ML050110112
| ML050110112 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/04/2005 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 028401 | |
| Download: ML050110112 (33) | |
Text
Jan. 04, 2005 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2005-548 USER INFORMATION /
Name:
LACH SE M EMPL#:028401 CA#:0363 Address:
2 Phone#:
4-3 TRANSM AL INFORMATION:
TO:
aT'BT
'A 01/04/2005 LOCATION:
USNRC FROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TSB2 -
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 12/23/2004
'DD MANUAL TABLE OF CONTENTS DATE: 01/03/2005
"'-TEGORY: DOCUMENTS TYPE: TSB2 ID:
TEXT 3.6.4.1 REMOVE:
REV:0 ADD:
REV: 1 CATEGORY:
DOCUMENTS TYPE: TSB2 ID:
TEXT 3.6.4.2 REMOVE:
REV:1 ADD:
REV: 2 CATEGORY:
DOCUMENTS TYPE: TSB2 ID:
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FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
'~-"
Ada
-SSES MANUAL Manual Name:
TSB2 "anual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date:
01/03/2005 Procedure Name Rev Issue Date TEXT LOES 52 01/03/2005
Title:
LIST OF EFFECTIVE SECTIONS Change ID Change Number TEXT TOC
Title:
TABLE OF CONTENTS TEXT 2.1.1
Title:
SAFETY LIMITS (SLS) 5 11/22/2004 1
REACTO 10/27/2004 R CORE SLS -
1:
I l
TEXT 2.1.2 0
11/18/2002
Title:
SAFETY LIMITS (SLS)
PREP TEXT 3.0 0
11/182v
Title:
LIMITING CONDITION FOR OPERATIONS (LCO)j.APPLICABILITY TEXT 3.1.1 0i;11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS RCTDOWN MARGIN (SDM)
TEX 3..
li IOj, 11
/18/200 TEXT 3.1.3 0
11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY SL TEXT 3.1.4
Title:
REACTIVITY CONTROL TEXT 3.1.5
Title:
REACTIVITY CONTROL 0
11/18/2002 SYSTEMS CONTROL ROD'SCRAM TIMES I
0 11/18/2002 SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6
--0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Page 1 of 8
Report Date: 01/03/05 Page I of 8 Report Date: 01/03/05
SSES MANUAL f
Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7
Title:
REACTIVITY CONTROL TEXT 3.1.8
Title:
REACTIVITY CONZAOl.
TEXT 3.2.1
Title:
POWER DISTRIBUTION TEXT 3.2.2
Title:
POWER DISTRIBUTION TEXT 3.2.3 0
11/18/2002 SYSTEb..S STANDBY LIQUID COtIPTROL (SLC) SYSTEM 0
11/18/2002 SYStEMS SCRAM DISCHARGE VOLUME (SDV)
VENT AND DRAIN VALVES 0
11/18/2002 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 0 11/18/2002 LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
- 0.
11/18/2002
Title:
POWER DISTRIBTJTION. LIMITS LINEAR HEAT GENERATION RATE (LHGR)
TEXT 3.2.4 0
11/18/2002
Title:
POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE-MONITOR (APRM) GAIN AND SETPOINTL.>
TEXT 3.3.1.1 0
11/18/2002
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) -INSTRUMENTATION TEXT 3.3.1.2 0
11/18/2002
Title:
INSTRUMENTATION SOURCE RAMNGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 0
11/18/2002
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0
11/18/2002
Title:
INSTRUMENTATION FEEDWATER - MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 0
11/18/2002
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION LDCN 3710 TEXT 3.3.3.2
Title:
INSTRUMENTATION 0
11/18/2002 REMOTE SHUTDOWN SYSTEM Page2 of 8
Report Date: 01/03/05 Page 2 of 8 Report Date: 01/03/05
SSES.MANUAL
' Manual Hame:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.4.1 0
11/18/2002
Title:
INSTRUMENTATION END OF-CYCLE RECIRCULATION PUMP TRIP'(EOC-RPT) INSTRUMENTATION TEXT 3.3.4.2 0
11/18/2002 '
Title:
INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP-(ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 1
11/09/2004.
