ML061230675
| ML061230675 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/24/2006 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML061230675 (26) | |
Text
Apr. 24, 2006 Page 1
of 2
MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-19951 USER INFORMATION:
GERLACH*ROSE M EMPL#:028401 CA#:
0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO:
GERLACH*ROSE M 04/24/2006 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.
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ATTENTION:
"REPLACE0 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: 04/18/2006 ADD MANUAL TABLE OF CONTENTS DATE: 04/21/2006 CATEGORY: DOCUMENTS TYPE: TSB1 Ao0)
Apr. 24, 2006 Page 2
of 2
ID:
TEXT 3.4.10 REMOVE:
REV:0 ADD:
REV: 1 CATEGORY:
ID:
TEXT REMOVE:
DOCUMENTS TYPE: TSB1 LOES REV:71 ADD:
REV: 72 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE.
UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 5 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.
x-SSES MANUAL Manual Name:
TSB*-
Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:
04/21/2006 Procedure Name Rev TEXT LOES 72
Title:
LIST OF EFFECTIVE SECTIONS Issue Date 04/21/2006 Change ID Change Number TEXT TOC
Title:
TABLE OF CONTENTS 9
04/18/2006 TEXT 2.1.1 2
Title:
SAFETY LIMITS (SLS) REACTOR TEXT 2.1.2 0
Title:
SAFETY LIMITS (SLS) REACTOR 04/18/2006 CORE SLS 11/15/2002 COOLANT SYSTEM (RCS)
PRESSURE SL TEXT 3.0 1
04/18/2005
Title:
LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3.1.1
Title:
REACTIVITY 1
CONTROL SYSTEMS 04/18/2006 SHUTDOWN MARGIN (SDM)
TEXT 3.1.2
Title:
REACTIVITY 0
11/15/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3
Title:
REACTIVITY TEXT 3.1.4
Title:
REACTIVITY TEXT 3.1.5
Title:
REACTIVITY 1
CONTROL SYSTEMS 2
CONTROL SYSTEMS 1
CONTROL SYSTEMS 07/06/2005 CONTROL ROD OPERABILITY 04/18/2006 CONTROL ROD SCRAM TIMES 07/06/2005 CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 2
04/18/2006
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8
Report Date: 04/21/06 Page 1 of 8
Report Date: 04/21/06
SS F.'
w-LM Manual Name:
TSB--
aanual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1. MANUAL-TEXT 3.1.7 1
08/30/'2005
Title:
- REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM-TEXT 3.1.8 1
10/19/2005
Title:
REACTIVITY CONTROL-SYSTEMS SCRAM DISCHARGE VOLUME. (SDV)
VENT AND DRAIN VALVES TEXT 3.2.1 1
04/18/2006
Title:
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR-HEAT GENERATION RATE (APLHGR)
TEXT 3.2.2 1
04/18/2006.
Title:
FQWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATZO (MCPR)
TEXT 3.2.3 0
11/1512002
Title:
POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)-
TEXT 3.2.4 2
04/12/2006
Title:
POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS'I" TEXT 3.3.1.1 Title :.INSTRUMENTATION TEXT 3.3.1.2
Title:
INSTRUMENTATION TEXT 3.3.2.1
Title:
INSTRUMENTATION TEXT 3.3.2.2
Title:
INSTRUMENTATION TEXT 3.3.3.1
Title:
INSTRUMENTATION TEXT 3.3.3.2
Title:
INSTRUMENTATION 3
04/12/2006 REACTOR PROTECTION SYSTEM (RPS)
INSTRUMENTATION 1
04/12/2006 SOURCE RANGE:MONITOR (SRM) INSTRUMENTATION 2
04/12/2006 CONTROL.ROD. BLOCKZ INSTRUMENTATION 0
11/15/2002 FEEDWATER - MAIN TURBINE HIGH WATER LEVEL-TRIP INSTRUMENTATION 3
04/12/2006 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION 1
04/18/2005 REMOTE SHUTDOWN_-SYSTEM Page2 of 8 Report Date: 04/21/06 Page 2
of 8 Report Date: 04/21/06
SSES. ?IU1VAt1
- M~anual Name:
TSB~ :7
-r
- iza!7, ; ~
Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT I MANUAL TEXT 3.3.4.1 0
11/15/2002
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION' PUMP TRIP' (EOC-RPT) INSTRUMEkTXT6ON 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
Title:
INSTRUMENTATION 2
07/06/2005 EMERGENCY CORE COOLING-SYSTEM (ECCS)- INSTRUMENTATION TEXT 3.3.5.2 0
11/1572002
Title:
INSTRUMENTATION REACTOR CORE ISOLATION COOLING (ACIC) SYSTEM INSTRUME TATION TEXT 3.3.6.1 1
11/09/2004-
Title:
INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION-INSTRUMENTATION 11.
