ML15034A310

Susquehanna Steam Electric Station Technical Specification Bases Unit 1 Manual

ML15034A310
Person / Time
Site:	Susquehanna
Issue date:	01/23/2015
From:	Susquehanna
To:	Office of Nuclear Reactor Regulation
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Download: ML15034A310 (26)

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Jan. 23, 2015 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2015-2824 USER INFORMATION:

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SSES MANUAL Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 01/22/2015 Procedure Name Rev TEXT LOES 120 Title: LIST OF EFFECTIVE SECTIONS Issue Date 01/22/2015 Change ID Change Number TEXT TOC Title: TABLE OF CONTENTS 23 07/02/2014 TEXT 2.1.1 6 Title: SAFETY LIMITS (SLS) REACTOR TEXT 2.1.2 1 Title: SAFETY LIMITS (SLS) REACTOR 01/22/2015 CORE SLS 10/04/2007 COOLANT SYSTEM (RCS) PRESSURE S 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 04/18/2006 CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/15/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES 2 01/19/2009 CONTROL SYSTEMS CONTROL ROD OPERABILITY 4 01/30/2009 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES 1 07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 3 02/24/2014 CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 01/22/15 Page I of .8 Report Date: 01/22/15 SSES MANUAL~Manual Name: TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7 3 04/23/2008 Title: REACTIVITY CONTROL 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 2 04/23/2008 Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 3 05/06/2009 Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 04/23/2008 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)TEXT 3.3.1.1 6 02/24/2014 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 2 01/19/2009 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 4 02/24/2014 Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 2 04/05/2010 Title: INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 9 02/28/2013 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 Title: INSTRUMENTATION TEXT 3.3.4.1 Title: INSTRUMENTATION 1 04/18/2005 REMOTE SHUTDOWN SYSTEM 2 02/24/2014 a END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATION Page 2 of 8 Report Date: 01/22/15 Page 2 of 8 Report Date: 01/22/15 SSES MANUAL Manual Name: TSBI W Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.2 0 11/15/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 3 08/20/2009 Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/15/2002 Title: INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 7 03/31/2014 Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 4 09/01/2010 Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 Title: INSTRUMENTATION INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.3.8.1 2 12/17/2007 Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0 11/15/2002 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 4 04/27/2010 Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 3 10/23/2013 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 h TEXT 3.4.4 0 11/15/2002 Title: REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Page 3 of .8 Report Date: 01/22/15 SSES MANUAL Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 1 01/16/2006 Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 4 02/19/2014 Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 2 10/04/2007 Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 Title: REACTOR COOLANT-HOT SHUTDOWN TEXT 3.4.9 Title: REACTOR COOLANT-COLD SHUTDOWN 2 SYSTEM (RCS)1 SYSTEM (RCS)03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM 03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM TEXT 3.4.10 3 04/23/2008 Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0 11/15/2002 Title: REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 4 07/16/2014 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM ECCS -OPERATING TEXT 3.5.2 0 11/15/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM ECCS -SHUTDOWN TEXT 3.5.3 3 02/24/2014 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM RCIC SYSTEM CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)TEXT 3.6.1.1 Title: PRIMARY CONTAINMENT 5 02/24/2014 TEXT 3.6.1.2 1 04/23/2008 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page of Reort ate 01/2/1 Page 4 of 8 Report Date: 01/211/15 SSES MANUAL.! Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.3 11 07/02/2014 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)TEXT 3.6.1.4 1 04/23/2008 Title: CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 1 10/05/2005 Title: CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURE TEXT 3.6.1.6 0 11/15/2002 Title: CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 2 04/23/2008 Title: CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE TEXT 3.6.2.2 0 11/15/2002 Title: CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL TEXT 3.6.2.3 1 01/16/2006 Title: CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING TEXT 3.6.2.4 0 11/15/2002 Title: CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 2 06/13/2006 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005 Title: CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 1 02/28/2013 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION

.TEXT 3.6.4.1 11 11/06/2014 Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page 5 of -8 Report Date: 01/22/15 SSES MANUAL Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 9 04/25/2014 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 4 04/05/2010 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE SINK (UHS)TEXT 3.7.2 Title: PLANT 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 2 02/11/2009 SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM 1 01/08/2010 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 0 11/15/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 1 10/04/2007 SYSTEMS MAIN CONDENSER OFFGAS 2 04/23/2008 SYSTEMS MAIN TURBINE BYPASS SYSTEM 1 10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.7.8 Title: PLANT SYSTEMS 0 04/23/2008 TEXT 3.8.1 7 02/24/2014 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.8.2 0 11/15/2002 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWN Page6 of 8 Report Date: 01/22/15 Page 6 of a Report Date: 01/22/15 SSES MANUALJ Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 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 4 10/23/2013 POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR POWER SYS=POWER SYST POWER SYST POWER SYST POWER SYST OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 3 01/19/2009 2EMS DC SOURCES -OPERATING 1 12/14/2006

'EMS DC SOURCES -SHUTDOWN 1 12/14/2006 FEMS BATTERY CELL PARAMETERS 1 10/05/2005

'EMS DISTRIBUTION SYSTEMS -OPERATING 0 11/15/2002 2EMS DISTRIBUTION SYSTEMS -SHUTDOWN 0 11/15/2002 REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/15/2002 CONTROL ROD POSITION 0 11/15/2002 CONTROL ROD POSITION INDICATION 0 11/15/2002 CONTROL ROD OPERABILITY

-REFUELING 1 10/04/2007 REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page 7 Report Date: 01/22/15 Page7 Report Date: 01/22/15 SSES MANUAL Manual Name: TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 0 11/15/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVEL TEXT 3.9.8 0 11/15/2002 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 11/15/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0 11/15/2002 SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN 0 11/15/2002 SINGLE CONTROL ROD WITHDRAWAL

-COLD SHUTDOWN 0 11/15/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING 0 11/15/2002 MULTIPLE CONTROL ROD WITHDRAWAL

-REFUELING 1 04/18/2006 CONTROL ROD TESTING -OPERATING 1 04/12/2006 SHUTDOWN MARGIN (SDM) TEST -REFUELING?age8 of 8 Report Date: 01/22/15?age 8 of 8 Report Date: 01/22/15 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision TOC Table of Contents 23 B 2.0 SAFETY LIMITS BASES Page TS / B 2.0-1 1 Page TS / B 2.0-2 3 Page TS / B 2.0-3 6 Page TS / B 2.0-4 4 Page TS / B 2.0-5 6 Page TS / B 2.0-6 1 Pages TS / B 2.0-7 through TS / B 2.0-9 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 A, 1 Page TS / B 3.0-8 3 Pages TS / B 3.0-9 through TS / B 3.0-11 2 Page TS / B 3.0-1 Ia 0 Page TS / B 3.0-12 1 Pages TS / B 3.0-13 through TS --2 Pages TS / B 3.0-16 and TS /B3 0 B 3.1 REACTIVITY CONTROL B Pages B 3.1-1 through 3.1- 0 Page TS / B 3.1-5 1 Pages TS / B 3.1 andT 13E-7 2 Pages B 3.1-8 thiuirhu B 3.1-i'R1 0 Page TS/B 3.14 -1 Page B 3. 0.Page TS 1hrough B 3.1-19 0 Pa e -20 and TS/B 3.1-21 1 PaT 1-22 P T 3.1-23 1 9T / B 31-24 0.ITS / B 3.1-25 through TS / B 3.1-27 1 NgTS / B 3.1-28 2 Page TS / B 3.1-29 1 Pages B 3.1-30 through B 3.1-33 0 Pages TS / B 3.3-34 through TS / B 3.3-36 1 Page TS / B 3.1-37 2 Page TS / B 3.1-38 3 Pages TS / B 3.1-39 and TS / B 3.1-40 2 Page TS / B 3.1-40a 0 Pages TS / B 3.1-41 and TS / B 3.1-42 2 SUSQUEHANNA

