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)0 11/18/2002 SYSTEM (RCS) RCS OPERATIONAL LEAKAGE TEXT 3.4.1 Title: REACTOR TEXT 3.4.2 Title: REACTOR TEXT 3.4.3 Title: REACTOR TEXT 3.4.4 Title: REACTOR COOLANT COOLANT COOLANT COOLANT Page 3 of 8 Report Date: 01/25/11 Page3 of -8 Report Date: 01/25/11 SSES MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.5 Title: REACTOR COOLANT TEXT 3.4.6 Title: REACTOR COOLANT TEXT 3.4.7 Title: REACTOR COOLANT TEXT 3.4.8 Title: REACTOR COOLANT-HOT SHUTDOWN TEXT 3.4.9 Title: REACTOR COOLANT-COLD SHUTDOWN TEXT 3.4.10 Title: REACTOR COOLANT TEXT 3.4.11 Title: REACTOR COOLANT TEXT 3.5.1 3 03/10/2010 SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 3 01/25/2011 SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION 2 10/04/2007 SYSTEM (RCS) RCS SPECIFIC ACTIVITY 1 04/18/2005 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM 0 11/18/2002 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING 3 05/06/2009 SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS 0 11/18/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE 3 01/16/2006 SYSW Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM ECCS -OPERATING TEXT 3.5.2 0 11/18/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM ECCS -SHUTDOWN TEXT 3.5.3 2 07/09/2010 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM RCIC SYSTEM TEXT 3.6.1.1 3 05/06/2009 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 1 05/06/2009 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC).Page4 of 8 Report Date: 01/25/11 Page 4 of .Report Date: 01/25/11 SSES MANUALManual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.1.3 Title: CONTAINMENT TEXT 3.6.1.4 Title: CONTAINMENT TEXT 3.6.1.5 Title: CONTAINMENT TEXT 3.6.1.6 Title: CONTAINMENT TEXT 3.6.2.1 Title: CONTAINMENT TEXT 3.6.2.2 Title: CONTAINMENT TEXT 3.6.2.3 Title: CONTAINMENT TEXT 3.6.2.4 Title: CONTAINMENT TEXT 3.6.3.1 Title: CONTAINMENT TEXT 3.6.3.2 Title: CONTAINMENT TEXT 3.6.3.3 Title: CONTAINMENT TEXT 3.6.4.1 Title: CONTAINMENT 11 04/14/2010 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009 SYSTEMS CONTAINMENT PRESSURE 1 10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0 11/18/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 2 12/17/2007 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0 11/18/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1 01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING 0 11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY 2 06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1 04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM 0 11/18/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 7 10/04/2007 SYSTEMS SECONDARY CONTAINMENT Page 5: of .a Report Date: 01/25/11 Page a of8 Report Date: 01/25/11 SSES MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.4.2 3 03/10/2010 Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006 Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 Title: PLANT SYSTEMS ULTIMATE HEAT TEXT 3.7.2 Title: PLANT SYSTEMS 4 04/05/2010 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE SINK (UHS)2 05/02/2008 EMERGENCY SERVICE WATER (ESW) SYSTEM TEXT 3.7.3 Title: PLANT TEXT 3.7.4 Title: PLANT TEXT 3.7.5 Title: PLANT TEXT 3.7.6 Title: PLANT TEXT 3.7.7 Title: PLANT TEXT 3. 8.1 1 01/08/2010 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 0 11/18/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 1 10/04/2007 SYSTEMS MAIN CONDENSER OFFGAS 3 01/25/2011 SYSTEMS MAIN TURBINE BYPASS SYSTEM 1 10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 8 05/06/2009 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.7.8 0 05/06/2009 Title: MAINE TURBINE PRESSURE REGULATION SYSTEM TEXT 3.8.2 0 11/18/2002 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWN Page6 of 8 Report Date: 01/25/11 Page 6 of .8 Report Date: 01/25/11 SSES MANULTM iO Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.3 Title: ELECTRICAL TEXT 3.8.4 Title: ELECTRICAL TEXT 3.8.5 Title: ELECTRICAL TEXT 3.8.6 Title: ELECTRICAL TEXT 3.8.7 Title: ELECTRICAL TEXT 3.8.8 Title: ELECTRICAL TEXT 3.9.1 Title: REFUELING TEXT 3.9.2 Title: REFUELING TEXT 3.9.3 Title: REFUELING TEXT 3.9.4 Title: REFUELING TEXT 3.9.5 Title: REFUELING TEXT 3.9.6 Title: REFUELING 2 04/14/2010 POWER SYSTEMS DIESEL FUEL OIL LUBE OIL AND STARTING AIR POWER SYST POWER SYST POWER SYST POWER SYST POWER SYST OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 3 01/19/2009

