ML050330148
| ML050330148 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/18/2005 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML050330148 (18) | |
Text
Jan. 18, 2005 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2005-2814 USER INFORMATION:-
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.SSES MANUAL y Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:
01/17/2005 Procedure Name Rev Issue-Date TEXT LOES 55 01/17/2005
Title:
LIST OF EFFECTIVE SECTIONS Change ID c
Change Number TEXT TOC
Title:
TABLE OF CONTENTS I
5 11/22/2004 1
nA/V7/)nnA
Title:
SAFETY LIMITS (SLS) REACTOR CORE SLS eO TEXT 2.1.2 0
11/15/2002
Title:
SAFETY LIMITS (SLS) REACTOR COOLANT-SYSTEM,(RCS) PRESSURE SL TEXT 3.0
.0 11/15/2002))
Title:
LIMITING CONDITION FOR OPERATIO.(LCO). APPLICABILITY TEXT 3.1.1 0,
11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS-SHUTDOWN MARGIN (SDM)-
TEXT 3.1.2 11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES-TEXT 3.1.3 K
0 11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL'ROD OPERABILITY
\\
-',d,2 TEXT 3.1.4
Title:
REACTIVITY TEXT 3.1.5
Title:
REACTIVITY 0
11/15/2002 CONTROL SYSTEMS CONTROL-ROD SCRAM TIMES 0
11/15/2002 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 0
11/15/2002 CONTROL SYSTEMS ROD PATTERN-CONTROL TEXT 3.1.6
Title:
REACTIVITY Pagel of 8
Report Date: 01/17/05 Page 1 of -8 Report Date: 01/17/05
,II
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TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT I. MANUAI
[
7-TEXT 3.1.7 0
11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS STANDBY.LIQUID1 'CCCNTROL
'(SLC) SYSTEM TEXT 3.1.8
Title:
REACTIVITY CONTROL TEXT 3.2.1
Title:
POWER DISTRIBUTION 0
11/15/2002.:
SYSTEMS SCRAM.DISCHARGE'VOLUME-(SDY)'VENT AND DRAIN VALVES 0
11/15/2002 LIMITS-AVERAGE PLANAR LINEAR'HEAT GENERATION-RATE (APLlIGR)
TEXT 3.2.2 0
11/15/2002
Title:
POWER DISTRIBUTION LIMITS MINIMUM CRITICAL' POWER RATIO (MCPR)
TEXT 3.2.3
Title:
POWER DISTRIBUTION
.. 0 11/15/2002 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\\' )
TEXT 3.3.1.1 0
11/15/2002
Title:
INSTRUMENTATION.REACTORPROTECTION'SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 0
11/15/2002,..'
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM):INSTRUMENTATION TEXT 3.3.1.3 0
11/22/2004
Title:
OPRM 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 Page2 of 8 Report Date: 01/17/05 Page 2 of 8 Report Date: 01/17/05
-,SSE9;.,NANUAL
> Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION.BASES uNIT, 1MANUAL' -.
TEXT 3.3.3.2 0
11/15/2002'...
Title:
INSTRUMENTATION REMOTE-SHUTDOW!N.SYSTEM-TEXT 3.3.4.1 0
11/1512002,
Title:
INSTRUMENTATION END.,OFCYCLE:RECIRCULATION^PUMP'TRIP.;(EOC-RPT) INSTRUMENTATION TEXT 3.3.4.2 0
11/15/.2002
Title:
-INSTRUMENTATION ANTICIPATED TRANSIENT,WI{IHOUT::SCRAM-RECIRCULATION PUMP TRIP-(ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 0
11/15/2002..
Title:
INSTRUMENTATION EMERGENCY. CORE COOLING'SYSTEM (ECCS) INSTRUMENTATION-TEXT 3.3.5.2 0
11/15/2002i..
Title:
INSTRUMENTATION REACTOR CORE.ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 1
11/09/2004
'.Title: INSTRUMENTAtION PRIMARY CONTAINMENT..ISOLATION INSTRUMENTATION-TEXT 3.3.6.2 1
11/09/2004
Title:
INSTRUMENTATION SECONDARY CONTAINMENT.ISOLATION INSTRUMENTATION' TEXT 3.3.7.1 0
11/1512002,..
