ML053250337
| ML053250337 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/07/2005 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 028401, 2005-48642 | |
| Download: ML053250337 (64) | |
Text
Nov. 07, 2005 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2005-48642 USER INFORMATION:
Name:GERLACH*ROSE M EMPL#:028401 CA#:0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO:
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SSES MANUAL 2 Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date:
11/04/2005 Procedure Name Rev Issue Date Change ID
-Change'Number TEXT LOES 23 11/04/2005
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC.
5 02/04/2005
Title:
TABLE OF CONTENTS TEXT 1.1 0
11/18/2002 A
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1
02/04/2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 3
12/14/2004
Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT -TRIP SETPOINT TABLE TEXT 3.0 0
..;.11/18/2002
Title:
TECHNICAL REQUIREMENT FOR OPERATION '(TRO) APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY TEXT 3.1.1 0
.11/18/2002
Title:
REACTIVITY CONTROL 'SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)" INSTRUMENTATION TEXT 3.1.2 A
0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD)
HOUSING SUPPORT TEXT 3.1.3 1
03/10/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL' ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0
11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL' ROD SCRAM ACCUMULATORS INSTRUMENTATION &
CHECK VALVE TEXT 3.2.1 5
11/04/2005
Title:
CORE OPERATING LIMITS REPORT (COLR)-a--
Pagel of 15 Report Date: 11/04/05 Page I I
of 15 Report Date: 11/04/05 -
SSES MANUAL Manual Name:
TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0
11/18/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2.
0 11/18/2002
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 0
11/18/2002
Title:
INSTRUMENWATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 1
07/06/2005
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION 1'
1
._. I TEXT 3.3.5
Title:
INSTRUMENTATION TEXT 3.3.6
Title:
INSTRUMENTATION TEXT 3.3.7
Title:
INSTRUMENTATION TEXT 3.3.8
Title:
INSTRUMENTATION TEXT 3.3.9 Title-INSTRUMENTATION TEXT 3.3.10
Title:
INSTRUMENTATION TEXT 3.3.11
Title:
INSTRUMENTATION TEXT 3.4.1
Title:
11/18/2002 THIS PAGE INTENTIONALLY LEFT BLANK 2
10/19/2005 TRM ISOLATION ACTUATION INSTRUMENTATION
-0 11/18/2002 MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1
10/22/2003 TRM RPS INSTRUMENTATION 1
11/22/2004 LPRM UPSCALE ALARMf INSTRUMENTATION 1
12/14/2004 REACTOR RECIRCULATION PUMP MG SET STOPS 1
10/22/2003 MVP ISOLATTON INSTRUMENTATION 0
11/18/2002 SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY am S
Page 2 of 15 Report Date: 11/04/05 Page 2 of 15 Report Date: 11/04/05
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-...1 1 "
SSES.-l.MANUALs
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Title:
REACTOR TEXT 3.4.5
Title:
REACTOR TEXT 3.5.1 0
11/18/2002 COOLANT SYSTEM STRUCTURAL,'INTEGRITY.
0 11/18/2002 COOLANT SYSTEM HIGH/LOW'PRESSURE' INTERFACE LEAKAGE MONITORS' 1
12/14/2004 COOLANT SYSTEM. REACTOR..RECIRCULATION' FLOW AND ROD LINE LIMIT 0
11/18/2002 COOLANT SYSTEM REACTORVESSEL MATERIALS"',
1 02/04/2005:
Title:
EMERGENCY CORE COOLING!AND RCIC ADS MANUAL -INHIBIT ga r
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11/18/2002>-,
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Title:
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- 0 11/18/2002.
Title:
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11/18/2002
Title:
CONTAINMENT VENTING OR PURGING
^.
TEXT 3.6.2 0
11/18/2002-,
Title:
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION :INDICATION TEXT 3.6.3 0
11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM -INSTRUMENTATION TEXT 3.6.4 0
11/18/2002.
Title:
CONTAINMENT PRIMARY CONTAINMENT.-CLOSED SYSTEM BOUNDARIES' TEXT 3.7.1 0
11/18/2002.
Title:
PLANT SYSTEMS EMERGENCY SERVICE:.WATER SYSTEM (ESW),'SHUTDOWN'"
Page 3 of 15 Report Date: 11/04/05 Page 3 of 15 Report Date: 11/04/05
SSES MANUAL Manual Name:
TREM Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1
.I
,j JID TEXT 3.7.2
Title:
PLANT TEXT 3.7.3.1
Title:
PLANT TEXT 3.7.3.2
Title:
PLANT TEXT 3.7.3.3
Title:
PLANT TEXT 3.7.3.4
Title:
PLANT TEXT 3.7.3.5
-Title: PLANT TEXT 3.7.3.6
Title:
PLANT TEXT 3.7.3.7
Title:
PLANT TEXT 3.7.3.8
Title:
PLANT TEXT 3.7.4
Title:
PLANT TEXT 3.7.5.1
Title:
PLANT TEXT 3.7.5.2
Title:
PLANT 0
11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL 0
11/18/2002 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 1
08/24/2005 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 2
08/18/2005 SYSTEMS C02 SYSTEMS 0
11/18/2002 SYSTEMS HALON SYSTEMS 0
11/18/2002 SYSTEMS FIRE HOSE STATIONS 0
11/18/2002 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0
11/18/2002 SYSTEMS FIRE RATED ASSEMBLIES 4
09/08/2005 SYSTEMS FIRE DETECTION INSTRUMENTATION 0
11/18/2002 SYSTEMS SOLID RADWASTE SYSTEM 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE
-s Page 4 of 15 Report Date: 11/04/05 Page 4 of 15 Report Date: 11/04/05
SSES.' MANUA.
Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.3 0
11/18/2002 '
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 1
03/01/2005.
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0
11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADlATION MONITORING TEXT 3.7.8 1
12/14/2004.
Title:
PLANT SYSTEMS SNUBBERS
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11/18/2002-
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PLANT SYSTEMS CONTROL STRUCTURE HVAC'
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12/14/2004.
X l-Title: PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)': -'
TEXT 3.8.1
.1 02/04/2005'.
Title:
ELECTRICAL POWER-PRIMARY CONTAINMENT2-PENETRATION CONDUCTOR -OVERCURREN PROTECTIVE DEVICES TEXT 3.8.2.1 1
12/14/2004.
Title:
ELECTRICAL POWER MOTOR OPERATED-VALVES. (MOV) THERMAL OVELOAD PROTECTIONS CONTINUOUS TEXT 3.8.2.2 2
12/14/2004
Title:
ELECTRICAL POWER MOTOR OPERATEDWVALVES (MOV) -THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT 3.8.3 0
11/18!2002_'.'.
Title:
ELECTRICAL POWER DIESEL GENERATOR -(DG) -MAINTENANCE ACTIVITIES-TEXT 3.8.4 0
11/18/2002
Title:
ELECTRICAL POWER 24 VDC.ELECTRICAI-7POWER-SUBSYSTEM'.
TEXT 3.8.5 0
11/18/2002:
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION '.
