ML062290281
| ML062290281 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/09/2006 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 028401 | |
| Download: ML062290281 (25) | |
Text
Aug.
09, 2006 Page 1
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MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-34054 USER INFORMATION:
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0363 Address: NUCSA2 Phone#:
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TO:
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THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU.
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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: 06/20/2006 ADD MANUAL TABLE OF CONTENTS DATE: 08/08/2006 CATEGORY: DOCUMENTS TYPE: TSB1
Aug.
09, 2006 Page 2
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ID:
TEXT 3.6.4.1 REMOVE:
REV:5 ADD:
REV: 6 CATEGORY:
ID:
TEXT REMOVE:
DOCUMENTS TYPE: TSBI LOES REV:75 ADD:
REV: 76 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.
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FOR ELECTRONIC MANUAL
- USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
SSES MANUAL Manual Name :
TSBI-
"¶anual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:
08/08/2006 Procedure Name Rev TEXT LOES 76
Title:
LIST OF EFFECTIVE SECTIONS Issue Date 08/08/2006 Chimnge ID Change Number TEXT TOC
Title:
TABLE OF CONTENTS 10 06/13/2006 TEXT 2.1.1 2
Title:
SAFETY LIMITS (SLS)
REACTOR 04/18/2006 CORE SLS TEXT 2.1.2 0
11/15/2002
Title:
SAFETY LIMITS (SLS)
PRESSURE SL TEXT 3.0 1
04/18/2005
Title:
LIMITING CONDITION FOR OPERATION-(LCO)'APPLICABILITY TEXT 3.1.1
Title:
REACTIVITY TEXT 3.1.2
Title:
REACTIVITY 1
CONTROL SYSTEMS 0
CONTROL SYSTEMS
'04718/2006 SHUTDOWN MARGIN (SDM) 11/15/2002 REACTIVITY ANOMALIES TEXT 3.1.3 1
07/06/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4
Title:
REACTIVITY TEXT 3.1.5
Title:
REACTIVITY TEXT 3.1.6
Title:
REACTIVITY 2
04/18/2006 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES 1
07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 2
CONTROL SYSTEMS 04/18/2006 ROD PATTERN CONTROL Page 1 of 8
Report Date: 08/08/06 Page 1 of 8
Report Date: 08/08/06
SSES MAUJAL Manual Name:
TSBt-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL 4
TEXT 3.1.7
Title:
REACTIVITY CONTROL TEXT 3.1.8
Title:
REACTIVITY CONTROL 1
08/30/2005 SYSTEMS STANDBY LIQUID CONTROL (SLC)
SYSTEM 1
10/-19/2005 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
Title:
POWER DISTRIBUTION
.i 04/18/2006 LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
TEXT 3.2.3 0
11/15/2002
Title:
POWER DISTRIBUTION, LIMITS LINEAR _IEAT GENERATION RATE (LHGR)
TEXT 3.2.4 2
04/12/2006
Title:
POWER DISTRIBUTION LIMITS AVERAGZ POWER RANGE MONITOR (APRM)
GAIN AND SETPOINTS
(,-/I TEXT 3.3.1.1
Title:
INSTRUMENTATION 3
04/12/2006 REACTOR PROTECTION SYSTEM (RPS)
INSTRUtxENTATION TEXT 3.3.1.2 1
04/12/2006
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1
Title:
INSTRUMENTATION TEXT 3.3.2.2
Title:
INSTRUMENTATION TEXT 3.3.3.1
Title:
INSTRUMENTATION 2
04/12/2006 CONTROL ROD BLOCK iNSTRU!4ENTATION 0
11/15/2002 FEEDWATER -
MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION 5
06/13/2006 POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION TEXT 3.3.3.2 1
04/18/2005
Title:
INSTRUMENTATION REMOTE SHOITDOWN SYSTEM Report Date: 08/08/06 Page 2 of 8
SSESrM MNUTAL
- Manual Name:
TSBT*
Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.1 0
11/15/2002
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)
INSTRUMENTATION 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 TEXT 3.3.5.2
Title:
INSTRUMENTATION TEXT 3.3.6.1
Title:
INSTRUMENTATION TEXT 3.3.6.2
Title:
INSTRUMENTATION TEXT 3.3.7.1
Title:
INSTRUMENTATION INSTRUMENTATION TEXT 3.3.8.1
Title:
INSTRUMENTATION TEXT 3.3.8.2 2
07/06/2005 EMERGENCY CORE COOLING SYSTEMW--(ECCS)' -INSTRUMENTATION
.0 11/15/2002.