-UNIT 1 TS / B LOES-1 Revision 120 SUSQUEHANNA

-UNIT 1 TS / B LOES-1 Revision 120 SUSQUEHANNA*

STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B,3.1.43 1 Page TS / B 3.1-44 0 Page TS / B 3.1-45 3 Pages TS / B 3.1-46 through TS / B 3.1-49 1 Page TS / B 3.1-50 0 Page TS / B 3.1-51 3 B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 2 Pages TS / B 3.2-2 and TS / B 3.2-3 3 Pages TS / B 3.2-4 and TS / B 3.2-5 2 Page TS I B 3.2-6 3 Page B 3.2-7 1 Pages TS / B 3.2-8 and TS / B 3.2-9 3 Page TS / B 3.2.10 2 Page TS / B 3.2-11 3 Page TS / B 3.2-12 1 Page TS / B 3.2-13 2 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 3.3-7a 1 Page TS / B 3.3-8 5 Pages TS / B 3.3-9 through TS / B 3.3-12 3 Pages TS / B 3.3-12a 1 Pages TS / B 3.3-12b and TS / B 3.3-12c 0 Page TS / B 3.3-13 1 Page TS / B 3.3-14 3 Pag'es TS / B 3.3-15 and TS / B 3.3-16 1 Pages TS / B 3.3-17 and TS / B 3.3-18 4 Page TS / B 3.3-19 1 Pages TS / B 3.3-20 through TS / B 3.3-22 2 Page TS / B 3.3-22a 0 Pag'es TS / B 3.3-23 and TS / B 3.3-24 2 Pages TS / B 3.3-24a and TS / B 3.3-24b 0 Page TS / B 3.3-25 3 Page TS / B 3.3-26 2 Page TS / B 3.3-27 1 Page TS / B 3.3-28 3 Page TS / B 3.3-29 4 Page TS I B 3.3-30 3 Page TS /B 3.3-30a 0'SO800EHANNA

-UNIT 1 TS / B LOES-2 k6v:,ision 120 SUSQUEHANNA STEAM ELECTRIC STATION LIST 6F EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-31 4 Page TS / B 3.3-32 5 Pages TS / B 3.3-32a 0 Page TS / B 3.3-32b 1 Page TS / B 3.3-33 5 Page TS / B 3.3-33a 0 Page TS / B 3.3-34 1 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 Page TS/. B 3.3-39 2 Pages TS / B 3.3-40 through TS / B 3.3-43 1 Page TS / B 3.3-44 4 Pages TS / B 3.3-44a and TS J B 3.3-44b 0 Page TS / B 3.3-45 3 Pages TS / B 3.3-45a and TS / B 3.3-45b 0 Page TS / B 3.3-46 3 Pages TS /B 3.3-47 2 Pages TS / B 3.3-48 through TS / B 3.3-51 3 Pages TS / B 3.3-52 and TS / B 3.3-53 2 Page TS / B 3-3-53a 0 Page TS / B 3.3-54 5 Page TS-/ B 3.3-55 2 Pages TS / B 3.3-56 and TS / B 3.3-57 1 Page TS / B 3.3-58 0 Page TS / B 3.3-59 1 Page TS / B 3.3-60 0 Page TS / B 3.3-61 1 Pages TS / B 3.3-62 and TS / B 3.3-63 0 Pages TS / B3.3-64 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 Pages 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 Page TS / B 3.3-75a 6 Page TS / B 3.3-75b 7 Page TS / B 3.3-75c 6 Pages B 3.3-76 through B 3.3-77 0 Page TS / B 3.3-78 1-SU]QUEH".A NA -NT1 T OS3Rvso 2 809QUEWANNA

-UNIT 1 TS / B LOES-3 ReVisi6n 120 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages B 3.3-79 through B 3.3-81 0 Page TS / B 3.3-82 2 Page B 3.3-83 0 Pages B 3.3-84 and B 3.3-85 1 Page B 3.3-86 0 Page B 3.3-87 1 Page B 3.3-88 0 Page B 3.3-89 1 Page TS / B 3.3-90 1 Page B 3.3-91 0 Pages TS / B 3.3-92 through TS I B 3.3-100 1 Pages TS / B 3.3-101 through TS / B 3.3-103 0 Page TS / B 3.3-104 2 Pages TS / B 3.3-105 and TS / B 3.3-106 0 Page TS / B 3.3-107 1 Page TS / B 3.3-108 0 Page TS / B 3.3-109 1 Pages TS / B 3.3-110 and TS / B 3.3-111 0 Pages TS / B 3.3-112 and TS / B 3.3-112a 1 Pages TS / B 3.3-113 through TS / B 3.3-115 1 Page TS / B 3.3-116 3 Page TS / B 3.3-117 1 Pages TS / B 3.3-118 through TS / B 3.3-122 0 Pages TS / B 3.3-123 and TS / B 3.3-124 1 Page TS / B 3.3-124a 0 Page TS / B 3.3-125 0 Pages TS / B 3.3-126 and TS / B 3.3-127 1 Pages TS / B 3.3-128 through TS/ B 3.3-130 0 Page TS / B 3.3-131 1 Paddes TS / B 3.3-132 through TS / B 3.3-134 0 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 and TS / B 3.3-160 1 Page TS / B 3.3-161 2 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 through TS / B 3.3-167 2 SU0SQUEHANNA

