ML043570518
| ML043570518 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/15/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 028401 | |
| Download: ML043570518 (122) | |
Text
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I SSES MANtUAL Manual Name:-...M&
Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date:
12/14/2004 Procedure Name Rev Issue Date Chans TRM1
- N/A 08/01/2003
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 (07/28/2003)
- e ID Change Number 3748 TEXT LOES 11
Title:
LIST OF EFFECTIVE SECTIONS 12/14/2004 TEXT TOC
Title:
TEXT 1.1
Title:
TEXT 2.1
Title:
4 12/14/2004 TABLE OF CONTENTS 0
USE AND APPLICATION DEFINITIONS 0
PLANT PROGRAMS AND K
TEXT 2.2 3 7 12/14/2004
Title:
PLANT PROGRAMS AND SETPOINTSINSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 0
11/18/2002
Title:
TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY s.
TEXT 3.1.2
/
0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT xi A a TEXT 3.1.3 0
11/18/2002
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 4
11/22/2004
Title:
CORE OPERATING LIMITS REPORT (COLR)
Pa e
f 1 e o t D t : 1 / 4 0 Page I of 15 Report Date:'12/14/04
SSES MANUAL Manual Name 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:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 0
11/18/2002
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION I
i IK)
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 1
.10/22/2003 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 ALARM INSTRUMENTATION I-1 12/14/2004 REACTOR RECIRCULATION PUMP MG SET STOPS
-. 1 10/22/2003 MVP ISOLATION INSTRUMENTATION 0
11/18/2002 SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Report Date: 12/14/04 -
Page 2 of 15
SSES,MANUAL Manual Name:...MM Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.2
Title:
REACTOR TEXT 3.4.3
Title:
REACTOR TEXT 3.4.4
Title:
REACTOR TEXT 3.4.5
Title:
REACTOR TEXT 3.5.1 o
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 REACTOR VESSEL MATERIALS 0
11/18/2002
Title:
EMERGENCY CORE COOLING AND RCIC ADS MANUAL.INHIBIT TEXT 3.5.2 0
11/18/2002-.-
Title:
EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC-SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0
11/18/2002 I:
Title:
EMERGENCY CORE COOLING-AND RCIC-LONG TERM-NITROGEN SUPPLY TO ADS TEXT 3.6.1 0
11/18/2002.
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0
11/18/2002
Title:
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWIELL'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 PRIMARYCONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0
11/18/2002
Title:
PLANT SYSTEMS-EMERGENCY SERVICE WATER SYSTEM'(ESW) :SHUTDOWN Page3 of 15 Report Date: 12/14/04 Page 3 of 15 Report Date: 12/14/04
- SSES; MANUAL Manual Name:--TRML m
.., al,1;4 1
Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 0
11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL 0
11/18/2002 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
11/18/2002 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 0
11/18/2002 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 1
01/12/2004 SYSTEMS FIRE DETECTION INSTRUMENTATION LDCN 3503 TEXT 3.7.4 0
11/18/2002
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1
Title:
PLANT TEXT 3.7.5.2
Title:
PLANT 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVESGAS MIXTURE Page 4 of 15 Report Date: 12/14/04
Page 4.
- of 15 Report Date:
12/14/04'-
SSES MANUAL
- Manual Name-. - TREMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.3
Title:
PLANT SYSTEMS TEXT 3.7.6
Title:
PLANT SYSTEMS TEXT 3.7.7
Title:
PLANT SYSTEMS MONITORING TEXT 3.7.8
Title:
PLANT SYSTEMS LIQUID H(
0 11/18/2002
)LDUP TANKS 0
11/18/2002 ESSW PUMPHOUSE VENTILATION-0 11/18/2002 MAIN CONDENSER OFFGAS.PRETREATMENT LOGARITHMIC RADIATION 1
12/14/2004..'
SNUBBERS TEXT 3.7.9 0
11/18/2002
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1
12/14/2004.
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.8.1 0
11/18/2002
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION-CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 1
12/14/2004
Title:
ELECTRICAL POWER MOTOR OPERATED:VALVES (MOV).THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT 3.8.2.2 2
12/14/2004.-
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (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 'ELECTRICAL-POWER SUBSYSTEM' TEXT 3.8.5 0
11/18/2002 >
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Page 5 of 15 Report Date: 12/14/04 Page 5 of 15 Report Date: 12/14/04
SSES MANUAL Manual Name-
- MM Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 l1 TEXT 3.8.6 0
11/18/2002
Title:
ELECTRICAL POWER EMERGENCY 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 SEAL SOURCE CONTAMINATION 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 TEXT 3.11.1.1
Title:
RADIOACTIVE EFFLUENTS TEXT 3.11.1.2
Title:
RADIOACTIVE EFFLUENTS TEXT 3.11.1.3
Title:
RADIOACTIVE EFFLUENTS TEXT 3.11.1.4
Title:
RADIOACTIVE EFFLUENTS 0
11/18/2002 EDGE FLOW METER (LEFM) 0 11/18/2002 LIQUID EFFLUENTS CONCENTRATION 0
11/18/2002 LIQUID EFFLUENTS DOSE 0
11/18/2002 LIQUID WASTE TREATMENT SYSTEM 1
12/14/2004 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION Page 6 -
of 15 Report Date: 12/14/04'-"'
.SSES MANUAL Manual Name:.-.,TEM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1-TEXT 3.11.1.5 1
12/14/2004
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 1
01/27/2004
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS DOSE -
NOBLE GASES TEXT 3.11.2.3
Title:
RADIOACTIVE EFFLUENTS FORM 0
11/18/2002 DOSE -
TEXT 3.11.2.4
Title:
RADIOACTIVE TEXT 3.11.2.5
Title:
RADIOACTIVE EFFLUENTS EFFLUENTS 0
11/18/2002 GASEOUS RADWASTE TREATMENT SYSTEM 0
11/18/2002 VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6
Title:
RADIOACTIVE TEXT 3.11.3
Title:
RADIOACTIVE TEXT 3.11.4.1
Title:
RADIOACTIVE 2
12/14/2004A EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LDCN 3592 0
11/18/2002 -.
EFFLUENTS TOTAL DOSE 1
12/14/2004 EFFLUENTS MONITORING-PROGRAM TEXT 3.11.4.2 1
12/14/2004-
Title:
RADIOACTIVE EFFLUENTS LAND USE'CENSUS'
..... I.
TEXT 3.11.4.3 0
11/18/2002.
Title:
RADIOACTIVE EFFLUENTS IINTERLABORATORY:COMPARISON PROGRAM TEXT 3.12.1 0
11/19/2002
Title:
LOADS CONTROL PROGRAM. CRANE TRAVEL-SPENT FUEL' POOL STORAGE'POOL Page7 of-iS Report Date: 12/14/04 Page 7-
. of--15 Report Date: 12/14/04
SSES MANUAL Manual Name:--. TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Is TEXT 3.12.2
Title:
LOADS CONTROL TEXT 3.12.3
Title:
LOADS CONTROL TEXT B3.0
Title:
APPLICABILITY TEXT B3.1.1 0
11/19/2002 PROGRAM HEAVY LOADS REQUIREMENTS 0
11/19/2002 PROGRAM LIGHT LOADS REQUIREMENT 0
11/19/2002 BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS 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 0
11/19/2002
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 AND CHECK VALVE INSTRUMENTATION 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 TEXT B3.3.3 0
11/19/2002
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 0
11/19/2002
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Page 8 of 15 Report Date: 12/14/04.
Page _
of 15 Report Date: 12/14/04:;-"'
SSES; MANUAL
- Manual Name -.-2ITEM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1' TEXT B3.3.5
Title:
INSTRUMENTATION TEXT B3.3.6
Title:
INSTRUMENTATION TEXT B3.3.7
Title:
INSTRUMENTATION TEXT B3.3.8
Title:
INSTRUMENTATION TEXT B3.3.9
Title:
INSTRUMENTATION TEXT B3.3.10
Title:
INSTRUMENTATION TEXT B3.3.11 0
11/19/2002 BASES THIS PAGE INTENTIONALLY LEFT BLANK 2
12/14/2004 BASES TRM ISOLATION'ACTUATION INSTRUMENTATION 0
11/19/2002.
BASES MAIN-TURBINE OVERSPEED PROTECTION SYSTEM 1
10/22/2003 BASES TRM REACTOR PROTECTION SYSTEM (RPS)
INSTRUMENTATION 1
11/22/2004' BASES LPRM'UPSCALE ALARM INSTRUMENTATION 0
11/19/2002 BASES REACTOR RECIRCULATION-PUMP MG'SET STOPS 1
10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1
Title:
REACTOR TEXT B3.4.2
Title:
REACTOR TEXT B3.4.3
Title:
REACTOR TEXT B3.4.4
Title:
REACTOR 0
11/19/2002' COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY' 0
11/19/2002'-
COOLANT SYSTEM BASES:-STRUCTURAL INTEGRITY 0
11/19/2002 COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0
11/19/2002 '
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS"'
Page 9 of 15 Report Date: 12/14/04 Page 9 of 15 Report Date: 12/14/04
SSES MANUAL Manual Name:-TS
-T Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.5.1
Title:
Title:
Title:
11/19/2002 BASES ADS MANUAL INHIBIT 0
11/19/2002 BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION 0
11/19/2002 BASES LONG TERM NITROGEN SUPPLY TO ADS 0
11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0
11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 0
11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 1
12/14/2004
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1
Title:
PLANT TEXT B3.7.2
Title:
PLANT TEXT B3.7.3.1
Title:
PLANT TEXT B3.7.3.2
Title:
PLANT TEXT B3.7.3.3
Title:
PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN) 0 11/19/2002 ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL 0
11/19/2002 FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
11/19/2002 SPRAY AND SPRINKLER SYSTEMS
- 0.
