ML042940269
| ML042940269 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/11/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042940269 (22) | |
Text
Oct. 11, 2004 Page I of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-40585 USER INFORMAJION:
Nam A tC ROSE M Address:
2 Phone#: 2 -
TRANSMITTAL INFORMATION:
EMPL#:028401 CA#:0363 TO:
^
7I 10/11/2004 LOCATION:
USNRC FROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER CNUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TSB1 -
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 10/07/2004
'D MANUAL TABLE OF CONTENTS DATE: 10/08/2004 CATEGORY:
DOCUMENTS TYPE: TSB1 ID:
TEXT 3.6.4.3 REPLACE:
REV:1 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.
PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
Oct. 08, 2004 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-40196 USrz INFORMATION: A Name:G NCH*RO M
Address: NU Phone#: 254 TRANSMIT INFORMATION:
EMPL#:028401 CA#:0363 TO:
N*pi*q 10/08/2004 LOCATION:
USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TSB1 -
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL v -
U.4 1 V Q I d. w w -1
-D n _
_r
~
'C'ATEGORY: DOCUMENTS TYPE: TSB1 In...
]
CATEGORY: DOCUMENTS TYPE: TSB1 ID:
TEXT LOES REMOVE:
REV:50 ADD:
REV: 51 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.
PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY.
FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
N.
SSES.MANUAL
' Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL' Table Of Contents Issue Date:
10/08/2004 Procedure Name Rev TEXT LOES 51
Title:
LIST OF EFFECTIVE SECTIONS Issue Date 10/07/2004 change ID change Number TEXT TOC
Title:
TABLE OF CONTENTS 3
09/02/2004 TEXT 2.1.1 1.
e,.;-Ia.
CAVTr"V T.TMT'rC ICT.Cl DrFht-WV 04/27/2004 tInTM CT.C TEXT 2.1.2 0
11/15/2002
(
7N'
Title:
SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM (RCS)'PRESSURE SL TEXT 3.0 0
11/15/*2002'-,
Title:
LIMITING CONDITION FOR OPERATION-(LCO),,APPLICABILITY TEXT 3.1.1 0
'.4>l/15/2002
Title:
REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)
TEXT 3.1.2 g ~-"-0 11/15/2002
Title:
REACTIVITY CONTROL.SYSTEMS, REACTIVITY ANOMALIES TEXT 3.1.3 0
11/15/2002
Title:
REACTIVITY-CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 0
11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 0
Title:
REACTIVITY CONTROL SYSTEMS TEXT 3.1.6
'0
Title:
REACTIVITY CONTROL SYSTEMS 11/15/2002 CONTROL ROD SCRAM ACCUMULATORS 11/15/2002 ROD PATTERN CONTROL Page 1 of 8
Report Date: 10/11/04 P~age I of 8 Report Date: 10/11/04
U SSES MANUAL Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL 11 TEXT 3.1.7
Title:
REACTIVITY CONTROL TEXT 3.1.8
Title:
REACTIVITY CONTROL TEXT 3.2.1
Title:
POWER DISTRIBUTION TEXT 3.2.2
Title:
POWER DISTRIBUTION 0
11/15/2002 SYSTEMS STANDBY LIQUID CONTROL (SLC)
SYSTEM 0
11/15/2002 SYSTEMS SCRAM DISCHARGE VOLUME (SDV)
VENT AND DRAIN VALVES 0
11/15/2002 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 0 11/15/2002 LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
TEXT 3.2.3 0
11/15/2002
Title:
POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)
TEXT 3.2.4 0
11/15/2002
Title:
POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS\\ j TEXT 3.3.1.1 0
11/15/2002
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 0
11/15/2002
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 0
11/15/2002
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0
11/15/2002
Title:
INSTRUMENTATION FEEDWATER -
MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 0
11/15/2002
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION LDCN 3702 TEXT 3.3.3.2
Title:
INSTRUMENTATION 0
11/15/2002 REMOTE SHUTDOWN SYSTEM Report Date: 10/11/04 Page 2 of 8
SSES-MAINUAL
' Manual Name: TSB1 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 0
11/15/2002 EMERGENCY CORE COOLING SYSTEM (ECCS) -INSTRUMENTATION 0
11/15/2002..'
REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION.
0 11/15/2002 PRIMARY CONTAINMENT.ISOLATION INSTRUMENTATION' 0
11/15/2002 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 0
11/15/2002 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM TEXT 3.3.8.1 1
09/02/2004
Title:
INSTRUMENTATION LOSS OF POWER (LOP) 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:
11/15/2002.
REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING 1
11/06/2003 SYSTEM (RCS).RECIRCULATION LOOPS OPERATING.
0 11/15/2002 SYSTEM (RCS)
JET. PUMPS 0
11/15/2002 SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)
Page 3 of 8 Report Date: 10/11/04 Page 3 of 8 Report Date: 10/11/04
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 0
11/15/2002 COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 0
11/15/2002 COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION 0
11/15/2002 COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 0
11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM HOT SHUTDOWN TEXT 3.4.9 0
11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM.._)
COLD SHUTDOWN TEXT 3.4.10 0
11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0
11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 0
11/15/2002
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 0
11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM COOLING (RCIC)
COOLING (RCIC)
COOLING (RCIC)
TEXT 3.6.i.1 0
11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Page4 of 8
Report Date: 10/11/04 Page 4 of 8 Report Date: 10/11/04
SSES MANUAL I lanual Name:
TSB1 Kanual
Title:
TECHNICAL SPECIFICATION.BASES'UNIT l'MANUAL'. '.'
TEXT 3.6.1.2
Title:
CONTAINMENT SYSTEMS 0
11/15/2002.
PRIMARY CONTAINMENT AIR LOCK TEXT 3.6.1.3
Title:
CONTAIN$MENT SYSTEMS 0
11/15/2002 PRIMARY-CONTAINMENT ISOLATION VALVES LDCN (PCIVS) 3092 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 0
11/15/2002 SYSTEMS CONTAINMENT PRESSURE 0
11/15/2002 SYSTEMS DRYWELL AIR TEMPERATURE 0
11/15/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS
. 0 11/15/2002 '-
SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0
11/15/2002 SYSTEMS SUPPRESSION POOL iWATER LEVEL 0
11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL-(RHR):SUPPRESSION POOL COOLING 0
11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)
SUPPRESSION POOL-SPRAY 0
11/15/2002 SYSTEMS PRIMARY CONTAINMENT:HYDROGEN RECOMBINERS 0
11/15/2002 SYSTEMS DRYWELL AIR FLOW SYSTEM 0
11/15/2002-
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Page 5 of 8 Report Date: 10/11/04 Page.5 of 8 Report Date: 10/11/04
SSES MANUAL Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT. MANUAL TEXT 3.6.4.1 0
11/15/2002
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 0
11/15/2002
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.6.4.3 1
10/08/2004
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 0
11/15/2002 SYSTEMS E1MERGENCY SERVICE WATER (ESW) SYSTEM I0 11/15/2002 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 CONDENSER OFFGAS 0
11/15/2002 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0
11/15/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 1
10/17/2003
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING TEXT 3.8.2 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN PageS of 8
Report Date: 10/11/04 Page 6 of 8 Report Date: 10/11/04
SSES; MANUAL j Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES-UNIT 1 MANUAL.'
TEXT 3.8.3 0
11/15/2002 I
Title:
ELECTRICAL POWER SYSTEMS DIESEL.FUEL OIL, LUBE OIL, AND STARTING AIR' TEXT 3.8.4 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS DC SOURCES OPERATING TEXT 3.8.5 0
11/15/2002.
Title:
ELECTRICAL POWER-SYSTEMS DC SOURCES -
SHUTDOWN TEXT 3.8.6 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMSDISTRIBUTION SYSTEMS OPERATING TEXT 3.8.8 0
11/15/2002.
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS -
SHUTDOWN TEXT 3.9.1
Title:
REFUELING OPERATIONS 0
11/15/2002 REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2
Title:
REFUELING 0
11/15/2002 REFUEL POSITION ONE-ROD-OUT INTERLOCK OPERATIONS TEXT 3.9.3
Title:
REFUELING TEXT 3.9.4
Title:
REFUELING TEXT 3.9.5
Title:
REFUELING 0
11/15/2002.