Page~~,
5 of 15Rpr at:1/40 Page 5 of 15 Report Date: 11/04/05
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1
-j1 TEXT 3.8.6 0
Title:
ELECTRICAL POWER EMERGENCY 11/18/2002 SWITCHGEAR ROOM COOLING TEXT 3.9.1 0
11/18/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0
11/18/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0
11/18/2002
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 0
11/18/2002
Title:
MISCELLANEOUS SEALZSOURCE CON1TAMINATTON TEXT 3.10.2 0
11/18/2002
-Title: MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 0
11/18/2002
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4
Title:
MISCELLANEOUS LEADING 0
11/18/2002 EDGE FLOW METER (LEFM)
TEXT 3.11.1.1
Title:
RADIOACTIVE TEXT 3.11.1.2
Title:
RADIOACTIVE TEXT 3.11.1.3
Title:
RADIOACTIVE TEXT 3.11.1.4
Title:
RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 0
LIQUID 0
LIQUID 0
LIQUID 1
LIQUID 11/18/2002 EFFLUENTS CONCENTRATION 11/18/2002 EFFLUENTS DOSE 11/18/2002 WASTE TREATMENT SYSTEM 12/14/2004 RADWASTE EFFLUENT MONITORING INSTRUMENTATION Page 6
of 15R p _
at : 1 / 4 0 Page 6 of 15 Report Date: 11/04/05
L SSES.
XTJWL manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT -1 TEXT 3.11.1.5
Title:
RADIOACTIVE TEXT 3.11.2.1
Title:
RADIOACTIVE TEXT 3.11.2.2
Title:
RADIOACTIVE TEXT 3.11.2.3
Title:
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12/14/2004' EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION 2
08/24/2005 EFFLUENTS DOSE RATE 0
11/18/2002 EFFLUENTS DOSE -
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11/18/2002.
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05/20/2005 -I VENTILATION EXHAUST TREATMENT SYSTEM '
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'2 12/14/2004'
Title:
RADIOP.CTI7E EFFLUENTS-RADIOACTIVE GASEOUS El TEXT 3.11.3 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 1
12/14/2004"
Title:
RADIOACTIVE EFFLUENTS MONITORING'PROGRAM.
TEXT 3.11.4.2 1
12/14/2004':
Title:
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TEXT 3.11.4.3 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM '
TEXT 3.12.1 0
11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL' STORAGE POOL Page 7 of 15 Report Date: 11/04/05 Page 7 of 15 Report Date: 11/04/05
SSES ILAWAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1
' j TEXT 3.12.2
Title:
LOADS CONTROL 0
11/19/2002 PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT B3.0
Title:
APPLICABILITY TEXT B3.1.1 0
11/19/2002 BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTF2S BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 1
03/10/2005.
-Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL:ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0
11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT_ (COLR)
TEXT B3.3.1 0
11/19/2002
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 0
11/19/2002
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION l-TEXT B3.3.3
Title:
INSTRUMENTATION BASES TEXT B3.3.4
Title:
INSTRUMENTATION BASES 1
02/04/2005 METEOROLOGTCAL MONITORING INSTRUMENTATION 1
07/06/2005 TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Page 8 of 15 Report Date: 11/04/05
r SSES A-NAL
- Manual Name
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.5
Title:
INSTRUMENTATION 0
11/19/2002 ' :
BASES THIS: PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3
10/19/2005
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 0
11/19/2002
Title:
INSTRUMEN'TATION BPSES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8
Title:
INSTRUMENTATION TEXT B3.3.9
Title:
INSTRUMEZNTATION
'BEXT B3.3.10 1
10/22/2003.
BASES TRM REACTOR'PROTECTION SYSTEM (RPS)'INSTRUMENTAi'ION ' :
1 11/2212004-'
BASES *LPRM UPSCALE'i5ALARM INSTRUMENTATION 0
11/19/2002-J -Title: INSTRUMENTATION.BASES.-REACTOR'RECIRC'ULATION PUMPM "MG SET "STOPS" TEXT B3.3.11 1
10/22/2003-
Title:
-INSTRUMENTATIONBASES-MVP,-ISOLATION-:INSTRUMENTATION TEXT B3.4.1 0
11/19/2002
Title:
REACTOR COOLANT.-SYSTEM BASES-REACTOR-COOLANT SYSTEM CHEMISTRY' TEXT B3.4.2
Title:
REACTOR TEXT B3.4.3
Title:
REACTOR TEXT B3.4.4
Title:
REACTOR TEXT B3.4.5
Title:
REACTOR 0
11/19/2002 COOLANnT-SYSTEM:BASESSTRUCTURAL'INTEGRITY 0
11/19/2002.
COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE-MONITOR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR RECIRCULATION FLCW SAND ROD LINE LIMIT 0
11/19/2002 COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS
Pag 9
of 15 Reo. Dae 11040 Page 9 of 15 Report Date:.11/04/05
SSES WANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.5.1
Title:
ECCS AND RC-TEXT B3.5.2
Title:
ECCS AND RC-TEXT B3.5.3
Title:
ECCS AND RC' TEXT B3.6.1
Title:
CONTAINMENT TEXT B3.6.2
Title:
CONTAINMENT INDICATION TEXT B3.6.3
-Title: CONTAINMENT TEXT B3.6.4
Title:
CONTAINMENT TEXT B3.7.1
Title:
PLANT SYSTE1 TEXT B3.7.2
Title:
PLANT SYSTE2 TEXT B3.7.3.1
Title:
PLANT SYSTEI TEXT B3.7.3.2
Title:
PLANT SYST81 TEXT B3.7.3.3
Title:
PLANT SYSTEI I
0 11/19/2002
[C BASES ADS MANUAL INHIBIT 0
11/19/2002
[C BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION 0
11/19/2002
11/19/2002 BASES VENTING OR PURGING 0
11/19/2002 BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION 0
11/19/2002 BASES SUPPRESSION POOL ALARM INSTRUMENTATCION 1
12/14/2004-BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES 0
11/19/2002 IS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWNm 0
11/19/2002 IS BASES ULTIMATE HEAT SINK (UHS)
GROUIM WATER LEVEL 0
11/19/2002 IS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM 1
08/24/2005
[S'BASES SPRAY AND SPRINKLER SYSTEMS 0
11/19/2002
[S BASES C02 SYSTEMS Page 10 of 15 Reor Dae_1/40 Page 10 of 15 Report Date: 11/04/05
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'. Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.4
Title:
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Title:
PLANT SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 HALON SYSTEMS ',
0 11/19/2002-FIRE HOSE STATIONS-TEXT B3.7.3.6
Title:
PLANT 0
11/19/2002 YARD FIRE HYDRANTS AND SYSTEMS BASES HYDRANT HOSE HOUSES TEXT B3.7.3.7
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PLANT TEXT B3.7.3.8
Title:
PLANT SYSTEMS BASES SYSTEMS -BASES 0
11/19/2002','
FIRE RATED ASSEMBLIES i
1 01/12/2004.,
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-Title: PLANT 0
11/19/2002:'
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11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR -
2 TEXT B3.7.5.2 0
11/19/2002
Title:
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TEXT B3.7.5.3
Title:
PLANT 0
11/19/2002 SYSTEMS BASES LIQUID HOLDUP TANKS.-:
TEXT B3.7.6
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PLANT 1
03/01/2005 SYSTEMS BASES ES.SWPUMPHOUSE.vEN2TILATION
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11/19/2002 :'.-,
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12/14/2004
Title:
PLANT SYSTEMS BASES SNUBBERS Page 11 of 15 Report Date: 11/04/05 Page 11 of 15 Report Date: 11/04/05
SSES NoUAL Manual Name:
TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.9 1
12/14/2004
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS NJ TEXT B3.8.1
Title:
ELECTRICAL PROTECTIVE TEXT B3.8.2.1
Title:
ELECTRICAL CONTINUOUS TEXT B3.8.2.2
Title:
ELECTRICAL AUTOMATIC 1
02/04/2005 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES 0
11/19/2002 POWER BASES MOTOR OPERATED VALVES (MOV)
THER'MAL OVERLOAD PROTECTION 1
09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
TEXT B3.8.3
-Title: ELECTRICAL 0
11/19/2002 POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4
Title:
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Title:
ELECTRICAL TEXT B3.8.6
Title:
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11/19/2002 POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM 0
11/19/2002 POWER BASES DEGRADED VOLTAGE PROTECTION 1
