ML15034A310
| ML15034A310 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/23/2015 |
| From: | Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15034A310 (26) | |
Text
Jan. 23, 2015 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2015-2824 USER INFORMATION:
GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TPANqMTTTAT, TNTORMATTOCTh TO: GERLACH*ROSEY M 01/23/2015 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.
TSB1 - TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 11/06/2014 ADD MANUAL TABLE OF CONTENTS DATE: 01/22/2015 CATEGORY: DOCUMENTS TYPE: TSB1
Jan. 23, 2015 Page 2 of 2 ID: TEXT 2.1.1 REMOVE: REV:5 ADD: REV: 6 CATEGORY: DOCUMENTS TYPE: TSB1 ID: TEXT LOES ADD: REV: 120 REMOVE: REV:119 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: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 01/22/2015 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 120 01/22/2015
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 23 07/02/2014
Title:
TABLE OF CONTENTS TEXT 2.1.1 6 01/22/2015
Title:
SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2.1.2 1 10/04/2007
Title:
SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM (RCS) PRESSURE S TEXT 3.0 3 08/20/2009
Title:
LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3. 1.1 1 04/18/2006
Title:
REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)
TEXT 3.1.2 0 11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 2 01/19/2009
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 4 01/30/2009
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 1 07/06/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 3 02/24/2014
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Report Date: 01/22/15 PagelI Page of of .88 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 1 04/18/2005
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1
Title:
2 02/24/2014 INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP a
(EOC-RPT) INSTRUMENTATION Report Date: 01/22/15 Page 22 of of 8 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 2 10/27/2008
Title:
INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION 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
Title:
0 REACTOR COOLANT SYSTEM (RCS) 11/15/2002 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 2 03/28/2013
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM
- HOT SHUTDOWN TEXT 3.4.9 1 03/28/2013
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM
- COLD SHUTDOWN 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 CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - OPERATING TEXT 3.5.2 0 11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 3 02/24/2014
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM RCIC SYSTEM TEXT 3.6.1.1 5 02/24/2014
Title:
PRIMARY CONTAINMENT TEXT 3.6.1.2 1 04/23/2008
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Reort ate 01/2/1 Page of Page 4 of 8 Report Date: 01/211/15
SSES MANUAL
.! Manual Name:
Manual
Title:
TSB1 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
Title:
11 11/06/2014 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 4 04/05/2010
Title:
PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ULTIMATE HEAT SINK (UHS)
TEXT 3.7.2 2 02/11/2009
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM TEXT 3.7.3 1 01/08/2010
Title:
PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.7.4 0 11/15/2002
Title:
PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 1 10/04/2007
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3. 7.6 2 04/23/2008
Title:
PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 3.7.7 1 10/04/2007
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.7.8 0 04/23/2008
Title:
PLANT SYSTEMS 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 Report Date: 01/22/15 Page6 Page 6 of of 8 a Report Date: 01/22/15
SSES MANUALJ Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 4 10/23/2013
Title:
ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 3 01/19/2009
Title:
ELECTRICAL POWER SYS=2EMS DC SOURCES - OPERATING TEXT 3.8.5 1 12/14/2006
Title:
ELECTRICAL POWER SYST'EMS DC SOURCES - SHUTDOWN TEXT 3.8.6 1 12/14/2006
Title:
ELECTRICAL POWER SYSTFEMS BATTERY CELL PARAMETERS TEXT 3.8.7 1 10/05/2005
Title:
ELECTRICAL POWER SYST'EMS DISTRIBUTION SYSTEMS - OPERATING TEXT 3.8.8 0 11/15/2002
Title:
ELECTRICAL POWER SYST2EMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/15/2002
Title:
REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 1 09/01/2010
Title:
REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.6 1 10/04/2007
Title:
REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Report Date: 01/22/15 Page7 Page 7 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 1 01/23/2008
Title:
SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 0 11/15/2002
Title:
SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 0 11/15/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN TEXT 3.10.4 0 11/15/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 0 11/15/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING TEXT 3.10.6 0 11/15/2002
Title:
SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 1 04/18/2006
Title:
SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 1 04/12/2006
Title:
SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Report Date: 01/22/15
?age88
?age of of 88 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 B3.1 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 Pages.*. hrough B 3.1-19 01 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 Revision 120 SUSQUEHANNA SUSQUEHANNA - UNIT- UNIT 11 TS B LOES-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 NT1 T OS3Rvso 2
-SU]QUEH".A NA -
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
-B3.4 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 S V I P I fLFO--5 B
- *M *V RAi'inin 192 I'*V V iV0*I, i i *V
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
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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
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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
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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 E A N*/ NT1T,OSl R........ 120 SIUSQOEPANNA - UNIT 1 SUQ TS / B LOES-1 0 We~i91onh 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 cracking,. the thermally caused.
cladding perforations signal a.%thr6shOld beyond which still'greater thermal stresses may cause gross, rather th6n: ~crenental,. claddj*.. detbriQration.