OPERATIONS CONTROL ROD POSITION 0
11/15/2002 OPERATIONS CONTROL ROD POSITION INDICATION 0
11/15/2002 OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.6
Title:
REFUELING 0
11/15/2002 REACTOR PRESSURE VESSEL (RPV) WATER LEVEL OPERATIONS Page7 of 8
Report Date: 10/11/04 Page 7
.of 8
Report Date: 10/11/04
SSES MANUAL Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 0
11/15/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -
HIGH WATER LEVEL TEXT 3.9.8 0
11/15/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -
LOW WATER LEVEL TEXT 3.10.1
Title:
SPECIAL TEXT 3.10.2
Title:
SPECIAL TEXT 3.10.3
Title:
SPECIAL TEXT 3.10.4
Title:
SPECIAL TEXT 3.10.5
Title:
SPECIAL TEXT 3.10.6
Title:
SPECIAL TEXT 3.10.7
Title:
SPECIAL TEXT 3.10.8
Title:
SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0
11/15/2002 INSERVICE LEAK AOND HYDROSTATIC TESTING OPERATION 0
11/15/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0
11/15/2002 SINGLE CONTROL ROD WITHDRAWAL -
HOT SHUTDOWN 0
11/15/2002 SINGLE CONTROL ROD WITHDRAWAL -
COLD SHUTDOWN 0
11/15/2002 SINGLE CONTROL ROD DRIVE (CRD)
REMOVAL -
REFUELING 0
11/15/2002 MULTIPLE CONTROL ROD WITHDRAWAL -
REFUELING 0
11/15/2002 CONTROL ROD TESTING -
OPERATING 0
11/15/2002 SHUTDOWN MARGIN (SDM)
TEST -
REFUELING Page8 of 8
Report Date: 10/11/04 Page 8.
of 8 Report Date: 10/11/04
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title TOC Table of Contents Revision 3
B 2.0 SAFETY LIMITS BASES Page B 2.0-1 PageTS/B2.0-2 Page TS i B 2.0-3 Pages TS/ B 2.0-4 and TS i B 2.0-5 Page TS lB 2.0-6 Pages B 2.0-7 through B 2.0-9 B 3.0 LCO AND SR APPLICABILITY BASES -
Pages B 3.0-1 through B 3.0-7 Pages TS I B 3.0-8'and TS / B 3.0-9 Pages B 3.0-10 through B 3.0-i2 Pages TS / B 3.0-13 through TS'i B 3.0-15 '
B 3.1 REACTIVITY CONTROL BASES:
\\
\\./
Pages B 3.1-1 through B 3.1-5 PigesTS/B3.1-6andTS/B3.1-72\\
Pages B 3.1-8 through B 3.1-27 Pages TS I B 3.1-28
'Pages B 3.1-29 through B 3:1-36 Pages TS / B 3.1-37
/4 3 k'>
Pages B 3.1-38 through B 3.1-51 B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS i B 3.2-1 Page TS i B,382-2 Page TS i B.3.2-3 Page 7S /B.3.2.--4 Pages TS fB 3.2-5 and TS I B 3.2-6 Page,'B 3.2-7J Pages,,TS i B 3.2-8 through TS / B 3.2-10 PageTS i B 3.2-11 (fage"B 3.2-12 Page"'TS / B 3.2-13 Pages B 3.2-14 and B 3.2-15 Page TS I B 3.2-16 Pages B 3.2-17 and B 3.2-18 Page TS i B 3.2-19 0
2 3
- 2.
. 2 I
0 0
.10 I
0 01I 0
1 O
I 1
2 1
0 1
2 0
2.