Title:
INSTRUMENTATION CONTROL.ROOM EMERGENCY'OUTSIDE:AIR-SUPPLY (CREOAS)'SYSTE4-.
INSTRUMENTATION TEXT 3.3.8.1 1
09/02/2004,...
Title:
INSTRUMENTATION LOSS OF'POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0
11/15/2002'.
Title:
INSTRUMENTATION REACTOR PROTECTION.SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 2
11/22/2004..!
Title:
REACTOR COOLANT SYSTEM-(RCS) RECIRCULATION LOOPS:OPERATING
-E TEXT 3.4.2 0
11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) JET PUMPS; Page 3 of 8 Report Date:'01/17/05
l
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Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 :MANUAL.: :.
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L TEXT 3.4.3
Title:
REACTOR TEXT 3.4.4
Title:
REACTOR TEXT 3.4.5
Title:
REACTOR TEXT 3.4.6
Title:
REACTOR TEXT 3.4.7
Title:
REACTOR TEXT 3.4.8
Title:
REACTOR HOT SE 0
11/15/2002,..
COOLANT SYSTEM (RCS), SAFETY/RELIEF; VALVES *:(S/RVS).':
0 11/15/2002 COOLANT SYSTEM (RCS)
RCS. OPERATIONAL LEAKAGE'.'.':0' '.'...:.;
0 11/15/2002 COOLANT; SYSTEM--(RCS.):RCS.PRESSURE'ISOLATION: VALVE (PlV)
LEAKAGE 0
11/15/2f002.
COOLANT SYSTEM (RCS)' RCS LEAKAGE.DETECTION.INSTRUMENTATION 0
11/15/2002 COOLANT SYSTEM (RCS)..RCS SPECIFIC ACTIVITY.
0 11/15/2002 COOLANT SYSTEM:(RCS) RESIDUAL HEAT..REMOVAL.'(RHR)
SHUTDOVIN COOLING SYSTEM__.
[UTDOWN 0
11/15/2002 COOLANT SYSTEM (RCS).RESIDUAL,'HEAT'REMOVAL (RHR)
SHUTDOWN COOLING SYSTEM SHUTDOWN 0
11/15/2002.
TEXT 3.4.9
Title:
REACTOR COLD S TEXT 3.4.10
Title:
REACTOR COOLANT SYSTEM (RCS): RCS'PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0
11/15/2002
Title:
REACTOR STEAM DOME PRESSURE TEXT 3.5.1 0
11/15/2002..
Title:
EMERGENCY CORE COOLING SYSTEMSk(ECCS) AND-REACTOR CORE SYSTEM ECCS -
OPERATING TEXT 3.5.2 0
11/15/2002
Title:
EMERGENCY CORE.COOLING SYSTEMS.(ECCS) AND REACTOR CORE SYSTEM ECCS -
SHUTDOWN ISOLATION COOLING (RCIC)
ISOLATION COOLING (RCIC)
TEXT 3.5.3 0
11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM RCIC SYSTEM Page 4 of 8 Report Date: 01/17/05 Page 4 of 8 Report Date: 01/17/05
.SSES; -JANUL Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT-.1.MANUAL.'.:'.
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Title:
CONTAINMENT TEXT 3.6.1.2
Title:
CONTAINMENT.
TEXT 3.6.1.3
Title:
CONTAINMENT 0
11/15/2.002 I.
.:I SYSTEMS PRIMARY CONTAINMENT.,
I 0
11/15/.2002.'
SYSZEMS.PRIMARY CONTAINMENTtAIR.LOCK-T`CC 7i f
L 0
11/15/2002 -
SYSTEMS PRIMARY CONTAINMENTUISOLATION:VALVES '(PCIVS)
-l' L
TEXT 3.6.1.4
Title:
CONTAINMENT LDCN 0
11/15/2002 SYSTEMS CONTAINMENT.PRESSURE 3092 I..
TEXT 3.6.1.5 0
11/15/2002
Title:
CONTAINMENT SYSTEMS DRYWEILL AIR TEMPERATURE'.'