REACTOR CORE ISOLATION COOLINGi (RCIC) iSYSTEM.dIISTRUMENTATION 1
11/09/200A. -.1 PRIMARY CONTAINMENT ISOLATION.INSTRUMENTATION 1
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
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWERMONITORING TEXT 3.4.1 3
04/12/2006
Title:
RECIRCULATION LOOPS OPERATING TEXT 3.4.2 0
11/15/2002
Title:
JET PUMPS TEXT 3.4.3 1
01/16/2006
Title:
SAFETY/RELIEF VALVES (SZRVS)
Page 3 of 8
Report Date:' 08/08/06
SSES MAL-UAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.4
Title:
REACTOR-COOLANT TEXT 3.4.5
Title:
11/15/2002 SYSTEM (RCS)
RCS OPERATIONAL LEAFAGE 1
01/16/2006 SYSTEM (RCS)
RCS PRESSURE ISOLATION VALVE (PIV)
LEAKAGE TEXT 3.4.6 1
04/18/2005
Title:
RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 1
04/18/2005
Title:
RCS SPECIFIC ACTIVITY TEXT 3.4.8
Title:
REACTOR COOLANT HOT SHUTDOWN TEXT 3.4.9
Title:
REACTOR COOLANT COLD-SHUTDOWN TEXT 3.4.10
Title:
REACTOR COOLANT TEXT 3.4.11
Title:
REACTOR COOLANT TEXT 3.5.1 1
04/18/2005 SYSTEM (RCS)
SHUTDOWN COOLING SYSTEM 0
SYSTEM (RCS) 11/15/2002 RESIDUAL HEAT REMOVAL (RHR)
SHUTDOWN COOLING SYSTEM 2
05/10/2006 SYSTEM (RCS)
RCS PRESSURE AND TEMPERATURE (P/T) LIMITS 0
11/15/2002 SYSTEM (RCS)
REACTOR STEAM DOME PRESSURE 2
01/16/2006
Title:
EMERGENCY :CORE COOLING SYSTEMS (ECCS)
AND:REACTOR CORE ISOLATION SYSTEM ECCS -
OPERATING TEXT 3.5.2 0
11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND'REACTOR CORE ISOLATION SYSTEM ECCS -
SHUTDOWN TEXT 3.5.3 1
04/18/2005
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM TEXT 3.6.1.1 0
11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT COOLING (RCIC)
COOLING (RCIC)
COOLING (RCIC)
Page 4 of 8
Report Date: 08/08/06
SSES MIR.!ANUAL Manual Name:
TSB!-
Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1I MANUAL TEXT 3.6.1.2 0
11/15/2002,
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK TEXT 3.6.1.3 3
12/08/2005
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS).