11/19/2002 C02 SYSTEMS Page 10 of 15 Report Date: 12/14/04 Page 10 of 15 Report Date: 12/14/04
SSES MANUAL Manual Name:--.-TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL'UNIT'1 TEXT B3.7.3.4
Title:
PLANT TEXT B3.7.3.5
Title:
PLANT TEXT B3.7.3.6
Title:
PLANT 0
11/19/2002 SYSTEMS BASES HALON SYSTEMS 0
11/19/2002 SYSTEMS BASES FIRE HOSE STATIONS' 0
11/19/2002 SYSTEMSBASES YARD FIRE HYDRANTSAND HYDRANT HOSE HOUSES TEXT B3.7.3.7
Title:
PLANT TEXT B3.7.3.8
Title:
PLANT TEXT B3.7.4 k,
v
Title:
PLANT SYSTEMS-BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 FIRE RATED ASSEMBLIES 1
01/12/2004 FIRE DETECTION INSTRUMENTATION 0
11/19/2002'i' SOLID RADWASTE SYSTEM TEXT B3.7.5.1
Title:
PLANT TEXT B3.7.5.2
Title:
PLANT TEXT B3.7.5.3
Title:
PLANT TEXT B3.7.6
Title:
PLANT TEXT B3.7.7 0
11/19/2002 SYSTEMS BASES -MAIN CONDENSER OFFGAS'HYDROGEN MONITOR 0
11/19/2002 SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE 0
11/19/2002' SYSTEMS BASES LIQUID HOLDUP TANKS 0
11/19/2002' SYSTEMS BASES ESSW PUMPHOUSE VENTILATION
0 11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 1
12/14/2004
Title:
PLANT SYSTEMS BASES SNUBBERS Page 11 of. 15 Report Date: 12/14/04 Page 11
- of 15 Report Date: 12/14/04
SSES MANUAL Manual Name_ - -TZHl 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 4
TEXT B3.8.1
Title:
ELECTRICAL PROTECTIVE 0
11/19/2002 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES TEXT B3.8.2.1
Title:
ELECTRICAL CONTINUOUS TEXT B3.8.2.2
Title:
ELECTRICAL AUTOMATIC 0
11/19/2002 POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD 1
09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
PROTECTION -
TEXT B3.8.3
Title:
ELECTRICAL TEXT B3.8.4
Title:
ELECTRICAL TEXT B3.8.5
Title:
ELECTRICAL TEXT B3.8.6
Title:
ELECTRICAL TEXT B3.9.1 0
11/19/2002 POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES 0
11/19/2002 POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM 0
11/19/2002 POWER BASES DEGRADED VOLTAGE PROTECTION 0
11/19/2002 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: 12/14/04 Page 12 of 15 Report Date: 12/14/04
SSES MANUAL Manual Name,-...,TXIB Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.10.1
Title:
MISCELLANEOUS TEXT B3.10.2
Title:
MISCELLANEOUS TEXT B3.10.3
Title:
MISCELLANEOUS TEXT B3.10.4
Title:
MISCELLANEOUS 0
11/19/2002 BASES SEALED SOURCE CONTAMINATION 0
11/19/2002 BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION 0
11/19/2002-BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 0 11/19/2002 BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.11.1.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.1.2 i,
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.1.3
Title:
RADIOACTIVE EFFLUENTS 0
BASES 11/19/2002 LIQUID EFFLUENTS CONCENTRATION 0
11/19/2002.
BASES LIQUID EFFLUENTS DOSE 0
BASES 11/19/2002 LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.2.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.2
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.3 0
11/19/2002 BASES RADIOACTIVE LIQUID PROCESS MONITORING 1
12/14/2004 BASES DOSE RATE 0
11/19/2002 BASES DOSE -
NOBLE GASES 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE -
IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM Page 13 of. 15 Report Date: 12/14/04 Page 13 of 15 Report Date:' 12/14/04
I SSES MANUAL Manual Name:
TM-1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.4 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 2
10/27/2004
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION 1
BASES 01/27/2004 RADIOACTIVE GASEOUS EFFLUENT MONITORING LDCN 3592 TEXT B3.11.3 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE 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 TEXT 4.1 1
BASES 0
BASES 0
BASES 0
BASES 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 0
11/19/2002 BASES HEAVY LOADS REQUIREMENTS 0
11/19/2002 BASES LIGHT LOADS REQUIREMENTS 0
08/31/1998
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0
08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION Page 14 of 15 Report Date: 12/14/04 Page 14 of 15 Report Date: 12/14/04
SSES MANUAL Manual Name:-TRE1 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:
Page 15 of ADMINISTRATIVE CONTROLS 0
ADMINISTRATIVE CONTROLS 0
ADMINISTRATIVE CONTROLS 0
ADMINISTRATIVE CONTROLS 0
ADMINISTRATIVE CONTROLS 08/31/1998 SAFETY LIMIT VIOLATION 08/31/1998 PROCEDURES & PROGRAMS 08/31/1998 REPORTING REQUIREMENTS 08/31/1998 RADIATION PROTECTION PROGRAM 08/31/1998 TRAINING 15 Report Date: 12/14/04 f 15 Report Date: 12/14/04
I
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., - - -
7
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 11 LIST OAEF-FECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Tide
'Effective Dat'e""'==~~~=~' '
TOC TABLE OF CONTENTS 12/03/2004 l
1.0 2.0 USE AND APPLICATION Pages TRM /1.0-1 through TRM /1.0-3 PLANT PROGRAMS Pages 2.0-1 through 2.0-2 Page TRM / 2.0-3 Page TRM I 2.0-4 Page TRM / 2.0-5 Pages TRM / 2.0-6 and TRM 12.0-7 Page TRM 1 2.0-8
~~'
Pages TRM /2.0-9 through TRM /2.0-14 3.0 APPLICABILITY Pages TRM / 3.0-1l-and TRM I3.0-2 11-1 Pages TRM /3.0-3 Page TRM / 3.0-4 3.1 REACTIVITY CONTROL SYSTEM Pages 3.1-1 through 3.1-6 Pages TRM / 3.1-7 andT PPages TRM /'3.1-9 an a
Page TRM /3.1 -10 3.2 CORE OPERATINftI REPORT Page TRM / 3.,, L Pages TRI7 3 t5rough TRM / 3.2-38 3.3 INSTRU Pages TRM7.3-1 through TRM / 3.3-3 TM73-
- .3-4 Pages3.3-5 through 3.3-8 Pa~geRM / 3.3-9 and TRM / 3.3-9a Pa~s TRM / 3.3-10 and TRM / 3.3-11 Page TRM / 3.3-12 Pages TRM / 3.3-13 and 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 / 3.3-22 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 10/04/2002 08/31/1998 08/01/2001 06/2512002 04/02/1999 11/15/2004 12/03/2004 11/15/2004 04/08/1999 03/15/2002 04/08/1999 08/31/1998 06/05/2002 02/18/1999 02/18/1999 07/07/1999 11/15/2004 07/16/1999 11/28/2000 08/31/1998 12/17/1998 12/17/1998 03/30/2001 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 SUSQUEHANNA - UNIT I TRM /LOES-1 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 11 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL) w
.t...