Title:
INSTRUMENTATION,EMERGENCYCORE -COOLING'SYSTEM'(ECCS). INSTRUMENTATION TEXT 3.3.5.2
Title:
INSTRUMENTATION TEXT 3.3.6.1
--Title: INSTRUMENTATION TEXT 3.3.6.2
Title:
INSTRUMENTATION TEXT 3.3.7.1
Title:
INSTRUMENTATION INSTRUMENTATION TEXT 3.3.8.1
Title:
INSTRUMENTATION TEXT 3.3.8.2
Title:
INSTRUMENTATION TEXT 3.4.1
Title:
REACTOR COOLANT TEXT 3.4.2
Title:
REACTOR COOLANT TEXT 3.4.3
Title:
11/18/2002 REACTOR CORE ISOLATION COOLING'(RCIC) SYSTEM INSTRUMENTATION 1
11/09X2004 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION 1
11/09/2004 SECONDARY.CONTAINMENT ISOLATION INSTRUMENTATION 0
11/18/2002 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM 1
09/02/2004 LOSS 'OF-POWER (LOP) INSTRUMENTATION' 0
11/18/2002 REACTOR: PROTECTION :SYSTEM (RPS) ELECTRIC POWER MONITORING' 2
11/22/2004, SYSTEM -(RCS) RECIRCULATION LOOPS OPERATING 0
11/18/2002 SYSTEM (RCS) JET PUMPS 0
11/18/2002 SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)
Page 3 of 8
Report Date: 01/03/05 Page3 -
of 8 Report Date: 01/03/05
SSES MANUAL l
Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL I
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
11/18/2002 COOLANT SYSTEM.(RCS) RCS OPERATIONAL LEAKAGE 0
11/18/2002 COOLANT. SYSTEM (RCS)
RCS PRESSURE'ISOLA'TION VALVE (PIV) LEAKAGE 0
11/18/2002 COOLANT SYSTEM (RCS) RCS LFAKAGE DETECTION INSTRUMENTATION 0
11/18/2002 COOLANT SYSTEM (RCS).RCS SPECIFIC ACTIVITY TEXT 3.4.8 0
11/18/2002
Title:
REACTOR COOLANT.SYSTEM (RCS)
RESIDUAL HEAT.'REMOVALJ (RHR)
SHUTDOWN COOLING SYSTEM HOT SHUTDOWN TEXT 3.4.9 0
11/18/2002
Title:
RESIDUAL HEAT'REMOVAL (RHR)
SHUTDOWN COOLING SYSTEK.-
COLD SHUTDOWN TEXT 3.4.10 0
11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0
Title:
REACTOR COOLANT SYSTEM (RCS) 11/18/2002 REACTOR STEAM DOME PRESSURE TEXT 3.5.1 0
11/18/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM ECCS -
OPERATING TEXT 3.5.2 0
11/18/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM ECCS -
SHUTDOWN TEXT 3.5.3 0
11/18/2002 Titles EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM TEXT 3.6.1.1 0
11/18/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT COOLING (RCIC)
COOLING (RCIC)
COOLING (RCIC)
Page 4 of 8 Report Date: 01/03/05 Page 4 of 8 Report Date: 01/03/05'
...4. -. -
-SSES"MANlUAL
-'a Manual Nam~e:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL:
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 Q '
Title:
CONTAINMENT TEXT 3.6.2.2
Title:
CONTAINMENT 0
11/18/2002 SYSTEMS PRIMARY CONTAINMENT AIR LOCK.
0 11/18/2002 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS) 0 11/18/2002-SYSTEMS CONTAINMENT2PRESSURE 0
11/18/2002 SYSTEMS DRYWELL'AIR'TEMPERATURE' 0
11/18/2002 SYSTEMS SUPPR.ESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 0
11/18/2002 SYSTEMS SUPPRESSION'POOL'AVERAGE TEMPERATURE 0
11/18/2002 '
SYSTEMS SUPPRESSION POOL -WATER LEVEL TEXT 3.6.2.3 0
11/18/2002
Title:
CONTAINMENT SYSTEMS RESIDUAL.HEAT REMOVAL (RHR) -SUPPRESSION POOL COOLING TEXT 3.6.2.4
Title:
CONTAINMENT 0
11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)
SUPPRESSION POOL SPRAY'-'
TEXT 3.6.3.1
Title:
CONTAINMENT TEXT 3.6.3.2 0
11/18/2002 '-'
SYSTEMS PRIMARY -CONTAINMENT HYDROGEN RECOMBINERS 0
11/18/2002
Title:
CONTAINMENT SYSTEMS DRYWELI AIR FLOW'SYSTEM TEXT 3.6.3.3 0
11/18/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION oa
- re5, of,8, Report Date:'01/03i05 Pag
SSES MANUAL Manual Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL '
TEXT 3.6.4.1 1
01/03/2005
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMFNT TEXT 3.6.4.2 2
01/03/2005-
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.3 2
11/09/2004-
Title:
CONTAINMENT SYSTEMS STANDBY GAS TRENTMENT ISOLATION VALVES (SCIVS)
(SGT)' SYSTEM TEXT 3.7.1
Title:
PLANT SYSTEMS ULTIMATE HEAT 0
11/18/2002 RESIDUAL HEAT RPYMOVAL 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 (ESWJ)'SYSTEM 0
11/18/2002 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM 0
11/18/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS 0
11/18/2002 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0
11/18/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 1
10/17/2003
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING TEXT 3.8.2 0
11/18/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN Page6 of 8
Report Date: 01/03/05 Page 6 of 8 Report Date: 01/03/05
SSESr MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.3
Title:
ELECTRICAL POWER TEXT 3.8.4
Title:
ELECTRICAL POWER TEXT 3.8.5
Title:
ELECTRICAL POWER TEXT 3.8.6
Title:
ELECTRICAL POWER TEXT 3.8.7
Title:
ELECTRICAL POWER TEXT.3.8.8
Title:
ELECTRICAL POWER 0
11/18/2002 SYSTEMS DIESEL'FUEL OIL,. LUBE'OIL,. AND'STARTING AIR 0
11/18/2002 SYSTEMS 'DC SOURCES OPERATING-0 11/18/2002 SYSTEMS :DC SOURCES - SHUTDOWN 0
11/18/2002' SYSTEMS:jBATTERY 'CELL PARAMETERS 0
11/18/2002 '
SYSTEMS.DISTRIBUTION SYSTEMS -'OPERATING;'
0 11/18/2002 SYSTEMS DISTRIBUTION SYSTEMS -' SHUTDOWN TEXT 3.9.1
Title:
REFUELING TEXT 3.9.2
Title:
REFUELING OPERATIONS OPERATIONS 0
11/18/2002.-
REFUELING 4EQUIPMENT INTERLOCKS:
0 11/18/2002 REFUEL POSITION ONE-ROD-OUT INTERLOCKR TEXT 3.9.3
Title:
REFUELING 0
11/18/2002 CONTROL RODPOSITION OPERATIONS 1,. -
TEXT 3.9.4
Title:
REFUELING 0
11/18/2002 CONTROL ROD POSITION INDICATION OPERATIONS TEXT 3.9.5
Title:
REFUELING 0
11/18/2002 OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.7
Title:
REFUELING 0
.11/18/2002 RESIDUAL HEAT REMOVAL (RHR) -
HIGH WATER LEVEL OPERATIONS Page 7 of.8 Report Date: 01/03/05 Page 7 of 8-Report Date: 01/03J05
In SSES MANUAL Manual Name:
TSB2 I
Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL
-i TEXT 3.9.8 0
11/18/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1
Title:
SPECIAL TEXT 3.10.2
Title:
SPECIAL TEXT 3.10.3
Title:
SPECIAL TEXT 3.10.4
Title:
SPECIAL TEXT 3.10.5
Title:
SPECIAL TEXT 3.10.6
Title:
SPECIAL TEXT 3.10.7
Title:
SPECIAL TEXT 3.10.8
Title:
SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0
11/18/2002 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0
11/18/2002.