TEXT 3.6.1.4 0
11/15/2002
Title:
CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5
.1 10/05/2005
Title:
CONTAINMENT SYSTEMS DRYWELL AIR TEMPEFRTURE TEXT 3.6.1.6 0
11/15/2002
Title:
CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 0
11/15/2002
~,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 0
11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Page 5 of 8 Report Date: 08/08/06
SSES *FAIUAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1,MANUAL TEXT 3.6.4.1 6
08/08/2006
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
10/24/2005
Title:
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT)
SYSTEM TEXT 3.7.1
Title:
PLANT ULTIMA 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
.0 11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)
SYSTEM AND THE
.TE HEAT SINK (UHS) 1 11/09/2004 SYSTEMS EMERGENCT.-SERVICE WATER (ESW)
SYSTEM 0
11/15/20.02 SYSTEMS CONTROL'ROOM EM.ERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM 0
11/15/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 0
11/15/2002 SYSTEMS MAIN.-CONDENSER 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
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN Pe 6 of 8R otDe 0/
0 Paq Report Date: 08/08/06
AS SES,"..MIWAL
.4 Manual Name :
TSBT-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 J
Title:
ELECTRICAL TEXT 3.9.1
Title:
REFUELING C TEXT 3.9.2
Title:
REFUELING C TEXT 3.9.3
Title:
REFUELING C 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 DIESEL FUEL OIL, LUBE OIL,.AND STARTINGAIR 1
POWER SYSTEMS 0
POWER SYSTEMS 06/13/2006 DC-SOURCES -
OPERATING 11/15/2002 DC SOURCES -
SHUTDO11N'-*1"
.0 11/15/2002 POWER SYSTEMS BATTERY CELL PARAMETERS, 1
10/05/2005 POWER SYSTEMS DISTRIBUrION"SYSTE14S',
OPERATING 0
POWER SYSTEMS 11/15/2002 DISTRIBUTION'SYSTEMS -:SHUTDOWN':.,
)PERATIONS
)PERATIONS
)PERATIONS
)PERATIONS
)PERATIONS
)PERATIONS 0
11/15/2002 REFUELING EQUIPMENT INTERLOCKS 0
11/15/2002 REFUEL POSITION ONELROD-OtLrý'INTERLOCK 0
11/15/2002 CONTROL ROD:POSITION 0
11/15/2002 CONTROL ROD.POSITIONvINDICATION 0
11/15/2002 CONTROL'ROD.OPERABILITY -
REFUELING 0
11/15/2002 REACTOR PRESSURE VESSEL (RPV) WATER`:LEVEL.
Page 7 of 8
Report Date: 08/08/06 Page 7
.of 8
Report Date: 08/08/06
SSES MANUAL Manual Name :
TSBt-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 0
11/15/2002.
INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION
.0 11/15/2002" REACTOR MODE SWITCH INTERLOCK TESTING 0
11/15/2002 SINGLE CONTROL ROD WITHPRAWAL -
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 OPERATIONS Q~
OPERATIONS OPERATIONS 1
04/18/2006';
OPERATIONS CONTROL ROD TESTING -
OPERATING 1
04/12/2006 OPERATIONS SHUTDOWN MARGIN (SDM)
TEST -
REFUELING Page 8
- ~f>8.,
Report Date:. 08/08/06 Page 8 Rep6rt'D&te:.08/08/06
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC B 2.0 B 3.0 Table of Contents 10 B 3.1 B 3.2 SAFETY LIMITS BASES
- Page B 2.0-1 Page TS / B 2.0-2 Page TS / B 2.0-3 Pages TS / B 2.0-4 and TS / B 2.0-5 Page TS / B 2.0-6 Pages B 2.0-7 through B 2.0-9 LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through B 3.0-4 Pages TS / B 3.0-5 through TS / B 3.0-7 Pages TS / B 3.0-8 through TS I B 3.0-9 Pages TS / B 3.0-10 through TS / B 3.0-12 Pages TS / B 3.0-13 through TS / B 3.0-15 Pages TS / B 3.0-16 and TS / B 3.0-17 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 Page TS / B 3.1-5 Pages TS / B 3.1-6 and TS/IB 3.1-7.
Pages B 3.1-8 through B 3.1-13 Page TS / B 3.1-14 Pages B 3.1-15 through B 3.1-22 Page TS / B 3.1-23 Pages B 3.1-24 through B 3.1-27 Page TS / B 3.1-28 Page TS / B 3.1-29 Pages B 3.1-30 through B 3.1-33 Pages TS / B 3.3-34 through TS / B 3.3-36 Pages TS / B 3.1-37 and TS / B 3.1-38 Pages B 3.1-39 through B 3.1-44 Page TS / B 3.1-45 Pages B 3.1-46 and B 3.1-47 Pages TS / B 3.1-48 and TS / B 3.1-49 Page B 3.1-50 Page TS / B 3.1-51 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 Pages TS / B 3.2-2 through TS / B 3.2-6 3
4 3.