?EMS DC SOURCES -OPERATING 1 12/14/2006 EMS DC SOURCES -SHUTDOWN 1 12/14/2006 EMS BATTERY CELL PARAMETERS 3 03/31/2006 EMS DISTRIBUTION SYSTEMS -OPERATING 0 11/18/2002 EMS DISTRIBUTION SYSTEMS -SHUTDOWN 0 11/18/2002 REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/18/2002 CONTROL ROD POSITION 0 11/18/2002 CONTROL ROD POSITION INDICATION 0 11/18/2002 CONTROL ROD OPERABILITY

-REFUELING 1 10/04/2007 REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page7 of 8 Report Date: 01/25/11 Page 7 of .8 Report Date: 01/25/11 SSES MANUTAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.9.7 0 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVEL TEXT 3.9.8 0 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -LOW WATER LEVEL TEXT 3.10.1 Title: SPECIAL TEXT 3.10.2 Title: SPECIAL TEXT 3.10.3 Title: SPECIAL TEXT 3.10.4 Title: SPECIAL TEXT 3.10.5 Title: SPECIAL TEXT 3'.10.6 Title: SPECIAL TEXT 3.10.7 Title: SPECIAL TEXT 3.10.8 Title: SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1 01/23/2008 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0 11/18/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0 11/18/2002 SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN 0 11/18/2002 SINGLE CONTROL ROD WITHDRAWAL

-COLD SHUTDOWN 0 11/18/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING 0 11/18/2002 MULTIPLE CONTROL ROD WITHDRAWAL

-REFUELING 1 03/24/2005 CONTROL ROD TESTING -OPERATING 2 04/09/2007 SHUTDOWN MARGIN (SDM) TEST -REFUELING Page8 of 8 Report Date: 01/25/11 Page 8 of .8 Report Date: 01/25/11 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision TOC Table of Contents 18 B 2.0 SAFETY LIMITS BASES Page TS / B 2.0-1 1 Pages TS / B 2.0-2 and TS / B 2.0-3 4 Page TS / B 2.0-4 6 Pages TS / B 2.0-5 through TS / B 2.0-8 1 B 3.0 LCO AND SR APPLICABILITY BASES Page TS / B 3.0-1 1 Pages TS / B 3.0-2 through TS / B 3.0-4 0 Pages TS / B 3.0-5 through TS / B 3.0-7 1 Page TS / B 3.0-8 3 Pages TS / B 3.0-9 through Page TS / B 3.0-11 2 Page TS / B 3.0-11a 0 Page TS / B 3.0-12 1 Pages TS / B 3.0-13 through TS / B 3.0-15 2 Pages TS / B 3.0-16 and TS / B 3.0-17 0 B 3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 0 Page TS / B 3.1-5 1 Pages TS / B 3.1-6 and TS / B 3.1-7 2 Pages B 3.1-8 through B 3.1-13 0 Page TS / B 3.1-14 1 Page TS / B 3.1-15 0 Page TS / B 3.1-16 1 Pages TS / B 3.1-17 through TS / B 3.1-19 0 Pages TS / B 3.1-20 and TS / B 3.1-21 1 Page TS / B 3.1-22 0 Page TS / B 3.1-23 1 Page TS/B 3.1-24 0 Pages TS / B 3.1-25 through TS / B 3.1-27 1 Page TS / B 3.1-28 2 Page TS / 3.1-29 1 Pages B 3.1-30 through B 3.1-33 0 Pages TS / B 3.1.34 through TS / B 3.1-36 1 Pages TS / B 3.1-37 and TS / B 3.1-38 2 Pages TS / B 3.1-39 and TS / B 3.1-40 2 Page TS / B 3.1-40a 0 Page TS / B 3.1-41 1 Page TS / B 3.1-42 2 SUSQUEHANNA-UNIT2 TS / B LOES-1 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LO ES- 1 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.1-43 1 Page TS / B 3.1-44 0 Page TS / B 3.1-45 3 Page TS / B 3.1-46 0 Page TS / B 3.1-47 1 Pages TS / B 3.1-48 and TS / B 3.1-49 1 Page B 3.1-50 0 Page TS / B 3.1-51 3 B 3.2 POWER DISTRIBUTION LIMITS BASES Pages TS / B 3.2-1 and TS / B 3.2-2 2 Page TS / B 3.2-3 4 Page TS / B 3.2-4 1 Page TS / B 3.2-5 3 Page TS / B 3.2-6 4 Page TS / B 3.2-7 3 Pages TS / B 3.2-8 and TS / B 3.2-9 4 Pages TS / B 3.2-10 through TS / B 3.2-12 2 Page TS / B 3.2-13 1 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1 Page TS / B 3.3-5 2 Page TS / B 3.3-6 1 Page TS / B 3.3-7 3 Page TS / B 3.3-8 4 Pages TS / B 3.3-9 through TS / B 3.3-13 3 Page TS / B 3.3-14 4 Pages TS / B 3.3-15 and TS / B 3.3-16 2 Pages TS / B 3.3-17 through TS / B 3.3-21 3 Pages TS / B 3.3-22 through TS / B 3.3-27 2 Page TS / B 3.3-28 3 Page TS / B 3.3-29 4 Pages TS / B 3.3-30 and TS / B 3.3-31 3 Pages TS / B 3.3-32 and TS / B 3.3-33 4 Page TS / B 3.3-34 2 Page TS / B 3.3-34a I Pages TS / B 3.3-34b through TS / B 3.3-34d 0 Page TS / B 3.3-34e 1 Pages TS / B 3.3-34f through TS / B 3.3-34i 0 Pages TS / B 3.3-35 and TS / B 3.3-36 2 Pages TS / B 3.3-37 and TS / B 3.3-38 1 SUSQUEHANNA