L 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 TEXT 3.4.1
Title:
REACTOR COOLANT TEXT 3.4.2
Title:
REACTOR COOLANT TEXT 3.4.3
Title:
11/09/2004.
SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 0
11/15/2002.
CONTROL ROOM'.EMERGENCY OUTSIDE AIR'SUPPLY (CREOAS) SYSTEM 1
09/02/2004 LOSS-OF POWER (LOP) INSTRUMENTATION 0
11/15/2002.
REACTOR PROTECTION.SYSTEM (RPS) ELECTRIC POWER MONITORING 3
04/12/2006 SYSTEM (RCS) RECIRCULATION LOOPS OPERATING 0
11/15/2002 SYSTEM (RCS) JET PUMPS 1
01/16/2006 SYSTEM (RCS)
SAFETYIRELIEF VALVES (S/RVS) -
Pag 3
of 8
Reo Dt:0/10 Page 3 of 8
Report Date: 04/21/06
SSES'.
MANUAL Manual Name: TSB1 manual
Title:
TECHNICAL SPECIFICATION BASES'UNIT.1 MANUAL TEXT 3.4.4
Title:
REACTOR TEXT 3.4.5
Title:
REACTOR TEXT 3.4.6
Title:
REACTOR TEXT 3.4.7
Title:
REACTOR 0
11/15/2002 COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE 1
01/16/2006 COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 1
04/18/2005 COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION 1
04/18/2005 COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8
Title:
REACTOR COOLANT HOT SHUTDOWN 1
04/18/2005 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM TEXT 3.4.9
Title:
REACTOR COOLANT COLD SHUTDOWN 0
SYSTEM (RCS) 11/15/2002 RESIDUAL HEAT REMOVAL (RHR)
SHUTDOWN COOLING SYSTEM-_
TEXT 3.4.10 1
04/21/2006
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11
Title:
SYSTEM (RCS) 11/15/2002 REACTOR STEAM DOME PRESSURE TEXT 3.5.1 2
01/16/2006
Title:
EMERGENCY CORE COOLING-SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM ECCS -
OPERATING COOLING (RCIC)
TEXT 3.5.2 0
11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS-(ECCS)
AND SYSTEM ECCS -
SHUTDOWN REACTOR CORE ISOLATION COOLING (RCIC)
TEXT 3.5.3 1
04/18/2005
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM COOLING (RCIC)
TEXT 3.6.1.1 0
11/15/2002 Titles CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Page4 of 8 Report Date: 04/21/06 Page 4 of 8 Report Date: 04/21/06
SSES.ZA1ATL s Manual Name:
TSB-3 Manual
Title:
TECHNICAL SPECIFICATION.BASES-UNIT I MANUAL r.
TEXT 3.6.1.2
Title:
CONTAINMENT 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 0
11/15f2002 SYSTEMS PRIMARY CONTAINMENT-AIR LOCK 3
12/08/2005.
SYSTEMS PRIMARY'CONTAINMENT ISOLATION VALVES (PCIVS) 0 11/15/2002 SYSTEMS CONTAINMENT PRESSURE 1
10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE' 0
11/15/2002 SYSTEMS SUPPRESSIONICHAMBER-TO-DRYWELL VACUUM-BREAKERS 0
11/15/2002 :
SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0
11/15/2002 SYSTEMS SUPPRESSION POOL WATER:LEVEL 1
01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)YSUPPRESSION POOL COOLING 0
11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY 1
04/18(2.005:
SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1
04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM 0
11/15/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Page5 of 8 Report Date: 04/21/06 Page 5 of 8 Report Date: 04/21/06
SSES MRMtAL Manual Name: TSBi-.