Section Title Effective Date
.e 4;.;-
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 1210312004 08/31/1998 3.5 3.6 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 CONTAINMENT Pages 3.6-1 through 3.6-3 Page TRM 13.6-4 Page 3.6-5 Pages TRM 13.6-6 through TRM I 3.6-8 08/31/1998 04/17/2000 08/31/1998 08/31/1998 01/07/2002 08/31/1998 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08131/1998 Pages TRM /3.7-4 through TRM / 3.7-10 08102/1999
=
Page TRM /3.7-11 12/29/1999 Pages TRM / 3.7-12 through TRM / 3.7-27 08/02/1999 Pages TRM / 3.7-28 through TRM 13.7-32 11/16/2001 Page TRM / 3.7-33 01/09/2004 Page TRM / 3.7-34 11/16/2001 Page TRM / 3.7-34a 10/05/2002 Pages TRM /3.7-35 through TRM /3.7-37 02/01/1999 Pages 3.7-38 through 3.7-40 08/31/1998 Pages TRM / 3.7-41 and TRM / 3.741a 08/11/2000 Pages 3.7-42 and 3.7-43 08/31/1998 Page TRM / 3.7-44 12/03/2004 Pages 3.7-45 through 3.7-48 10/13/1998 Page TRM /3.7-49 03/08/2003 Pages TRM / 3.7-50 and TRM / 3.7-51--
03:0992001 Pages TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 3.8 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM / 3.8-2 04/02/2002 Page 3.8-3 08/31/1998 Page TRM / 3.8-4 12/31/2002 Pages TRM / 3.8-5 and TRM /3.8-6 04/02/2002 Pages TRM / 3.8-7 through TR11T810 12/03/2004 Page TRM / 3.8-11 08/10/2004 SUSQUEHANNA - UNIT 1 TRM I LOES-2 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION' LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS PPL Rev. 11 MANUAL)
-- = Section Title Effective Date 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 1 3.8-23 Pages 3.8-24 and 3.8-25 12103/2004 08/31/1998 04/02/2002 08/3111998 04/02/2002 08/3111998 06/0611999 08/3111998 3.9 3.10 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 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 08/31/1998 08/31/1998 03/08/2003 06/05/2002 04/07/2000 Corrected 04117/2002 3.11-RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-9 Page TRM / 3.1 1-10 Pages 3.11-11 and 3.11-12 Page 3.11-13 Page TRM / 3.11-14 Pages 3.11-15 and 3.11-16 Pages 3.11-17 and 3.11-18 Page TRM / 3.11-19 Pages 3.11-20 and 3.11-21 Pages TRM / 3.11-22 through 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 /3.11-45 Pages 3.11-46 and 3.11-47 08/31/1998 12/03/2004 08/31/1998 09/011998 12/0312004 09/01/1998 08/3111998 01/2112004 08/31/1998 04/02/2002 09/01/1998 01/21/2004 12/03/2004 01/21/2004 08/31/1998 12/03/2004 08/31/1998 12/03/2004 08/31/1998 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 02/05/1999 1-e. r 4.0 w -ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4. 0-8
-08/31/1998' U
SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 12/0312004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 11 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
I Section B3.0 B 3.1 Title Effective Date APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM I B 3.0-11 through TRM / B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Pages TRM I B 3.1-1 through TRM I B 3.1-3 Page B 3.14 Pages TRM / B 3.1-5 through TRM / B 3.1-7 Page TRM / B 3.1-8 08/31/1998 03/15/2002 07/13/1999 08/31/1998 07/13/1999 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 B 3.3 INSTRUMENTATION BASES Page TRM I B 3.3-1 Page B 3.3-2 Pages TRM / B 3.3-3 and TRM / B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM I B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM I B 3.3-14b Pages TRM I B 3.3-15 and TRM I B 3.3-16 Page TRM I B 3.3-17 Pages TRM / B 3.3-17a through TRM I B 3.3-17f Pages TRM / B3.3-18 and TRM / B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 08/3111998 04/07/2000 08/31/1998 12/29/2000 03/21/2003 03/30/2001 08/31/1998 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 I
B3.4 B 3.5 B 3.6 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 Page TRM / B 3.4-5 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 Pages TRM / B 3.6-6 Pages B.3.6-7 through TRM / B 3.6-11 08/3111998 10/15/1999 08/31/1998 08/31/1998 07/26/2001 02/01/1999 08/31/1998 09/23/1999 01/07/2002 12/03/2004 12/31/2002
.. mv. w
SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 11 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
.U m; -
Section Title Effective Date I R
B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM / B 3.7-3 through TRM I B 3.7-7 Page TRM / B 3.7-7a Pages TRM / B 3.7-8 through TRM / B 3.7-10 Page TRM / B 3.7-10a Pages TRM I B 3.7-11 and TRM / B 3.7-11 a 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 Page TRM/B 3.7-21 through TRM/B 3.7-21 a Pages TRM/B 3.7-22 and TRM/B 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 I B 3.7-34 Page TRM / B 3.7-35 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM / B 3.8-2 Page TRM / B 3.8-2a Page TRM / B 3.8-3 Page TRM / 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 3.8-17 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 08/3111998 08/02/1999 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 05/11/2001 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 04/02/2002 04/02/2002 04/02/2002 08/10/2004 04/02/2002 08/31/1998 04/02/2002 08/31/1998 08/3111998 03/08/2003 08/2311999 04/17/2002 B 3.8 B.3.9 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 SUSQUEHANNA - UNIT 1 TRM / LOES-5 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 11 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
-7,71m7m 1-1--/ 11 -
-
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 TRM/B 3.11 -11 and TRM/B 3.11-11 a Pages TRM/B 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 1 B 3.11-20a Page TRM I B 3.11-21 Page TRM / B 3.11-22 Page TRM / B 3.11-23 Page TRM / B 3.11-23a Pages TRM / B 3.11-24 and TRM IB 3.11-25 Pages B 3.11-26 through B 3.11-28 Page TRM / 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 08/30/1998 02/01/1999 04/07/2000 02/01/1999 12/03/2004 02/01/1999 08/3011998 04/02/2002 04/02/2002 10/15/2004 09/26/2003 04/02/2002 04/02/2002 01/21/2004 08/30/1998 12/03/2004 8/30119998 02/12/1999 02/05/1999 TRMI text LOES 11/22104
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-~-,-
SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLEPF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
PSECTION tITLE PAGE-1.0 USE AND APPLICATION..................................
TRM/1.0-1 1.1 Definitions..................................
TRM/1.0-2 2.0 PLANT PROGRAMS...................................
2.0-1 2.1 Plant Programs...................................
2.0-1 2.2 Instrument Trip Setpoint Table..........
......................... TRM/2.0-5 3.0 APPLICABILITY..................................
TRM/3.0-1 3.0 TRO) - TR for Operation (TRO) Applicability.................................. TRM/3.0-1 3.0 (TRS) - TR Surveillance (TRS) Applicability................................... TRM/3.0-3 3.1 REACTIVITY CONTROL SYSTEMS.................;
................ 3.1-1 3.1.1 Alternate Rod Injection...................................
3.1-1 3.1.2 CRD Housing Support...................................
3.1-4 3.1.3 Control Rod Block Instrumentation...................................
3.1-5 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve............................
TRM/3.1-9 3.2 CORE OPERATING LIMITS REPORT........
.................... TRM/3.2-1 3.2.1 Core Operating Limits Report............................
TRM/3.2-1 3.3.1 Radiation Monitoring Instrumentation..........................
TRM/3.3-1 3.3.2 Seismic Monitoring Instrumentation.........................
TRM/3.3-4 3.3.3 Meteorological Monitoring Instrumentation.........................
3.3-7 3.3.4 TRM Post-Accident Monitoring Instrumentation.........................
TRM/3.3-9 3.3.5 Section Not Used.........................
TRM/3.3-12 3.3.6 TRM Containment Isolation Instrumentation.........................
TRM/3.3-13 3.3.7 Turbine Overspeed Protection System.........................
TRM/3.3-17 3.3.8 Section Not Used.........................
TRM/3.3-19 3.3.9 OPRM Instrumentation.....................................................................
TRM/3.3-22 3.3.10 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops.....................................
TRM/3.3-23 3.3.11 MVP Isolation Instrumentation.....................................
TRM/3.3-25 3.4 REACTOR COOLANT SYSTEM......................................................................3.4-1 3.4.1 Reactor Coolant System Chemistry.....................................
3.4-1 3.4.2 Structural Integrity..................................
3.4-6 3.4.3 High/Low Pressure Interface Leakage Monitors..................................
3.4-9 3.4.4 Reactor Recirculation Flow and Rod Line Limit................................. TRM/3.4-12 3.4.5 Reactor Vessel Material Surveillances Program..................................
3.4-13 SUSQUEHANNA - UNIT 1 TRM / TOC-1 EFFECTIVE DATE 12/03/2004 U
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING AND RCIC........................................ 3.5-1 3.5.1 ADS Manual Inhibit........................................
3.5-1 3.5.2 ECCS and RCIC System Monitoring Instrumentation................................. 3.5-3 3.5.3 Long Term Nitrogen Supply to ADS..............
.......................... 3.5-6 3.6 CONTAINMENT.........................................
3.6-1 3.6.1 VENTING or PURGING........................................ 3.6-1 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication.....................................
3.6-2 3.6.3 Suppression Pool Alarm Instrumentation....................
.................. 3.6-3 3.6.4 Primary Containment Closed System Boundaries............................. TRM/3.6-6 3.7 PLANT SYSTEMS......................................
3.7-1 3.7.1 Emergency Service Water System (Shutdown)...................................... 3.7-1 3.7.2 Ultimate Heat Sink and Ground Water Level..................................... 3.7-3 3.7.3.1 Fire Suppression Water Supply System...........................
TRM/3.7-4 3.7.3.2 Spray and Sprinkler Systems...........................
TRM/3.7-8 3.7.3.3 C02 systems...........................
TRM/3.7-12 3.7.3.4 Halon Systems...........................
TRM/3.7-16 3.7.3.5 Fire Hose Stations...........................
TRM/3.7-18 3.7.3,.6 asYard Fire Hydrants and Hydrant Hose Houses........................... TRM/3.7-22 3.7.3.7 Fire Rated Assemblies...............
TRM/3.7-24 3.7.3.8 Fire Detection Instrumentation.TRM/3.7-26 3.7.4 Solid Radwaste System.TRM/3.7-35 3.7.5.1 Main Condenser Offgas Hydrogen Monitor.
3.7-38 3.7.5.2 Main Condenser Explosive Gas Mixture...............................
3.7-39 3.7.5.3 Liquid Holdup Tanks...............................
3.7-40 3.7.6 ESSW Pumphouse Ventilation.TRM/3.7-41 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation.3.7-42 3.7.8 Snubbers..TRM/3.7-44 3.7.9 Control Structure HVAC.TRM/3.7-50 3.7.10 Spent Fuel Storage Pools.TRM/3.7-52 SN U_
E SUSQUEHANNA -UNIT 1 TRM I TOC-2 EFFECTIVE DATE 12103/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLEOF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION t1TLE PAGE 3.8 ELECTRICAL POWER....................................
TRM/3.8-1 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices......
TRM/3.8-1 3.8.2.1 Motor Operated Valves Thermal Overload Protection -
Continuous.