-UNIT 1 TS FB LOES-4 Revision 120 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS'/ B 3.3-168 and TS / B 3.3-169 1 Page TS / B 3.3-170 3 Page TS / B 3.3-171 2 Pages TS / B 3.3-172 through TS / B 3.3-177 1 Pages TS / B 3.3-178 and TS / B 3.3-179 2 Page TS / B 3.3-179a 2 Pages TS / B 3.3-179b and TS / B 3.3-179c 0 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 Pages TS / B 3.3-197 through TS / B 3.3-204 0 Page TS / B 3.3-205 1 Pages B 3.3-206 through B 3.3-209 0 Page TS / B 3.3-210 1 Pages B 3.3-211 through B 3.3-219 0-B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 0 Pages TS / B 3.4-3 and Page TS / B 3.4-4 4 Page TS / B 3.4-5 3 Pages TS / B 3.4-6 through TS / B 3.4-9 2 Page TS / 8 3.4-10 1 Pages TS / 3.4-11 and TS /B 3.4-12 0 Page TS / B 3.4-13 2 Page TS / 8 3.4-14 1 Page TS / 8 3.4-15 2 Pages TS / B 3.4-16 and TS / B 3.4-17 4 Page TS / B 3.4-18 2 Pages B 3.4-19 through B 3.4-27 0 Pages TS / B 3.4-28 and TS / B 3.4-29 1 Page TS/B 3.4-30 2 Page TS B 3.4-31 1 ,Pages TS / B 3.4-32 and TS / B 3.4-33 2 Page TS / B 3.4-34 1 Page TS / B 3.4-34a 0 5ll."fi IFHANNlA -I INJIT 1 TR B P I fLFO--5 RAi'inin 192 S V I V i i SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS I B 3.4-35 and TS / B 3.4-36 1 Page TS / B 3.4-37 2 Page TS / B 3.4-38 1 Pages B' 3.4-39 and B 3.4-40 0 Page TS / B 3.4-41 2 Pages TS / B 3.4-42 through TS / B 3.4-45 0, Page TS / B 3.4-46 1 Pages TS B 3.4-47 and TS / B 3.4-48 0 Page TS/B 3.4-49 3 Page TS / B 3.4-50 1 Page TS / B 3.4-51 3 Page TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 through TS / B 3.4-56 2 Page TS / B 3.4-57 3 Pages TS / B 3.4-58 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0 Page TS / B 3.5-3 3 Page TS / B 3.5-4 1 Page TS / B 3.5-5 2 Page TS / B 3.5-6 1 Pages B 3.5-7 through B 3.5-10 0 Page TS /B 3.5-11 1 Page TS / B 3.5-12 0 Page TS / B 3.5-13 2 Pages TS / B 3.5-14 and TS / B 3.5-15 0 Pages TS / B 3.5-16 and TS / B 3.5-17 3'Page TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 1 Page TS / B 3.5-26 and TS / B 3.5-27 2 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 Pages TS / B 3.6-5 and TS / B 3.6-6 3.U .E AN A-..... BLO S-.Rviio 12. 0 : SUSQUEHANNA