Manual
Title:
TECHNICAL SPECIFICATION BASES.UNXT.1 MANUAL TEXT 3.6.4.1 5
03116/2006
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 2
01/03/2005
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.6.4.3 3
10/24/2Q05
Title:
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT.(SGT)
SYSTEM TEXT 3.7.1
Title:
PLANT SYSTEMS ULTIMATE HEAT 0
11/15/2002 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 TEXT 3.8.1 1
11/09/2004 SYSTEMS EMERGENCY SERVICE.WATER (ESW) SYSTEM 0
11/15120D2 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR-SUPPLY (CREOAS) SYSTEM 0
11/15/2002 SYSTEMS CONTROL ROOM-FLOOR COOLING SYSTEM 0
11/15/2002 SYSTEMS MAIN.3ONDENSERt.OFFGAS-.
1 01/17/2005 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0
11/15/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 4
04/18/2006
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING TEXT 3.8.2 0
11/1512002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN ae of Report Date 04/21/06_
Page 6 of 8
Report Date: 04/21/06
a,,
6SESBMANUA 1
I iManual Name: TSB+/-
Manual
Title:
TECHNICAL SPECIFICATION BASES:UNIT 1 MANUAL TEXT 3.8.3
Title:
ELECTRICAL 0
POWER SYSTEMS 11/15D2002-DIESEL FUJEL -OIL, LUBE OIL, AND STARTING AIR 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 C TEXT 3.9.5
Title:
REFUELING C TEXT 3.9.6
Title:
REFUELING C 0
11/15/2002 POWER SYSTEMS DC SOURCES -
OPERATING-0 11/15/2002 POWER SYSTEMS DC SOURCES -
SHUTDOWN 0
11/15/2002 POWER SYSTEMS BATTERY CELL PARAMETERS 1
10/05/2005 POWER SYSTEMS DISTRIBUTION:SYSTEMS OPERATING 0
11/15/2002 POWER SYSTEMS DISTRIBUTION SYSTEMS SHUTDOWN 0
11/15/2002 REFUELING EQUIPMENT INTERLOCKS
)PERATIONS OPERATIONS
)PERATIONS OPERATIONS
)PERATIONS
)PERATIONS I.
0 11/15/2002 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 0
11/15/2002 REACTOR PRESSURE VESSEL (RPV)
WATER LEVEL Page7 of 8
Report Date: 04/21/06 Page 7 of 8 Report Date: 04 /21/06
SSES MANUAL Manual Name: TSBi-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT.1 MANUAL
-:1 e --
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 0
11/15/2002 INSERVICE LEAK AND-HYDROSTATIC TESTING OPERATION 0
111i5/2002 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 Page8 of 8 Report Date: 04/21/06 Page 8 of 8
Report Date: 04/21/06
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC Table of Contents 9
B 2.0 SAFETY LIMITS BASES Page B 2.0-1 0
Page TS/B2.0-2 3
Page TS/B2.0-3 4.