REACTOR MODE SWITCH INTERLCCK TESTING 0
11/18/2002 SINGLE CONTROL ROD WITHDRAWAL HOT SHUTDOWN 0
11/18/2002 SINGLE CONTROL ROD WITHDRAWAL COLD SHUTDOWN 0
11/18/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -
REFUELING 0
11/18/2002.
MULTIPLE CONTROL ROD'WIT.{DRAWAL REFUELING 0
11/18/2002 CONTROL ROD TESTING OPERATING 0
11/18/2002 SHUTDOWN MARGIN (SDM)
TEST -
REFUELING Page8 of 8
Report Date: 01/03/05 Page 8 of 8 Report Date: 01/03/05
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC Table of Contents 5
B 2.0 SAFETY LIMITS BASES PageTS/B2.0-1, I
1 PageTS,/ B 2.0-2 2
Page TS / B 2.0-3 3
Page TS / B2.G4 e{'
'4
- PageTS/B2.0-5 ;, -- :^.
r.;,............. -::
1 Pages B 2.0-6 through B 2.0-8 0
B 3.0 LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through B 3.0-7, 1 '
-0.
Pages TS / B 3.0-8 and TS / B 3:0-9 1
PagesB3.0-10throughB3.0-12 0
Pages TS / B 3.0-13 through TS I B'3.0-15
/
1 B 3.1 REACTIVITY CONTROL BASES N
Pages B 3.1-1 through B 3.1-5 0
PagesTS/B3.1-6andTS/B3.1-7
> 7 Pages B 3.1-8 throuigh'B 3.'1-27/~-
0 PageTS/B3.1-28 1
Pages B 3.1-29 through B 3.-36 K... i 0
Page TS / B 3.1-37.;
Pages B 3.1-38 throughwB 3.1-511
.0 B 3.2 POWER DISTRIBUTION LIMITS BASES Pages TS / B 32-l ti4Žough TS / B 3.2-4 1
Pages TS B.312-5and TS B 3.2-6 2
Page TS / B3.2-7 Pages TS7 B 3.2-8 and TS B 3.2-9 2
Page'sTS'/B3.2-io through TS / B 3.2 1 B 3.3 INSTRUMENTATION (Paget TS / B 3.3-1 through TS/ B 3.3-10 1
NiagegTS /B3.3-11 2
Pages TS / B 3.3-12 through TS / B 3.3-27 1
Pages TS / B 3.3-28 through TS / B 3.3-30 2
Page TS / B 3.3-31 1
Pages TS / B 3.3-32 and TS / B 3.3-33 2
Pages TS / B 3.3-34 through TS I B 3.3-43 1
Pages TS / B 3.3-43a though TS I B 3.3-43i 0
Pages TS / B 3.3-44 through TS I B 3.3-54 1
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/B3.3-67 3
Page TS/B3.3-68 4
SUSQUEHANNA -'UNIT 2 TS I B LOES-1 Revision 52
' "' SUSQUEHANNA'- UNIT 2 TS / B LOES-1 Revision 52.
SUSQUEHANNA STEAM ELECTRIC. STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title.