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 0
11/15/.,2002 SYSTEMS SUPPRESSION CHAMBER-TO'-DRYWELL VACUUM BREAKERS or:
0 11/15/2002 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0
11/15/2002 SYSTEMS SUPPRESSION POOL-WATER'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 Pages of 8
Report Date: 01/17/05 Page 5 of 8 Report Date: 01/17/05
l
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.S r S.ES MALM V Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION`BASES.UNIT.-1 MANUAL'-.X TEXT 3.6.3.3 0
11/1512002.
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONdENTRATION
., I "'
TEXT 3.6.4.1 1
01/03/,2005
Title:
CONTAINMENT SYSTEMS CSECONDARY 'CONME
- -:A TEXT 3.6.4.2.
2 01/03/2005'*'-'
Title:
- CONTAINMENT SYSTEMS SECONDARY.CONTAINMENT-ISOLATION:VALVES (SCIVS)
TEXT 3.6.4.3 2
11/09/2004>>.:.'
Title:
CONTAINMENT.SYSTEMS STANDBY'GAS:TREATMENT (SGT)' SYSTEM :
TEXT 3.7.1 0
11/15/2002.
Title:
PLANT SYSTEMS RESIDUAL HEATREMOVALi*SERVICE WATER1(RHRSW)'SYSTEM AND THE ULTIMATE HEAT SINK (UHS) tEXT 3.7.2 1
11/09/2004.
-Title:
- PLANTSYSTEMS EMERGENCY:'SERVICE, WATER-(ESW) SYSTEM.-
TEXT 3.7.3 0
11115/2002
Title:
PLANT.SYSTEMS CONTROL ROOM:EMERGENCY.OUTSIDE:AIR SUPPLY'(CREOAS) ;SYSTEM-TEXT 3.7.4 0
11/15/2002.
Title:
PLANT SYSTEMS CONTROL ROOM FLOOR. COOLING.'SYSTEM TEXT 3.7.5 0
11/15/2002'...
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS' '-
TEXT 3.7.6 1
01/17/2005'.
Title:
PLANT SYSTEMS.MAIN TURBINE.BYPASS SYSTEM..
TEXT 3.7.7 0
11/15/2002
Title:
,PLANT SYSTEMS SPENT.FUEL STORAGE POOL WATER:LEVEL-TEXT 3.8.1 1
10/17/2003
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING Page6 of 8
Report Date: 01/17/05 Page 6 of 8 -
Report Date: 01/17/05
iSSE-S;iXA2UAL (Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION:BASES UNIT 1 'MANUAL TEXT 3.8.2 0
11/15/2002'-..'
Title:
ELECTRICAL POWER SYSTEMS AC:SOURCES' -;SHUTDOWN-i TEXT 3.8.3 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS.:DIESEL.JUELV'OILf JLUBE3'OIL, cEAND 'STARTING AIR TEXT 3.8.4 0
il/15/2002':
l
Title:
ELECTRICAL:POWER SYSTEMS ^DC SOURCES:-. OPERATING TEXT 3.8.5 0
11/15/2002\\.^.
Title:
ELECTRICAL POWER -SYSTEMS DC SOURCES`- -SHUTDOWN I
TEXT 3.8.6 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS.BATTERY.-CELL.PARAMETERS;-
"EXT 3.8.7 0
11/15/2002 K
Title:
ELECTRICAL!-POWER'.SYSTEMS DISTRIBUTION SYSTEMS
-'OPERATING TEXT 3.8.8 0
11/15/2002
Title:
ELECTRICAL POWER.SYSTEMS DISTRIBUTION-SYSTEMS -SHUTDOWN TEXT 3.9.1 0
11/15/2002-:
Title:
REFUELING OPERATIONS REFUELING SQUIPMENT.: INTERLOCKS :'.
TEXT 3.9.2
Title:
REFUELING TEXT 3.9.3
Title:
REFUELING 0
11/15/2002 OPERATIONS REFUEL POSITION ONE-ROD-OUT -INTERLOCK 0'
11/15/2002 OPERATIONS CONTROL ROD'POSITION
- ~~
~ ~
,f I
TEXT 3.9.4
Title:
REFUELING TEXT 3.9.5
Title:
REFUELING 0
11/15/2002 OPERATIONS 'CONTROL.ROD:.POSITION.INDICATION.