-UNIT 2 TSIBLOES-2 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LOES-2 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-39 2 Pages TS / B 3.3-40 through TS / B 3.3-43 2 Pages TS / B 3.3-44 through TS / B 3.3-54 3 Pages TS / B 3.3-54a through TS / B 3.3-54e 0 Page TS / B 3.3-55 1 Page B 3.3-56 0 Page TS / B 3.3-57 1 Page B 3.3-58 0 Page TS / B 3.3-59 1 Pages B 3.3-60 through B 3.3-63 0 Pages TS / B 3.3-64 and TS / B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 Page TS / B 3.3-68 4 Page TS / B 3.3.69 5 Page TS / B 3.3-70 4 Page TS / B 3.3-71 3 Pages TS / B 3.3-72 and TS / B 3.3-73 2 Page TS / B 3.3-74 3 Page TS / B 3.3-75 2 Pages TS / B 3.3-75a and TS / B 3.3-75 b 6 Page TS / B 3.3-75c 5 Pages B 3.3-76 and TS / B 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through B 3.3-81 0 Page TS / B 3.3-82 1 Page B 3.3-83 0 Pages TS / B 3.3-84 and TS / B 3.3-85 1 Page 3.3-86 0 Page TS / B 3.3-87 1 Page B 3.3-88 0 Page TS / B 3.3-89 1 Pages B 3.3-90 and B 3.3-91 0 Pages TS / B 3.3-92 through TS / B 3.3-103 1 Page TS / B 3.3-104 3 Pages TS / B 3.3-105 and TS / B 3.3-106 1 Page TS / B 3.3-107 2 Page TS / B 3.3-108 1 Page TS / B 3.3-109 2 Pages TS / B 3.3-110 through TS / B 3.3-112 1 Page TS / B 3.3-113 2 Page TS / B 3.3-114 1 Page TS / B 3.3-115 2 Page TS / B 3.3-116 3 Pages TS / B 3.3-117 and TS/B 3.3-118 2 SUSQUEHANNA

-UNIT 2 TSIBLOES-3 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LOES-3 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.3-119 through TS / B 3.3-120 1 Pages TS / B 3.3-121 and TS / B 3.3-122 2 Page TS / B 3.3-123 1 Page TS / B 3.3-124 2 Page TS / B 3.3-124a 0 Page TS / B 3.3-125 1 Page TS / B 3.3-126 2 Page TS / B 3.3-127 3 Page TS / B 3.3-128 2 Pages TS / B 3.3-129 through TS / B 3.3-131 1 Page TS / B 3.3-132 2 Pages TS / B 3.3-133 and TS / B 3.3-134 1 Pages B 3.3-135 through B 3.3-137 0 Page TS / B 3.3-138 1 Pages B 3.3-139 through B 3.3-149 0 Pages TS/ B 3.3-150 and TS / B 3.3-151 1 Pages TS / B 3.3-152 through TS / B 3.3-154 2 Page TS / B 3.3-155 1 Pages TS / B 3.3-156 through TS / B 3.3-158 2 Pages TS / B 3.3-159 through TS / B 3.3-161 1 Page TS / B 3.3-162 1 Page TS / B 3.3-163 2 Page TS / B 3.3-164 1 Pages TS / B 3.3-165 and TS / B 3.3-166 2 Pages TS / B 3.3-167 and TS / B 3.3-168 1 Pages TS / B 3.3-169 and TS / B 3.3-170 2 Pages TS / B 3.3-171 through TS / B 3.3-177 1 Page TS / B 3.3-178 2 Page TS / B 3.3-179 3 Page TS / B 3.3-179a 2 Page TS / B 3.3-180 1 Page TS / B 3.3-181 3 Page TS / B 3.3-182 1 Page TS / B 3.3-183 2 Page TS / B 3.3-184 1 Page TS / B 3.3-185 4 Page TS / B 3.3-186 1 Pages TS / B 3.3-187 and TS / B 3.3-188 2 Pages TS / B 3.3-189 through TS / B 3.3-191 1 Page TS / B 3.3-192 0 Page TS / B 3.3-193 1 Pages TS / B 3.3-194 and TS / B 3.3-195 0 Page TS / B 3.3-196 2 SUSQUEHANNA