02/04/2005 POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING 0
11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 0
11/19/2002
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM Page 12 of 15 Report Date: 11/04/05 Page 12 of 15 Report Date: 11/04/05
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TRM1 Manual
Title:
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Title:
MISCELLANEOUS 0
11/19/2002 BASES ?SEALED SOURCE CONTAMINATION 0
11/19/2002, '
BASES SHUTDOWN 'MARGIN TEST RPS INSTPUMENTATION TEXT B3.10.3 0
11/19/2002'
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT"rFUEI-STORAGE INSTALLATION C(SFSI)
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11/19/2002:"
Title:
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11/19/2002 Y
-Title: RADIOACTIVE-EFFLUENTS BASES. LIQUID-EFFLUTENTS DOSE TEXT B3.11.1.3
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11/19/2002'
Title:
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11/19/20D2i
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RADIOACTIVE EFFLUENTS,BASES RADIOACTIVE LIQUID-PROCESS MONITORING' INSTRUMENTATION TEXT B3.11.2.1 1
12/14/2004 1:
Title:
RADIOACTIVE EFFLUENTS BASES 'DOSE-RATE '-
TEXT B3.11.2.2 0
11/19/2002
Title:
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05/20/2005
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TEXT B3.11.2.6 1
01/27/2004
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS INSTRUMENTATION TREATMENT SYSTEM EFFLUENT MONITORING TEXT B3.11.3
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.2
-Title: RADIOACTIVE EFFLUENTS TEXT B3.11.4.3
Title:
RADIOACTIVE EFFLUENTS TEXT B3.12.1
Title:
LOADS CONTROL PROGRAM TEXT B3.12.2
Title:
LOADS CONTROL PROGRAM TEXT B3.12.3
Title:
LOADS CONTROL PROGRAM 0
BASES 1
BASES 0
BASES 0
BASES 0
BASES 0
BASES 0
BASES 11/19/2002 TOTAL DOSE 12/14/2004 MONITORING PROGRAM-11/19/2002 LAND USE CENSUS 11/19/2002 INTERLABORATORY COMPARISON PROGRAM 11/19/2002 CRANE TRAVEL-SPENT FUEL STORAGE POOL 11/19/2002 HEAVY LOADS REQUIREMENTS 11/19/2002 LIGHT LOADS REQUIREMENTS TEXT 4.1 0
08/31/1998
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0
08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION a-e 14 o 15 Report Date 11/ 4/0 Page 14 of 15 Report Date: 11/04/05
SSES 1ANUAL
= Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.3
Title:
TEXT 4.4
Title:
TEXT 4.5
Title:
TEXT 4.6
Title:
TEXT 4.7
Title:
ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE 0
08/31/1998.
CONTROLS SAFETY-LIMIT VIOLATION 0
08/31/1998 CONTROLS PROCEDURES & PROGRAMS 0
08/31/1998 CONTROLS REPORTING'REQUIREMENTS 0
08/31/1998 CONTROLS RADIATION PROTECTION PROGRAM 0
08/31/1998 CONTROLS TRAINING 1t Page 15 of 15 Report Date: -11/04/05 Page 15 of 15 Report Date: 11/04/05
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 23 UST OF EFFECT7VE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC 1.0 2.0 3.0 3.1 3.2 3.3 TABLE OF CONTENTS USE AND APPLICATION Pages TRM /1.0-1 through TRM /1.0-3 PLANT PROGRAMS
- Page 2.0-1 Pages TRM / 2.0-2 and TRM /2.0-3 Page'TRM / 2.0-4 Page TRM / 2.0-5 Pages TRM / 2.0-6 and TRM /2.0-7 Page TRM / 2.0-8 Pages TRM / 2.0-9 through TRM / 2.0-14 APPLICABILITY Pages TRM / 3.0-1 and TRM /3.0-2 Pages TRM / 3.0-3 Page TRM /3.0-4 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.1-6, Pages TRM / 3.1-7. and TRM / 3.1-8,,.
Pages TRM / 3.1-9 and TRM / 3.1-9a Page TRM/3.1-10 CORE OPERATING LIMITS REPRT Page TRM / 3.2-1
/
Pages TRM / 3.2-2 throough TRM 13Y238 INSTRUMENTATION..-
\\,.N\\,
Pages TRM / 3.3*1 through TRM /3.3-3 Page TRM /3.3.:4'<
Pages 3.3-5 through'3.3-8 Pages TRM / 3.3-9 and TRM / 3.3-9a Page TRM i 3.3-16' Pages TRM /,3.3-11 and TRM / 3.3-11 a Page.TRM /3.3-12 Page TRM / 3.3-13 Page TRM / 3.3-14 Page TRM / 3.3-15 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 through TRM /3.3-21 Page TRM 13.3-22 Pages TRM / 3.3-22a through TRM / 3.3-22d Page TRM / 3.3-23 Pages TRM / 3.3-24 and TRM /3.3-25 Page TRM / 3.3-26 01/28/2005 10/04/2002 08/31/1998 01/28/2005 06/25/2002 04/02/1999 11/15/2004
..II 1
j..' ^, 04/08/1999
'1 03/15/2002 04/08/1999 08/31/1998
'02/25/2005 02/18/1999 02/18/1999 07/07/1999 10/31/2005 07/16/1999 11/28/2000 08/31/1998 12/17/1998 12/17/1998 06/02/2005 03/30/2001 09i1 3/2005 12/14/1998 10/22/2003 06/27/2001 06/14/2002 10/22/2003 11/15/2004 11/15/2004 12/03/2004 05/16/2003 10/22/2003 I
SUSQUEHANNA - UNIT 1 TRM / LOES-1 EFFECTIVE DATE 10131/2005
v 7 I
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 23 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.4 REACTOR COOLANT SYSTEM
-Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-11 Page TRM / 3.4-12 Page 3.4-13 10/23/1998 08/31/1998 12/03/2004 08/31/1998 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 Pages 3.5-2 and 3.5-3 Page TRM /3.5-4 Pages 3.5-5 through 3.5-7 -.-
01/28/2005 08/31/1998
- 04/17/2000 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6 Page TRM / 3.634 -
4-
- Page 3.6-5 Pages TRM / 3.6-6 through TRM /3.6-8 08/31/1998 01/07/2002 08/31/1998 12/31/2002 3.7 PLANT SYSTEMS Pages3.7-1thmugh 3.7-3 Pages TRM / 3.7-4 through TRM /3.7-8 Pages TRM / 3.7-9 and TRM / 3.7-10 Page TRM / 3.7-11 Pages TRM / 3.7-12 and TRM /3.7.13 Page TRM / 3.7-14 Pages TRM /3.7-15 through TRM /3.7-27 Pages TRM / 3.7-28 and TRM /3.7-29 Page TRM / 3.7-30 Pages TRM / 3.7-31 and TRM 3.7-32 Page TRM /3.7-33 Page TRM /3.7-34 Page TRM /3.7-34a Pages TRM / 3.7-35 through TRM /3.7-37 Pages 3.7-38 through 3.7-40 Pages TRM /3.7-41 and TRM i 3.7-41a Pages 3.7-42 and 3.7-43 Page TRM / 3.7-44 Pages 3.7-45 through 3.7-48 Page TRM /3.7-49 Pages TRM / 3.7-50 and TRM /3.7-51 Pages TRM / 3.7-52 Page TRM / 3.7-53 Page TRM 3.7 08/31/1998 08/02/1999 08/16/2005 12/29/1999
.08/02/1999 08/09/2005 08/02/1999 08/09/2005 08/25/2005 11/16/2001 01/09/2004 11/16/2001 10/05/2002 02/01/1999 08/31/1998 02/14/2005 08/31/1998 12/03/2004 10/13/1998 03/08/2003 03/09/2001 12/03/2004 04/15/2003 07/29/1999 SUSQUEHANNA - UNIT 1
- 1. TRM / LOES-2 EFFECTIVE DATE 10/31/2005
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 23 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.8 3.9 ELECTRICAL POWERl-Page TRM / 3.8-1 Pages TRM / 3.8-2 through TRM i 3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM /3.8-10
- Page TRM / 3.8-11 Page TRM /3.8-12 Pages 3.8-13 and 3.8-14; Pages TRM / 3.8-15 through TRM /3.8-17 Page 3.8-18 Page TRM / 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM i3.8-23 Pages 3.8-24 and 3.8-25 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 04/02/2002 01/28/2005 04/02/2002 12/03/2004 08/10/2004 12/03/2004 08/31/1998 04/02/2002 08/31/1998 04/02/2002 08/31/1998 06/06/1999 08/31/1998 08/31/1998 3.10 14 3.11 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Page TRM / 3.10-5 Page TRM / 3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-9 Page TRM/3.11-10 Pages 3.11-11 and 3.11-12 Page 3.11-13 Page TRM / 3.11-14 Pages 3.11-15 and 3.11-186-Pages 3.11-17 and 3.11-18 Page TRM / 3.11-19 Pages 3.11-20 and 3.11-21 Page TRM / 3.11-22 Pages TRM / 3.11-23 and TRM /3.11-24 Page 3.11-25 Pages TRM / 3.11-26 through TRM /3.11-28 Page TRM / 3.11-29 Pages TRM / 3.11.30 through TRM /3.11.32 Pages 3.11-33 through 3.11-37 Page TRM / 3.11-38 Pages 3.11-39 through 3.11-44 Page TRM / 3.i1 Pages 3.11-46 and 3.11-47 08/31/1998 03/08/2003 06/0512002 04/07/2000
- 04/17/2002 08/31/1998 12/0312004 08/31/1998 09/011998 12103/2004 09/01/1998 08/3111998 08/15/2005 08/31/1998 04/02/2002 05/13/2005 09/01/1998 01121/2004 1210312004 01121/2004 08/31/1998 12/0312004 08/31/1998 12103/2004 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 10/31/2005
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 23 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.12 LOADS CONTROL PROGRAM.