0 0
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21 2
0 0
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0 0
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0 0
1" 0
1 2
SUSQUEHANNA-UNIT 1 TS I B LOES-1 Revision 76
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE.SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Page B 3.2-7 Pages TS / B 3.2-8 and TS I B 3.2-9 Page TS / B 3.2.10 Page TS / B 3.2-11 Page B 3.2-12 Page TS / B 3.2-13 Pages B 3.2-14 and B 3.2-15 Page TS / B 3.2-16 Page B 3.2-17 Page TS / B 3.2-18
- Page TS / B 3.2-19 Revision 0
21 2
0 2
0 2
0 1
.4 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS I B 3.3-4 Page TS / B 3.3-5 Page TS / B 3.3-6 Page TS / B 3.3-7 Page TS / B 3.3-7a Pages TS / B 3.3-8 through TS / B 3.3-12 Pages TS / B 3.3-12a through TS I B 3.3-12c Page TS / B 3.3-13 Page TS / B 3.3-14 Pages TS / B 3.3-15 and TS / B 3.3-16 Pages TS / B 3.3-17 and.TS / B 3.3-18.
Page TS / B 3.3-19 Pages TS / B 3.3-20 through TS I B 3.3-22 Page TS / B 3.3-22a Pages TS / B 3.3-23 and TS / B 3.3-24 Pages TS / B 3.3-24a and TS / B 3.3-24b Pages TS / B 3.3-25 and TS / B 3.3-26 Page TS / B 3.3-27 Pages TS / B 3.3-28 throuigh TS I B 3.3-30 Page TS / B 3.3-30a Page TS / B 3.3-31 Page TS / B 3.3-32 Pages TS / B 3.3-32a and TS I B 3.3-32b Page TS I B 3.3-33 Page TS / B 3.3-33a Page TS / B 3.3-34 Pages TS / B 3.3-35 and TS / B 3.3-36 Pages TS / B 3.3-37 through TS / B 3.3-43 !
Page TS / B 3.3-44 1
2 1*
3 03 0
3 3
231 2
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1 3
0 3
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5 0
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1 3
SUSQUEHANNA-UNIT 1
,TS [B LOES-2
-.:-Revision 76
SUSQUEHANNA STEAM ELECTRIC STATION:
LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS / B 3.3-45 through TS I 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 I
Page TS / B 3.3-54 3
Pages B 3.3-55 through B 3.3-63 0
Pages TS / B 3.3-64 and TS I 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 and 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
PageTS/B3.3-75 2
Page TS / B 3.3-75a 5
Page TS / B 3.3-75b 6
Page TS / B 3.3-75c 4
Pages B 3.3-76 through 3.3.
0 PageTS/B 3.3-78
. I Pages B 3.3-79 through B 3.3-89 0
Page TS / B 3.3-90 Page B 3.3-91.
0 Pages TS /B3.3-92 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
PageTS/B3.3-107 1
Page B 3.3-108 0
PageTS/B3.3-109 1
Pages B 3.3-110 and B 3.3-111 0
Pages TS / B 3.3-112 and TS /.B 33-112a -
I PagesTS/B3.3-113throughTSIB3.3-115 1
PageTS/B3.3-116 2
Page TS / B 3.3-117 I
.1 I
Pages B 3.3-118 through B13.3-122 0
Pages TS / B 3.3-123 and TS I 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 i
0 SUSQUEHANNA - UNIT I js1 B LOES-3
--~~> ~R&C4si~6n 76
,SUSQQEHAN'NA - UNITT 151-1113 LOESý3 AR&Wdn 7-6
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL, SPECIFICATIONS BASES)
Section Title Page TS / B 3.3-138 Pages B 3.3-139 through B 3.3-149 Pages TS / B 3.3-150 through TS / B 3.3-162 Page TS / B 3.3-163 Pages TS / B 3.3-164 through TS / B 3.3-177 Pages TS / B 3.3-178 and TS / B 3.3-179 Pages TS / B 3.3-179a and TS / B 3.3-179b Page TS / B 3.3-179c Page TS / B 3.3-180 Page TS / B 3.3-181 Pages TS / B 3.3-182 through TS / B 3.3-186 Pages TS / B 3.3-187 and TS / B 3.3-188 Pages TS / B 3.3-189 through TS / B 3.3-191, Pages B 3.3-192 through B 3.3-204 Page TS / B 3.3-205 Pages B 3.3-206 through B 3.3-219
- Revision, 1
0 1
2 1
2 2
0 1
2 1
2 1
0 1
0 B 3.4 REACTOR COOLANT SYSTEM BASES,'--
Pages B 3.4-1 and B 3.4-2 Pages TS / B 3.4-3 and Page TS / B 3.4-4 Pages TS / B 3.4-5 through TS7 B 3.4-9,..