0 11/15/2002 OPERATIONS CONTROL ROD OPERABILITY - REFUELING Page7 of 8 Report Date: 01/17/05 Page 7 of 8 Report Date: 01/17/05
I SSES MANUAL Manual Name :
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1/2
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Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL-Y 4.*
TEXT 3.9.6
Title:
REFUELING TEXT 3.9.7
Title:
REFUELING TEXT 3.9.8
Title:
REFUELING TEXT 3.10.1
Title:
SPECIAL 01 TEXT 3.10.2
Title:
SPECIAL 01 TEXT.3.10.3
Title:
SPECIAL 01 TEXT 3.10.4
Title:
SPECIAL 01 TEXT 3.10.5
Title:
SPECIAL 01 TEXT 3.10.6
Title:
SPECIAL 01 TEXT 3.10.7
Title:
SPECIAL 01 TEXT 3.10.8
Title:
SPECIAL 0]
OPERATION OPERATION OPERATION
?ERATIONS
?ERATIONS
?ERATIONS
?ERATIONS
?ERATIONS
?ERATIONS
?ERATIONS PERATIONS 0
11/15/2002 I IS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL
(,
0 11/15/2002 IS RESIDUAL HEAT REMOVAL (RHR) -.
a HIGH'WATER LEVEL
, <A 0
11/15/2002 -
rS RESIDUAL HEAT REMOVAL (RHR)
LOW.WATER LEVEL 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 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 Page 8 of 8 Report Date: 01/17/05 Page 8 of 8 Report Date: 01/17/05
f i; t.~,<f Jv' SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS.(TECHNICAL SPECIFICATIONS BASES),
Section TOC Title.
Table of Contents I I f,-
B 2.0 SAFETY LIMITS BASES s..
'Page SiB20-2' Page TS/B2.0-3 Pages TS/ B 2.0-4 and TS /eB 2:-0 Page S:,/rB 2.0-,&.,; :
Pages B 2.0-7 through B 2.09" B 3.0 LCO AND SR APPLICABILITYBASES
/
Pages Br3.0-1 through B-3'.0S- -
Pages TS / B 3.0-8 and TS / B 3.0-9 Pages B 3.0-10 through'B 3.0-12
\\
.7 Pages TS B 3.0-13 throughtTSt/ B 3.0-15,, $'
B3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-5 PagesTS / B.3.1-6andTS/B 31-77 Pages'B 3.1-8 through B 31-27 'i Pages TS / B 3.1-28 /
Pages B 3.1-29 through'BZ3?1-36'
,Pages TS /.B 3.1-37`,i-Pages B 3.1-38 through B 31-51 '
B 3.2 POWER DISTRIBUTION LIMITS BASES Page TSlB 3.2-1 _4<
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Page TS / B3.2-2 Page TS lB 3.2-3 Page.TS / B 3.2-4 PagesTS IB 32-5 and TS 7 1B'3.2-6
,Page B 3.2-7 Pages TS / B 3.2-8 through 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.
..PageTS/B3.2-16, Pages B 3.2-17 and B 3.2-18 Page TS /.B 3.2-19 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS I B 3.3-10 PageTS/B3.3-11 Pages TS / B 3.3-12 through TS / B 3.3-27 Pages TS / B 3.3-28 through TS / B 3.3-31 Pages TS / B 3.3-32 and TS /B 3.3-33 SUSQUEHANNA-UNIT 1
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Section' Title Pages TS B 3.3-34 through TS B 3.3-43 Pages TS I B 3.3-43a through TS I B 3.3-43i Pages TS / B 3.3-44 through TS / B 3.3-54 Pages B 3.3-55 through B 3.3-63 Pages TS l B 3.3-64 and TS l B 3.3-65 Page TS I B 3.3-66 Page TS I B 3.3-67 Page TS B 3.3-68 Pages TS I B 3.3-69 and TS I B 3.3-70 Pages TS I B 3.3-71 through TS / B 3.3-75 Page TS / B 3.3-75a Pages TS I B 3.3-75b through TS / B 3.3-75c Pages B 3.3-76 through B 3.3-89 Page TS I B 3.3-90 Page B 3.3-91 Page TS I B 3.3-92 through'TS I B 3.3-1 00 Pages B 3.3-101 through B 3.3-103 Page TS I B 3.3-104.