Pages TRM / 3.12-1 through TRM 13.12-5 ADMINISTRATIVE CONTROLS
- Pages 4.0-1 through 4.0-8 4.0 02/05/1999 08/31/1 998 SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 10/31/2005
. r d
SUSQUEHANNA STEAM ELECTRIC STATION-PPL Rev. 23 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 B3.1 B 3.2 B 3.3
-B 3.4 B 3.5 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through TRM I B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES
- Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Page TRM / B 3.1-5 Pages TRM / B 3.1.6 and TRM I B 3.1-7 Page TRM B 3.1-8 CORE OPERATING LIMITS BASES Page B 3.2-1 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page B 3.3-2 Pages TRM / B 3.3-3 and TRM I B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through-TRM / B 3.3-9 Page B 3.3-10 Pages TRM / B 3.3-11 and TRM / B 3.3-12 Page TRM / B 3.3-13 Page TRM I B 3.3-14 Page TRM / B 3.3-14a -
Page TRM / B 3.3-14b:
Pages TRM / B 3.3-15 and TRM / B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B 3.3-17a through TRM / B 3.3-17f Pages TRM / B3.3-18 and TRM I B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 Page TRM / B 3.4-S5 Page B 3.4-6 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4 Page TRM / B 3.6-5 I
08/31/1998 03/15/2002 07/13/1999 08/31/1998 02/25/2005 07/13/1999 02/18/1999 08/31/1998 04/07/2000 08/31/1998 01/31/2005 06/02/2005 03/30/2001 08/31/1998 09/13/2005 12/03/2004 06/25/2002 06/14/2002 06/14/2002 10/22/2003 11/15/2004 11/15/2004 05/16/2003 10/22/2003 05/16/2003 08/31/1998 10/15/1999 08/31/1998 08/31/1998 B 3.6 07/26/2001 02/01/1999 08/31/1998 09/23/1999 01/07/2002 SUSQUEHANNA - UNIT 1
. TRM / LOES-5 SEFFECTIVE DATE 10/31/2005
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 23 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL):
Section Title I.. : '.
Effective Date Pages TRM / B 3.6-6 Pages B.3.6-7 through TRM / B 3.6-11 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2,
- Pages TRM I B 3.7-3 through TRM I B 3.7-5 Page TRM I B 3.7-6 Pages TRM / B 3.7-7 and TRM I B 3.7-7a Pages TRM / B 3.7-8 through TRM I B 3.7-10 Page TRM / B 3.7-1 Oa Pages TRM / B 3.7-11 and TRM I B 3.7-11a Pages TRM / B 3.7-12 through TRM / B 3.7-14 Page TRM I B 3.7-14a Page TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Pages TRMIB 3.7-21 and TRM/B 3.7-21 a Pages TRMIB 3.7-22 and TRMIB 3.7-23 Page B 3.7-24 Page TRM / B 3.7-25
-Pages B 3.7-26 through B 3.7-30 Page TRM / B 3.7-31 Page TRM / B 3.7-32 Page TRM / B 3.7-33 Page TRM / B 3.7-34:
Page TRM I B 3.7-35 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 Pages TRM / B 3.8-2 and TRM I B 3.8-2a Page TRM / B 3.8-3 Page TRM I B 3.8-3a Page TRM / B 3.8-4 Page TRM / B 3.8-4a Page TRM / B 3.8-5 Pages TRM / B 3.8-6 through TRM / B 3.8-16 Page TRM / B 3.8-17 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 Page TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Pages TRM / B 3.10-6 and TRM / B 3.10-7 12/03/2004 12/31/2002 08/31/1998 08/02/1999.
08/16/2005 08/02/1999
' 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999
'01/09/2004 02/01/1999 08/31/1998 02/14/2005 04/07/2000 08/31/1998 12/03/2004 08/31/1998 12/03/2004 03/09/2001.
- 04/15/2003 12/03/2004 07/05/2000 04/02/2002 01/28/2005 04/02/2002 04/02/2002 08/10/2004 04/02/2002 08/31/1998 04/02/2002 01/28/2005 08/31/1998 08/31/1998 03/08/2003 08/23/1999 04/17/2002 SUSQUEHANNA - UNIT 1 TRM / LOES-5 EFFECTIVE DATE 10/3112005
- I I
.. _-_ _. -.--
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 23 LIST OF EFFECTIVE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Page TRM / B 3.11-10 Pages TRMIB 3.11-11 and TRMIB 3.11-11a Pages TRMIB 3.11-12 and TRM/B 3.11-13
- Page TRM/ B 3.11-14 Page TRM/ B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM I B 3.11-20 Page TRM I B 3.11-20a Pages TRM / B 3.11-21 through TRM / B 3.11.23a Pages TRM / B 3.11-24 and TRM /B 3.11-25 Pages B 3.11-26 through B 3.11-28 Page TRM I B 3.11-29 and TRM / B 3.11-30 Pages B 3.7-31 through B 3.7-35 Page TRM / B 3.11-36 B.3.12-LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 08130/1998 02/01/1999 04/07/2000 02/01/1999 12/03/2004 02/01/1999 08/30/1998 04/02/2002 04/0212002 05/13/2005 01/21/2004 08/30/1998 12/03/2004 8130119998 02/12/1999 02/05/1999 TRM1 ted LOES 10127105 SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 10/3112005
Core Operating Limits Report (COLR) 3.2.1 PPL Rev. 5 3.2 Core Operating Umits Report (COLR) 3.2.1 Core Operating Umits Report (COLR)
TRO 3.2.1 The Core Operating Umits specified in the attached COLR shall be met.