TRM/3.8-5 3.8.2.2 Motor Operated Valves Thermal Overload Protection -
Automatic.TRM/3.8-11 3.8.3 Diesel Generator (DG) Maintenance Activities.
3.8-13 3.8.4 24VDC Electrical Power Subsystem.TRM/3.8-1 5
3.8.5 Degraded Voltage Protection.TRM/3.8-21 3.8.6 Emergency Switchgear Room Cooling.3.8-24 3.9 REFUELING OPERATIONS.3.9-1 3.9.1 Decay Time.3.9-1 3.9.2 Communications.3.9-2 3.9.3 Refueling Platform..
3.9-3 3.10---
MISCELLANEOUS....................................
3.10-1 3.10.1 Sealed Source Contamination.............
........ 3.10-1 3.10.2 MODE 5 Shutdown Margin Test RPS Instrumentation............................... 3.10-4 3.10.3 Independent Spent Fuel Storage Installation (ISFSI)......................... TRM/3.10-7 1.6 leading Ede FlwMtrEM............................I RMI3.1O-8 3.11 RADIOACTIVE EFFLUENTS........................................
3.11-1 3.11.1.1 Liquid Effluents Concentration........................................
3.11-1 3.11.1.2 Liquid Effluents Dose.........................................
3.11-4 3.11.1.3 Liquid Waste Treatment System......................................... 3.11-6 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation................................. 3.11-8 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation............................. 3.11-13 3.11.2.1 Dose Rate........................................
3.11-17 3.11.2.2 Dose - Noble Gases........................................
3.11-20 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form............................
3.11-21 3.11.2.4 Gaseous Radwaste Treatment System............
................ TRM/3.11-22 3.11.2.5 Ventilation Exhaust Treatment System............................
TRM/3.11-23 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation..........................
3.11-25 3.11.3 Total Dose..........................
3.11-33 3.11.4.1 Monitoring Program..........................
3.11-35 3.11.4.2 Land Use Census..........................
TRMI3..11-45 3.11.4.3 Interlaboratory Comparison Program..........................
3.11-47 I. I I
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UQUEHNA-TRM___EFFECTE A
SUSQUEHANNA - UNIT 1 TRM / TOC-3 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLE OF CONTENTS TECHNICAL REQUIREMENTS MANUAL)
S'E-CTION ~A'~ '
E'
~
~"
-'---T-TLE ' '
=~ ' ' '
" '~ --PAGE 3.12 LOADS CONTROL PROGRAM.....................................
...................... TRMI3.12-1 3.12.1 Crane Travel - Spent Fuel Storage Pool.........
................... TRM/3.12-1 3.12.2 Heavy Loads Requirements............................
TRM/3.12-3 3.12.3 Light Loads Requirements............................
TRM/3.12-5 4.0 ADMINISTRATIVE CONTROLS.............................
4.0-1 4.1 Organization............................
4.0-1 4.2 Reportable Event Action............................
4.0-2 4.3 Safety Limit Violation............................
4.0-3 4.4 Procedures and Programs.............................
4.0-4 4.5 Reporting Requirements.............................
4.0-5 4.6 Radiation Protection Program............................
4.0-7 4.7 Training............................
4.0-8 MI "PIM-01"O"Yow"W"I"IM j
in.....1........1111....111
-.....1...111.......11,.
I ~ -
1 1
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- ~ -,~
SUSQUEHANNA -UNIT I TRM I TOC4 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLE-OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE B 3.0 Applicability..................................
B 3.0-1 B 3.0 (TRO) - TR for Operation (TRO) Applicability....
............................... B 3.0-1 B 3.0 (TRS) - TR Surveillance (TRS) Applicability..................
................ B 3.0-9 B 3.1.1 Alternate Rod Injection..................................
TRMIB 3.1-1 B 3.1.2 CRD Housing Support..................................
TRM/B 3.1-4 B 3.1.3 Control Rod Block Instrumentation..................................
TRM/B 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve..................................
TRM/B 3.1-8 B 3.2.1 Core Operating Limits Report (COLR)..................................
B 3.2-1 B 3.3.1 Radiation Monitoring Instrumentation..................................
TRM/B 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation.........
......................... B 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation..................................
TRM/B 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation................................ TRMIB 3.3-4 B 3.3.5 Section Not Used..................................
TRM/B 3.3-7 B 3.3.6 TRM Containment Isolation Instrumentation...................................
B 3.3-10 B 3.3.7 Turbine Overspeed Protection System..................................
TRM/B 3.3-14 B 3.3.8 Section Not Used........................................
TRMIB 3.3-15 B3.3.9
~
P iA i~ tu e tton..................................
- B3.3-10' Set Electrical and Mechanical Stops.TRMB 3.3-18 B 3.3.11 MVP Isolation Instrumentation.TRMIB 3.3-20 B 3.4.1 Reactor Coolant System Chemistry..................................
B 3.4-1 B 3.4.2 Structural Integrity.B 3.4-2 B 3.4.3 High/Low Pressure Interface Leakage Monitors.B 3.4-4 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit.TRM/B 3.4-5 B 3.4.5 Reactor Vessel Material Surveillances Program.B 3.4-6 B 3.5.1 ADS Manual Inhibit.B 3.5-1 B 3.5.2 ECCS and RCIC System Monitoring Instrumentation................................. B 3.5-3 B 3.5.3 Long Term Nitrogen Supply to ADS............
.......................... B 3.5-4 r-SUSQUEHANNA - UNIT 1 TRM I TOC-5 EFFECTIVE DATE 12/03/2004 m
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLE.-OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE B 3.6.1 VENTING or PURGING....................................TRM/B 3.6-1 B 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication...................................................B 3.6-3 B 3.6.3 Suppression Pool Alarm Instrumentation......................TRM/B 3.6-4 B 3.6.4 Primary Containment Closed System Boundaries................TRM/B 3.6-6 B 3.7.1 Emergency Service Water System (Shutdown)......................B 3.7-1 B 3.7.2 Ultimate Heat Sink and Ground Water Level........................B 3.7-2 B 3.7.3.1 Fire Suppression Water Supply System.......................TRM/B 3.7-3 B 3.7.3.2 Spray and Sprinkler Systems...............................
TRM/B 3.7-5 B 3.7.3.3 C02 systems...........................................
TRM/B 3.7-7 B 3.7.3.4 Halon Systems..........................................
TRM/B 3.7-8 B 3.7.3.5 Fire Hose Stations........................................TRM/B 3.7-10 B 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses..................TRM/B 3.7-11 B 3.7.3.7 Fire Rated Assemblies....................................
TRM/B 3.7-12 B 3.7.3.8 Fire Detection Instrumentation..............................
TRM/B 3.7-14 B 3.7.4 Solid Radwaste System...................................
TRM/B 3.7-15 B 3.7.5.1 Main Condenser Offgas Hydrogen Monitor.........................B 3.7-17 B 3.7.5.2 Main Condenser Explosive Gas Mixture............................B 3.7-19 B 3.7.5.3 Liquid Holdup Tanks..........................................
B 3.7-20 B 3.76 ESSW Pumphouse Ventilation...............................TRM/B 3.7-21 B 777" MWain Condenser Offg-as Pr-etre6atment Logarithmic Radiation
" _Mo7nvito&ringIs ue in...............................TRM/B 3.7-22 B 3.7.8 Snubbers...................................................B 3.7-24 B 3.7.9 Control Structure HVAC...................................
TRM/B 3.7-31 B 3.7.10 Spent Fuel Storage Pools..................................TRM/B 3.7-33 B 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices.......................................
TRM/B 3.8-1 B 3.8.2.1 Motor Operated Valves Thermal Overload Protection -
Continuous.............................................
TRM/13 3.8-3 B 3.8.2.2 Motor Operated Valves Thermal Overload Protection -
Automatic...............................................TRM/B 3.8-4 B 3.8.3 Diesel Generator (DG) Maintenance Activities.......................B 3.8-5 B 3.8.4 24VDC Electrical Power Subsystem...............................B 3.8-6 B 3.8.5 Degraded Voltage Protection...............................
TRM/B 3.8-16 B 3.8.6 Emergency Switchgear Room Cooling........................TRM/B 3.8-17 B.3.9.1 Decay Time.................................................
B 3.9-1 B 3.9.2 Communications..............................................
B 3.9-2 SUSQUEHANNA - UNIT 1 TRM I TOC-6 EFFECTIVE DATE 12/03/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 4 TABLE.OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL) e A:
4 SECTION TITLE PAGE B 3.9.3 Refueling Platform B 3.9-3 B 3.10.1 Sealed Source Contamination.B 3.10-1 B 3.10.2 MODE 5 Shutdown Margin Test RPS Instrumentation.B 3.10-2 B 3.10.3 Independent Spent Fuel Storage Installation (ISFSI).TRM/B 3.10-4 B 3.10.4 Leading Edge Flow Meter (LEFM).TRM/B 3.10-6 B 3.11.1.1 Liquid Effluents Concentration.B 3.11-1 B 3.11.1.2 Liquid Effluents Dose.B 3.11-4 B 3.11.1.3 Liquid Waste Treatment System.B 3.11-6 B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation.B 3.11-7 B 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation.TRM/B 3.11-1 0 B 3.11.2.1 Dose Rate.TRM/B 3.11-12 B 3.11.2.2 Dose - Noble Gases.B 3.11-16 B 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form.............................