Revision Pages TS / B 3.3-69 and TS / B 3.3-70 3
Pages TS / B 3.3-71 through TS / B 3.3-75 2
PageTS/B3.3-75a 4
Pages TS / B 3.3-75b through TS I B 3.3-75c 3
Pages B 3.3-76 through B 3.3-91 0
Pages TS / B 3.3-92 through TS / B 3.3-103 1
Page TS / B 3.3-104 2
Pages TS I B 3.3-105 and TS / B 3.3-106 1
PageTS/B3.3-107 2
Page TS / B 3.3-108 1
Page TS / B 3.3-109 2
Pages TS / B 3.3-110 through TS / B 3.3-115 1
Pages TS / B 3.3-116 through TS I B 3.3-118 2
Pages TS / B 3.3-119 through TS / B 3.3-120 1
Pages TS / B 3.3-121 and TS I B 3.3-122 2
Page TS I B 3.3-123 1
Page TS / B 3.3-124 2
Page TS / B 3.3-124a 0
Pages TS / B 3.3-125 and TS I B 3.3-126 1
Page TS / B 3.3-127 2
Pages TS / B 3.3-128 through TS / B 3.3-131 1
Page TS/B3.3-132 2
Pages TS / B 3.3-133 and TS / B 3.3-134 1
Pages B 3.3-135 through B 3.3-137 0
Page TS / B 3.3-138 1
Pages B 3.3-139 through B 3.3-149 0
Pages TS/ B 3.3-150 through TS / B 3.3-162 1
Page TS / B 3.3-163 2
Pages TS / B 3.3-164 through TS I B 3.3-177 1
Page TS / B 3.3-178 2
Page TS / B 3.3-179 3
Page TS / B 3.3-179a 2
Page TS / B 3.3-180 1
Page TS / B 3.3-181 2
Pages TS / B 3.3-182 through TS I 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
Pages B 3.3-192 through B 3.3-205 0
Page TS / B 3.3-206 1
Pages B 3.3-207 through B 3.3-220 0
B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 1
Pages TS / B 3.4-3 through TS / B 3.4-9 3
Pages B 3.4-10 through B 3.4-14 0
Page TS / B 3.4-15 I
Pages TS / B 3.4-16 and TS / B 3.4-17 2
SUSQUEHANNA - UNIT 2 TS /B LOES-2 Revision 52
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page TS B 3.4-18 1
Pages B 3.4-19 through B 3.4-28 0
Page TS / B 3.4-29 1
Pages B 3.3-30 through B 3.3-48 0
PageTS/B3.4-49 2
Page TS / B 3.4-50 1
Page TS / B 3.4-51 2
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
Pages TS / B 3.4-56 through TS / B 3.4-60 1
B 3.5 ECCS AND RCIC BASES Pages TS / B 3.5-1 and TS B 3.5-2 1
Page TS / B 3.5-3 2
Pages TS / B 3.5-4 through TS / B 3.5-10 1
Page TS / B 3.5-11 2
Pages TS / B 3.5-12 through TS / B 3.5-14 1
Pages TS / B 3.5-15 through TS / B.3.5-17 2
PageTS/B3.18 1
Pages B 3.5-19 through B 3.5-24 0
Page TS / B 3.5-25 1
Pages B 3.5-26 through B 3.5-31 0
B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2
Page TS I B 3.6-1 a 3
Pages TS / B 3.6-2 through TS / B 3.6-5 2
PageTS/B3.6-6 3
Pages TS / B 3.6-6a and TS / B 3.6-6b 2
Page TS / B 3.6-6c 0
Pages B 3.6-7 through B 3.6-14 0
PageTSIB3.6-15 3
Pages TS I B 3.6-15a and TS I B 3.615b 0
Page TS / B 3.6-16 1
Page TS / B 3.6-17 2
Page TS / B 3.6-17a 0
Pages TS / B 3.6-18 and-TS B 3.6-19 1
Page TS / B 3.6-20 2
Page TS / B 3.6-21 3
Pages TS / B 3.6-21a and TS / B 3.6-21b 0
Pages TS / B 3.6-22 and TS / B 3.6-23 2
Pages TS / B 3.6-24 through TS / B 3.6-26 1
Page TS / B 3.6-27 3
Page TS / B 3.6-28 6
PageTS B3.6-29 3
Page TS / B 3.6-29a 0
Page TS/B3.6-30 2
SUSQUEHANNA
- UNIT 2 TS I B LOES-3 Revision 52 SUSQUEHANNA - UNIT 2 TS / B LOES-3 Revision 52
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page TS/B3.6-31 3
Pages TS / B 3.6-32 through TS / B 3.6-34 1
Pages TS / B 3.6-35 through TS / B 3.6-37 2
Page TS / B 3.6-38 1
Page TS / B 3.6-39 4
Pages B 3.6-40 through B 3.6-42 0
Pages TS / B 3.6-43 through TS / B 3.6-50 1
Page TS / B 3.6-51 2
Pages B 3.6-52 through B 3.6-62 0
Page TS / B 3.6-63 1
Pages B 3.6-64 through B 3.6-82 0
PageTS/B3.6-83 3
Pages TS / B 3.6-84 and TS / B 3.6-85 2
Pages TS / B 3.6-86 through TS I B 3.6-87a 1
Page TS / B 3.6-88 2
Page TS i B 3.6-89 1
Page TS / B 3.3-90 3
Pages TS / B 3.6-91 through TS / B 3.6-95 1
Page TS/B3.6-96 2
Pages TS / B 3.6-97 and TS I B 3.6-98 1
Page TS / B 3.6-99 2
Page TS B 3.6-99a 0
Pages TS / B 3.6-100 and TS / B 3.6-101 1
Pages TS / B 3.6-102 through TS / B 3.6-104 2
Pages TS / B 3.6-105 and TS / B 3.6-106 1
B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 2
Page TS / B 3.7-6a 2
Pages TS I B 3.7-6b and TS / B 3.7-6c 0
Page TS / B 3.7-7 2
PageTS/B3.7-8 1
Pages B 3.7-9 through B 3.7-11 0
Pages TS / B 3.7-12 and TS / B 3.7-13 1
Pages TS / B 3.7-14 through TS / B 3.7-18 2
Page TS / B 3.7-18a 0
Pages TS / B 3.7-19 through TS / B 3.7-26 1
Pages B 3.7-24 through B 3.7-26 0
Pages TS / 3.7-27 through TSI B 3.7-29 1
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SUSQUEHANNA
- UNIT 2 TSIB LOES-4 Revision 52 SUSQUEHANNA - UNIT 2 TS / B LOES-4 Revision 52
SUSQUEHANNA STEAM ELECTRIC STATION.
LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title.