-UNIT 2 TS/BLOES-4 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LOES-4 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.3-197 through TS / B 3.3-205 0 Page TS / B 3.3-206 1 Pages B 3.3-207 through B 3.3-209 0 Page TS / B 3.3-210 1 Page TS / B 3.3-211 2 Pages TS / B 3.3-212 and TS / B 3.3-213 1 Pages B 3.3-214 through B 3.3-220 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 2 Pages TS / B 3.4-3 through TS / B 3.4-5 4 Pages TS / B 3.4-6 through TS / B 3.4-9 3 Page TS / B 3.4-10 1 Pages TS / B 3.4-11 and TS / B 3.4-12 0 Page TS / B 3.4-13 1 Page TS / B 3.4-14 0 Page TS / B 3.4-15 2 Pages TS / B 3.4-16 and TS / B 3.4-17 3 Page TS / B 3.4-18 2 Pages B 3.4-19 through B 3.4-23 0 Pages TS / B 3.4-24 through TS / B 3.4-27 0 Page TS / B 3.4-28 1 Page TS / B 3.4-29 3 Page TS / B 3.4-30 1 Page TS / B 3.4-31 0 Pages TS / B 3.4-32 and TS / B 3.4-33 1 Page TS / B 3.4-34 0 Pages TS / B 3.4-35 and TS / B 3.4-36 1 Page TS / B 3.4-37 2 Page B 3.4-38 1 Pages B 3.4-39 and B 3.4-40 0 Page TS / B 3.4-41 1 Pages B 3.4-42 through B 3.4-48 0 Page TS / B 3.4-49 3 Pages TS / B 3.4-50 through TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 through TS / B 3.4-57 2 Pages TS / B 3.4-58 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages TS / B 3.5-1 and TS / B 3.5-2 1 Pages TS / B 3.5-3 through TS / B 3.5-6 2 Pages TS / B 3.5-7 through TS / B 3.5-10 1 Pages TS / B 3.5-11 and TS / B 3.5-12 2 Pages TS / B 3.6-13 and TS / B 3.5-14 1 SUSQUEHANNA

-UNIT 2 TS / B LOES-5 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.5-15 and TS / B.3.5-16 2 Page TS / B 3.5-17 3 Page TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Pages TS / B 3.5-25 through TS / B 3.5-27 1 Page TS / B 3.5-28 0 Page TS / B 3.5-29 1 Pages TS / B 3.5-30 and TS / B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2 Page TS / B 3.6-1a 3 Page TS / B 3.6-2 4 Page TS / B 3.6-3 3 Page TS / B 3.6-4 4 Page TS / B 3.6-5 3 Page TS / B 3.6-6 4 Pages TS / B 3.6-6a and TS / B 3.6-6b 2 Page TS / B 3.6-6c 0 Page B 3.6-7 0 Page TS / 3.6-8 1 Pages B 3.6-9 through B 3.6-14 0 Page TS / B 3.6-15 3 Page TS / B 3.6-15a 0 Page TS / B 3.6-15b 3 Pages TS / B 3.6-16 and TS / B 3.6-17 2 Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS / B 3.6-19 1 Page TS / B 3.6-20 2 Page TS / B 3.6-21 3 Pages TS / B 3.6-21a and TS / B 3.6-21 b 0 Pages TS / B 3.6-22 and TS / B 3.6-23 2 Pages TS / B 3.6-24 and TS / B 3.6-25 1 Pages TS / B 3.6-26 and TS / B 3.6-27 3 Page TS / B 3.6-28 7 Page TS / B 3.6-29 5 Page TS / B 3.6-29a 0 Page TS / B 3.6-30 2 Page TS / B 3.6-31 3 Pages TS / B 3.6-32 and TS / B 3.6-33 2 SUSQUEHANNA