Pages B 3.3-105 and B 3.3-106 Page TS I 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 I B 3.3-112 and TS I B 3.3-112a Pages B 3.3-1 13 and B 3.3-114*
Page TS/ B 3.3-115 Page TS/B 3.3-116 Page TSlB3.3-117 Pages B 3.3-118 through B 3.3-122 Pages TS I B 3.3-123 through TS I B 3.3-124 Page TS/ B 3.3-124a Pages B 3.3-125 and B 3.3-126 Page TS l B 3.3-127 Pages B 3.3-128 throught B 3.3-130 Page TS I B 3.3-131-Pages B 3.3-132 through'B 3.3-137 Page TSIB3.3-138 Pages B 3.3-139 through B 3.3-149 Page TS I B 3.3-150 through TS I B 3.3-162 Page TS/B3.3-163 Pages TS I B 3.3-164 through TS I B 3.3-177 Pages TS I B 3:3-178 and TS I B 3.3-179 Page TS B 3.3-179a Page TS B 3.3-179b Page TSlB3.3-179c Page TS I B 3.3-180 Page TS / B 3.3-181 Revision 0
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2, Section Title
-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 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 Page TS / B 3.4-3 and Page'TS / B 3.4-4 Pages TS / B 3.4-5 through TS I 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 i B 3.4-17 PageTS / B 3.4-18 Pages B 3.4-19 through B 3.4-28 Page TS/B3.4-29 Pages B 3.4-30 through B 3.4-48 Page TS I 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 I B 3.4-54 Page TS I B 3.4-55 Page TS I B 3.4-56 Page TS I B 3.4-57 Pages TS I B 3.4-58 through TS I B 3.4-60 B 3.5 ECCS AND RCIC BASES.,
Pages B 3.5-1 and B 3.5-2 Page TS / B 3.5-3 Pages TS / B 3.5-4 and TS I 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 / B 3.5-16 through TS / B 3.5-18 Pages B 3.5-19 through B 3.5-24 Page TS/B3.5-25 Pages B 3.5-26 through B 3.5-31 B 3.6
-CONTAINMENT SYSTEMS BASES Page TS/ B 3.6-1 Page TS I B 3.6-la Pages TS / B 3.6-2 through TS I B 3.6-5 Page TS/B3.6-6 Pages TS / B 3.6-6a and TS I B 3.6-6b Page TS I B 3.6-6c
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SUSQUEHANNA STEAM ELECTRIC STATION
-UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Pages B 3.6-7 through B 3.6-14 PageTS/B3.6-15 Pages TS / B 3.6-15a and TS / B 3.6-1 5b Page B 3.6-16 Page TS / B 3.6-17 Page TS/B3.6-17a-Pages TS / B 3.6-18 and TS-B 3.6-19 Page TS/B3.6-20 Page TS / B 3.6-21 Page TS / B 3.6-22 Page TS B 3.6-22a Page TS I 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/B3.6-27 Page TS/B3.6-28 Page TS / B 3.6-29 Page TS/B 3.6-30 Page TS/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 / B 3.6-40 Pages B 3.6-41 through B 3.6-43 Pages TS / B 3.6-44 through TS I B 3.6-51 Page. TS / B 3.6-52 Pages B 3.6-53 through B 3.6 PageTS/B3.6-64 Pages B 3.6-65 through B 3.6-83 PageTSIB3.6-84 Pages TS / B 3.685 and TS / B 3.6-86 Pages TS / B 3.6-87 through TS I B 3.6-88a Page TS /B 3.6-89 Page TS/B3.6-90 Page TS / B 3.6-91 Pages TS / B 3.6-92 through TS I B 3.6-96 Page TS / B 3.6-97 Pages TS / B 3.6-98 and TS I B 3.6-99 Page TS / B 3.6-100 Pages TS / B 3.6-101 and TS / B 3.6-102 Pages TS / B 3.6-103 through TS / B 3.6-105 Pages TS I B 3.6-106 and TS / B 3.6-107
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SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECT7ONS (TECHNICAL SPECIFICATIONS BASES)
Section Title.