Pages TS I B 2.0-4 and TS B 2.0-5
,3 PageTS/B2.0-6 1
Pages B 2.0-7 through B 2.0-9 0
B 3.0 LCO AND SR APPLICABILITY BASES,
Pages B 3.0-1 through B 3.0-4 0
Pages TS / B 3.0-5 through TS I B 3.0-7 1
Pages TS / B 3.0-8 through TS-/ B 3.0-9 2
Pages TS I B 3.0-10 through TS I 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
PagesTS/B3.1-6and TS/1 3.1-7 2
PagesB 3.1-8 through B.1-13 0
PageTS/B3.1-14 1
Pages B 3.1-15 through B 3.1-22 0
PageTS/B3.1-23 1
Pages B 3.i-24 through B 3.1-27 0
Page, TS / B 3.1-28 2
PageTS / B 3.1-29
-1 Pages B 3.1-30 through B 3.1 -
0 Pages TS / B 3.3-34 through TS / B 3.3-36 1
Pages TS / B 3.1-37 and TS / B 3.1-38 2
Pages B 3.1-39 through B 3.1-44 0
Page TS / B 3.1-45 1
Pages B 3.1-46 and B 3.1-47 0
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 1
B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 1
Pages TS / B 3.2-2 through TS / B 3.2-6 2
SUSQUEHANNA-UNITI TS I B LOES-I Revision 72 SUSQUEHANNA - UNIT 1 TS / B LOES-1 Revision 72
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page B 3.2-7 0
Pages TS / B 3.2-8 and TS I B 3.2-9 2
Page TS / B 3.2.10 1
Page TS / B 3.2-11 2
Page B 3.2-12 0
Page TS / B 3.2-13 2
Pages B 3.2-14 and B 3.2-15 0
Page TS / B 3.2-16 2
Page B 3.2-17 0
Page TS / B 3.2-18 1
Page TS / B 3.2-19 4
B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS I B 3.3-4 1
PageTS/B3.3-5 2
PageTS/B3.3-6 1
Page TS / B 3.3-7 3
Page TS / B 3.3-7a 0
Pages TS / B 3.3-8 through TS / B 3.3-12 3
Pages TS / B 3.3-12a through TS / B 3.3-12c 0
Page TS / B 3.3-13 1
Page TS I B 3.3-14 3
Pages TS I B 3.3-15 and TS / B 3.3-16 1
Pages TS / B 3.3-17 and TS / B 3.3-18 3
Pages TS / B 3.3-19 1
Pages TS I B 3.3-20 through TS / B 3.3-22 2
Page TS / B 3.3-22a 0
Pages 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
Pages TS / B 3.3-25 and TS I B 3.3-26 2
Page TS I B 3.3-27 1
Pages TS / B 3.3-28 through TS / B 3.3-30 3
Page TS / B 3.3-30a 0
Page TSlB3.3-31 3
Page TS / B 3.3-32 5
Pages TS I B 3.3-32a and TS / B 3.3-32b 0
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 I B 3.3-36 2
Pages TS / B 3.3-37 through TS / B 3.3-43 1
Page TS / B 3.3-44 3
SUSQUEHANNA-UNIT I TS I B LOES-2 Revision 72 SUSQUEHANNA - UNIT 1 TS / B LOES-2 Revision 72
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS / B 3.3-45 through TS / B 3.3-49 2
Page TS / B 3.3-50 3
Page TS / B 3.3-51 2
Pages TS / B 3.3-52 and TS / B 3.3-53 1
Page TS I B 3.3-54 3
Pages B 3.3-55 through B 3.3-63 0
Pages TS J B 3.3-64 and TS / B 3.3-65 2
Page TS / B 3.3-66 4
Page TS I B 3.3-67 3
Pages TS I B 3.3-68 and TS I B 3.3-69 4
Pages TS / B 3.3-70 and TS / B 3.3-71 3
Pages TS / 3.3-72 through TS / 3.3-75 2
Page TS I B 3.3-75a 4
Page TS / B 3.3-75b 5
Page TS I B 3.3-75c 4
Pages B 3.3-76 through 3.3-77 0
Page TS / B 3.3-78 1
Pages B 3.3-79 through B 3.3-89 0
Page TS / B 3.3-90 1
Page B 3.3-91 0
Pages TS / B 3.3-92 through TS / B 3.3-100 1
Pages B 3.3-101 through B 3.3-103 0
Page TS / B 3.3-104 1
Pages B 3.3-105 and B 3.3-106 0
Page TS /B3.3-107 1
Page B 3.3-108 0
Page TS / B 3.3-109 1
Pages B 3.3-110 and 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 2
Page TS / B 3.3-117 1
Pages B 3.3-118 through 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 B 3.3-125 0
Pages TS / B 3.3-126 and TS / B 3.3-127 1
Pages B 3.3-128 through B 3.3-130 0
Page TS / B 3.3-131 1
Pages B 3.3-132 through B 3.3-137 0
SUSQUEHANNA - UNIT 1SUSQUEHANNA
- UNIT I
TS / B LOES-3 Revision 72 TS / B LOES-3 Revision 72
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page TS l B 3.3-138 1
Pages B 3.3-139 through B 3.3-149 0
Pages TS / B 3.3-150 through TS I B 3.3-162 1
Page TS I B 3.3-163 2
Pages TS I B 3.3-164 through TS I B 3.3-177 1
Pages TS / B 3.3-178 and TS / B 3.3-179 2
Pages TS / B 3.3-179a and TS I B 3.3-179b 2