-UNIT 2 TS / B LOES-6 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LOES-6 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.6-34 1 Page TS / B 3.6-35 3 Pages TS / B 3.6-36 and TS / B 3.6-37 2 Page TS / B 3.6-38 3 Page TS / B 3.6-39 7 Page TS / B 3.6-40 1 Pages B 3.6-41 and B 3.6-42 0 Pages TS / B 3.6-43 and TS / B 3.6-44 1 Page TS / B 3.6-45 2 Pages TS / B 3.6-46 through TS / B 3.6-50 1 Page TS / B 3.6-51 2 Pages B 3.6-52 through B 3.6-55 0 Pages TS / B 3.6-56 and TS / B 3.6-57 2 Pages B 3.6-58 through B 3.6-62 0 Pages TS / B 3.6-63 and TS / B 3.6-64 1 Pages B 3.6-65 through B 3.6-68 0 Pages B 3.6-69 through B 3.6-71 1 Page TS / B 3.6-72 2 Pages TS / B 3.6-73 and TS I B .3.6-74 1 Pages B 3.6-75 and B 3.6-76 0 Page TS / B 3.6-77 1 Pages B 3.6-78 through B 3.6-82 0 Page TS / B 3.6-83 3 Page TS / B 3.6-84 2 Page TS / B 3.6-85 4 Page TS / B 3.6-86 through TS / B 3.6-87a 2 Page TS / B 3.6-88 4 Page TS / B 3.6-89 2 Page TS / B 3.6-90 3 Pages TS / B 3.6-91 through TS / B 3.6-95 1 Page TS / B 3.6-96 2 Pages TS / B 3.6-97 and TS / B 3.6-98 1 Page TS / B 3.6-99 3 Page TS / B 3.6-99a 0 Pages TS / B 3.6-100 and TS / B 3.6-101 1 Pages TS / B 3.6-102 and TS / B 3.6-103 2 Page TS / B 3.6-104 3 Page TS / B 3.6-105 2 Page TS / B 3.6-106 3 SUSQUEHANNA-UNIT2 TS/B LOES-7 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LOES-7 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision B 3.7 PLANT SYSTEMS BASES Page TS / B 3.7-1 3 Page TS / B 3.7-2 4 Pages TS / B 3.7-3 through TS / B 3.7-5 3 Page TS / B 3.7-5a 1 Page TS / B 3.7-6 3 Page TS / B 3.7-6a 2 Page TS / B 3.7-6b 1 Page TS / B 3.7-6c 2 Page TS / B 3.7-7 3 Page TS / B 3.7-8 2 Pages B 3.7-9 through B 3.7-11 0 Pages TS / B 3.7-12 and TS / B 3.7-13 2 Pages TS / B 3.7-14 through TS / B 3.7-18 3 Page TS / B 3.7-18a 1 Pages TS / B 3.7-18b through TS / B 3.7-18e 0 Pages TS / B 3.7-19 through TS / B 3.7-24 1 Pages TS / B 3.7-25 and TS / B 3.7-26 0 Page TS / B 3.7-27 4 Pages TS / B 3.7-28 and TS / B 3.7-29 3 Pages TS / B 3.7-30 and TS / B 3.7-31 1 Page TS / B 3.7-32 0 Page TS / B 3.7-33 1 Pages TS / B 3.7-34 through TS / B 3.7-37 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Page TS / B 3.8-1 1 Pages B 3.8-2 and B 3.8-3 0 Page TS / B 3.8-4 1 Pages TS / B 3.8-4a and TS / B 3.8-4b 0 Pages TS / B 3.8-5 and TS / B 3.8-6 3 Page TS / B 3.8-6a 1 Pages B 3.8-7 and B 3.8-8 0 Page TS / B 3.8-9 2 Pages TS / B 3.8-10 and TS / B 3.8-11 1 Pages B 3.8-12 through B 3.8-18 0 Page TS / B 3.8-19 1 Pages B 3.8-20 through B 3.8-22 0 Page TS / B 3.8-23 1 Page B 3.8-24 0 Pages TS / B 3.8-25 and TS / B 3.8-26 1 SUSQUEHANNA-UNIT 2 TS/BLOES-8 Revision 103 SUSQUEHANNA

-UNIT 2 TS / B LOES-8 Revision 103 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages B 3.8-27 through B 3.8-35 0 Page TS / B 3.8-36 1 Page TS / B 3.8-37 0 Page TS / B 3.8-38 1 Pages TS / B 3.8-39 through TS / B 3.8-46 0 Page TS / B 3.8-47 1 Pages TS / B 3.8-48 through TS / B 3.8-50 0 Pages TS / B 3.8-51 through TS / B 3.8-53. 1 Page TS / B 3.8-54 0 Page TS / B 3.8-55 1 Pages TS / B 3.8-56 through TS / B 3.8-59 2 Pages TS / B 3.8-60 through TS / B 3.8-64 3 Page TS / B 3.8-65 4 Page TS / B 3.8-66 5 Pages TS / B 3.8-67 and TS / B 3.8-68 4 Page TS / B 3.8-69 5 Pages TS / B 3.8-70 through TS / B 3.8-83 1 Pages TS / B 3.8-83A through TS / B 3.8-83D 0 Pages B 3.8-84 through B 3.8-85 0 Page TS / B 3.8-86 1 Page TS / B 3.8-87 2 Pages TS / B 3.8-88 through TS / B 3.8-93 1 Pages B 3.8-94 through B 3.8-99 0 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-2 1 Pages TS / B 3.9-2a through TS / B 3.9-5 1 Pages TS / B 3.9-6 through TS / B 3.9-8 0 Pages B 3.9-9 through B 3.9-18 0 Pages TS / B 3.9-19 through TS / B 3.9-21 1 Pages B 3.9-22 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 2 Pages TS / B 3.10-2 through TS / B 3.10-5 1 Pages B 3.10-6 through B 3.10-32 0 Page TS / B 3.10-33 2 Page B 3.10-34 0 Page B 3.10-35 1 Pages B 3.10-36 and B 3.10-37 0 Page B 3.10-38 1 Page TS / B 3.10-39 2 TSB2 Text LOES.doc 1/21/2011 SUSQUEHANNA