B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS I B 3.7-6 Page TS / B 3.7-6a Pages TS / B 3 3.7-6b and TS / B 3.7-6c Page TS / B 3.7-7 Pages TS / B 3.7-8 through TS / B 3.7-11 Pages TS / 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 PageTS/B3.7-30 Pages B 3.7-31 through B 3.7-33 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS / B 3.8-1 through TS I B 3.8-4 PageTS/B3.8-5 Pages TS / B 3.8-6 through TS/B 3.8-8 Pages TS / B 3.8-9 and TS / B 3.8-10 Pages TS / B 3.8-11 and TS / B 3.8-17 PageTS/B3.8-18 Pages TS / B 3.8-19 through TS / B 3.8-21 Pages TS / B 3.8-22 and TS /B3.8-23 Pages TS / B 3.8-24 through' TS / B 3.8-37 Pages B 3.8-38 through B 3.8-53 Pages TS / B 3.8-54 through TS I B 3.8-61 Page TS /B 3.8-62 PageTS/B3.8-63 Page TS / B 3.8-64 PageTS/B3.8-65 Pages TS/B 3.8-66 through B 3.890 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-1a Pages TS / B 3.9-2 through TS / B 3.9-4 Pages B 3.9-5 through B 3.9-30 B 3.10 SPECIAL OPERATIONS BASES PageTS/B3.10-1 Pages B 3.10-2 through B 3.10-31 PageTS/B3.10-32 Pages B 3.10-33 through B 3.10-37 PageTS/B3.10-38 TSB1 te LOES 12r29M4 Revision 2
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B 3.7-PLANT SYSTEMS B 3.7.6 Main Turbine Bypass System BASES Main Turbine PPL Rev. 1 Bypass System B 3.7.6..-
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BACKGROUND The Main Turbine Bypass System is designed to control steam pressure when reactor steam generation exceeds turbine requirements during unit startup, sudden load reduction, and cooldown. It allows excess steam flow from the reactor to the condenser without going through the turbine. The full bypass capacity of the system is approximately 25% of the Nuclear Steam Supply System rated steam flow. Sudden load reductions within the capacity of the steam bypass can be accommodated without reactor scram. The Main Turbine Bypass System consists of five valves connected to the main steam lines between the main steam isolation valves and the turbine stop valve bypass valve chest. Each of these five valves is operated by hydraulic cylinders. The bypass valves are controlled by the pressure regulation function of the Turbine Electro Hydraulic Control System, as discussed in the FSAR, Section 7.7.1.5 (Ref. 1). -The bypass valves are normally closed, and the pressure regulator controls the turbine control valves that direct all steam flow to the turbine. If the speed governor or the load limiter restricts steam flow to the turbine, the pressure regulator controls the system pressure by opening the bypass valves.
When the bypass valves open, the steam flows from the bypass chest, through connecting piping, to the pressure breakdown assemblies, where a series of orifices are used to further reduce the steam pressure before the steam enters the condenser.
APPLICABLI SAFETY ANALYSES E
The Main Turbine Bypass System has two modes of operation. A fast opening mode is assumed to function during the turbine generator load rejection, turbine trip, and feedwater controller failure transients as discussed in FSAR Sections 15.2.2, 15.2.3, and 15.1.2 (Refs. 2, 3, and 4).
- A pressure regulation mode is assumed to function during the control rod
- withdrawal error and recirculation flow controller failure transients as discussed in FSAR Sections 15.4.2 and 15.4.5 (Refs. 5 and 6). Both modes of operation are assumed to function for all bypass valves assumed in the applicable safety analyses. Opening the bypass valves during the above transients mitigates the increase in reactor vessel pressure, which affects both MCPR and LHGR during the event. An inoperable Main Turbine Bypass System may result in a MCPR and / or LHGR penalty.