APPLiCABILITY:
Specified in the referenced Technical Specifications.
ACTIONS CONDITION
-REQUIRED ACTION COMPLETION TIME A. Core Operating Umits A.1 Perform action(s)
Specified in not met.
described in referenced referenced Technical Specification.
Technical Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE
-,FREQUENCY'
--NOTEN/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 1 I TRM 1 32-1 EFFECTIVE DATE 7/07/1999
PPL Rev. 5 PL-NF-05-006 Rev.0 Page 1 of 37
-Susquehanna SES Unit 1 Cycle 14A CORE OPERATING LIMITS:
REPORT' Nuclear Fuels Engineering October 2005
- - % s t
I EN-.
$ o Do.-
SUSQUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 10/31/2005
PPL Rev. 5 PL-NF-05-006 Rev.0 Page 2 of 37 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected No.
Sections Description/Purpose of Revision 0
ALL Issuance of this COLR is in support of Unit I Cycle 14A operation.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1
-TRM/3.2-3 10/31/2005 EFFECTIVE DATE
-PPL Rev. 5 PL-NF-05-006 Rev. o Page 3 of 37 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1,Cycle 14A GORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
......................................................4 2.0 DEFINITIONS........................................................5 3.0 SHUTDOWN'MARGIN.................................................6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)............
7
-5.0 MINIMUM CRITICAL POWER RATIO (MCER 9
6.0 LINEAR HEAT GENER~ATION RATE (LHGR)...........................
- ..20 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS.........
23 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION......................
26 9.0.
POWER IFLOW MAP.................................................
33 10.0 OPRM SETPOINTS....................................................
35
11.0 REFERENCES
36 SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE-DATE 10/31/2005
PPL Rev: 5 PL-NF-05-006 Rev. 0 Page 4 of 37
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT (COLR) for Susquehanna Unit 1 Cycle 14A is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, APRM setpoints, and OPRM setpoints presented -
herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 1 TRMI3.2-5 EFFECTIVE DATE '10/31/2005
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 5 of 37 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE BUNDLE EXPOSURE shall be equal to the total energy
-produced by the bundle divided by the total initial weight of uranium in the fuel bundle.
2.2 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.3 The FRACTION OF LIMMNG POWER DENSITY (FLPD) shall be the LHGR existing at a given height divided by the applicable LHGR for APRM Setpoint Umit for that bundle type.
2.4 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
2.5 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by'the MCPR calculated by the core monitoring system for each fuel bundle.
2.7 MAPRAT is the -ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
2.8 FDLRC is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR for APRM Setpoint Limit for the applicable fuel bundle type.
2.9 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated 2.10 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.
2.11 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.12 Fp is the core flow below which the' OPRM RPS trip is activated.
SUSQUEHANNA UNIT 1 TRM/3.2-6 EFFECTIVE DATE 10/31/2005
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 6 of 37 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 028% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes In core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, MR." The adder, 'R," is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of CRY is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in-MODES 1, 2, 3, 4, and 5. This Includes core shuffling.
.SUSQUEHANNA UNIT 1 TRM/3.2-7 EFFECTIVE DATE 10/31/2005
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 7 of 37 4.0 AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) 4.1
-Technical Specification Reference Technical Specification 3.2.1 4.2 - Description The APLHGRs for ATRIUM-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOG-RPT Operable and Inoperable in Two Loop operation.
The APLHGR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 1
-TRM/3-.2-8.
EFFECTIVE DATE 10/31/2005
C=
1-4 Uj SSES UNIT 1 CYCLE 14A
(
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& 10.
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10000 20000 300 40000 50000 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUM 11 10 FUEL FIGURE 4.2-1 60000 70000
.-a m co0 0)
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 9 of 37 5.0 MINIMUM CRITICAL POWER RATIO (MWPR) 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.7.6, and 3.3.4.1 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a)
EOO-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EOC Figure 52-2: Power-Dependent MCPR value determined from BOO to EOC b)
Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 52-3: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-4: Power-Dependent MCPR valueldetermined from BOO to EOC-c)
EOC-RPT Inoperable I Main Turbine Bypass Operable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC-Figure 5.2-6: Power-Dependent MCPR value determined from BOO to EOC-The MCPR limits in Figures 5.2-1 through 5.2-6 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
5.3 Average Scram Time Fraction Table 5.3-1 provides the relationship between average scram time to control rod position and scram time fraction. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 1 TRM/3.2-10
, f -
EFFECTIVE DATE 10/31/2005
-PPL Rev. 5 PL-NF-05-006
-Rev. 0 Page 10 of 37 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT I TRM/.3.2-11 EFFECTIVE DATE 10/31/2005
.C Jc (A
m T.C=
t-43 2.3 2.2 2.1 2.0
-1 C.,
.-h E 1.9
, 0
..1 1.8
- O 0.7 251.
SSES UNIT 1 CYCLE 14A LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE 1: REALISTIC AVERAGE SCRAM INSERTION TIME L
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
[
~~USED IN DETERMINING MFLCPR J~cE.RNC:T.S.3..
,.4.0, 1.6 IV rI I
cD (108,1.48)
(108,1.40) n-n
-4
--i CA)
I-i 1-S.
(A
-1~
1.5 1.4 1.3 30 40 50 60 70 80 90 100
..,Total Core Flow (MLB/HR) 110 X
P,(D~ v 0-J a)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1
(.
C=
rr D
C
'-I
.H CD CD VI, S.
5-T u-i 3.0
- 2.4
'E n 2.3 0
0_ 2.2 g o 2.1
- i-
- . 2.0:
20
- 30
- 40.
50 60 70 80 90 100.
Core Power (% RATED).
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2 CD Z
m o"6 o
tn 0
a 00 0)
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 13 of 37
,I
. ",--j Main Turbine Bypass Inoperable-IEOC-RPT Operable TRM/3.-2 10/31/2005 SUSQUEHANNA UNIT 1E EFFECTIVE DATE I q
(..
I SSES UNIT 1 CYCLE 14A
(-
L I (A
JC' m
E
-I
--I
'-a 2.3 2.2 2.1 LEGEND
-CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
_ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR 2.0 1.9 CA3 CL
~ E1.8 cn, 1.7 1.6 (30,1.71).
A B
B 0 4
- 1 -
I
-u
-u r-1.1 8,1.71) o,
[1o I^
II r
n C-n
.-c I f.
C,,
1-4 c"
=_ I 1
I
.e 1.5 I
1.4.-
REFERENCE:
T.S. 3.7.6 antd 3.2.2 [-t t
4 4
I
.I 1.3
'I 110 S
I.
- 1.
.1 30 40 50 60 70 80
- Total Core Flow (MLB/HR) 90 100 2
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
- FIGURE 5.2-3
( 0 M< u
-D Z
.v o e
CA
° 0
91 ft0
-4
(i
(..
LI)
C=
r_,
2-4
-4 SSES UNIT 1 CYCLE 14A 3.0 2.9
- 1.
A.
2.8
- 2.7
- 2.6 I
II I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-(25,2.51)
.9-I I
-.1 I.
2.5
\\ I I
I lI SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.4
.E 13 2.3 W
'S4 2.2
.. N)
. ;L 2.1 IL 2.0 1.9 N
I -
I I
i USED IN DETERMINING MFLCPR (40,1.95)
(65.5,1.71)
REFERENCE:
T.S. 3.7.6 a 3.2 2 I
10 1.8
~T1 m
-4
'-A
- -hi U,
1.7 1.6 1.5 1.4 (100,1.71)
I I
I 1 l
.4
.9 9
I 1"
20 30 40 5b.