Page TS I B 3.3-179c 0
Page TS / B 3.3-180 1
Page TS / B 3.3-181 2
Pages TS / B 3.3-182 through TS / B 3.3-186 1
Pages TS I B 3.3-187 and TS / B 3.3-188 2
Pages TS I B 3.3-189 through TS I B 3.3-191 1
Pages B 3.3-192 through B 3.3-204 0
Page TS / B 3.3-205 1
Pages B 3.3-206 through B 3.3-219 0
B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and 8 3.4-2 0
Pages TS / B 3.4-3 and Page TS / B 3.4-4 4
Pages TS I B 3.4-5 through TS / B 3.4-9 2
Pages B 3.4-10 through B 3.4-14 0
Page TS I B 3.4-15 1
Pages TS / B 3.416 through TS I 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
Pages B 3.4-30 and B 3.4-31 0
Page TS I B 3.4-32 1
Pages B 3.4-33 through B 3.4-36 0
Page TS / B 3.4-37 1
Pages B 3.4-38 through B 3.4-40 0
Page TS I B 3.4-41 1
Pages B 3.4-42 through B 3.4-48 0
Page TS I B 3.4-49 3
Page TS / B 3.4-50 1
PageTS/B3.4-51 3
Pages TS / B 3.4-52 and TS / B 3.4-53 1
Pages TS / B 3.4-54 and TS / B 3.4-55 2
Page TS / B 3.4-56 1
Page TS / B 3.4-57 3
Pages TS / B 3.4-58 through TS I B 3.4-60 1
SUSQUEHANNA - UNIT I TS I B LOES-4 Revision 72 SUSQUEHANNA - UNIT I TS I B LOES4 Revision 72
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
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SUSQUEHANNA-UNIT I TS/BLOES-5 Revision 72 SUSQUEHANNA - UNIT I TS / B LOES-5 Revision 72
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
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TSB1 tex LOES O4m720o6 SUSQUEHANNA - UNIT 1SUSQUEHANNA
- UNIT I
TS I B LOES-7 Revision 72 TS I B LOES-7 Revision 72
PPL Rev. 1 RCS P/T Limits B 3.4.10 B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.10 RCS Pressure and Temperature (PIT) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.
This Specification contains P/T limit curves for heatup, cooldown, and inservice leakage and hydrostatic testing, and limits for the maximum rate of change of reactor coolant temperature. The heatup curve provides limits for both heatup and criticality.
Each P/T limit curve defines an acceptable region for normal operation.
The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.
The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel is the component most subject to brittle failure.
Therefore, the LCO limits apply mainly to the vessel.
10 CFR 50, Appendix G (Ref. 1), requires the establishment of PIT limits for material fracture toughness requirements of the RCPB materials.
Reference I requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests. It mandates the use of the ASME Code, Section Xl, Appendix G (Ref. 2).
The actual shift in the RTNDT of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with ASTM E 185 (Ref. 3) and Appendix H of 10 CFR 50 (Ref. 4). The operating PIT limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of RG 1.99, "Radiation Embrittlement of Reactor Vessel Materials" (Ref. 5). The calculations to determine neutron fluence will be developed using the BWRVIP RAMA code methodology, which is NRC approved and meets the intent of RG 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" (Ref. 11).
See FSAR Section 4.1.4.5 for determining fluence (Ref. 12).
(continued)
SUSQUEHANNA-UNIT 1 TS / B 3.4-49 Revision 3
PPL Rev. I RCS P/T Limits B 3.4.10 BASES BACKGROUND (continued)
The P/T limit curves are composite curves established by superimposing limits derived from stress analyses of those portions of the reactor vessel and head that are the most restrictive. At any specific pressure, temperature, and temperature rate of change, one location within the reactor vessel will dictate the most restrictive limit. Across the span of the P/T limit curves, different locations are more restrictive, and, thus, the curves are composites of the most restrictive regions.