The Main Turbine Bypass System satisfies Criterion 3 of the NRC Policy Statement. (Ref. 7)
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J PPL Rev. 1 Main Turbine Bypass System
'B 3.7.6 BASES (continued)
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LCO The Main Turbine Bypass System fast opening and pressure regulation modes are required to be OPERABLE to limit the pressure increase in the main steam lines and reactor pressure vessel during transients that cause a pressurization so that the SafetyLimit MCPR and LHGR are not exceeded. With the Main Turbine Bypass System inoperable, modifications to the MCPR limits (LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)") and LHGR limits (LCO 3.2.3, -LINEAR HEAT GENERATION RATE (LHGR)*) may be applied to allow this LCO to be met. The MCPR and LHGR limits for the inoperable Main Turbine Bypass System are specified in the COLR. An OPERABLE Main Turbine Bypass System requires the bypass valves to open in response to increasing main steam line pressure.. Licensing analyses credit an OPERABLE Main Turbine Bypass System as having both the bypass valve' fast opening mode and pressure regulation mode. The fast opening mode is required for transients initiated by a turbine control valve or turbine stop valve closure. The pressure regulation mode is required for transients where the power increase exceeds the capability of the turbine control valves.
The cycle specific safety analyses assume a certain number of OPERABLE main turbine bypass valves as an input (i.e., one through five). Therefore, the Main Turbine Bypass System is considered OPERABLE when the number of OPERABLE bypass valves is greater than or equal to the number assumed in
-the safety analyses. The number of bypass valves assumed in the safety analyses is'specified in the COLR. This response is within the assumptions of the applicable analysis (Refs. 2 - 6).
APPLICABILITY The Main Turbine Bypass System is required to be OPERABLE at 2 25% RTP to ensure that the fuel cladding integrity Safety Limit is not violated during all
- applicable transients. As discussed in the Bases for LCOs'3.2.2 and 3.2.3, sufficient margin to these limits exists at < 25% RTP. Therefore, these requirements are only necessary when operating at or above this power level.
ACTIONS A.1 If the Main Turbine Bypass System is inoperable and the MCPR and LHGR limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are not applied, the assumptions of the design basis transient analysis may not be met. Under such circumstances, prompt action should be taken to restore the Main Turbine Bypass System to OPERABLE status or adjust the MCPR and LHGR limits accordingly. The 2-hour Completion Time is reasonable, based on the time to complete the Required Action and:
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PPL Rev. 1 Main Turbine Bypass System B 3.7.6
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BASES ACTIONS A.1 (continued) the low probability of an event occurring during this period requiring the Main Turbine Bypass System.
B.1 If the Main Turbine Bypass System cannot be restored to OPERABLE status or the MCPR and LHGR limits for an inoperable Main Turbine Bypass l System are not applied, THERMAL POWER must be reduced to' c 25% RTP. As discussed in the Applicability section, operation at
< 25% RTP results in sufficient margin to the required limits, and the Main Turbine Bypass System is not required to protect fuel integrity during the applicable transients.
The 4-hour Completion Time is reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.6.1 REQUIREMENTS Cycling each required main turbine bypass valve through one complete cycle
-of full travel (including the fast opening feature) demonstrates that the valves are mechanically OPERABLE and will function when required. The 31-day Frequency is based on engineering judgment, is consistent with the' procedural controls governing valve operation, and ensures correct valve positions. Operating experience has shown that these components usually pass the SR when performed at the 31-day Frequency. Therefore, the Frequency is acceptable from a reliability standpoint.
SR 3.7.6.2 The Main Turbine Bypass System is required to actuate automatically to perform its design function. This SR demonstrates that, with the required system initiation signals (simulate automatic actuation), the valves will actuate to their required position. The 24-month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown the 24-month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.
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I PPL Rev. 1 Main Turbine Bypass System B 3.7.6 BASES SURVEILLANCE SR 3.7.6.3 REQUIREMENTS (continued)
This SR ensures that the TURBINE BYPASS SYSTEM RESPONSE TIME is in compliance with the assumptions of the appropriate safety analysis. The response time limits are specified in unit specific documentation. The 24-month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and because of the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown the 24-month Frequency, which is based on the refueling cycle, is acceptable from a reliability standpoint.
REFERENCES
- 1. FSAR, Section 7.7.1.5.
- 2. FSAR, Section 15.2.2.
- 5. FSAR, Section 15.4.2
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- 6. FSAR, Section 15.4.5
- 7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993.(58 FR 39132).
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