60 70 80 90 100 Core Power (%0 RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4 ID (0
(D
-4.
CA~
SCD 0
-o I.-
z
--T 91 000)
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 16 of 37 EOC-RPT-Inoperable I Main Turbine Bypass Operable TRM/3.2-17.
SUSQUEHANNA UNIT 1 EFFECTIVE DATE 10/31/2005
- 1.--------- -
_._ -- ---- -I
(
-4 Z-a 2.3 2.2 2.1 2.0 LEGEND
-CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM,
.INSERTION TIME
-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
USED IN DETERMINING MFLCPR I
-I4 R.
N, 4..f s 1.9 4 C-
.0.
r.5 1.7-
-u r-m:
,(D I.
.5 '
1.6 (30,1.53) f I.I i '
i il.
I II I II 7
i i
II I
i tI III-
-n
. -n 4-4
--4 P1 CAp
'-a~
U, P
4 4
I-Af B
1.5 -
~.-
I.
(37,1.52)
(108,1.52)
-I '
I 1.4 i
I_
I I
1 d
I I
REFERENCE:
T.S. 3.3.4.1 and 3.2.21
.* {I I
I I1 1.3 30.
40 50 60 70 80 Total Core Flow (M LBfIR) 90 100 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 110.
(0 (D-Z
-.4 0
0 91 0
C,,
0
-4 C)
I( J.I 14-
..I c--J' m
-- I SSES UNIT 1 CYCLE 14A 3.0 I
I Fa 2.9 2.8 2.7 2.6 I
l I
I I
I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
' l' l
F I
2.5 I
I 31 4
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-I4 I R
-2.4 3 2.3 0) i 2.2 II O 2.1
- a. 2.0 1.9
. (25,2.31)
I I
I I
I II 1.8
.USED IN DETERMINING MFLCPR
-(30,2.14)
A
.REFERENE:
T.S. 3.3.4.1 and 3.2.2 (741.52).
-r
- D (100,1.52) m
-n m
-4 r"3 CD 1.7 1.6
. 1.5 1.4 1.3 20 30 40 5o 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
-.FIGURE 5.2-6 (a~
09 co~
0
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 19 of 37 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.480
-0.490 0.500 0.510 0.520 39 0.630 0.676.
.0.722 0.768 0.814 0.860 25 1.500 1.582 1.664 1.746 1.828 1.910 5
2.700 2.848 2.996 3.144 3.292 3.440 Scram Time 0.000 0.200 OAOO 0.600 0.800 1.000 Fraction Average Scram Realistic Maximum Insertion Time Allowable
.I SUSQUEHANNA UNIT 1 TRM/3.2-20 EFFECTIVE DATE 10/31/2005
...----.------'
'PPL Rev. 5 PL-NF-05-006 Rev.O D"A-MO! At OfV
-raguewz Ul 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2
- Description The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:
Main Turbine Bvpass Operable The LHGR for ATRIUMTm-1 0 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine Bypass Inonerable The LHGR for ATRIUM8m-10 friel shall not exceed the LHGR limit determined from Figure 6.2-2.
0I I
The LHGR limits In Figures 6.2-1 and 6.2-2 are valid for Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 1 E
TRM/3.2-21 EFFECTIVE DATE
- 10/31/2005
If) 16 C
14
~12 10 P1.
3
'1 m
CD3
-- S I
(..
SSES UNIT 1 CYCLE 14A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1500,13.
a ai a
REFERENCE:
T.S. 3.2.3 a
~~~~~...
~~~~~...
=.....
.6;
.W a
I I
.4 aI 6..e..4.."..*..&.Z..*.
l..".
.t->.l.*
@l 6 @-*ll*@X@z'*e S
6 6
6 4
6 6
6 6
6 6
6 6
6 8
6 6
6 6
8 6
6 6
6 4
6 6
a 6
6,.
66
- 4.
6 6
6
' 6 0-§g l
l
- l*~..W@********
4
.6 6
4--
6.
I 6
6 6.*
4 6
6 6
6 6
4 6
I I
f
.6
- 6.
6 6
a 6,
- 6.
6 6..
6..
6 6.
,-..I 6....
-0
'U1 CD 01 CD IO 10C100 20000
.30000 40000 50000 60000 Avera'ge Planar Exposure (MWDIMTU).
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE ATRIUM
-10 FUEL FIGURE 6.2-1 70001
(I CA1 rri C=
I-I Q)
Cr 16-14 r%3 m
r-)
-!4 m
F-A CD, Iw.
's-s CD
-UCD t12 E
- .,(a c
° 10-
.a..rE
- I.
.c 6
4.
-4 SSES UNIT 1 CYCLE 14A a
a a
a SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
REFERENCE:
T.S. 3.2.3 and 3.7.6 J..
.~~~~~~~~~.
..J
.a a
a- -T a
a a
a a
- a :
- :[
USNEDTN EERMINING FDLRX
. I O.
wr..
X..- 7-1... z@
... 4" r
ww@*lXjvv
@ wv@aZbe.ew
...................... @zv@
- a.
a a
a
- ~.
@@@e_
lll
@@lw*.*
a
- a.
a a
a a
a a
a a
a a
a a
a a
a a
- a.
a a
- a a
a a
a a
a 6
0
.33 I
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a
... a.,
a a
a a
'a a '-
a a
a;.a ;
,t J
at a.
a a
~
IV r-CDm
()I I
0.
100 00 20000
.30000 40000 50000 601 Average Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS INOPERABLE ATRIUMXm-10 FUEL FIGURE 6.2-2 000 70000
-. (a n
CD Z
0(A
- %14 Q )
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 23 of 37 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN ANDSETPOINTS 7.1 Technical Specification Reference.
Technical Specification 32.4 and 3.3.1.1 Description The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRS) shall be established as specified in Table 72-1 and Table 7.2-2, including any adjustments per Technical SpecHication LCO 3.2.4.
Technical Specification LCO 3.2.4 provides an option to adjust the APRM setpoints when MFLPD is greater than FRACTION OF RATED THERMAL POWER (FRTP). The adjustment applies to both the APRM flow biased simulated thermal power-upscale scram trip setpoint and flow biased neutron flux-upscale control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Tables 7.2-1 and 7.2-2.
SUSQUEHANNA UNIT'1 TRM/3.2-24 EFFECTIVE DATE 10/31/2005
PPL Rev. 5
' PL-NF-05-006 Rev. 0 Page 24 of 37 Table 7.2-1 APRM Setpoint for
-Two Loop Operation Trip Setpoint Allowable Value S < (0.58W + 59%/6) T --
S (0.58W + 62%) T' SRB < (0.58W + 50%) T SRF S (0.58W + 53%) T Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint -
Allowable Value S s (0.58W + 54%) T
-S
- (0.58W + 57%/O) T' SAB < (0.58W + 45%) T SR8 < (0.58W + 48%) T where: S and SRB are in percent of RATED THERMAL POWER W =
Loop recirculation flow as a percentage of the loop recirculation flow which produces a core flow of 100 million lbs/hr T =
Lowest value of the ratio of FRTP divided by the MFLPD.2 The FLPD is the actual LHGR divided by the applicable LHGR limnit for APRM Setpoints. The LHGR limit for APRM setpoints for ATR1UMT-10 fuel shall be taken from Figure 7.2-1.
The LHGR for APRM setpoint limits in Figure 7.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable for both Two and Single Loop operation.'
For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations..
APRM flow biased simulated thermal power-upscale scram allowable value in this table is equal to the value established in Technical Specification 3.3.1.1.
2 For the calculation of T, the'value of MFLPD shall be the maximum value of FDLRC.
SUSQUEHANNA UNIT 1 TRM/3.2-25 EFFECTIVE DATE 10/31/2005 i
11 (I
I I
S C
SSES UNIT 1 C YCLE.14A N.