B 3.11-18 B 3.11.2.4 Gaseous Radwaste Treatment System.TRM/B 3.11-20 B 3.11.2.5 Ventilation Exhaust Treatment System.TRM/B 3.11-21 B 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation.............................
TRMIB 3.11-24 B 3.11.3 Total Dose...
B 3.11-26 B 3'11.4.1 Monitoring Program...................
B 311-280 B 3.11.4.2 Land Use Census.............................
B 3.11-34 B 3.11.4.3 Interlaboratory Comparison Program.........
................... TRM/B 3.11-36 8.3.12.1 Crane Travel - Spent Fuel Storage Pool.
TRM/B 3.12-1 B.3.12.2 Heavy Loads Requirements.
TRMWB 3.12-2 B.3.12.3 Light Loads Requirements.TRM/B 3.12-3 TRMI1 text TOC 11/22/04 tw-+/--,-w,,V 4-.--
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SUSQUEHANNA - UNIT I TRM / TOC-7 EFFECTIVE DATE 12/03/2004 SUSQUEHANNA -UNIT 1 TRM / TOC-7 EFFECTIVE DATE 12/03/2004
Instrument Trip Setpoint Program PPL Rev. 3 2.2 M'1
,_________,_...__. -.-I------ - ____ 1,
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2.0 -
PLANT PROGRAMS AN ell-II 1
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4
.n 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical Specifications and Technical Requirements. Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in square brackets.
Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.
Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.
Reference NDAP-QA-1 104 Setpoint Change Control
-7_11-1
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SUSQUEHANNA - UNIT 1 TRM 12.0-5 EFFECTIVE DATE 04/02/1999
Instrument Trip Setpoint Program 2.2 PPL Rev. 3
- -TABLE 2.2-1 (Page 1 of 8)
INSTRUMENTATION SETPOINTS
-,mmm SYSTEMIREFERENCE LCO [TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.1 Reactor Protection 2.2.1.1 3.3.1.1 2.2.1.2 3.3.1.1 2.2.1.3 3.3.1.1 2.2.1.4 3.3.1.1 2.2.1.5 3.3.1.1 2.2.1.6 3.3.1.1 Intermediate Range Monitor, Neutron Flux -
High Average Power Range Monitor, Neutron Flux
- High Setdown Average Power Range Monitor, Flow Biased Simulated Thermal Power - High Two Loop Operation Average Power Range Monitor, Flow Biased Simulated Thermal Power - High Single Loop Operation Average Power Range Monitor, Flow Biased Simulated Thermal Power - High Flow Clamped Average Power Range Monitor, Fixed Neutron Flux - High Reactor Vessel Steam Dome Pressure - High Reactor Vessel Water Level - Low, Level 3 Main Steam Isolation Valve - Closure This Sectin Not Used Drywell Pressure - High Scram Discharge Volume Water Level - High
- Level Transmitter Scram Discharge Volume Water Level - High
- Float Switch Turbine Stop Valve - Closure
- Turbine Control Valve Fast Closure, Trip Oil Pressure - Low
- 120/125 divisions of full scale
- 113.5% of RATED THERMAL POWER
- 118% of RATED THERMAL POWER
- 1087 psig 2 13.0 inches (Z 5 10% closed 2.2.1.7 2.2.1.8 2.2.1.9 2.2.1.10 2.2.1.11 2.2.1.12 2.2.1.13 2.2.1.14 2.2.1.15 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1
- 1.72 psig
- 65 gallons
- 61 gallons
- 5.5% closed 2 500 psig (continued)
(a) See Figure 2.2-1 0
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7-SUSQUEHANNA - UNIT 1 TRM /2.0-6 EFFECTIVE DATE 1111512004
Instrument Trip Setpoint Program 2.2 PPL Rev. 3-
-TABLE 2.2-1 (Page 2 of 8)
INST MENTATION SETPOINTS e
I SYSTEM/REFERENCE LCO [TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.1.16 OPRM Instrumentation 2.2.1.16.1 2.2.1.16.2 2.2.1.16.3 2.2.1.16.4 2.2.1.16.5 2.2.1.16.6 2.2.1.16.7 2.2.1.16.8 2.2.1.16.9 2.2.1.16.10 2.2.1.16.11 2.2.1.16.12 2.2.1.16.13 2.2.1.16.14 2.2.1.16.15 2.2.1.16.16 2.2.1.16.17 3.3.1.3 3.3.1.3
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
[3.3.9]
Sp Cell Signal Amplitude N2 Confirmation Count Permissive TOL Period Confirmation Tolerance Ta Averaging Filter Fc Conditioning Filter Cutoff Frequency Tmin Minimum Oscillation Period Tmax Maximum Oscillation Period Noise Floor Peak Discrimination Threshold Minimum LPRM/Cell Cell Operability Requirement SI Peak Threshold Setpoint S2 Valley Threshold Setpoint Smax Max. Amplitude Trip Setpoint DR3 Growth Rate Factor Setpoint T1 lo SI to S2 Timer Range T1 hi SI to S2 Timer Range T2 1o S2 to(S3 or Smax) Timer Range T2 hi S2 to(S3 or Smax) Timer Range See COLR - TRO 3.2 See COLR - TRO 3.2 0.10 sec 5 sec 1.5 Hz 1.0 sec 3.5 sec 1
2 1.20 0.85 1.50 1.60 0.5 sec 1.75 sec 0.5 sec 1.75 sec 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation 2.2.2.1.1 2.2.2.1.2 2.2.2.1.3 2.2.2.1.4 2.2.2.1.5 2.2.2.1.6 3.3.6.1 3.3.6.1 3.3.6-1 3.3.6.1 3.3.6.143.3.6]
[3.3.6]
Reactor Vessel Water Level Low, Level 3 Reactor Vessel Water Level Low Low, Level 2 Reactor Vessel Water Level Low Low Low, Level 1 Drywell Pressure - High SGTS Exhaust Radiation - High Main Steam Line Radiation - High High 2 13.0 inches(a)
Ž -38.0 inches(a)
Ž -129 inches(a)
- 1.72 psig s 23.0 mR/hr s 15 x full power background without hydrogen injection (continued)
.U I
I
- 1.
I -
. I-- ~
T-..
I. I SUSQUEHANNA - UNIT 1 TRM / 2.0-7 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program 2.2 PPL Rev. 3, TABLE
-o 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.2.2 2.2.2.2.1 2.2.2.2.2 2.2.2.2.3 2.2.2.2.4 2.2.2.2.5 Secondary Containment Isolation 3.3.6.2 3.3.6.2 3.3.6.2 3.3.6.2 3.3.6.2 Reactor Vessel Water Level - Low Low, Level 2 Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation -
High Railroad Access Shaft Exhaust Duct Radiation - High Refuel FloorWall Exhaust Duct Radiation -
High 2 -38.0 inches(a)
- 1.72 psig
- 18 mR/hr
- 5 mR/hr
- 21 mR/hr 2.2.2.3 2.2.2.3.1 2.2.2.3.2 2.2.2.3.3 2.2.2.3.4 2.2.2.3.5 2.2.2.3.6 2.2.2.3.7 2.2.2.3.8 Main Steam Line Isolal 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1
[3.3.6]
[3.3.6]
K....-'
2.2.2.4 2.2.2.4.1 2.2.2.4.2 2.2.2.4.3 2.2.2.4.4 2.2.2.4.5 2.2.2.4.6 2.2.2.4.7 2.2.2.4.8 2.2.2.4.9 ReactorWater Cleanu 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1
[3.3.6]
3.3.6.1
[3.3.6]
3.3.6.1
[3.3.6]
tion Reactor Vessel Water Level - Low Low Low, Level 1 Main Steam Line Pressure - Low Main Steam Line Flow - High Condenser Vacuum - Low Reactor Building Main Steam Line Tunnel Temperature - High T hi S~ection NMotUsed Reactor Building Main Steam Line Tunnel A Temperature - High Turbine Building Main Steam Tunnel Temperature - High p System Isolation Reactor Vessel Water Level - Low Low, Level 2 RWCU A Flow - High RWCU Flow - High RWCU Penetration Area Temperature - High RWCU Penetration Room Area A Temperature
- High RWCU Pump Area Temperature - High RWCU Pump Room Area A Temperature -
High RWCU Heat Exchanger Area Temperature -
High RWCU Heat Exchanger Room Area A Temperature - High
Ž -129 inches(a) 2 861 psig
- 113 psid
.Ž 9.0 inches Hg vacuum
- 177 0F
- 99 0F
- 197 0F 2 -38 inches(a)
- 59 gpm
- 462 gpm
- 131OF
- 690F
- 147 0F
- 69 0F
- 1470F
- 690F (continued)
(a) See Figure 2.2-1 m
_ - 7
- t.: Ad~ 1: 1 1-. I I:I:..
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- I 1-1
- 1111
i.,
WWWWAMPANOW"i iii iiii i iw i 0 N
SUSQUEHANNA - UNIT I TRM I 2.0-8 EFFECTIVE DATE 12/0312004
Instrument Trip Setpoint Program 2.2 PPL Rev. 3.