-UNIT 2 TS / B LOES-9 Revision 103 PPL Rev. 3 RCS Leakage Detection Instrumentation B 3.4.6 B 3.4 REACTOR COOLANT SYSTEM (RCS)B 3.4.6 RCS Leakage Detection Instrumentation BASES BACKGROUND GDC 30 of 10 CFR 50, Appendix A (Ref. 1), requires means for detecting and, to the extent practical, identifying the location of the source of RCS LEAKAGE. Regulatory Guide 1.45 (Ref. 2) describes acceptable methods for selecting leakage detection systems.Limits on LEAKAGE from the reactor coolant pressure boundary (RCPB)are required so that appropriate action can be taken before the integrity of the RCPB is impaired (Ref. 2). Leakage detection systems for the RCS are provided to alert the operators when leakage rates above normal background levels are detected and also to supply quantitative measurement of leakage rates. The Bases for LCO 3.4.4, "RCS Operational LEAKAGE," discuss the limits on RCS LEAKAGE rates.Systems for separating the LEAKAGE of an identified source from an unidentified source are necessary to provide prompt and quantitative information to the operators to permit them to take immediate corrective action.LEAKAGE from the RCPB inside the drywell is detected by at least one of two or three independently monitored variables, such as sump level changes and drywell gaseous and particulate radioactivity levels. The primary means of quantifying LEAKAGE in the drywell is the drywell floor drain sump monitoring system which consists of two drywell floor drain sump level Channels.

Both Channels are required to be Operable to satisfy the LCO.The drywell floor drain sump monitoring system monitors the LEAKAGE collected in the floor drain sump. This unidentified LEAKAGE consists of LEAKAGE from control rod drives, valve flanges or packings, floor drains, the Closed Cooling Water System, and drywell air cooling unit condensate drains, and any LEAKAGE not collected in the drywell equipment drain tank.The level of each drywell sump is continuously recorded in the Main Control Room. The change in (continued)

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-UNIT 2 TS / B 3.4-30 Revision 1 PPL Rev. 3 RCS Leakage Detection Instrumentation B 3.4.6 BASES BACKGROUND (continued) sump level per unit time determines the leak rate and is calculated from the recorder.The floor drain sump level indicators have switches that start and stop the sump pumps when required.

If the sump fills to the high high level setpoint, an alarm sounds in the control room.The primary containment air monitoring systems continuously monitor the primary containment atmosphere for airborne particulate and gaseous radioactivity.

A sudden increase of radioactivity, which may be attributed to RCPB steam or reactor water LEAKAGE, is annunciated in the control room. The primary containment atmosphere particulate and gaseous radioactivity monitoring systems are not capable of quantifying LEAKAGE rates. These monitors provide an alternate means of leak detection to that supplied by the sump level monitors, and although they cannot ensure detection of a 1 gpm leak in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in all cases, they provide a diverse means of leak detection (Ref. 3).APPLICABLE SAFETY ANALYSES A threat of significant compromise to the RCPB exists if the barrier contains a crack that is large enough to propagate rapidly. LEAKAGE rate limits are set low enough to detect the LEAKAGE emitted from a single crack in the RCPB (Refs. 4 and 5). Each of the leakage detection systems inside the drywell is designed with the capability of detecting LEAKAGE less than the established LEAKAGE rate limits. The allowed LEAKAGE rates are well below the rates predicted for critical crack sizes (Ref. 6). Therefore, these actions provide adequate response before a significant break in the RCPB can occur.RCS leakage detection instrumentation satisfies Criterion 1 of the NRC Policy Statement (Ref. 7).LCO The drywell floor drain sump monitoring system is required to quantify the unidentified LEAKAGE from the RCS. Thus, for the system to be considered OPERABLE, the system must be capable of measuring reactor coolant leakage. The other monitoring systems provide early alarms to the operators so closer examination of other detection systems will be made (continued)

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-UNIT 2 TS / B 3.4-31 Revision 0 PPL Rev. 3 RCS Leakage Detection Instrumentation B 3.4.6 BASES LCO to determine the extent of any corrective action that may be required.(continued)

With the leakage detection systems inoperable, monitoring for LEAKAGE in the RCPB is degraded.APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are required to be OPERABLE to support LCO 3.4.4. This Applicability is consistent with that for LCO 3.4.4.ACTIONS A.1 With the drywell floor drain sump monitoring system inoperable, the primary containment atmospheric activity monitor will provide indication of changes in leakage.With the drywell floor drain sump monitoring system inoperable, operation may continue for 30 days. However, RCS unidentified and total LEAKAGE is still required to be determined every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (SR 3.4.4.1).The 30 day Completion Time of Required Action A.1 is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.