-UNIT 1 TS / B LOES-6 Revision 120 SUSQUEHANNA.STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.6-6a 2 Page TS / B 3.6-6b 4 Page TS / B 3.6-6c 0 Page B 3.6-7 0 Page B 3.6-8 1 Pages B 3.6-9 through B 3.6-14 0 Page TS / B3.6-15 3 Page TS / B 3.6-15a 0 Page TS / B 3.6-15b 2 Pages TS / B 3.6-16 and TS / B 3.6-17 2 Page TS / B 3.6-17a 1 Pages TS / B 3.6-18 and TS / B 3.6-19 0 Page TS / B 3.6-20 1 Page TS / B 3.6-21 2 Page TS / B 3.6-22 1 Page TS / B 3'.6-22a 0 Page TS / B 3.6-23 1 Pages TS / B 3.6-24 and TS / B 3.6-25 0 Pages TS / B 3.6-26 and TS / B 3.6-27 2 Page TS / B 3.6-28 7 Page TS / B 3.6-29 2 Page TS / B 3.6-30 1 Page TS / B 3.6-31 3 Pages TS / B 3.6-32 and TS / B 3.6-33 1 Pages TS / B 3.6-34 and TS / B 3.6-35 0 Page TS / B 3.6-36 1 Page TS / B 3.6-37 0 Page TS / B 3.6-38 3 Page TS / B. 3.6-39 2 Page TS / B 3.6-40 6 Page TS / B 3.6-40a 1 Page B 3.6-41 1 Pages B 3.6-42 and B 3.6-43 0 Pages TS / B 3.6-44 and TS / B 3.6-45 1 Page TS / B 3.6-46 2 Pages TS / B, 3.6-47 through TS / B 3.6-51 1 Page TS / B 3.6-52 2 Pages TS / B 3.6-53 through TS / B 3.6-56 0 Page TS / B 3.6-57 1 Page TS / 3.6-58 2 Pages B 3.6-59 through B 3.6-63 0 Pages TS / B 3.6-64 and TS / B 3.6-65 1 Pages B 3.6-66 through B 3.6-69 0 SUSQUHANNA--UNT-1 T ..B..ES. .e...o 120 s0sQ0EHANNA

-UNIT 1 TS / B LOES-7 Rev/i~ion 1.20 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.6-70 through TS /B 3.6-75 1 Pages B 3.6-76 and B 3.6-77 0 Page TS / B 3.6-78 1 Pages B 3.6-79 and B 3.3.6-80 0 Page TS / B 3.6-81 1 Pages TS / B 3.6-82 and TS / B 3.6-83 0 Page TS / B 3.6-84 4 Page TS / B 3.6-85 2 Page TS / B 3.6-86 4 Pages TS / B 3.6-87 through TS / B 3.6-88a 2 Page TS / B 3.6-89 6 Page TS / B 3.6-90 4 Page TS / B 3.6-90a 0 Pages TS / B 3.6-91 and TS I B 3.6-92 3 Page TS / B 3.6-93 2 Pages TS / B 3.6-94 through TS / B 3.6-96 1 Page TS /B 3.6-97 2 Page TS / B 3.6-98 1 Page TS / B 3.6-99 2 Pages TS / B 3.6-100 and TS / B 3.6-100a 6 Page TS / B 3.6-100b 4 Page TS / B 3.6-100c 0 Pages TS I B 3.6-101 and TS / B 3.6-102 1 Pages TS / B 3.6-103 and TS B 3.6-104 2 Page TS / B 3.6-105 3 Page TS / B 3.6-106 2 Page TS / B 3.6-107 3 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 3 Page TS / B 3.7-2 4 Pages TS I B 3.7-3 through TS / B 3.7-5 3 Page TS / B 3.7-5a 3 Page TS / B 3.7-6 3 Page TS /B 3.7-6a 2 Page TS / B 3.7-6b 2 Page TS / B 3.7-6c 2 Page TS / B 3.7-7 3 Page TS / B 3.7-8 2 Pages TS / B 3.7-9 through TS / B 3.7-11 1 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 I B 3.7-18b through TS I B 3.7-18e 0 SUS'QUEHANNA