J (A
1-4 I a ao 14 -
'12a CA) lo 15000,15.0
~~~ ~
~
- a..
a a
.5 a
a.
a
- a.
a
.a
.REFERE CE:.S.2.4,:
- ~ :
USED INDETERMINING FDLRC an;: *..
.I. ^
l a
a aI I
5 l
- f S
a' S
S 5
5
-a
- ~
a*
a a,
5'a l
§ l
l a
-a a
S a
a 5
a_
a
'sl l
e l
l
.5 I
a a
a.
l s
§ e
l'!!t§!!tJt:4.J
.a a..'!
a a :,.
.6.
.0.
.0..8:
3 a
a a
.a a,
a a
a a
. 5.
- 5.
a..
, S j_
5.
a a
a a
, t a
a.,,,,.
a :.S. a
.,... j
, t S
a a
a 5
a a
.a a
a S
a a,
a, a
- a.
a a
- a.
a a
- a.
- a.
s@*@
l
,J a -
a a
al a
a s
.,S S
S a
S
-a.5
. a ',
_ a a
a a
- a.
a
.a I
-.1....
1 I ^
T-U (D
I 01D:,.,-..
m C-)
"I C.)
I-a
-S..
C=)
6 A
0 10000 20000 30000 40000 50000 60000 Averige Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE ATRIUM Tm -10 FUEL FIGURE 7.2-1 70 000 co <
CD Z
(A1
()
0
- ~ J 0)
t
-PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 26 of 37 4'
8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Snecification Reference Technical Specification 3.2.1,i 32.2, 3.2.3, 3.2.4, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLI-iGR The APLHGR limit for ATRiUMhf-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Single Loop operation.
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUMm-1 0) shall be the greater of:
a)
Flow-Dependent MCPR value determined from Figure 82-2 OR b)
The Power-Dependent MCPR value determined from one of the following figures, as appropriate:
Figure 82-3: EOC-RPT and Main Turbine Bypass Operable from BOC to EOC Figure 8.2-4: Main Turbine Bypass Inoperable / EOC-RPT Operable from
-BOC to EOC Figure 8.2-5: EOC-RPT Inoperable /Main Turbine Bypass Operable from BOC to EOG The MCPR limits in Figures 8.2-2 through 8.2-5 are valid only for Single Loop operation.
Linear Heat Generation Rate'Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
SUSQUEHANNA UNIT I TRM/3 2-27 EFFECTIVE DATE 10/31/2005
-PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 27 of 37 Average Power Ranae Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR lima for APRM setpoints for Single Loop operation are defined in Section 7.0.
i SUSQUEHANNA UNIT 1 I TRM/3.2-28 EFFECTIVE DATE 10/31/2005
SSES UNIT 1 CYCLE 14A C
m I
f-S 16 14
. :12 E
N. r-.7 5.
m Q
a....
- a.
a..
a I.
- a.
S a
S
.a 5........
I.
4 5
4*
S
- .l 4.-
..3.4.1.
an 3.2.1 4
4
-4SS S
I 4-4 4
m
.67a00a4
'-ii n1 I,,.
t--A CA)
'Il C-S U,0 6
Dr' o -,n 01 D00 0) 4 0
10000 20000 30000 40000 50000 60000 Avemge Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION ATRIUMTM 10 FUEL FIGURE 8.2-1 70000 0
-C
U..*
SSES UNIT 1 CYCLE 14A C'.
(A C
(A C
P1 C
-4
-j
-4 C3 63 P1
'1-n P1 C-)
-4
'-4 P1
-4 I',
63 N,
U, 2.6 2.5 2.4 2.3 E
-Z c
I 2.2
- 0..
.0
, C) 2 2.1 I
I I
I 4
5 1-4 113 YU~E i
ID E A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME E B: REALISTIC AVERAGE SCRAM INSERTION TIME 4
I I-
- 1 I
I I
I 4
I
- 1*
I USED IN DETERMINING MFLCPR 1-I Y
Y I
(30,2.19) 0A-B
.i,,,
II
.. I.-
I
. 1
'(108,2.19)
I 9
9 I
-u mI,..,
.cI-CD ot 2.0 1.9 1.8 NCE: T.S. 3.4.1 '
.2.
I 30 40 50 60 70 80 90 100
. Total Core Flow (MLB/HR) 110 (a
.., CD 6 0-4.
63.c
-4 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
- 0 7
z
'1 0
0 0)
<".-f' SSES UNIT 1 CYCLE 14A II'-- j I
J=
1-4 3.5 3.4 3.3 3.2 3.1 CA3.
I-.
3.0 2.9 cn 2.8 1 2.7 0 2.B
- a a, X 2.5 I'
I I
I I
I
____LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
_(25,2.76)
=9USED IN DETERMINING MFLCPR l
-u r
(10I.
(1 00,2.19) 2.4 m
-rn m
m 1---
U, 2.3 2.2 2.1 2.0 1.9 I
l
-1
REFERENCE:
T.S. 3.4.1 and 3.2.
I 4
I I
t
- e. I I.
I I
.1 1
4 4
9 9
4 20 30 40 50 60 Core Power (% RATED) 70 80 90
- MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
.FIGURE 8.2-3 100 CD *
,C) o n 0
C.0 0
. - S4 0)
C=
(A3 m
C)
H CA)
DO' CA) mn (S
SSES UNIT 1 CYCLE 14A (Q..
3.5 3.4 3.3 3.2
. 3.1 3.0 E 2.9 tm 2.8 2.7 0~
E 2.5 2.4 2.3 2.2 2.1 2.0 1.9 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
.INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (25,3.00)
A I
P S
O 376 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
\\.
. v VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I
USED IN DETERMINING MFLCPR I
t
_I_
I
9 5
- 9.
- 9.
4 (40,2.33)
B
.19 3.7.6, an
-u CD A- -
iC,',
(100,2.19) 20 30 40 50 60 70 80 90 Core Power (% RATED)
- MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE! EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4 100 (0 '
r I a,
CD' Z.
O 6'
- 6.
0 4
0)
(.
U SSES UNIT 1 CYCLE 14A
(
il GI C:
()
Jo C_
m
'-a A.I
.:CA3 N,
co)
Cd n
-n m
m C) m t-3 CA N,
%3, 3.5 3.4 3.3
1 l
I 1:
I l
l l1 l
- 1. IrtI ID A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 9: REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 3.1
- 3.0 3,0
'E 2.9 im 2.8 l
2.7,
- 0.
. ° 2.6 CL C.)
2 2.5 2.4 2.3
- 2.2
- 2.1 2.0 1.9 IV I~~~~
I I
I I
.1
.I I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES F7 I
1
tI I ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 H-vI44 4
I USED IN DETERMINING MFLCPR n
I N~~-(30,2.56) a.,.
-U
I-.
Cii I
-14REFE RS NCEi T.S. 3.4.1, 3.3.4.1, and 3.2.2 I I
I I
4 I
I I
I I II (100,2.19)
I0 I
1 1
I I
4
- 20.
30 40 s5 60 70 Core Power (%. RATED) 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5 (D
v Q )
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PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 33 of 37
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9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.3 9.2
- Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and 11 of the Power/ Flow map, Figure 9.1.
If the OPRM Instrumentation Is OPERABLE per TS 3.3.1.3, Region I of the Power / Flow map is considered an immediate exit region.
If the OPRM Instrumentation Is inoperable per TS 3.3.1.3, Region I of the Power I Flow map is considered an immediate scram region.