B.1 and B.2 With both gaseous and particulate primary containment atmospheric monitoring channels inoperable, grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic leakage information.

Provided a sample is obtained and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may be operated for up to 30 days to allow restoration of at least one of the required monitors.The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE. The 30 day Completion Time for (continued)

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-UNIT 2 TS / B 3.4-32 Revision I PPL Rev. 3 RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTIONS B.1 and B.2 (continued) restoration recognizes that at least one other form of leakage detection is available.

C.1 and C.2 If any Required Action of Condition A or B cannot be met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 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 perform the actions in an orderly manner and without challenging plant systems.D. 1 With all required monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate plant shutdown in accordance with LCO 3.0.3 is required.SURVEILLANCE REQUIREMENTS SR 3.4.6.1 This SR is for the performance of a CHANNEL CHECK of the required primary containment atmospheric monitoring system. The check gives reasonable confidence that the channel is operating.

properly.

The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is based on instrument reliability and is reasonable for detecting off normal conditions.(continued)

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-UNIT 2 TS / B 3.4-33 Revision 1 PPL Rev. 3 RCS Leakage Detection Instrumentation B 3.4.6 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.4.6.2 This SR is for the performance of a CHANNEL FUNCTIONAL TEST of the required RCS leakage detection instrumentation.

The test ensures that the monitors can perform their function in the desired manner. The Frequency of 31 days considers instrument reliability, and operating experience has shown it proper for detecting degradation.

SR 3.4.6.3 This SR is for the performance of a CHANNEL CALIBRATION of required leakage detection instrumentation channels.

The calibration verifies the accuracy of the instrument string, including the instruments located inside containment.

The Frequency of 24 months is a typical refueling cycle and*considers channel reliability.

REFERENCES

1. 10 CFR 50, Appendix A, GDC 30.2. Regulatory Guide 1.45, May 1973.3. FSAR, Section 5.2.5.1.2.
4. GEAP-5620, April 1968.5. NUREG-75/067, October 1975.6. FSAR, Section 5.2.5.4.7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA

-UNIT 2 TS / B 3.4-34 Revision 0 PPL Rev. 3 Main Turbine Bypass System B 3.7.6 B33.7 PLANT SYSTEMS B 3.7.6 Main Turbine Bypass System BASES BACKGROUND The Main Turbine Bypass System is designed to control steam pressure when reactor steam generation exceeds turbine requirements during unit startup, sudden load reduction, and cooldown.

It allows excess steam flow from the reactor to the condenser without going through the turbine.The full bypass capacity of the system is approximately 22% of the Nuclear Steam Supply System rated steam flow. Sudden load reductions within the capacity of the steam bypass can be accommodated without reactor scram. The Main Turbine Bypass System consists of five valves connected to the main steam lines between the main steam isolation valves and the turbine stop valve bypass valve chest. Each of these five valves is operated by hydraulic cylinders.

The bypass valves are controlled by the pressure regulation function of the Turbine Electro Hydraulic Control System, as discussed in the FSAR, Section 7.7.1.5 (Ref. 1). The bypass valves are normally closed, and the pressure regulator controls the turbine control valves that direct all steam flow to the turbine. If the speed governor or the load limiter restricts steam flow to the turbine, the pressure regulator controls the system pressure by opening the bypass valves. When the bypass valves open, the steam flows from the bypass chest, through connecting piping, to the pressure breakdown assemblies, where a series of orifices are used to further reduce the steam pressure before the steam enters the condenser.

APPLICABLE SAFETY ANALYSES The Main Turbine Bypass System has two modes of operation.

A fast opening mode is assumed to function during the turbine generator load rejection, turbine trip, and feedwater controller failure transients as discussed in FSAR Sections 15.2.2, 15.2.3, and 15.1.2 (Refs. 2, 3, and 4). A pressure regulation mode is assumed to function during the control rod withdrawal error and recirculation flow controller failure transients as discussed in FSAR Sections 15.4.2 and 15.4.5 (Refs. 5 and 6). Both modes of operation are assumed to function for all bypass valves assumed in the applicable safety analyses.