-UNIT 1 TS / B LOES-8 Rkevs ion 120 SUSQUEHANNA STEAM ELECTRIC STATION LISTQOFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.7-19 through TS / B 3.7-23 1 Page TS / B 3.7-24 1 Pages TS / B 3.7-25 and TS / B 3.7-26 0.Pages TS / B 3.7-27 through TS I B 3.7-29 5 Page TS / B 3.7-30 2 Page 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 I B 3.7-37 0 B 3.8 ELECTýRICAL POWER SYSTEMS BASES Page TS / B: 3.8-1 3 Pages TS / B 3.8-2 and TS / B 3.8-3 2 Page TS / B 3.8-4 3 Pages TS / B 3.8-4a and TS / B 3.8-4b 0 Page TS /B 3.8-5 5 Page TS / B 3.8-6 3 Pages TS / B 3.8-7 through TS/B 3.8-8 2 Page TS / B 3.8-9 4 Page TS / B 3.8-10 '3 Pages TS / B 3.8-11 and TS/ B 3.8-17 2 Page TS-/B 3.8-18 3-Pages TS / B 3.8-19 through TS / B 3.8-21 2 Pages TS / B 3.8-22 and TS / B 3.8-23 3 Pages TS / B 3.8-24 through TS / B 3.8-30 2 Pages TS / B 3.8-31 and TS / B 3.8-32 3'Pages TS / B 3.8-33 through TS / B 3.8-37 2 Pages B 3.8-38 through B 3.8-44 0 Page TS / B 3.8-45 .3 Pages TS / B 3.8-46 through TS / B 3.8-48 0 Pages TS / B 3.8-49 and TS I B 3.8-50 3 Page TS / B 3.8-51 1 Page TS / B 3.8-52 0 Page TS / B 3.8-53 1 Pages TS / B 3.8-54 through TS / B 3.8-57 2 Pages TS / B 3.8-58 through TS / B 3.8-61 3 Pages TS / B 3.8-62 and TS / B 3.8-63 5 Page TS / B 3.8-64 4 Page TS / 8 3.8-65 5 Pages TS / B 3.8-66 through TS / B 3.8-77 1 Pages TS / B 3.8-77A through TS / B 3.8-77C 0 Pages B 3.8-78 through B 3.8-80 0 Page TS / B 3.8-81 1 Pages B 3.8-82 through B 3.8-90 0 SUSQU9 HANNA -UNIT 1 TS B LOES-9 Revision 120 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-1a 1 Pages TS / B 3.9-2 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 3.10-31. 0 Page TS / B 3.10-32 2 Page B 3.10-33 0 Page TS / B 3.10-34 1 Pages 83.10-35 and B 3.10-36 0 Page TS / B 3.10-37 1 Page TS / B 3.10-38 2 SIUSQOEPANNA

-UNIT 1 SUQ E A N* NT1T / ,O Sl R. ....... 120 TS / B LOES-1 0 We~i91on h 20, PPL Rev. 6 Reactor Core. SLs B 2. 1.1 B 2.0 SAFETY LIMITS (SLs)B 2.1.1 Reactor Core SLs BASES BACKGROUND GDC 10 (Ref. 1) requires, and SLs ensure' that specified acceptable fuel design limits are not exceeded during steady state operation, normal operational transients, and anticipated operational occurrences (AOOs)., The fuel cladding integrity SL is set such that no significant fuel damage is, calculated to occur if the limit is not violated.

Because fuel damage is not directly observable, a stepback approach i's used to establish an SL, such that the MCPR is not less than the linmit specified-in Specification 2.1.1.2 for AREVA NP fuel. MCPR greater than the specified limit represents a conservative margin relative to the conditions required to maintain fuel cladding integrity.

The fuel cladding is one of the physical barriers that separate the radioactive materials from the environs.

The integrity of this cladding barrier is related to its relative freedom from perforations or cracking.Although some corrosion or use related cracking may occur during the life of the cladding, fission product migration from this source is incrementally cumulative and continuously measurable.

Fuel cladding perforations, however, can result from thermal stresses, which occur from reactor operation significantly above design" conditions.

While fission product migration from cladding perfbration, is just as measurable as that from use related crack ing,. the thermally caused.cladding perforations signal a.%thr6shOld beyond which still'greater thermal stresses may cause gross, rather th6n: ~crenental,.

detbriQration.

Therefore, the fuel cladding SL is defined wi'-h 'a margin to the that Would produce onset of transition b6iling (i.e., MCPR.= 1.00). These condioons represent a significant from the condition intended by design for planned operation.

Th. MCP fuel cladding integrityýSL.

ensures that during normal operation:

a'iddurirng Aoos, at'least 99.9% of'the fuel rods in the core do not exp0erience transition boiling.(contir -(d)-Q*I'r .Cl l -IAMKlA _ I lIMIT -I T M 0 r) / _I D i7,, .,4

/PPL Rev. 6-Reactor Core, S'Ls B 2.1.1 BASES BACKGROUND (Continued)

Operation above the boundary of the nucleate boi~ingýregime could result in. excessive cladding temnperature b ceoau ef the , ons6et of transition boiling and the resultant1 sharp reduction in, eaft transfer coefficient.