pages B 3.4-10 through B 3.4-14 Page TS / B 3.4-15 PagesTS / B 3.4-16 through TS / B 3.4-18 Pages B 3.4-19 through B 3.4-27 Pages TS / B 3.4-28 and TS / B 3.4-29 Pages B 3.4-30 and B 3.4 Page TS / B 3.4-32 Pages B 3.4-33 through B 3.4-36 Page TS / B 3.4-37 Pages B 3.4-38 through B 3.4-40".
Page TS / B 3.4-41 Pages B 3.4-42 through B 3.4-48 Page TS / B 3.4-49 Page TS I B 3.4-50 Page TS / B 3.4-51 Page TS / B 3.4-52 Page TS / B 3.4-53 Pages TS / B 3.4-54 and TS I B 3.4-55 Page TS / B 3.4-56 Page TS / B 3.4-57 Pages TS / B 3.4-58 through TS I B 3.4-60 0
4 2
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33 21' 2
3I S ISQU I-A A
I UNI T. S iBiiiiRevsio Rev'ision'76 SUSQUEHANNA - UNIT 1 TS / ý13 LOES SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Page TS/ B 3.5-3 2
Page TS / B 3.5-4 PageTS/B3.5-5 2
Page TS/ B 3.5-6 1
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Page TS / B 3.5-11 1
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Page TS / B 3.5-13 1
Pages TS / B 3.5-14 and TS /8 3.5-15 0
Pages TS / B 3.5-16 through TS./ B 3.5-18 I
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SUSQUEHANNA - UNIT 1 TS / B LOES-5,
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SUSQUEHANNA STEAM ELECTRIC STATION-.
LIST OF EFFECTIVE SECTIONS (TECHNICAL, SPECIFICATIONS BASES)
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SUSQUEHANNA - UNIT 1 TS B LOES;6 Revision 76
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFiCAIIONS BASES)
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K TSB1 text LOES 7113M06 SUSQUEHANNA - UNIT 1 TS.i B.LOES-7 Revon76
PPL Rev. 6 Secondary Containment B 3.6.4.1 B 3.6 CONTAINMENT SYSTEMS B 3.6.4.1 Secondary Containment BASES BACKGROUND The secondary containment structure completely encloses the primary containment structure such that a dual-containment design is utilized to limit the spread of radioactivity to the environment to within limits. The function of the secondary containment is to contain, dilute, and hold up fission products that may leak from primary containment into secondary containment following a Design Basis Accident (DBA). In conjunction with operation of the Standby Gas Treatment (SGT) System and closure of certain -valves whose lines penetrate the secondary containment, the secondary containment is designed to reduce the activity level of the fission products prior to release to the environment and to isolate and contain fission products that are released during certain operations that take place inside primary containment, when primary containment is not required to be OPERABLE, or that take place outside primary containment (Ref. 1)'
I The secondary containment is a structure that completely encloses the primary containment and reactor coolant pressure boundary components.
This structure forns a control volume that serves to hold up and dilute the fission products. It is possible for the pressure in the control volume to rise relative to the environmental pressure (e.g., due'to pump and motor heat load additions).
The secondary containment boundary consists of the reactor building structure and associated removable walls and panels, hatches, doors, dampers, sealed penetrations and valves. The secondary containment is divided into Zone I, Zone II and Zone III, each of which must be OPERABLE depending on plant status and the alignment of the seconhdry containment boundary. Specifically, the Unit I secondary containment boundary can be modified to exclude Zone II. Similarly, the Unit 2 secondary containment boundary can be modified to exclude Zone I.1.1 Secondary containment may consist of only Zone III when in MODE 4 or 5 during CORE ALTERATIONS, or during handling of irradiated fuel within the Zone III secondary containment boundary.