Opening the bypass valves during the above transients mitigates the increase in reactor vessel pressure, which affects both MCPR and LHGR during the event. An inoperable Main Turbine Bypass System may result in a MCPR and / or LHGR penalty.The Main Turbine Bypass System satisfies Criterion 3 of the NRC Policy Statement. (Ref. 7)(continued)

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-UNIT 2 TS / B 3.7-27 Revision 4 PPL Rev. 3 Main Turbine Bypass System B 3.7.6 BASES (continued)

LCO The Main Turbine Bypass System fast opening and pressure regulation modes are required to be OPERABLE to limit the pressure increase in the main steam lines and reactor pressure vessel during transients that cause a pressurization so that the Safety Limit MCPR and LHGR are not exceeded.With the Main Turbine Bypass System inoperable, modifications to the MCPR limits (LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)")and LHGR limits (LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)") may be applied to allow this LCO to be met. The MCPR and LHGR limits for the inoperable Main Turbine Bypass System are specified in the COLR. An OPERABLE Main Turbine Bypass System requires the bypass valves to open in response to increasing main steam line pressure.Licensing analyses credit an OPERABLE Main Turbine Bypass System as having both the bypass valve fast opening mode and pressure regulation mode. The fast opening mode is required for transients initiated by a turbine control valve or turbine stop valve closure. The pressure regulation mode is required for transients where the power increase exceeds the capability of the turbine control valves.The cycle specific safety analyses assume a certain number of OPERABLE main turbine bypass valves as an input (i.e., one through five). Therefore, the Main Turbine Bypass System is considered OPERABLE when the number of OPERABLE bypass valves is greater than or equal to the number assumed in the safety analyses.

The number of bypass valves assumed in the safety analyses is specified in the COLR. This response is within the assumptions of the applicable analysis (Refs. 2 -6).APPLICABILIT The Main Turbine Bypass System is required to be OPERABLE at Y _> 23% RTP to ensure that the fuel cladding integrity Safety Limit is not violated during all applicable transients.

As discussed in the Bases for LCOs 3.2.2 and 3.2.3, sufficient margin to these limits exists at < 23% RTP.Therefore, these requirements are only necessary when operating at or above this power level.ACTIONS A.1 If the Main Turbine Bypass System is inoperable and the MCPR and LHGR limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are not applied, the assumptions of the design basis transient analysis may not be met.(continued)

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-UNIT 2 TS / B 3.7-28 Revision 3 PPL Rev. 3 Main Turbine Bypass System B 3.7.6 BASES ACTIONS A.1 (continued)

Under such circumstances, prompt action should be taken to restore the Main Turbine Bypass System to OPERABLE status or adjust the MCPR and LHGR limits accordingly.

The 2-hour Completion Time is reasonable, based on the time to complete the Required Action and the low probability of an event occurring

'during this period requiring the Main Turbine Bypass System.B. 1 If the Main Turbine Bypass System cannot be restored to OPERABLE status or the MCPR and LHGR limits for an inoperable Main Turbine Bypass System are not applied, THERMAL POWER must be reduced to< 23% RTP. As discussed in the Applicability section, operation at< 23% RTP results in sufficient margin to the required limits, and the Main Turbine Bypass System is not required to protect fuel integrity during the applicable transients.

The 4-hour Completion Time is reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE REQUIREMENTS Cycling each required main turbine bypass valve through one complete cycle of full travel (including the fast opening feature) demonstrates that the valves are mechanically OPERABLE and will function when required.The 31-day Frequency is based on engineering judgment, is consistent with the procedural controls governing valve operation, and ensures correct valve positions.

Operating experience has shown that these components usually pass the SR when performed at the 31 day Frequency.

Therefore, the Frequency is acceptable from a reliability standpoint.

SR 3.7.6.2 The Main Turbine Bypass System is required to actuate automatically to perform its design function.

This SR demonstrates that, with the required system initiation signals (simulate automatic actuation), the valves will actuate to their required position.

The 24 month Frequency is based on the need to (continued)

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-UNIT 2 TS / B 3.7-29 Revision 3 PPL Rev. 3 Main Turbine Bypass System B 3.7.6 BASES SURVEILLANCE SR 3.7.6.2 (continued)

REQUIREMENT S perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown the 24-month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.

SR 3.7.6.3 This SR ensures that the TURBINE BYPASS SYSTEM RESPONSE TIME is in compliance with the assumptions of the appropriate safety analysis.

The response time limits are specified in unit specific documentation.

The 24-month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown the 24-month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.

REFERENCES

1. FSAR, Section 7.7.1.5.2. FSAR, Section 15.2.2.3. FSAR, Section 15.2.3 4. FSAR, Section 15.1.2 5. FSAR, Section 15.4.2 6. FSAR, Section 15.4.5 7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA

-UNIT 2 TS / B 3.7-30 Revision 1

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