The heatup curve used to develop the P/T limit curve composite represents a different set of restrictions than the cooldown curve used to develop the P/T limit curve composite because the directions of the thermal gradients through the-vessel wall are reversed. The thermal gradient reversal alters the location of the tensile stress between the outer and inner walls.
The criticality limits include the Reference 1 requirement that they be at least 400F above the heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.
The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident. In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components.
ASME Code, Section Xl, Appendix E (Ref. 6), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.
APPLICABLE SAFETY ANALYSES The P/T limits are not derived from Design Basis Accident (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed.
Reference 7 establishes the methodology for determining the P/T limits.
Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.
RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement (Ref. 8).
I (continued)
SUSQUEHANNA -UNIT 1 TS / B 3.4-50 Revision 1
PPL Rev. I RCS PIT Limits B 3.4.10 BASES APPLICABLE The Effective Full Power Years (EFPY) shown on the curves are SAFETY approximations of the ratio of the energy that has been and is anticipated ANALYSES to be generated in a year to the energy that could have been generated if (continued) the unit ran at original thermal power rating of 3293 MWT for the entire year. These values are based on fluence limits that are not to be exceeded.
LCO The elements of this LCO are:
- a. RCS pressure and temperature are to the right of the applicable curves specified in Figures 3.4.10-1 through 3.4.10-3 and within the applicable heat-up or cool down rate specified in SR 3.4.10.1 during RCS heatup, cooldown, and inservice leak and hydrostatic testing;
- b. The temperature difference between the reactor vessel bottom head coolant and the reactor pressure vessel (RPV) coolant is < 1450F during recirculation pump startup, and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow;
- c. The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is < 500F during recirculation pump startup, and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow;
- d. RCS pressure and temperature are to the right of the criticality limits specified in Figure 3.4.10-3 prior to achieving criticality; and
- e. The reactor vessel flange and the head flange temperatures are 2 700F when tensioning the reactor vessel head bolting studs.
These limits define allowable operating regions and permit a large number of operating cycles while also providing a wide margin to nonductile failure.
The P/T limit composite curves are calculated using the worst case of material properties, stresses, and temperature change rates anticipated under all heatup and cooldown conditions. The design calculations account for the reactor coolant fluid temperature impact on the inner wall of the vessel and the temperature gradients through the vessel wall.
Because these fluid temperatures drive the vessel wall temperature gradient, monitoring reactor coolant temperature provides a conservative method of ensuring the P/T limits are not exceeded. Proper monitoring of vessel temperatures to assure compliance with brittle fracture temperature limits and vessel thermal stress limits during normal heatup and cooldown, and during inservice leakage and hydrostatic testing, is established in PPL Calculation EC-062-0573 (Ref. 9). For P/T curves A, B, and C, the bottom head drain line coolant temperature should be monitored and maintained to the right of the most limiting curve.
(continued)
_UQEAN NTIT/34-1Rvso SUSQUEHANNA - UNIT I TS /B 3.4-51 Revision 3
PPL Rev. I RCS P/T Limits B 3.4.10 BASES LCO (continued)
Curve A must be used for inservice leakage and hydrostatic testing.
Curve A is based on pressure stresses only. During inservice leakage and hydrostatic testing, thermal stresses are assumed to be insignificant.
Therefore, heatup and cooldown rates are limited to 200F in a one-hour period when using Curve A to ensure minimal thermal stresses. The recirculation loop suction line temperatures should be monitored to determine the temperature change rate.
Curves B and C are to be used for non-nuclear and nuclear heatup and cooldown, respectively. Heatup and cooldown rates are limited to 100OF in a one-hour period when using Curves B and C. This limits the thermal gradient through the vessel wall, which is used to calculate the thermal stresses in the vessel wall. Thus, the LCO for the rate of coolant temperature change limits the thermal stresses and ensures the validity of the PIT curves. The vessel beltline fracture analysis assumes a 100°F/hr coolant heatup or cooldown rate in the beltline area. The 100OF limit in a one-hour period applies to the coolant in the beltline region, and takes into account the thermal inertia of the vessel wall. Steam dome saturation temperature (TsAT), as derived from steam dome pressure, should be monitored to determine the beltline temperature change rate at temperatures above 212 0F. At temperatures below 212 0F, the recirculation loop suction line temperatures should be monitored.