Inside the steam film, .hig'K:hcla.din te Umpeatres;aie reached, and a cladding water(zirc6riiurn water)reactioe r may ta ke place. This chemical reaction results int fuel cladding to a structurally weaker form. Tills' w`a`ker fori mai resulting in an uncontrolled release of, activity to th-.ereactbr coolant": APPLICABLE SAFETY ANALYSES The fuel cladding must not sustain damage: as a result of normal operation and AOOs. The reactor-core SLs are established to preclude violation of the fuel de'sign criteriorn th ,at. an- fMCPR limit is to be established, such that at least 99.9% of the fuel rods in the core would not be expected to experience the onset of transition boiling.The Reactor Protection System setpoints (LCO 3.3.1.1, "Reactor Protection System (RPS),lInstrumentation"), in combination with the other LCOs, are designed to preveLnt anylanticiqpateýt -combination of transient conditions for Reactor Co'olant'Systee r level, pressure, and THERMAL POWER level that *oull'result in! re6chinrg the MCPR lim it.2.1.1.1 Fuel Cladding Integrity' The use of the SPCB (Reference 4).correlati6r is vald fbr critical power calculations at pressures

>.571.4 psia ad, urd e mass fluxes'> 0.087 x 106 lb/hr-ft 2.For operation at. 6ft,,.i pre re:-Irlow'flows the fuel cladding integrity SL is established by a'h liftingl condition on core THERMAL POWER, with the foiiowing..bdsis:.

Provided that the water -level in. the vessel dovnd6omer is maintained abo5ve the top: of the act vfuei :,atqral&citcUlation is sufficient to ensure a minimum bundrefi bforlII 'ual 'assemblies that have a relatively high power arid 06t'enti'llV can64 approach a critical heat flux condition.

.1:A A ek contifiwed)',ýý.

SUSQUEHANNA

-UNIT 1 TS /B 2.0-2 BASES APPLICABLE SAFETY1 ANALYSES 2.1.1.1 Fuel Cladding Intecq For the > 28-x, 10 3 lb/hr. For theAl coolant minimum bundle flo mass flux is always > 0.25 data taken from various AR from 14.7 psia to 1400 psia 0.25 x 106 lb/hr-ft 2 is appro0 power of approximately 3.3 peaking factor of approxim.the expected peaking facto 23% RTP for reactor presst conditions of lesser powerV 2.1.1.2 MCPR.. ........PPLERev. 6 .Reactor ore& SLs B 2.1.1 A irity (continued).the minimum bundle flow'is REVA NP ATRIUM-I.0 fuel desjigni the'.w arid maximum airea. 8ae thatthe..10'1 b/hr-ft 2.Full, scal'ditei.

Fa lpower test ..EVA NP-and:-GEfuel desigrns-a-t pressures

" indica ..the fuelassemblrc Critica.l power at cimat6ty .3.35 Mwt, At 23% R1rP, a .bundle 56MW6'C166rresp.ond's.toa bundle radial ately 2.8, which :is significa.t ly-jhiher than 0 r. Thus, a THERMAL POWER lfimit of.ures..< 557 psig is conservative and for .4 wVould remain conservative. " * " " The MCPR SL ensures sufficient conservatism ih the operating MCPR limit that, in the event of an AOd"frim the limiting condition of.operation, at least 99.9% of the' fuieltrods in the core would be expected: to avoid boiling transition.

The mrargih between calculatedl boiling transition (i.e., MCPR = 1-.00) and the MCPR SL is based on a detailed statistical procedure that considers the. uncertainties in monitoring the core operating state. One specific uhn6reaintyinIuded in: the SL is the uncertainty in the critical power correlation:

References'.2, 4, and 5 describe the methodology used in determining theMCPR SL.The SPCB critical power correlation is based on a practical test data. As long, s'the cOre, res raige of validity of the correlations (refer toSectioi assumed reacfor conditions..sed in. defining thelSl conservatism into the limit, b.cause: bounding:

hig:" and bounding flat Io-o" kpeaKgasmtibutions C number of rods.in boiling, tr~astiti6n.