L1-4"..-
W--'
al HTA 2t2-1 (Page 4 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation 2.2.2.5.1 3.3.6.1 RCIC Steam Line A Pressure - High 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure
- High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High 2.2.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature -
High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High 2.2.2.5.8
[3.3.6]
RCIC Equipment Room A Temperature - High 2.2.2.5.9
[3.3.6]
RCIC Pipe Routing Area A Temperature -
High 2.2.2.6 High Pressure Coolant Injection System Isolation
- 188 inches H20
> 60 psig
- 10.0 psig
- 1670F
- 1670F
- 1670F
- 1.72 psig
- 890F
- 890F
w;',1- '
2.2.2.6.1 2.2.2.6.2 2.2.2.6.3 22264' 2.2.2.6.65 2.2.2.6.6 2.2.2.6.7 2.2.2.6.8 2.2.2.6.9 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1
[3.3.6]
[3.3.6]
HPCI Steam Line A Pressure - High HPCI Steam Supply Line Pressure - Low HPCI Turbine Exhaust Diaphragm Pressure -
High HPCI Equipment Room Temperature - High HPCI Emergency Area Cooler Temperature -
High HPCI Pipe Routing Area Temperature - High Drywell Pressure - High HPCI Equipment Room A Temperature - High HPCI Pipe Routing Area A Temperature -
High
- 370 inches H20 2 104 psig
- 10 psig
- 1670F
- 1670F
- 1670F
- 1.72 psig
- 890F
- 890F 2.2.2.7 Shutdown Cooling/System Isolation 2.2.2.7.1 3.3.6.1 2.2.2.7.2 3.3.6.1 2.2.2.7.3
[3.3.6]
2.2.3 ECCS Actuation 2.2.3.1 Core Spray System 2.2.3.1.1 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 Reactor Vessel Steam Dome Pressure - High RHR Flow - High Reactor Vessel Water Level - Low Low Low, Level 1 Drywell Pressure - High Reactor Vessel Steam Dome Pressure - Low injection permissive
> 13.0 inches~a)
- 98 psig
- 25,000 gpm
Ž -129 inches(a)
- 1.72 psig
> 413, < 427 psig 2.2.3.1.2 2.2.3.1.3 3.3.5.1 3.3.5.1 (continued)
See Figure 2.2-1 t-:---
SUSQUEHANNA - UNIT 1 TRM / 2.0-9 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program PPL Rev. 3 2.2 I.-.
T i
=
I
-f
) -
SATLE 2.2-1 (Page 5 of 8)
INSTRUMENTATION SETPOINTS
=
I ~ -.
..I -
SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches(a)
Level 1 2.2.3.2.2 3.3.5.1 Drywell Pressure - High
- 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low,
> 413, < 427 psig injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, 2 236 psig, decreasing Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, 2 -38 inches(a)
Level 2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High
- 1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low 2 36.0 inches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level - High, Level 8
- 54 inches 2.2.3.4 Automatic Depressurization System (ADS) 2.2.3.4.1 3.3.5.1 Reactr Vessel Water Lv - Low Low Low,
-129 inches Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure - High
- 1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer 102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure - High
> 135,
- 155 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump 2 121, < 129 psig Discharge Pressure - High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 2 13 inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer
- 420 seconds 2.2.3.5 Loss of Power - ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage < 20%)
2.2.3.5.1.1 3.3.8.1 Bus Undervoltage 2 823.2, < 856.8 Volts 2.2.3.5.1.2 3.3.8.1 Time delay 0.4, < 0.6 seconds (continued)
(a) See Figure 2.2-1 I
_ __-I_-_
EFFECTIVE DATE 11/15/2004 e
SUSQUEHANNA-UNIT 1 TRM / 2.0-10
Instrument Trip Setpoint Program 2.2 PPL Rev. 3
-A_
==
AW TABILE 2.2-1 (Page 6 of 8)
INSTRUMENTATION SETPOINTS I
SYSTEM/REFERENCE LCO 2.2.3.5.2 2.2.3.5.2.1 2.2.3.5.2.2 2.2.3.5.3 2.2.3.5.3.1 2.2.3.5.3.2 2.2.3.5.3.4 2.2.3.5.4 2.2.3.5.4.1 2.2.3.5.4.2 2.2.3.5.5 2.2.3.5.5.2 2.2.4 2.2.4.1 2.2.4.1 2.2.5 2.2.5.1 2.2.5.2 2.2.6 2.2.6.1 2.2.6.2 2.2.6.3 SYSTEWJREFERENCE LCO
[TRO]
TRIP FUNCTION 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)
3.3.8.1 Bus Undervoltage 3.3.8.1 Time delay 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)
3.3.8.1 Bus Undervoltage 3.3.8.1 Time Delay (Non-LOCA) 3.3.8.1 Time Delay (LOCA) 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 65%)
[3.8.5]
480V Basis
[3.8.5]
Time Delay 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 92%)
[3.8.5]
480V Basis
[3.8.5]
Time Delay' ATWS Alternate Rod Injection and Recirculation Pump Trip 3.3.4.243.1.1]
Reactor Vessel, Water Level - Low Low, Level 2 3.3.4.21[3.1.1]
Reactor Vessel Steam Dome Pressure - High End of Cycle Recirculation Pump Trip 3.3.4.1 Turbine Stop Valve-Closure 3.3.4.1 Turbine Control Valve - Fast Closure Reactor Core Isolation Cooling System Actuation 3.3.5.2 Reactor Vessel Water Level - Low Low, Level 2 3.3.5.2 Reactor Vessel Water Level - High, Level 8
3.3.5.2 Condensate Storage Tank Level - Low TRIP SETPOINT
Ž 2641. 1, < 2748.9 Volts
> 2.7,
- 3.3 seconds 2 3829.3, < 3906.7 Volts 2 4 minute, 30 seconds
- 5 minute, 30 seconds
> 9, <11 seconds
> 308.9, < 315.1 Volts
> 4.5, < 5.5 seconds
> 437.6, < 446.4 Volts 2 9,
- 11 seconds 2 -38 inches(a) 5 1135 psig
< 5.5% closed 2 500 psig 2-38 inches(a)
< 54 inches(a)
Ž 36.0 inches above tank bottom (continued)
(a) See Figure 2.2-1 I' I I .
I'
. -
'- '.:'
'- .
4"4"
z a_~~~~~~~~ ~
-= -----
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5 GY
........... e 11
~EFFECTIVE DATE 11/15/2004_
SUSQUEHANNA - UNIT 1 TRM / 2.0-1
Instrument Trip Setpoint Program 2.2 PPL Rev. 3 AOf INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.7 2.2.7.1 2.2.7.1.1 2.2.7.1.2 2.2.7.1.3 2.2.7.2 2.2.7.2.1 2.2.7.2.2 2.2.7.2.3 2.2.7.2.4 2.2.7.2.5 2.2.7.3 2.2.7.3.1 2.2.7.3.2 2.2.7.4 2.2.7.4.1 2.2.7.4.2 Control Rod Block Rod Block Monitor 3.3.2 3.3.2 Low Power Range Upscale - Two Loop Operation Low Power Range Upscale - Single Loop Operation Downscale 0.58W + 52%
- 0.58W+47%
5%
APRM n
[3.1.3]
[3.1.3]
[3.1.3]
[3.1.3]
[3.1.3]
Source Range Monitors
[3 1
.3]
[3.1.3]
[3.1.3]
[3.1.3]
Flow Biased Simulated Thermal Power-High
- Two Loop Operation Flow Biased Simulated Thermal Power High
- Single Loop Operation Flow Biased Simulated Thermal Power High
- High Flow Clamped Downscale Neutron Flux - High Setdown Upscale Downscale See COLR - TRO 3.2 See COLR - TRO 3.2 I 108% of RATED THERMAL POWER 2 5% of RATED THERMAL POWER
- 12% of RATED THERMAL POWER 9 R.-,:1,7' -
-=--_
I "-";.qi
- 2E5 cps 2 0.7 cps0° Upscale
- 108/125 divisions of full scale 2 5/125 divisions of full scale Downscale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1
[3.1.3]
Water Level - High 2.2.7.6 Reactor Coolant System Recirculation Flow 2.2.7.6.1
[3.1.3]
Upscale 2.2.7.6.2
[3.1.3]
Comparator
- 35.9 gallons 114%
< 10% flow deviation (continued)
° Provided signal-to-noise ratio is Ž 2. Otherwise, > 3 cps.
r,
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SUSQUEHANNA - UNIT 1 TRM I 2.0-12 EFFECTIVE DATE 11115/2004 kwd..
Instrument Trip Setpoint Program 2.2 PPL Rev. 3,
--- TA t2-(Page8of8' I
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.8 2.2.8.1 CREOASS 3.3.7.1 3.3.7.1 2.2.8.1.1 2.2.8.1.2 2.2.8.1.3 2.2.8.1.4 2.2.8.1.5 3.3.7.1 3.3.7.1 3.3.7.1 3.3.7.1 Main Control Room Outside Air Intake Radiation Monitor Reactor Vessel Water Level - Low Low, Level 2 Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation
- High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation
- High
<5 mR/hr 2 -38.0 inches(a)
- 1.72 psig
< 18 mR/hr
<5 mR/hr
< 21 mRlhr 2.2.9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.2.2 Reactor Vessel Level - High
< 54.0 inches(a) 2.2.10 2.2.10.1 MVP Isolation 13.3.11]
Main Steam Line Radiation - High High
< 15 x full power background without hydrogen injection
-WPM
,.FAA (a) See Figure 2.2-1
Iz7iI:mu.:c I
SUSQUEHANNA - UNIT 1 TRM/2.O-13 EFFECTIVE DATE 11/15/2004 7--
0"r
Instrument Trip Setpoint Table 2.2 PPL Rev. 3
- i.
WATER LEVEL NOMENCLATURE HEIGHT ABOVE NO.
vEEL zERO DwING (IN.)