2 0
2 B 3.3 INSTRUMENTATION Pages TS I B 3.3-1 through TS I B 3.3-10 PageTS/B3.3-11 Pages TS I B 3.3-12 through TS / B 3.3-27 Pages TS I B 3.3-28 through TS I B 3.3-31 Pages TS I B 3.3-32 and TS i B 3.3-33 I
2 I
2 3
SUSQUEHANNA
- UNIT I TS I B LOES-1 Revision 51 SUSQUEHANNA - UNIT 1 TS /f B LOES-1 Revision 51
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Pages TS / B 3.3-34 through TS / B 3.3-54 Pages B 3.3-55 through B 3.3-63 Pages TS / B 3.3-64 and TS I B 3.3-65 Page TS / B 3.3-66 Page TS / B 3.3-67 Page TS /B 3.3-68 Pages TS / B 3.3-69 and TS B 3.3-70 Pages TS / B 3.3-71 through TS / B 3:3-75 Page TS / B 3.3-75a Pages TS / B 3.3-75b through TS / B 3.3-75c Pages B 3.3-76 through B 3.3-89 Page TS / B 3.3-90 Page B 3.3-91 Page TS / B 3.3-92 through TS / B 3.3-100 Pages B 3.3-101 through B 3.3-103 Page TS / B 3.3-104' Pages B 3.3-105 and B 3.3-106 Page TS / B 3.3-107 Page B 3.3-108 Page TS / B 3.3-109 Pages B 3.3-110 and B 3.3-111 Pages TS / B 3.3-112 and TS / B 3.3-112a Pages B 3.3-113 and B 3.3-114 Page TS / B 3.3-115 Page TS / B 3.3-116 Page TS / B 3.3-117 Pages B 3.3-118 through' B 3.3-122 Pages TS / B 3.3-123 through TS / B 3.3-124 Page TS / B 3.3-124a Pages B 3.3-125 and B 3.3-126 Page TS / B 3.3-127 Pages B 3.3-128 through B 3.3-130 Page TS / B 3.3-131 Pages B 3.3-132 through B 3.3-137 Page TS / B 3.3-138 Pages B 3.3-139 through B 3.3-149 Page TS / B 3.3-150 through TS I 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 I B 3.3-179 Page TS / B 3.3-179a Page TS / B 3.3-179b Pages TS / B 3.3-180 through TS I 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 I
0 2
4 3
4 3
2 4
3 0
1 0
1 0
1 0
1 10 1
0 1
2 1
0 1
0 0
1 0
0 1
0 1
2 1
2 1
0 1
0 1.,
0 SUSQUEHANNA
- UNIT I TS/B LOES-2 Revision 51 SUSQUEHANNA - UNIT 1 TS / B LOES-2 Revision 51
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section B 3.4 Title REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 PageTS/B3.4-3 Page TS / B 3.4-4 Pages TS / B 3.4-5 and TS / B 3.4-6 Page B 3.4-7 Pages TS / B 3.4-8 and TS / B 3.4-9 Pages B 3.4-10 through B 3.4-14 Page TS / B 3.4-15 Pages TS / B 3.4-16 and TS / B 3.4-17 Page TS / B 3.4-18 Pages B 3.4-19 through B 3.4-28 Page TS / B 3.4-29 Pages B 3.4-30 through B 3.4-48 Page TS / B 3.4-49 Page TS / B 3.4-50 Page TS / B 3.4-51 Pages TS / B 3.4-52 and TS I B 3.4-53 Page TS / B 3.4-54 Page TS/B3.4-55 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 Revision 0
2 2
1 0
1 0
1 2
1 0
1 0
2 1
2 I
2 2
I 2
I B 3.5 B 3.6 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 PageTS/B3.5-3 Pages TS / B 3.5-4 and TS / B 3.5-5 Pages B 3.5-6 through B 3.5-10 Page TS / B 3.5-11 Pages B 3.5-12 through B 3.5-15 Pages TS I B 3.5-16 through TS / B 3.5-18 Pages B 3.5-19 through B 3.5-24 Page TS I B 3.5-25 Pages B 3.5-26 through B 3.5-31 0
2 1
0 1
0 I
0 I
0 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 Page TS / B 3.6-1a Pages TS / B 3.6-2 through TS / B 3.6-5 Page TS / B 3.6-6 Pages TS / B 3.6-6a and TS / B 3.6-6b Page TS/B3.6-6c Pages B 3.6-7 through B 3.6-14 Page TS / B 3.6-15 Pages TS / B 3.6-15a and TS / B 3.6-15b Page B 3.6-16 2
3 2
.3
- 2 0
0 2
0 0
SUSQUEHANNA
- UNIT I TS I B LOES-3 Revision 51 SUSQUEHANNA - UNIT 1 TS / B, LOES-3