(continued)
SUSQUEHANNA - UNIT 1 TS / 8 3.6-84 Revision 3
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES BACKGROUND To prevent ground level exfiltration while allowing the secondary (continued) containment to be designed as a conventional structure, the secondary containment requires support systems to maintain the control volume pressure at less than the external pressure. Requirements for the safety related systems are specified separately in LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)," and LCO 3.6.4.3, "Standby Gas Treatment (SGT) System." When one or more zones are excluded from secondary containment, the specific requirements for support systems will also change (e.g., required secondary containment isolation valves).
APPLICABLE There are two principal accidents for which credit is taken for secondary SAFETY containment OPERABILITY. These are a loss of coolant accident (LOCA)
ANALYSES (Ref. 2) and a fuel handling accident inside secondary containment (Ref. 3). The secondary containment performs no active function in response to either of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from the primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the SGT System prior to discharge to the environment.
Secondary containment satisfies Criterion 3 of the NRC Policy Statement (Ref. 4).
LCO An, OPERABLE secondary containment provides a control volume into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondary containment, can be diluted and processed prior to release to the environment. For the secondary containment to be considered OPERABLE, it must have adequate leak tightness to ensure thatfthe required vacuum can be established and maintained. The leak tigh'tness of secondary containment must also ensure that the release of radioactive materials to the environment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis. For example, secondary 'containment bypass leakage must be restricted to the leakage rate required by LCO 3.6.1.3. The secondary containment boundary required to be OPERABLE is dependent on the operating status of both units, as well as the configuration of walls, doors, hatches, SCIVs, and'available flow paths to the SGT System.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.6-85 Revision 2
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES (continued)
APPLICABILITY In MODES 1, 2, and 3, a LOCA could lead to a fission product release to primary containment that leaks to secondary containment. Therefore, secondary containment OPERABILITY is required during the same operating conditions that require primary containment OPERABILITY.
In MODES 4 and 5, the probability and consequences of the LOCA are reduced due to the pressure and temperature limitations in these MODES.
Therefore, maintaining secondary containment OPERABLE is not required in MODE 4 or 5 to ensure a control voluine, except for other situations for which significant releases of radioactive material can be postulated, such as during operations with a potential for draining the reactor vessel (OPDRVs), during CORE ALTERATIONS, or during movement of irradiated fuel assemblies in the secondary containment.
ACTIONS A.1 If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time provides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary contaihment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.
A temporary (one-time) Completion Time is connected to the Completion Time Requirements above (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) with an "OR" connector. The Temporary Completion Time is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and applies to the replacement of the Reactor Building Recirculating Fan Damper Motors. The Temporary Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may only be used once, and expires on December 31, 2005.
B.1 and B.2 If secondary containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.6-86 Revision 4
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES ACTIONS C.1, C.2, and C.3 (continued)
Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.
Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until OPDRVs are suspended.
Required Action C.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not'specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor thutdown.
SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude exfiltration under expected wind conditions.! i Expected wind conditions are defined as sustained wind speeds of less than 6r equal to 16 mph at the 60m meteorological tower or less than orqequal to 11 mph at the lOm meteorological tower if the 60m tower wind speed is not available. Changes in indicated reactor building differential pressure observed during periods of short-term wind speed gusts above these sustained speeds do not by themselves impact secondary containment integrity. H6wever, if secondary containment integrity is known to be compromised, the LCO must be entered regardless of wind speed.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.6-87 Revision 2
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.1 (continued)
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed based on operating experience related to secondary containment vacuum variations during the applicable MODES and the low probability of a DBA occurring between surveillances.
Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the operator to an abnormal secondary containment vacuum condition.
SR 3.6.4.1.2 and SR 3.6.4.1.3 Verifying that secondary containment equipment hatches, removable walls and one access door in each access opening required to be closed are closed ensures that the infiltration of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur.
Verifying that all such openings are closed also provides adequate assurance that exfiltration from the secondary containment will not occur.
In this application, the term "sealed" has no connotation of leak tightness.
An access opening typically contains one inner and one-outer door.
Maintaining secondary containment OPERABILITY requires verifying one door in each access opening to secondary containment zones is closed.