(8) 581.5
+54 (7)
-56.5
+39 t(4) 557.5
+30.
(3) 540.5
+13 (2) 489. S
-38 (1) 398.5
-1:29.
+6 60 2E-:54:-.()
+60-+$Ob
_ 8154 (7)k39 HIL4 H.cf&.(4 30'O ALA"
-- 38 SCRAR
. M.
.1K TRIP RECIRC: PQtPS-
--129 (1) INITIATE RHR. CS START DIESEL CONTRIBUTE TO ADS 0LOS MSIV-S NOTE: SCALE IN INCHES ABOVE VESSEL ZERO K' o FIGURE 2.2-1 :
xRE-iCTJR VESSEL WATER LEVEL QCAAAM ID: F1F2 TI2..
A SUSQUEHANNA - UNIT I TRM /2.0-14 EFFECTIVE DATE 11/15/2004
I Reactor Recirculation Pump MG Set Stops 3.3.10 PPL Re. 1 3.3 Instrumentaton 3.3.10 Reactor Recirculation Pump MG Set Stops TRO 3.3.10 Each Reactor Recirculation pump MG set scoop tube electrical and mechanical stop shall be OPERABLE with overspeed setpoints corresponding to a core flow of:
Electrical Stop: < 109.5 million Ibm/hr, and Mechanical Stop: < 110.5 million Ibm/hr APPLICABILITY:
MODES 1 and 2 ACTIONS
-a----Nn Separate Condition entry allowed for each recirculation pump MG set.
CONDITION REQUIRED ACTION COMPLETION TIME
- 4.
4 A.
One electrical or mechanical stop for either or both reactor recirculation pump MG set scoop tube(s) inoperable.
A.1 Restore the inoperable stop(s) to OPERABLE status.
Next scheduled performance of TRS 3.3.10.1
+
I.
B. Both electrical and mechanical stops for either Reactor Recirculation pump MG set scoop tube inoperable.
-NOTE--
Scoop tube may be unlocked intermittently under administrative control.
I B.1 Initiate actions to lock the scoop tube on the affected Reactor Recirculation MG Set in place.
Immediately h
SUSQUEHANNA - UNIT I TRM / 3.3-23 EFFECTIVE DATE 12/03/2004
Reactor Recirculation Pump MG Set Stops PPL Rev. 1 3.3.10
- s.
no-v TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.3.10.1 Demonstrate each Reactor Recirculation 24 months pump MG set-scoop tube electrical and mechanical stop to be OPERABLE.
- -1 1----1-1.1,t--11----:. 1..- -
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11 -
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SUSQUEHANNA - UNIT I TRM / 3.3-24 S EFFECTIVE DATE 05/16/2003
Reactor Recirculation Flow and Rod Line Limit 3.4.4 PPL Rev. 1 3.4 Reactor Coolant System (RCS) 3.4.4 Reactor Recirculation Flow and Rod Line Limit TRO 3.4.4 Operating loop flow rate shall be < 50% of rated loop flow rate and the reactor shall be operating at a THERMAL POWER/core flow condition below the 80%
rod line shown in the Power Flow map specified in the COLR.
.D.By, I
APPLICABILITY:
MODES 1, 2, 3, and 4 during recirculation pump start.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A
Requirements of the TRO not met A. 1 Restore parameter(s) to within limits Prior to recirculation pump start
-~
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.4.4.1 Verify the operating loop flow rate is Once within 15 minutes prior
< 50% of rated loop flow rate and that the to each recirculation pump reactor is operating at a THERMAL start POWER/core flow condition below the 80%
rod line shown in the power flow map specified in the COLR.
=.. =..I w o.7 3
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SUSQUEHANNA UNIT 1 TRM I 3.4-12 EFFECTIVE DATE 12/03/2004
-3.7~
Piaknt Sytems~
3.7.8 Snubbers TRO 3.7.8 All snubbers shall be OPERABLE APPLICABILITY:
At all times ACTIONS Sepraecndtioetyisallwe fore--- NOTE Separate condition entry is allowed for each snubber CONDITION REQUIRED ACTION COMPLETION TIME At --------- NOTE----
R~equired Action A.2 shall be completed if this Condition is entered.
One or more snubbers inoperable A.1 Declare the supported system inoperable AND A.2 Perform an engineering evaluation on the supported component OR A.3 If an engineering evaluation has been performed on the supported component, replace or restore the inoperable snubber(s) to OPERABLE status Immediately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours I=0 B. Required Action and B.1 Declare the supported Immediately associated Completion system inoperable Time of Condition A not met (continued)
SUSQUEHANNA - UNIT I TRM / 3.7-44 EFFECTIVE DATE 12/03/2004
.. 11-
-711- ;-
-I,-.,--,-
.,-----,--,-
,--:,
'Actions (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Any snubber selected C.1
NOTE------
Within the for functional testing This action shall be current either fails to independent of the Inspection activate or fails to Testing Requirements for interval move due to snubbers not meeting the manufacturer or design functional test deficiency acceptance criteria per TRS 3.7.8.2 All snubbers of the same design subject to the same defect shall be functionally tested D. The snubber service life will be exceeded prior to the next
, nscheduled snubber
- 'service life review D. 1 Reevaluate the snubber service life OR D.2 Replace or recondition the snubber so as to extend its service life beyond the date of the next scheduled service life review Prior to exceeding snubber service life Prior to exceeding snubber service life TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.7.8.1 Demonstrate each snubber OPERABLE by As directed by performance of visual inspection Table 3.7.8-1 TRS 3.7.8.2 Perform functional test of a representative 24 months sampling of all snubbers per Table 3.7.8-3.
(continued)
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SUSQUEHANNA - UNIT 1 3.7-45 EFFECTIVE DATE 10113/1998
-IMM"'Mr-W -ml P I
Mm""M
- PH F_
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.7.8.3
NOTE ---------------
24 months Documentation of critical parts replaced so that the maximum service life is not exceeded shall be retained as required by FSAR 17.2-17 Monitor the installation and maintenance records for each snubber to ensure that the service life has not been exceeded and will not be exceeded prior to the next snubber surveillance inspection.
TRS 3.7.8.4
NOTE -----
Snubber tested per this surveillance are in addition to snubbers selected for the
=
... I.
I..
At the time of the next functional test I
o
~
-s-imple plan per TRS 3.7.8.2 Test snubbers in locations of snubbers that failed the functional test during the previous test period and test repaired failed snubbers placed in new locations.
TRS 3.7.8.5 An inspection shall be performed of all Within 6 months snubbers attached to sections of systems of transient that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems.
a U
SUSQUEHANNA - UNIT 1 3.7-46 EFFECTIVE DATE 10/13/1998
Snubbers PPL Rey. 1 3.7.8 Table 3-.7.8-1 S
INTERVAL SNUBBER VISUAL INSPECTION INTERVAL Number Of Unacceptable Visually Inspected Snubbers in Previous Inspection Interval Inspection Interval
- 1. Equal to or less than the May be twice the previous interval but not applicable number in Table 3.7.8-2 greater than 48 months Column A
- 2. Equal to or less than the Same as the previous interval applicable number in Table 3.7.8-2 Column B but greater than the applicable number in Column A
- 3. Equal to or greater than the Two-thirds of the previous interval applicable number in Table 3.7.8-2 Column C
- 4. Less than the applicable number in Table 3.7.8-2 Column C but greater than the applicable number in
--Column B Equal to the previous interval (Ii-1), reduced proportionally by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval (Ni-,) and the number in Column B (NB) to the difference in the numbers in Columns C (Nc) and B, or:
Ii =.,
- - 1Ii NiN
,- NB)
NC - NB )
-MMM" I
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SUSQUEHANNA - UNIT I 3.7-47 EFFECTIVE DATE 10/13/1998
Snubbers 3.7.8 PP-LReyv. I TABLE 3.7.8-2 NUMBER OF UNACCEPTABLE SNUBBERS PREVIOUS SNUBBER VISUAL INSPECTION IKTERVAL Population Column A Column B Column C 1
0 0
80 100 150 200 300 400 500 750 0
0 0
2 5
8 12 20 0
I 3
5 12 18 24 40 2
4 8
13 25 36 48 78 1,000 or greater 29 56 109
~~NOTES------
- 1.
Interpolation between population or category sizes and the-number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
2.
The provisions of TRS 3.0.2 are applicable for all inspection intervals up to and including 48 months SUSQUEHANNA - UNIT I 3.7-48 SUSQEHANA
-UNITI 3.-48EFFECTIVE DATE 10/13/1998
ro__
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Snubbers A,
I
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=
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9.
He C:.....
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TABLE 3.7.8-3 FUNCTIONAL TESTING SAMPLE FAILED SNUBBERS REPRESENTATIVE SAMPLING (a)
- 1. Initial 0
10%
- 2. Re-Test
>0 in initial sample Additional 5%(b for each failure
- 3. Continued Testing
>0 In Re-tester or Additional 5% for each failure to Continued Testing 1 0 0 %(b)
Samples I
I (a) Percentage of the total population of each type of snubber (b) An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure and the determine the
-6rmtAB LTY *o fother niubbers, Irrespective of type, wch may be s bjecft6 t he same -
failure mode. The results of thiisevalition shall be used. If applicable, in selecting snubbers to be tested. If additional sampling is required due to failure of only one type of snubber, additional samples should be limited to the type of snubber which has failed the functional testing.
i
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SUSQUEHANNA - UNIT 1 TRM I 3.7-49 EFFECTIVE DATE 03/08/2003 U
Spent Fuel Storage Pools (SFSPs) 3.7.10 PPL Rev. 1
- GILT. m 3.7 Plant Systems 3.7.10 Spent Fuel Storage Pools (SFS JsY TRO 3.7.10 The following conditions shall be met when the Unit 1 and Unit 2 SFSPs are not cross-connected through the Cask Storage Pit.