-.Revision 51
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Page TS / B 3.6-17 Page TS I B 3.6-17a Pages TS / B 3.6-18 and TS I B 3.6-19 Page TS / B 3.6-20 Page TS / B 3.6-21 Page TS I B 3.6-22 Page TS / B 3.6-22a Page TS / B 3.6-23 Pages TS / B 3.6-24 through TS i B 3.6-25 Page TS / B 3.6-26 Page TS /B 3.6-27 Page TS / B 3.6-28 Page TS / B 3.6-29 Page TS/B 3.6-30 PageTS/B3.6-31 Pages B 3.6-32 through B 3.6-35 Page TS / B 3.6-36 Page B 3.6-37 Page TS/B 3.6-38 Page B 3.6-39 Page TS I B 3.6-40 Pages B 3.6-41 through B 3.6-43 Pages TS / B 3.6-44 through TS / B 3.6-51 PageTS/B3.6-52 Pages B 3.6-53 through B 3.6-63 Page TS / B 3.6-64 Pages B 3.6-65 through B 3.6-83 PageTS/B3.6-84 Pages TS / B 3.6-85 through TS / B 3.6-88 Page TS I B 3.6-88a Page TS / B 3.6-89 Pages TS / B 3.6-90 through TS / B 3.6-1 00 Page B 3.6-101 Pages TS / B 3.6-102 through TS / B 3.6-107 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 Page TS / B 3.7-6a Pages TS / 13 3.7-6b and TS / B 3.7-6c Pages TS / B 3.7-7 through TS / B 3.7-11 Pages TS I B 3.7-12 and TS / B 3.7-13 Pages TS / B 3.7-14 through TS / B 3.7-18 Page TS / B 3.7-18a Pages TS / B 3.7-19 through TS / B 3.7-23 Pages B 3.7-24 through B 3.7-26 Pages TS / B 3.7-27 through TS / B 3.7-29 Revision 1
0 0
I 2
I 0
1 0
0 Corrected 2
5 1
1 3
0 1
0 1
0 3
01 1
2 0
i 0
2.
1 I
.2 1
0 1
I B 3.7 2
2 0
I I
2 0
I 0
3 SUSQUEHANNA
- UNIT I TS/BLOES-4 Revision 51 SUSQUEHANNA - UNIT 1 TS / B LOES-4 Revision 5.1
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page TS / B 3.7-30 1
Pages B 3.7-31 through B 3.7-33 0
B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS I B 3.8-1 through TS / B 3.8-4 2
Page TS / B 3.8-5 3
Pages TS / B 3.8-6 through TS/B 3.8-8 2
PagesTS/B3.8-9andTS/B3.8-10 3
Pages TS / B 3.8-11 and TS I B 3.8-17 2
Page TS / B 3.8-18 3
Pages TS / B 3.8-19 through TS / B 3.8-21 2
Pages TS / B 3.8-22 and TS / B 3.8-23 3
Pages TS / B 3.8-24 through TS / B 3.8-37 2
Pages B 3.8-38 through B 3.8-53 0
Pages TS / B 3.8-54 through TS / B 3.8-61 1
Page TS / B 3.82 2
Page TS/B3.8-63 2
PageTS/B3.8-64 1
Page TS/B3.8-65 2
Pages TS/B 3.8-66 through B 3.8-90 0
B 3.9 REFUELING OPERATIONS BASES PagesTS/B3.9-1 andTS/B3.9-1a 1
Pages TS / B 3.9-2 through TS / B 3.9-4 1
Pages B 3.9-5 through B 3.9-30 0
B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 1
Pages B 3.10-2 through B 3.10-31 0
PageTS/B3.10-32 1
Pages B 3.10-33 through B 3.10-37 0
PageTS/B3.10-38 1
TSB1 text LOES 917104 SUSQUEHANNA - UNIT 1 TS / B LOES-5 Revision 51
PPL Rev. 1 SGT System B 3.6.4.3 B3.6 CONTAINMENT SYSTEMS B 3.6.4.3 Standby Gas Treatment (SGT) System BASES BACKGROUND The SGT System is required by 10 CFR 50, Appendix A, GDC 41, "Containment Atmosphere Cleanup" (Ref. 1). The safety'function of the SGT System is to ensure that radioactive materials that leak from the primary containment into the secondary containme-nt following a Design Basis Accident (DBA) are filtered and adsorbed prior to exhausting to the environment.,
'2 The SGT System consists of two redundant subsystems, each with its own 'set of dampers, filter train, a recirculation fan, and associated dampers and controls.