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TSB2LOES 12115a4 SUSQUEHANNA
-. UNIT 2 TS I B LOES-5 Revision 52 SUSQUEHANNA - UNIT 2' TS / BLOES-5 Revision 52
PPL Rev. 1 Secondary Containment B 3.6.4.1 I
.... I 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).
The secondary containment is a structure that completely encloses the primary containment and reactor coolant pressure boundary components.
This structure forms 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).
I 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 l1l, each of which must be OPERABLE depending on plant status and the alignment of the secondary containment boundary. Specifically, the Unit 1 secondary containment boundary can be modified to exclude Zone II. Similarly, the Unit 2 secondary containment boundary can be modified to exclude Zone I. Secondary containment may consist of only Zone IlIl when in MODE 4 or 5 during CORE ALTERATIONS, or during handling of irradiated fuel within the Zone IlIl secondary containment boundary.
(continued)
SUSQUEHANNA - UNIT 2
.TS / B 3.6-83 Revision 3
PPL Rev. 1 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 that the required vacuum can be established and maintained. The leak tightness 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 2 TS /B 3.684 Revision 2
i",
PPL Rev. 1 Secondary Containment*
B 3.6.4.1 hi BASES.
1-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.
I 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 volume, 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 containment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.
(continued)
SUSQUEHANNA - UNIT 2 TS / B3.685 Revision 2
PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES ACTIONS B.1 and B.2 (continued)
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.
C.1. C.2. and C.3 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 shutdown.
SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary is sufficiently leak tight to preclude'exfiltration.
(continued)
SUSQUEHANNA - UNIT 2 TS / B3.6-86 Revision I
PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.1 (continued)
REQUIREMENTS 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 access doors 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.
When the railroad bay door (No. 101) is closed; all Zone I and IlIl hatches, removable walls, dampers, and doors 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 IlIl hatches and/or dampers are open to the railroad access shaft. When the railroad bay door (No. 101) is open; all Zone I and IlIl hatches, removable walls, dampers, and doors 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 l1l.
Verifying that all such openings are closed provides adequate assurance that exfiltration from the secondary containment will not occur. In this application, the term "sealed" has no connotation of leak tightness.
Maintaining secondary containment OPERABILITY requires verifying each door in each access opening to the secondary containment zones and each access opening between the secondary containment zones is closed.
When an access opening to secondary containment is being used for exit l
and entry, then at least one door must remain closed.
(continued)
SUSQUEHANNA - UNIT 2 TS / B 3.6-87 Revision 1
- -- IPPL Rev. 1 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 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.
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 2 TS / B 3.6-87a Revision 1
il _ ::- "
PPL Rev. I 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 2 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 2 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 DRAWNDOWN TIME(SEC)
MAXIMUM FLOW RATE (CFM)
CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5 CONFIGURATION ACCEPTANCE CRITERIA)
ACCEPTANCE CRITERIA)
Three Zone Operation with
- 15 Seconds
(Zones II and III)
(Verify by calculation that one SGT subsystem will maintain 2:.25 inches of vacuum water gauge in secondary containment at a flow rate of
- 4000 CFM (From Zones It 11, and 111.)
Three Zone Operation with
- 125 Seconds
- 4000 CFM Zones I, II and Ill.
(Zones I, II, and I11)
(From Zones I, II, and I11)
Two Zone Operation with
- 118 Seconds
- 2960 CFM Unit I Shutdown and (Zones II and III)
(From Zones Wland III)
Zone I isolated.
Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.
(continued)
I SUSQUEHANNA - UNIT 2 B
TS / B3.688 Revision 2
i V7-- -.
W, -
r t 1,,
PPL Rev. 1 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE REQUIREMENTS SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)
A Note also modifies the Frequency for each SR. This Note identifies that each SR must be performed in the most limiting Secondary Containment Configuration every 60 m6nths. 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 FR 39132).
SUSQUEHANNA - UNIT 2 TS / B 3.6-89 Revision I
Vi' PPL Rev. 2 SCIVs B 3.6.4.2 B 3.6 CONTAINMENT SYSTEMS B 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)
BASES BACKGROUND The function of the SCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Ref. 1). Secondary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that fission products that leak from primary containment into secondary containment following a DBA, or that are released during certain operations when primary containment is not required to be OPERABLE or take place outside primary containment, are maintained within the secondary containment boundary.
I The OPERABILITY requirements for SCIVs help ensure that an adequate secondary containment boundary is maintained during and after an accident by minimizing potential paths to the environment. These isolation devices consist of either passive devices or active (automatic) devices. Manual valves or dampers, de-activated automatic valves or dampers secured in their closed position (including check valves with flow through the valve secured), and blind flanges are considered passive devices.
Automatic SCIVs close on a secondary containment isolation signal to establish a boundary for untreated radioactive material within secondary containment following a DBA or other accidents.
Other non-sealed penetrations which cross a secondary containment boundary are isolated by the use of valves in the closed position or blind flanges.
APPLICABLE SAFETY ANALYSES The SCIVs must be OPERABLE to ensure the secondary containment barrier to fission product releases is established. The principal accidents for which the secondary containment boundary is required are a loss of coolant accident (Ref. 1) and a fuel handling accident inside secondary containment (Ref. 2). The secondary containment performs no active function in response to either of these limiting events, but the boundary (continued)
SUSQUEHANNA - UNIT 2 TS / B3.690 Revision 3
-. I B 3.6.4.2 BASES APPLICABLE SAFETY ANALYSES (continued) established by SCIVs is required to ensure that leakage from the primary containment is processed by the Standby Gas Treatment (SGT) System before being released to the environment.