Therefore, the fuel cladding SL is defined wi'-h 'a margin to the condinio*s that Would produce onset of transition b6iling (i.e., MCPR.= 1.00). These condioons represent a significant de*aftu~e 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 .,4 lIMIT -I T / M 0 r) _I D *, i7,,
/ .1:A PPL Rev. 6-Reactor Core, S'Ls B 2.1.1 BASES BACKGROUND Operation above the boundary of the nucleate boi~ingýregime could of ef the ons6et
,
(Continued) result in. excessive cladding temnperature b ceoau 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 intoxidrio*h'ott:.,hd` fuel cladding to a structurally weaker form. Tills'w`a`ker fori mai (9S* itsihte*ti, resulting in an uncontrolled release of, activity to th-.ereactbr coolant":
APPLICABLE The fuel cladding must not sustain damage: as a result of normal SAFETY ANALYSES 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 wat*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-ft2 . For operation at. 6ft,,.ipre re:-Irlow'flows the fuel cladding integrity SL is established by a'hliftingl 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 that have a relatively high power arid 06t'enti'llV can64
'assemblies approach a A
critical heat flux condition.
contifiwed)',ýý.
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BASES Reactor ore&SLs B 2.1.1 A APPLICABLE 2.1.1.1 Fuel Cladding Intecqirity (continued).
SAFETY1 ANALYSES For the AREVA*NP ATRIuI*
- /-10:desiagn, the minimum bundle flow'is
> 28-x, 10 3 lb/hr. For theAlREVA NP ATRIUM-I.0 fuel desjigni the'.
coolant minimum bundle flo w arid maximum airea. 8ae s*cih thatthe.
mass flux is always > 0.25 b/hr-ft2. Full, scal'ditei. Fa lpower test
.10'1 ..
data taken from various AREVA NP-and:-GEfuel desigrns-a-t pressures "
from 14.7 psia to 1400 psia indica ..the fuelassemblrc Critica.l power at 0.25 x 106 lb/hr-ft2 is appro0cimat6ty .3.35 Mwt, At 23% R1rP, a.bundle power of approximately 3.3 56MW6'C166rresp.ond's.toa bundle radial peaking factor of approxim. ately 2.8, which :is significa.t ly-jhiher than 0 the expected peaking facto r. Thus, a THERMAL POWER lfimit of.
23% RTP for reactor presstures..< 557 psig is conservative and for .4 conditions of lesser powerVwVould remain conservative. " * " "
2.1.1.2 MCPR 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.
4 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
,-.aiu*-.: 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.
,.41 (continued)
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eactorCor*e SLs ..
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BASES APPLICABLE 2.1.1.2 MCPR (continued)
SAFETY ANALYSES If boiling transition were to occur, there is reason to beliveý that t~he',
integrity of the fuel would fifot be cor*tpromised.
Significant test data, accumulted by the, NRC and private organizations indicate that the use**,bfa boi*in'tra isition limritation to' protect against cladding failure is a very'c66nserVal iy:a'pproa dh.' Much of the.data indicate .hat BWR if'ue"li canýs"u'rvive for an,. ent ne- eriod of time in an environment of boiling tran'sition.
AREVA NP ATRIUM-10 fuel is: monitor.edusing thie.`PC'B; Crtical Power Correlation. The effects of chanhol- bwo"on I MIRare,.expl icitly included in the calculation' of the, M.PRkSL' Expli ci treatm6n..f channel bow in the MCQR SL addresses, the con .c erns. of NRýC Bulletin' No. 90-02 entitled "Loss of Thermal.Margin Cause d by Chatnel Box Bow.".
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'uet.
the effect of decay heat. if the*a er, evei s.'shoialdýdropý below th to'tp of the active irradiated fuel during thi speiod..the'abity to remo've .;k dacay heat isreduced. This r'dti on*in cobo ng.cpabii.tycould. eard to elevated cladding an.. temperatuesand clad perforation the. event that the water level becomes <-2/'3.oteoff;thedo6h6ight. The reactor
-vessel water level SL has been- es~bi shed at 5f the t ve irrad .ated fuel-to provide a .poiht.ittcan be monitored and to also "
provide adequate margin for effective action.
.
(c6ntihued)
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PPL Re,6v. 6 Reactor Coe*oSLs BASES .
SAFETY LIMITS The reactor core SLs are established.tolpro L.ct the'"integrity of the fuel clad barrier to 'the release Of radioactive ma;terilals to the environs.
SL 2.1.1.1 and SL 2.1.1.2 ensure t;a~tth.e c re operates Within the fu e'l design criteria. SL 2.1.1.3 ensures.thatte" r."eactor vessel**water lev.e'li'-.
is greater than the top of the actieie,.radia'e d fuel in order to prevent elevated clad temperatures and: resutbnt cc adperforations. : I ...
9
-APPLICABILITY SLs 2.1.1.1, 2.1.1.2, and 2.1.1.3 are applicable in alrMODES. I -1 SAFETY LIMIT VIOLATIONS Exceeding an SL may cause fuel damage and create a potential for radioactive rel'eases-inexceSs.ýofýýreg*6latory" limits. Therefore, it is K .,I:
- required to inse6rt al. insertablie c*ont ;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 sx the operators take prompt reme:ial action and also ensures that the , . , 41.
, ;5 probability of an accident occurring during. this period is minimal.
REFERENCES 1. 10 CFR 50, Appendix A, GDC 10. **:* I
- 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. ateMR etors: ..Evaluatib.o and Validation of CASMO-4/Mi'oburB2, October 1q99.
Revsio 6,.."12.
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