Each filter train consists of (compone'nts listed in order of the direction of the air flow):
- a. A demister;
- b. An electric" eater; h
- c. A prefilter\\,,.
- d. A-high efficiency particulate air (H EPA) filter; r'A
-charcoal adsorber;
'1 f.-A second HEPA filter, and
- g. A centrifugal fan.
The sizing of the SGT System equipment and components is based on handling an incoming air mixture at a maximum of 125oF. The internalE pressure of the secondary containment is maintained at a negative pressure of 0.25 inches water gauge when the system is in operation.
Maintenance of a negative pressure precludes direct outleakage.
C-,.
The demister is provided to remove entrained water.in the air, while the electric heater reduces the relative humidity of the airstream to less than 70% (Ref. 2). The prefilter removes large particulate matter, while the HEPA filter (continued)
SUSQUEHANNA - UNIT 1 B 3.6-101 Revision 0 I
PPL Rev. 1 SGT System B 3.6.4.3 BASES BACKGROUND (continued) removes fine particulate matter and protects the charcoal from fouling.
The charcoal adsorber removes gaseous elemental iodine and organic iodides, and the final HEPA filter collects any carbon fines exhausted from the charcoal adsorber.
The SGT System automatically starts and operates in response to actuation signals indicative of conditions or an accident that could require' operation of the system. Following initiation in each division, the associated filter train fan starts. Upon verification that both subsystems are operating, the redundant subsystem may be shut down.
The SGT System also contains a cooling function to remove heat generated by fission product decay on the HEPA filters and charcoal adsorbers during shutdown of an SGT subsystem. The cooling function consists of two separate and independent filter cooling modes per SGT subsystem. The two cooling modes are:
- 1)
Outside air damper and the filter cooling bypass damper open, -
allowing outside air to flow through the shutdown SGT subsystem's filter train and exit via the opposite SGT subsytem's exhaust fan.
- 2)
Outside air damper opens and the SGT exhaust fan of the shutdown SGT subsystem starts. This configurations draws outside air through the shutdown SGT subsystem's filter train and exits via the associated SGT subsystem's exhaust fan.
APPLICABLE The design basis for the SGT System is to mitigate the consequences of a
.SAFETY loss7 of coolant accident and fuel handling accidents (Ref. 2). For all ANALYSES events analyzed, the SGT System is shown to be automatically initiated to reduce, via filtration and adsorption, the radioactive material released to the environment.
The SGT System satisfies Criterion 3 of the NRC Policy Statement (Ref. 3).
LCO Following a DBA, a minimum of one SGT subsystem is required to maintain the secondary containment at a negative pressure with respect to the environment and to process gaseous releases. Meeting the LCO requirements for two OPERABLE subsystems ensures operation of at least (continued)
SUSQUEHANNA - UNIT 1 T
. TS / B 3.6-102 Revision 1
PPL Rev. 1 SGT System B 3.6.4.3 BASES LCO (continued) one SGT subsystem in the event of a single active failure. A SGT subsystem is considered OPERABLE when it has an OPERABLE set of dampers, filter train, recirculation fan and associated dampers, and associated controls. This includes the components required for at least one of the two SGTS filter cooling modes.
APPLICABILITY In MODES 1, 2, and 3, a DBA could lead to a fission product release to primary containment that leaks to secondary containment. Therefore, SGT System OPERABILITY is required during these MODES.
In MODES 4 and 5, the probability and consequences of these events are reduced due to the pressure and temperature limitations in these MODES.