Maintaining SCIVs OPERABLE with isolation times within limits ensures that fission products will remain trapped inside secondary containment so that they can be treated by the SGT System prior to discharge to the environment SCIVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 3).
LCO SCIVs that form a part of the secondary containment boundary are required to be OPERABLE. Depending on the configuration of the secondary containment only specific SCIVs are required. The SCIV safety function is related to control of offsite radiation releases resulting from DBAs.
The automatic'isolation valves are considered OPERABLE when their isolation times are within limits and the valves actuate on an automatic isolation signal. The valves covered by this LCO, along with their associated stroke times, are listed in Table B 3.6.4.2-1.
The normally closed isolation valves or blind flanges are considered OPERABLE when manual valves are closed or open in accordance with appropriate administrative controls, automatic SCIVs are deactivated and secured in their closed position, or blind flanges are in place. These passive isolation valves or devices are listed in Table B3.6.4.2-2. Penetrations closed with sealants are considered part of the secondary containment boundary and are not considered penetration flow paths.
APPLICABILITY In MODES 1, 2, and 3, a DBA could lead to a fission product release to the primary containment that leaks to the secondary containment. Therefore, the OPERABILITY of SCIVs is required.
In MODES 4 and 5, the probability and consequences of these events are reduced due to pressure and temperature (continued)
SUSQUEHANNA - UNIT 2 TS / a 3.6-91 Revision 1
BASES APPLICABILITY limitations in these MODES. Therefore, maintaining SCIVs OPERABLE is (continued) not required in MODE 4 or 5, except for other situations under which significant radioactive releases 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. Moving irradiated fuel assemblies in the secondary containment may also occur in MODES 1, 2, and 3.
ACTIONS The ACTIONS are modified by three Notes. The first Note allows penetration flow paths to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device. In this.way, the penetration can be rapidly isolated when a need for secondary containment isolation is indicated.
The second Note provides clarification that for the purpose of this LCO separate Condition entry is allowed for each penetration flow path. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable SCIV. Complying with the Required Actions may allow for continued operation, and subsequent inoperable SCIVs are governed by subsequent Condition entry and application of associated Required Actions.
The third Note ensures appropriate remedial actions are taken, if necessary, if the affected system(s) are rendered inoperable by an inoperable SCIV.
A.1 and A.2 In the event that there are one or more required penetration flow paths with one required SCIV inoperable, the affected penetration flow path(s) must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure.
Isolation barriers that meet this criterion are a closed and de-activated automatic SCIV, a closed manual valve, and a blind flange. For penetrations isolated in (continued)
SUSQUEHANNA - UNIT 2
.TS / B3.692 Revision 1
0
".L-PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS A.1 and A.2 (continued) accordance with Required Action A.1, the device used to isolate the penetration should be the closest available device to secondary containment. The Required Action must be completed within the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time. -The specified time period is reasonable considering the time required to isolate the penetration, and the probability of a DBA, which requires the SCIVs to close, occurring during this short time is very low.
For affected penetrations that have been isolated.in accordance with Required Action A.1, the affected penetration must be verified to be isolated on a periodic basis. This is necessary to ensure that secondary
-containment penetrations required to be isolated following an accident, but no longer capable of being automatically isolated, will be in the isolation position should an event occur. The Completion Time of once per 31 days is appropriate because the valves are operated under administrative controls and the probability of their misalignment is low. This Required Action does not require any testing or device manipulation. Rather, it involves verification that the affected penetration remains isolated.
Condition A is modified by a Note indicating that this Condition is only applicable to those penetration flow paths with two SCIVs. For penetration flow paths with one SCIV, Condition C provides the appropriate Required
'Actions.
Required Action A.2 is modified by a Note that applies to devices located in high radiation areas and allows them to be verified closed by use of administrative controls. Allowing verification by administrative controls is considered acceptable, since access to these areas is typically restricted.
Therefore, the probability of misalignment, once they have been verified to be in the proper position, is low.
8.1 With two SCIVs in one or more penetration flow paths inoperable, the affected penetration flow path must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The method of isolation must (continued)
SUSQUEHANNA - UNIT 2 TS /B 3.693 Revision I
PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS B.1 (continued) include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a cdosed and de-activated automatic valve, a closed manual valve, and a blind flange. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is reasonable considering the time required to isolate the penetration and the probability of a DBA, which requires the SCIVs to close, occurring during this short time, is very low.
The Condition has been modified by a Note stating that Condition B is only applicable to penetration flow paths with two isolation valves. For penetration flow paths with one SCIV, Condition C provides the appropriate Required Actions.
C.1 and C.2 With one or more required penetration flow paths with one required SCIV inoperable, the inoperable valve must be restored to OPERABLE status or the affected penetration flow path must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a dosed and de-activated automatic valve, a closed manual valve, and a blind flange. A check valve may not be used to isolate the affected penetration. Required Action C.1 must be completed within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time. The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is reasonable considering the relative stability of the system (hence, reliability) to act as a penetration isolation boundary and the relative importance of supporting secondary containment OPERABILITY during MODES 1, 2, and 3.
In the event the affected penetration flow path is isolated in accordance with Required Action C.1, the affected penetration must be verified to be isolated on a periodic basis. This is necessary to ensure that secondary containment penetrations required to be isolated following an accident are isolated.
The Completion Time of once per 31 days for verifying each affected penetration is isolated is appropriate because the (continued)
SUSQUEHANNA - UNIT 2 TS / B3.694 Revision 1
PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS C.1 and C.2 (continued) valves are operated under administrative controls and the probability of their misalignment is low.