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 1 TRM/3.2-34 EFFECTIVE DATE 10/31/2005
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100-90 STABIuTY REGIiN I IF OPRAM INOPERABLE, IMMEDIATE SCRAM AW ON-178.C F OPRM OPERABLE, IMMEDIATE EaT AW ON-178U=
i -L UNIT I POWER I FLOM 100% Rod Line APRM Rod B Trfp Setpofnt LJ point J-J I
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STABtItTY REGION 1i IMMEDIATELY ED(T 1AW ON-1t-002 l
RESTR=CED REGIO (As derWInedh A~achmeit G to NDA.-OA4MSS 120 110 100 90 80
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Figure 9.1 Power / Flow Map TRM/3.2-35 SUSQUEHANNA UNIT 1 EFFECTIVE DATE 10/31/2005
PPL Rev. 5 PL-NF-05-006 Rev. 0 Page 35 of 37 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.3 102 - Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 1.0 and are listed below:
Sp
=
1.11 Np
=
14 Fp Defined in TS SR 3.3.1.3.5 SUSQUEHANNA UNIT 1
.TRM/3.2-36 EFFECTIVE DATE 10/31/2005.
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PL-NF-05-006 Rev. 0O Page 36 of 37
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. PL-NF-90-001 -A, Application of Reactor Analysis Methods for BWR Design and Analysis, July 1992.
- 2. PL-NF-90-O01, Supplement 1-A, 'Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1," August 1995.
- 3. PL-NF-90-001, Supplement 2-A, OApplication of Reactor Analysis Methods for BWR Design and Analysis: CASMO-3G Code and ANFB Critical Power Correlation,; July 1996.
- 4. PL-NF-90-001, Supplement 3-A, mApplication of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," March 2001.
- 5. XN-NF-80-19(A), Volume1, and Volume 1 Supplements 1 and 2 (March 1983),
and Volume 1 Supplement 3 (November 1990), 'Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis,*
Exxon Nuclear Company, Inc.
- 6. XN-NF-80-19(P)(A), Volurmes 2, 2A, 2B, and 2C 'Exxon Nuclear Methodology for Boiling Water Reactors-EXEM BWR ECCS Evaluation Model," September 1982.
- 7. XN-NF-80-1 9(P)(A), Volume 3 Revision 2 'Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Umits Methodology Summary Description," January 1987.:'
- 8. XN-NF-80-19(P)(A), Volume 4, Revision 1, Exxon Nuclear.Methodology for Boiling Water Reactors: 'Application of the ENC Methodology to BWR Reloads,N Exxon Nuclear Company, Inc. June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel,' Exxon Nuclear Company, Inc.,
September 1986.
- 10. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, *Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-001A, Revision 1, gUcensing Topical Report for Power Uprate With Increased Core Flow,' Pennsylvania Power & Ught Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT 1 TRM/3.2-37 EFFECTIVE DATE. -10/31/2005
PPE Rev. 5 PL-NF-05-006 Rev. 0 Page 37 of 37
- 12. ANF-89-98(P)(A) Revision I and Revision 1 Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs,' Advanced Nuclear Fuels Corporation, May 1995.
- 13. ANF-91 -048(P)(A), Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors'EXEM BWR Evaluation Model," January 1993.
- 14. XN-NF-79-71 (P)(A) Revision 2, Supplements 1,2, and 3, 'E~xon Nuclear Plant Transient Methodology for Boiling Water Reactors,' March 1986.
- 15. EMF-1997(P)(A) Revision 0, "ANFB-10 Critical Power Correlation," July 1998, and EMF-1997(P)(A) Supplement 1 Revision 0, OANFB-10 Critical Power Correlation High Local Peaking Results," July 1998.
.16. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMN'm System," Engineering Report - 80P, March 1997.
- 17. Caldon, lnc.,'"SS.Wplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM"'
or LEFM CheckPlus~m System," Revision 0, Engineering Report ER-1i6OP, May 2000.
- 18. EMF-85-74(P)(A), -RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.
- 19. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 20. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November 1999.
- 21. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
SIISOQIlFHANNA UNTT I
~
TRMI3.2-39 FFFFCT1VF DATE ~l 1 12311?OO
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PPL Rev. 0 Seismic Monitoring Instrumentation 3.3.2 3.3 Instrumentation 3.3.2 Seismic Monitoring Instrumentation TRO 3.3.2 The seismic monitoring instrumentation showri in Table 3.3.2-1 shall be OPERABLE.
APPLICABILITY:
At all times ACTIONS NOTE
- 1.
Separate condition entry is allowed for each monitor or event.
I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 'Restore seismic 30 days above required seismic
'-monitoring instrument to monitoring instruments OPERABLE status OR inoperable.
At next outage with containment entry, not to exceed the next refueling outage for inaccessible containrment component.
B. Instrument channels B.1 Initiate action to Immediately actuated during a retrieve all data from seismic event greater actuated instruments and than or equal to 0.05g.
to determine magnitude of
- the vibratory ground motion.
AND B.2 Restore each affected -
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> instrument channel to OPERABLE status.
AND B.3 -Perform CHANNEL
-CALIBRATION for each 5
y affected instrument channel I
I SUSQUEHANNA - UNIT I IRM /3.3-4 EFFECTIVE DATE 11/28/2000
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PPL Rev. 0 Seismic Monitoring Instrumentation
- 3.3.2 TECHNICAL REQUIREMENT SURVEILLANCE NOTE
- 1.
Refer to Table 3.3.2-1 to determine which TRSs apply for each Seismic Monitoring Channel.
- 2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE FREQUENCY TRS 3.3.2.1 Perform CHANNEL FUNCTIONAL TEST 184 days TRS 3.3.2.2 Perform CHANNEL CALIBRATION 24 months x
K SUSQUEHANNA.7 UNIT 1 -
TRM 3.3-5 EFFECTIVE DATE 8/31/1998
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11 Seismic Monitoring Instrumentation 3.3.2.
PPL Rev. 0 INSTRUMENTS AND SENSOR L
- 1. Triaxial Accelerometers and T
- a. Reactor Equipment, Unit I
- b. Reactor Bldg. Floor (RHR),
- c. ESSW Pumphouse Floor
- d. Containment Foundation, t
- e. Containment Structure, Un
- f. Containment Foundation, L
- 2. Peak Accelerographs TABLE 3.3.2-1 SEISMIC MONITORING INSTRUMENTATION MINIMUM MINIMUM MEASUREMENT INSTRUMENTS
.OCATIONS RANGE OPERABLE riggers
- -025 to +0.25g 1
,Unit 1
-0.25 to +0.25g 1
-0.25 to +0.25g 1
Jnit 1
-0.25 to +0.25g iti
-0.25 to +0.25g 1
lnIt2
-0.25 to +O.25g 1
TEST REQUIREMENTS TRS 3.3.2.1 TRS 3.3.2.2 TRS 3.3.2.1 TRS 3.3.2.1 TRS 3.3.2.2 TRS 3.3.2.1 TRS 3.3.2.2 TRS 3.3.2.1 TRS 3.3.2.2 TRS 3.3.2.1 TRS 3.3.2.2 TRS 3.3.2.2
- a. Reactor Equipment, Unit 2
-0.5 to +0.5g -
1 TRS 3.3.2.2
- b. Reactor Piping, Unit 2
-0.5 to +0.5g 1
-TRS 3.3.2.2
- c. RHR Pump Room, Unit 2
-w0.5 to +0.5g 1
- TRS 3.3.2.2
- 3. Response-Spectrum Analyzer()I/Recorders° 1.0 to 32 Hz TRS 3.3.2.1 One Instrument: on-line capability, with control room annunciation for triggered channels; off-line capability for all channels.
(
Receive signals from respective accelerometers.
-. 1 '
J SUSQUEHANNA-UNIT 1 TRM I 3.3-6 EFFECTIVE DATE 8/31/1998