Therefore, maintaining the SGT System in OPERABLE status is not required in MODE 4 or 5, except for other situations under 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 With one SGT subsystem inoperable, the inoperable subsystem must be restored to OPERABLE status in 7 days. In this Condition, the remaining OPERABLE SGT subsystem is adequate to perform the required radioactivity release control function. However, the overall system reliability is reduced because a single failure in the OPERABLE subsystem could result in the radioactivity release control function not being adequately performed. The 7 day Completion Time is based on consideration of such factors as the availability of the OPERABLE redundant SGT System and the low probability of a DBA occurring during this period.
B.1 and B.2 If the SGT subsystem cannot be restored to OPERABLE status within the required Completion Time in MODE 1, 2, or 3, 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 (continued)
SUSQUEHANNA - UNIT I R
TS I B 3.6-103 Revision 1
PPL Rev. 1 SGT System B 3.6.4.3 BASES ACTIONS B.1 and B.2 (continued) operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1. C.2.1. C.2.2. and C.2.3 During movement of irradiated fuel assemblies, in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, when Required Action A.1 cannot be completed within the required Completion Time, the OPERABLE SGT filter train should immediately be placed in operation. This action ensures that the remaining filter train is OPERABLE, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected.
An alternative to Required Action C.1 is to immediately suspend activities that represent a potential for releasing radioactive material to the secondary containment, thus placing the plant in a condition that minimizes risk. If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies must immediately be suspended. Suspension of these activities must not preclude completion of movement of a component to a safe position. Also, if applicable, actions must immediately be initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.
The Required Actions of Condition C have 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 nof 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.
D.1 If both SGT subsystems are inoperable in MODE 1, 2, or 3, the SGT system may not be capable of supporting the required radioactivity release control function. 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 (continued)'
SUSQUEHANNA - UNIT I TS / B3.6104 Revision 1
PPL Rev. 1 SGT System B 3.6.4.3 BASES ACTIONS D.1 (continued) the problem that is commensurate with the importance of maintaining the SGT System contribution to secondary containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring SGT OPERABILITY) occurring during periods where SGT is inoperable is minimal.
E.1 and E.2 If at least one SGT subsystem 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.
F.1. F.2. and F.3 When two SGT subsystems are inoperable, if applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in secondary containment must immediately be suspended. Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, actions must immediately be initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.
Required Action F.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.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.6-105 Revision 1
PPL Rev. 1 SGT System B 3.6.4.3 BASES (continued)
SURVEILLANCE SR 3.6.4.3.1 REQUIREMENTS Operating each SGT filter train for 2 10 continuous hours ensures that both filter train are OPERABLE and that all associated controls are functioning properly. It also ensures that blockage, fan or motor failure, or excessive vibration can be detected for corrective action. Operation with the heaters on (automatic heater cycling to maintain temperature) for 2 10 continuous hours every 31 days eliminates moisture on the adsorbers and HEPA filters. The 31 day Frequency is consistent with the requirements of Reference 4.
SR 3.6.4.3.2 This SR verifies that the required SGT filter testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.
SR 3.6.4.3.3 This SR verifies that each SGT subsystem starts on receipt of an actual or*
simulated initiation signal. While this Surveillance can be performed with the reactor at power, operating experience has shown 'that these components usually pass the Surveillance when performed at the 24 month Frequency. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. Therefore, the Frequency was found to be acceptable from a reliability standpoint.
SR 3.6.4.3.4 This SR verifies that both cooling modes for each SGT subsystem are available. Although both cooling modes are tested, only one cooling mode for each SGT subsystem is required for an SGT subsystem to be considered OPERABLE. While this Surveillance can be performed with the reactor at power, operating experience has shown that these components usually pass the Surveillance when performed at the 24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was found to be acceptable from a reliability standpoint.
(continued)
SUSQUEHANNA - UNIT 1 TS /B 3.6-106 Revision 1
PPL Rev. 1 SGT System B 3.6.4.3
- BASES (continued REFERENCES I
- 2. FSAR, Section 6.5.1
- 3. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
- 4. Regulatory Guide 1.52, Rev. 2.
I SUSQUEHANNA-UNIT I TS I B 3.6-107 Revision I