Condition C is modified by a Note indicating that this Condition is only applicable to penetration flow paths with only one SCIV. For penetration flow paths with two SCIVs, Conditions A and B provide the appropriate Required Actions.
Required Action C.2 is modified by a Note that applies to valves and blind flanges located in high radiation areas and allows them to be verified by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted.
Therefore, the probability of misalignment of these valves, once they have been verified to be in the proper position, is low.
D.1 and D.2 If any Required Action and associated Completion Time cannot be met, 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 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />s: 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.
E.1. E.2. and E.3 If any Required Action and associated Completion Time are not met, the plant must be placed in a condition in which the LCO does not apply. If applicable, CORE ALTERATIONS and the movement of irradiated fuel assemblies in the secondary containment must be immediately suspended.
Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, actions must be immediately initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and the subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.
(continued)
SUSQUEHANNA - UNIT 2 TS I B 3.6-95 Revision 1
PPL Rev. 2 SCIVs B 3.6.4.2 BASES ACTIONS E.1. E.2, and E.3 (continued)
Required Action E.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 fuel 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 shutdown.
SURVEILLANCE SR 3.6.4.2.1 REQUIREMENTS This SR verifies that each secondary containment manual isolation valve and blind flange that is required to be closed during accident conditions is closed. The SR helps to ensure that post 'accident leakage of radioactive fluids or gases outside of the secondary containment boundary is within design limits. This SR does not require any testing or valve manipulation.
Rather, it involves verification (typically visual) that those required SCIVs in secondary containment that are capable of being mispositioned are in the correct position.
Since these SCIVs are readily accessible to personnel during normal operation and verification of their position is relatively easy, the 31 day Frequency was chosen to provide added assurance that the SCIVs are in the correct positions.
Two Notes have been added to this SR. The first Note applies to valves and blind flanges located in high radiation areas and allows them to be verified by use of administrative controls. Allowing verification by administrative controls is considered acceptable, since access to these areas is typically restricted during MODES 1, 2, and 3 for ALARA reasons. Therefore, the probability of misalignment of these SCIVs, once they have been verified to be in the proper position, is low.
A second Note has been included to clarify that SCIVs that are open under administrative controls are not required to meet the SR during the time the SCIVs are open.
(continued)
SUSQUEHANNA - UNIT 2 TS /B 3.696 Revision 2
- PPL Rev. 2 SCIVs B 3.6.4.2 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.4.2.2 SCIVs with maximum isolation times specified in Table B 3.6.2.4-1 are tested every 92 days to verify that the isolation time is within limits to demonstrate OPERABILITY. Automatic SCIVs without maximum isolation times specified in Table B 3.6.4.2-1 are tested under the requirements of SR 3.6.4.2.3. The isolation time test ensures that the SCIV will isolate in a time period less than or equal to that assumed in the safety analyses.
SR 3.6.4.2.3 Verifying that each automatic required SCIV closes on a secondary containment isolation signal is required to prevent leakage of radioactive material from secondary containment following a DBA or other accidents.
This SR ensures that each automatic SCIV will actuate to the isolation position on a secondary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. 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.
- 2.
FSAR, Section 15.
- 3.
Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
SUSQUEHANNA - UNIT 2 TS I B 3.6-97 Revision I
I PPL Rev. 2 SCIVs B 3.6.4.2 Table B 3.6.4.2-1 Secondary Containment Ventilation System Automatic Isolation Dampers
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Maximum Reactor Valve Number Valve Description Type of Valve Isolation Building Tm Zone.....Tm Zone (sSeconds)
I HD-17586 A&B Supply System Dampers Automatic Isolation Damper 10.0 HD-17524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0 I HD-17576A&B Unfitered Exhaust System Automatic Isolation Damper 10.0 HD-27586 A&B Supply System Dampers Automatic Isolation Damper 10.0 II HD-27524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0 1I HD-27576 A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0 Ill HD-17564 A&B Supply System Dampers Automatic Isolation Damper 14.0 Ill HD-17514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 Ill HD-17502'A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0 IlIl HD-27564 A&B Supply System Dampers Automatic Isolation Damper 14.0 Ill HD-27514 A&$
Filtered Exhaust System Dampers Automatic Isolation Damper 6.5 IlIl HD-27502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0 N/A HD-17534A Zone 3 Airlock 1-606 Automatic Isolation Damper NA N/A HD-17534B Zone 3 Airlock 1-611 Automatic Isolation Damper NIA N/A HD-17534C Zone 3 Airlock 1-707 Automatic Isolation Damper N/A N/A HD-17534D Zone 3 Airlock 1-803 Automatic Isolation Damper N/A N/A HD-17534E Zone 3 Airlock 1-805 Automatic Isolation Damper N/A N/A HD-17534F Zone 3 Airlock 1-617 Automatic Isolation Damper N/A N/A HD-17534H Zone 3 Airlock 1-618 Automatic Isolation Damper N/A N/A HD-27534A Zone 3 Airlock 11-606 Automatic Isolation Damper N/A N/A HD-27534C Zone 3 Airlock 11-707 Automatic Isolation Damper N/A N/A HD-27534D Zone 3 Airlock 11-803 Automatic Isolation Damper N/A N/A HD-27534E Zone 3 Airlock 11-805 Automatic Isolation Damper N/A N/A HD-27534G Zone 3 Airlock C-806 Automatic Isolation Damper N/A N/A HD-27534H Zone 3 Airlock 11-618 Automatic Isolation Damper N/A N/A HD-275341 Zone 3 Airlock 11-609 Automatic Isolation Damper NIA SUSQUEHANNA - UNIT 2 TS / B3.698 Revision 1
,'C.:': ', ' t' tt PPL Rev. 2 SCIVs B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System Passive Isolation Valves or Devices (Page 1 of 2)
I Device Number Device Description Area/Elev.