These corier inh~erent accuracy of th'e.SP.C"co

..rrela'tio

..provi'd, of assurance that during sustaihne'd

&peration aktft would be no transition, boi ig i the core.4 , .41 (continued)

Revision 6:SUSQUEHANNA

-UNIT 1 TIS /B 2.0-3

9....BASES APPLICABLE SAFETY ANALYSES 2.1.1.2 MCPR (continued)

If boiling transition were to occur, there is reason t integrity of the fuel would fifot be Significant test data, accumulted by the, NRC and organizations indicate that the 'tra protect against cladding failure is a very'c66nserVal of the.data indicate .hat BWR if'ue"li canýs"u'rvive for of time in an environment of boiling tran'sition.

AREVA NP ATRIUM-10 fuel is: monitor.edusing thi Power Correlation.

The effects of chanhol- bwo" on included in the calculation' of the, M.PRkSL' Expli channel bow in the MCQR SL addresses, the con .c No. 90-02 entitled "Loss of Thermal.Margin Cause Bow.".PP.L.ev 6...

SLs o beliveý that t~he', private isition limritation to'iy:a'pproa dh.' Much an,. ent ne- eriod e.`PC'B; Crtical I MIRare,.expl icitly ci treatm6n..f erns. of NRýC Bulletin'd by Chatnel Box AM.Monitoring.

required, for compliance with the MCPR SL; is specified in LCO 3.2.2, Minimum Critical Power Ratio.2.1.1.3 Reactor Vessel Water Level During MODES 1 and 2 the reactor vessel water level. is re~quired to be above the top-,of the active fuel% t, provide. core cooling- capatijitý.

" With fuel in the reactor Vessel' during-peio ds vh'en"the rbenactoris Shut down, consideration must be.g'e!n towater level requiirem'ets .d'ue t.the effect of decay heat. if the er, evei s .'shoialdý dropý below th to'tp of the active irradiated fuel during thi speiod..the'abity to remo've dacay heat isreduced.

This r'dti cobo ng.cpabii.tycould.

eard to elevated cladding temperatuesand clad perforation an.. the. event that the water level becomes <-2/'3.oteoff;thedo6h6ight.

The reactor-vessel water level SL has been- es~bi shed at the 5f t ve irrad .ated fuel-to provide a .poi ht.ittcan be monitored and to also " provide adequate margin for effective action.(c6ntihued)

.k .;SUSQUEHANNA

-UNIT 1 TS / B 2.0-4 Revisibn 4,----------------------------------.:.

sx BASES .PPL Re,6v. 6 Reactor SLs L.ct the'"integrity of the fuel terilals to the environs.re operates Within the fu e'l r."eactor vessel**water lev.e'li'-.

d fuel in order to prevent adperforations.

SAFETY LIMITS The reactor core SLs are established.tolpro clad barrier to 'the release Of radioactive ma;SL 2.1.1.1 and SL 2.1.1.2 ensure t;a~tth.e c design criteria.

SL 2.1.1.3 ensures.thatte" is greater than the top of the actieie,.radia'e elevated clad temperatures and: resutbnt cc-APPLICABILITY SLs 2.1.1.1, 2.1.1.2, and 2.1.1.3 are applicable in alrMODES.SAFETY LIMIT Exceeding an SL may cause fuel damage and create a potential for VIOLATIONS radioactive limits. Therefore, it is required to inse6rt al. insertablie ;i.rods and restore compli ance with .the SLs within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The&2 hour Completion Time ensures that the operators take prompt reme:ial action and also ensures that the probability of an accident occurring during. this period is minimal.REFERENCES

1. 10 CFR 50, Appendix A, GDC 10.2. ANF-524. (P)(A), Revision 2,. Cnritical Power Meth.odology for Boiling Water Reactors," Syipplement 1 Revision 2 and Supplement 2, Novembýer l1990.3.' Deleted.4. EMF-2209(P)(A), "SPCGB Critical-.

owe r Co rrelation,." AREVA NP, [See Core'Operating Limits ReSpi-t for Revision LeVel].5. EMF-2ý158(P)(A), Revision 0 .e ation MethodBoiliJpm, einms. Po-wer. Corporation Methodology for Boihng. ateM R etors: ..Evaluatib.o and Validation of CASMO-4/Mi'oburB2, October 1q99.41.I -1,7 I 9 : ...K .,I: , ., , ; 5* I SUSQUEHANNA -UNIT 1 TS / B 2.0-5 Revsio 6,.."12.,. .. 4 BrE* : ..: -. ..- .. ..1: .ReV*'i§uSbEH AN'NA -UNIT 1 TS / B 2.0-6