Violation of the limits places the reactor vessel outside of the bounds of the stress analyses and can increase stresses in other RCS components.
The consequences depend on several factors, as follows:
- a. The severity of the departure from the allowable operating pressure temperature regime or the severity of the rate of change of temperature;
- b. The length of time the limits were violated (longer violations allow the temperature gradient in the thick vessel walls to become more pronounced); and
- c. The existences, sizes, and orientations of flaws in the vessel material.
APPLICABILITY The potential for violating a P/T limit exists at all times. For example, P/T limit violations could result from ambient temperature conditions that result in the reactor vessel metal temperature being less than the minimum allowed temperature for boltup. Therefore, this LCO is applicable even when fuel is not loaded in the core.
(continued)
SUSQUEHANNA - UNIT 1 TS / B3.452 Revision I
PPL Rev. 1 RCS P/T Limits B 3.4.10 BASES (continued)
ACTIONS A.1 and A.2 Operation outside the P/T limits while in MODES 1, 2, and 3 must be corrected so that the RCPB is returned to a condition that has been verified by stress analyses.
The 30 minute Completion Time reflects the urgency of restoring the parameters to within the analyzed range. Most violations will not be severe, and the activity can be accomplished in this time in a controlled manner.
Besides restoring operation within limits, an evaluation is required to determine if RCS operation can continue. The evaluation must verify the RCPB integrity remains acceptable and must be completed if continued operation is desired. Several methods may be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, or inspection of the components.
ASME Code, Section Xl, Appendix E (Ref. 6), may be used to support the evaluation. However, its use is restricted to evaluation of the vessel beltline.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable to accomplish the evaluation of a mild violation. More severe violations may require special, event specific stress analyses or inspections. A favorable evaluation must be completed if continued operation is desired.
Condition A is modified by a Note requiring Required Action A 2 be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action A.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
B.1 and B.2 If a Required Action and associated Completion Time of Condition A are not met, the plant must be placed in a lower MODE because either the RCS remained in an unacceptable P/T region for an extended period of increased stress, or a sufficiently severe event caused entry into an unacceptable region. Either possibility indicates a need for more careful examination of the event, best accomplished with the RCS at reduced pressure and temperature. With the reduced pressure and temperature conditions, the possibility of propagation of undetected flaws is decreased.
(continued)
SUSQUEHANNA - UNIT I TS /B 3.453 Revision 1
PPL Rev. I
. RCS P/T Limits B 3.4.10 BASES ACTIONS B.1 and B.2 (continued)
Pressure and temperature are reduced by placing the plant in 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 in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1 and C.2 Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified by stress analyses. The Required Action must be initiated without delay and continued until the limits are restored.
Besides restoring the P/T limit parameters to within limits, an evaluation is required to determine if RCS operation is allowed. This evaluation must verify that the RCPB integrity is acceptable and must be completed before approaching criticality or heating up to > 2000F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components. ASME Code, Section Xl, Appendix E (Ref. 6), may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.
SURVEILLANCE SR 3.4.10.1 REQUIREMENTS Verification that operation is within limits (i.e., to the right of the applicable curves in Figures 3.4.10-1 through 3.4.10-3) is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limits are specified in hourly increments, 30 minutes permits a reasonable time for assessment and correction of minor deviations.
Surveillance for heatup, cooldown, or inservice leakage and hydrostatic testing may be discontinued when the criteria given in the relevant plant procedure for ending the activity are satisfied.
This SR has been modified with a Note that requires this Surveillance to be performed only during system heatup and cooldown operations and inservice leakage and hydrostatic testing.
(continued)
SUSQUEHANNA - UNIT I TS /B 3.4-54 Revision 2
PPL Rev. I RCS P/T Limits B 3.4.10 BASES SURVEILLANCE REQUIREMENTS SR 3.4.10.1 (continued)
Notes to the acceptance criteria for heatup and cooldown rates ensure that more restrictive limits are applicable when the P/T limits associated with hydrostatic and inservice testing are being applied.
SR 3.4.10.2 A separate limit is used when the reactor is approaching criticality.