Required Position X-28-2-3000 Utility Penetration to Unit I East Stairwell YardI670 Blind Flanged X-29-2-44 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged X-29-2-45 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged X-29-2-46 Temporary Chiller to RBCW Yard/670 Blind Flanged X-29-2-47 Temporary Chiller to RBCW YardI670 Blind Flanged X-29-2-48 Utility Penetration to Unit 1 RR Bay Yard/670 Capped X-33-2-3000 Utility Penetration to Unit 2 East Stairwell YardI670 Blind Flanged X-28-2-3000 Utility Penetration to Unit 1 East Stairwell 28/670 Blind Flanged X-29-2-48 Utility Penetration to Unit 1 RR Bay 29/670 Capped X-33-2-3000 Utility Penetration to Unit 2 East Stairwell 33/670 Blind Flanged X-29-3-54 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged X-29-3-55 Utility Penetration to Unit 1 RBCCW Hx Area 271683 Blind Flanged X-29-5-95 Temporary Chiller to Unit 1 RBCW 291749 Blind Flanged X-29-5-96 Temporary Chiller to Unit 1 RBCW 291749 Blind Flanged X-29-5-91 Temporary Chiller to Unit 2 RBCW 331749 Blind Flanged X-29-5-92 Temporary Chiller to Unit 2 RBCW 331749 Blind Flanged X-29-5-97 Utliity Penetration from Unit I RR Bay to 331749 Capped Unit 2 Elev. 749 X-27-6-42 Diamond Plate Cover over Floor Penetration 27/779' Installed X-27-6-92 Instrument Tubing Stubs 271779' Capped X-29-7-4 V Spare Conduit Threaded Plug 29/818' Installed X-30-6-72 Instrument Tubing Stubs 301779' Capped X-30-6-1002 Stairwell #214 Rupture Disc 30)779' Installed Intact X-30-6-1003 Airlock 11-609 Rupture Disc.
301779' Installed Intact X-25-6-1008 Airlock 1-606 Rupture Disc 251779' Installed Intact X-29-4-102 Penetration at Door 433 291719' Blind Flange Installed X-29-4-103 Penetration at Door 433 291719' Blind Flange Installed X-29-4-102 Penetration at Door 433 331719' Blind Flange Installed X-29-4-103
'Penetration at Door 433 331719' Blind Flange Installed 1S2104 N2 Purge Line to U1 Containment Spectacle 29/683' Blind Side Installed Flange 2S2104 N2 Purge Line to U2 Containment Spectacle 341672' Blind Side Installed Flange XD-17513 Isolation damper for Railroad Bay Zone II l
291799' Position is dependent on HVAC Supply Railroad Bay alignment XD-17514 Isolation damper for Railroad Bay Zone III 291719' Position is dependent on HVAC Exhaust Railroad Bay alignment 187388 RBCW Temp Chiller Discharge Iso Vlv 29/670 Closed Manual Isolation Valve 187389 RBCW Temp Chiller Supply Iso Vlv 291670 Closed Manual Isolation Valve 187390 RBCW Temp Chiller Supply Drain Vlv 291670 Closed Manual Isolation Valve 187391 RBCW Temp Chiller Discharge Drain Vlv 29/670 Closed Manual Isolation Valve 110176 SDHR Supply Drain VIv 29/670 Closed Manual Isolation Valve 110186 SDHR Discharge Drain Vlv 29/670 Closed Manual Isolation Valve SUSQUEHANNA - UNIT 2 TS / B 3.6-99 Revision 2
,. ' i l i PPL Rev. 2 SCIVs B 3.6.4.2 Table B 3.6.4.2-2 Secondary Containment Ventilation System Passive Isolation Valves or Devices (Page 2 of 2)
I 187388 RBCW Temp Chiller Discharge Iso Vlv 291670 Closed Manual Isolation Valve 187389 RBCW Temn Chiller Supply Iso VIv 29/670 Closed Manual Isolation Valve 187390 RBCW Temp Chiller Supply Drain Vlv 291670 Closed Manual Isolation Valve 187391 RBCW Temp Chiller Discharge Drain Vlv 29/670 Closed Manual Isolation Valve 110176 SDHR Supply Drain Vlv 29/670 Closed Manual Isolation Valve 110186 SDHR Discharge Drain Vlv 29/670 Closed Manual Isolation Valve 110180 SDHR Supply Vent Vtv 291749 Closed Manual Isolation Valve 110181 SDHR Discharge Fill Vlv 271749 Closed Manual Isolation Valve 110182 SDHR Discharge Vent Vlv 271749 Closed Manual Isolation Valve 110187 SDHR Supply Fill Vlv 29/749 Closed Manual Isolation Valve 210186 SDHR Supply Drain Vlv 33/749 Closed Manual Isolation Valve 210187 SDHR Supply Vent Vlv 331749 Closed Manual Isolation Valve 210191 SDHR Discharge Vent Vlv 301749 Closed Manual Isolation Valve 210192 SDHR Discharge Drain Vlv 3049 Closed Manual Isolation Valve 210193 SDHR Discharge Vent Vlv 331749 Closed Manual Isolation Valve SUSQUEHANNA - UNIT 2 TS / B 3.6-99a Revision 0