In some cases (e.g., railroad bay), secondary containment access openings are shared such that a secondary containment barrier may have multiple inner or multiple outer doors. The intent is to maintain the secondary containment barrier intact, which is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, all secondary containment access doors are normally kept closed, except when the access opening is being used forentry and exit or when maintenance is being performed on an access opening.
When the railroad bay door (No. 101) is closed; all Zone land III hatches, removable walls, dampers, and one door in each access opening connected to the railroad access bay are closed; or, only Zone I removable walls and/or" doors are open to the railroad access shaft; or, only Zone III hatches and/or dampers are open to the railroad access shaft. When the railroad bay door (No. 101) is open; all Zone I and III hatches, removable walls, dampers, and one door in each access opening connected to the railroad access bay are closed. The truck bay hatch is closed and the truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and III.
(continued)
I SUSQUEHAN1NA - UNIT 1 TS / B 3.6-88 Revision 2
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)
When an access opening between required secondary containment zones is being used for exit and entry, then at least one door (where two doors are provided) must remain closed. The access openings between secondary containment zones which are not provided with two doors are administratively controlled to maintain secondary containment integrity during exit and entry. This Surveillance is modified by a Note that allows access openings with a single door (i.e., no airlock) within the secondary containment boundary (i.e., between required secondary containment zones) to be opened for entry and exit. Opening of an access door for entry and exit allows sufficient'administrative control by individual personnel making the entries and exits to assure the secondary containment function is not degraded. When one of the zones is not a zone recquired for secondary containment OPERABILITY, the Note allowance would not apply.
The 31 day Frequency for these SRs has been shown to be adequate, based on operating experience, and is considered adequate in view of the other indications of door and hatch status that are available to the operator.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.6-88a Revision 2
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.4.1.4 and SR 3.6.4.1.5 The SGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment. To ensure that all fission products are treated, SR 3.6.4.1.4 verifies that the SGT System will rapidly establish and maintain a pressure in the secondary containment that is less than the pressure external to the secondary containment boundary. This is confirmed by demonstrating that one SGT subsystem will draw down the secondary containment to > 0.25 inches of vacuum water gauge in less than or equal to the maximum time allowed. This cannot be accomplished if the secondary containment boundary is not intact. SR 3.6.4.1.5 demonstrates that one SGT subsystem can maintain
_> 0.25 inches of vacuum water gauge for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at less than or equal to the maximum flow rate permitted for the secondary containment configuration that is operable. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows secondary containment to be in thermal equilibrium at steady state conditions. As noted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits are dependent upon the secondary containment configuration when testing is being performed. The acceptance criteria for the SRs based on secondary containment configuration is defined as follows:
SECONDARY MAXIMUM DRAWDOWN TIME(SEC)
MAXIMUM FLOW RATE (CFM)
CONTAINMENT (SR 3.6.4.1.4.
(SR 3.6.4:1.5 TEST CONFIGURATION ACCEPTANCE CRITERIA)
ACCEPTANCE CRITERIA)
Zones I, II and III.
5 125 Seconds
- 4000 CFM (Zones I, II, and III)
(From Zones I, II, and III)
Zones I and III.
- 117 Seconds
- 2885 CFM (Zones I and III)
(From Zones I and III)
(continued)
I SUSQUEHANNA - UNIT 1 TS / B 3.6-89 Revision 3
PPL Rev. 6 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)
Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.
A Note also modifies the Frequency for each SR. This Note identifies that each configuration is to be tested every 60 months. Testing each configuration every 60 months assures that the most limiting configuration is tested every 60 months. The 60 month Frequency is acceptable because operating experience has shown that these components usually pass the Surveillance and all active components are tested more frequently. Therefore, these tests are used to ensure secondary containment boundary integrity.
Since these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, either SGT subsystem will perform SR 3.6.4.1.4 and SR 3.6.4.1.5. Operating experience has shown these components usually pass the Surveillance when performed at the 24 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.:
REFERENCES
- 1. FSAR, Section 6.2.3.
- 2. FSAR, Section 15.6.
- 3. FSAR, Section 15.7.4.
- 4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 F R 39132).
SUSQUEHANNA-UNIT 1 TS / B 3.6-90 Revision 2