Consequently, the RCS pressure and temperature must be verified within the appropriate limits (i.e., to the right of the criticality curve in Figure 3.4.10-3) before withdrawing control rods that will make the reactor critical.
Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of reactor criticality. Although no Surveillance Frequency is specified, the requirements of SR 3.4.10.2 must be met at all times when the reactor is critical.
SR 3.4.10.3 and SR 3.4.10.4 Differential temperatures within the applicable limits ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances. In addition, compliance with these limits ensures that the assumptions of the analysis for the startup of an idle recirculation loop (Ref. 10) are satisfied.
Performing the Surveillance within 15 minutes before starting the idle recirculation pump provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start.
An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 is to compare the temperatures of the operating recirculation loop and the idle loop. If both loops are idle, compare the temperature difference between the reactor coolant within the idle loop to be started and coolant in the reactor vessel.
(continued)
SUSQUEHANNA - UNIT 1 TS /B 3.455 Revision 2
PPL Rev. I RCS P/T Umits B 3.4.10 BASES REUVIRLEMNTS SR 3.4.10.3 and SR 3.4.10.4 (continued)
SR 3.4.10.3 has been modified by a Note that requires the Surveillance to be performed only in MODES 1, 2, 3, and 4. In MODE 5, the overall stress on limiting components is lower. Therefore, AT limits are not required. The Note also states the SR is only required to be met during a recirculation pump start-up, because this is when the stresses occur.
SR 3.4.10.5 and SR 3.4.10.6 Differential temperatures within the applicable limits ensure that thermal stresses resulting from increases in THERMAL POWER or recirculation loop flow during single recirculation loop operation will not exceed design allowances. Performing the Surveillance within 15 minutes before beginning such an increase in power or flow rate provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the change in operation.
An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.6 is to compare the temperatures of the operating recirculation loop and the idle loop.
Plant specific startup test data has determined that the bottom head is not subject to temperature stratification at power levels > 30% of RTP and with single loop flow rate 2 21,320 gpm (50% of rated loop flow).
Therefore, SR 3.4.10.5 and SR 3.4.10.6 have been modified by a Note that requires the Surveillance to be met only under these conditions. The Note for SR 3.4.10.6 further limits the requirement for this Surveillance to exclude comparison of the idle loop temperature if the idle loop is isolated from the RPV since the water in the loop cannot be introduced into the remainder of the Reactor Coolant System.
SR 3.4.10.7. SR 3.4.10.8. and SR 3.4.10.9 Limits on the reactor vessel flange and head flange temperatures are generally bounded by the other P/T limits during system heatup and cooldown. However, operations approaching MODE 4 from MODE 5 and in MODE 4 with RCS temperature less than or equal to certain specified values require assurance that these temperatures meet the LCO limits.
(continued)
SUSQUEHANNA - UNIT I TS / B 3.4-56 Revision 1
PPL Rev. 1 RCS P/T Limits B 3.4.10 BASES REQUIREMENTS SR 3.4.10.7. SR 3.4.10.8. and SR 3.4.10.9 (continued)
The flange temperatures must be verified to be above the limits 30 minutes before and while tensioning the vessel head bolting studs to ensure that once the head is tensioned the limits are satisfied. When in MODE 4 with RCS temperature < 800F, 30 minute checks of the flange temperatures are required because of the reduced margin to the limits.
When in MODE 4 with RCS temperature < 1 00F, monitoring of the flange temperature is required every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure the temperature is within the specified limits.
The 30 minute Frequency reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature limits could be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rate of temperature change possible at these temperatures.
REFERENCES
- 2. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix G.
- 3. ASTM E 185-73.
- 5. Regulatory Guide 1.99, Revision 2, May 1988.
- 6. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.
- 7. NEDO-21778-A, December 1978.
- 8. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
- 9. PPL Calculation EC-062-0573, "Study to Support the Bases Section of Technical Specification 3.4.10."
- 10. FSAR, Section 15.4.4.
- 11. Regulatory Guide 1.190, March 2001.
- 12. FSAR, Section 4.1.4.5.
SUSQUEHANNA - UNIT 1 TS / B 3.4-57 Revision 3