- a. The Unit 1 SFSP water temperature is less than or equal to 115 OF.
- b. Both subsystems of the ESW system must have at least one pump and the respective flow path to the Spent Fuel Storage Pool OPERABLE.
- c.
One RHR Fuel Pool Cooling subsystem must be OPERABLE.
(Cannot be the same set of equipment used to meet item d.)
- d.
RHR must have one subsystem of Suppression Pool Cooling OPERABLE. (Cannot be the same set of equipment used to meet item c.)
- e.
Zone I is capable of being aligned to the Recirculation Plenum.
APPLICABILITY:
MODES 1, 2, 3, and 4 when the analyzed nominal decay heat in one SFSP is
- 5.1 x 106 BTU/hr concurrent with the analyzed nominal decay heat in the other SFSP
- 4.0 x 106 BTU/hr.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Fuel pool water A.1 Restore the temperature 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> temperature > 115 OF.
- 115 OF.
B. Less than two B.1 Restore two subsystems of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> subsystems of ESW with ESW with at least one at least one pump or pump and the respective the respective flow flow path to the Spent path to the Spent Fuel Fuel Storage Pool to Storage Pool OPERABLE.
OPERABLE status.
C. No RHR Fuel Pool C.1 Restore one subsystem to 7 days Cooling subsystem's OPERABLE status.
(continued)
U.
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SUSQUEHANNA - UNIT 1 TRM I 3.7-52 EFFECTIVE DATE 12/03/2004
Spent Fuel Storage Pools (SFSPs)
PPL Rev. 1 3.7.10 ACTIONS (con-nued)
1,
, .-
-
u'-
-
i e
,s~_-r CONDITION REQUIRED ACTION COMPLETION TIME D. No RHR Suppression Pool D.1 Restore one subsystem to 7 days Cooling subsystem's OPERABLE status.
E. Zone I not capable of E.A Restore alignment 7 days being aligned to the capability.
Recirculation plenum.
F. Required Actions and F.1 Initiate actions to cross-Immediately associated Completion connect the Unit 1 and Unit Times not met.
2 Spent Fuel Storage Pools through the Cask Storage Pit.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.7.10.1 Verify the fuel pool temperature is less than or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> equal to 115 OF.
TRS 3.7.10.2 Verify both subsystems of ESW have at least Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> one pump and the respective flow path to after the SFSP is the Spent Fuel Storage Pool OPERABLE.
isolated from the Cask Storage Pit AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter TRS 3.7.10.3 Verify that an RHR Fuel Pool Cooling Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> subsystem is OPERABLE.
after the SFSP is isolated from the Cask Storage Pit AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter (continued)
I IWAIFAIl
==
r.
SUSQUEHANNA - UNIT 1 TRM / 3.7-53 EFFECTIVE DATE 04/15/2003
Spent Fuel Storage Pools (SFSPs)
PPL Rev. 1 3.7.10 N
TECHNICAL REQUIREMENT SURVEILLANCE (continued)
=-
-A e
L L
~
S-W a
SURVEILLAN FREQUENCY 4.
TRS 3.7.10.4 Verify that RHR has one subsystem of Suppression Pool Cooling OPERABLE.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the SFSP is isolated from the Cask Storage Pit AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter 4.
TRS 3.7.10.5 Verify that Zone I is capable of being aligned to the Recirculation Plenum.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the SFSP is isolated from the Cask Storage Pit AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter I
7
SUSQUEHANNA - UNIT 1 TRM / 3.7-54 EFFECTIVE DATE 07/29/1999
Motor Operated Valves Thermal Overload Protection - Continuous PPL Rev. 1 3.8.2.1 3.8.2 Motor Operated Valves Thermal Overload Protection 3.8.2.1 Motor Operated Valves (MOV)Thermal Overload Protecfi-on - Continuous TRO 3.8.2.1 Thermal overload protection for each valve in Table 3.8.2. 1-1 shall be bypassed.
APPLICABILITY:
When the motor operated valve is required to be OPERABLE unless otherwise specified.
ACTIONS NOTE-Separate Condition entry is allowed for each valve.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more valves with
--, I -- -t~hermal overload protection l~,
-not bypassed.
A. 1 Declare affected valve(s) inoperable.
AND A.2 Enter applicable Conditions and Required Actions for affected system(s).
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8 hours
.1.
I SUSQUEHANNA - UNIT I TRM /3.8-5 EFFECTIVE DATE 04/02/2002
Motor Operated Valves Thermal Overload Protection - Continuous 3.8.2.1 PPL Rev. 1
-T-E-C-HNi4CALR-EQUI=R-EMENT-S-U-RV~ILL-CE SURVEILLANCE FREQUENCY TRS 3.8.2.1.1 Verify thermal overload protection for required valves is bypassed.
24 months AND Following maintenance on motor starter AND Following activities during which thermal overload protection was temporarily placed in force I
I
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1.
.
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SUSQUEHANNA - UNIT 1 TRM /3.8-6 EFFECTIVE DATE 04/02/2002
Motor Operated Valves Thermal Overload Protection - Continuous PPL Rev. 1 3.8.2.1 TABLE 3.8.2.1-1 (Page 1 of 4)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION - CONTINUOUS SYSTEM(S)
VALVE NUMBER AFFECTED 1
-1111ZM.411M1V I-VIM
=._s_.
HV-11313 Cont. Isol.
HV-11314 Cont. Isol.
HV-1 1345 Cont. Isol.
HV-1 1346 Cont. Isol.
HV-12603 Cont. Isol.
HV-15766 Cont. Isol.
HV-15768 Cont. Isol.
HV-152F001A CS HV-152F001B CS HV-152F004A CS HV-152F004B CS HV-152F005A CS HV-152F005B CS HV-1 52F01 5A CS HV-152F015B CS HV-152F031A CS HV-152F-031B CS HV-08693A ESW HV-08693B ESW HV-155F001 HPCI HV-155F002 HPCI HV-155F003 HPCI HV-155F004 HPCI HV-155F006 HPCI HV-155F007 HPCI HV-155F008 HPCI HV-155F011 HPCI HV-155F012 HPCI HV-155F042 HPCI HV-155F059 HPCI HV-155F066 HPCI HV-155F075 HPCI HV-155F079 HPCI HV-141F016 NSSS HV-141F019 NSSS (continued)
` -
SUSQUEHANNA - UNIT 1 TRM I13.8-7 EFFECTIVE DATE 12/03/2004
Motor Operated Valves-Thermal Overload Protection - Continuous PPL Rev. 1 3.8.2.1 T~mE8TAB I.1-1 (Page 2 of 4)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION - CONTINUOUS SYSTEM(S)
VALVE NUMBER AFFECTED HV-15012 RCIC HV-149F007 RCIC HV-149F008 RCIC HV-149F010 RCIC HV-149F012 RCIC HV-149F013 RCIC HV-149F019 RCIC HV-149F022 RCIC HV-149F031 RCIC HV-149F045 RCIC HV-149F046 RCIC HV-149F059 RCIC HV-149F060 RCIC HV-149F062 RCIC HV-149F084 RCIC HV-15112 RHR HV-151 F003A RHR
-1 F003B RHR
.HV-151 F04A RHR HV-151 F004B RHR HV-151 F004C RHR HV-151 F004D RHR HV-151 F006A RHR HV-151 F006B RHR HV-151 F006C RHR HV-151 F006D RHR HV-151 F007A RHR HV-151 F007B RHR HV-151 F008 RHR HV-151 F009 RHR HV-15IF010A RHR HV-15IF01OB RHR HV-151F015A RHR HV-151F015B RHR HV-151F016A RHR HV-151F016B RHR HV-151F017A RHR HV-151F017B RHR HV-151F021A RHR HV-151F021B RHR HV-1 51 F022 RHR (continued)
SUSQUEHANNA - UNIT 1 TRM I 3.8-8 EFFECTIVE DATE 12/03/2004
Motor Operated Valves Thermal Overload Protection - Continuous 3.8.2.1 PPL Rev. 1
-- ~
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- TABLE 3.8.2.1-1 (Page 3 of 4)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION - CONTINUOUS SYSTEM(S)
VALVE NUMBER AFFECTED 1
HV-151 F023 HV-151 F024A HV-151 F024B HV-1 51 F027A HV-151 F027B HV-151 F028A HV-151 F028B HV-151 F040 HV-151 F047A HV-151 F047B HV-151 F048A HV-151 F048B HV-1 51 F049 HV-151 F103A HV-151 F103B HV-151 F104A HV-151 F104B HV-01201A1 HV-01201A2 HV-01201 BI HV-01201 B2 HV-01222A HV-01222B HV-01224A1 HV-01224A2 HV-01224B1 HV-01224B2 HV-11210A HV-1 1210B HV-1 1215A HV-1 1215B HV-1 51 F073A HV-151 F073B HV-1 51 F075A HV-151 F075B HV-144F001 RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RWCU (continued)
SUSQUEHANNA - UNIT 1 TRMI/3.8-9 EFFECTIVE DATE 12/03/2004
Motor Operated Valves Thermal Overload Protection - Continuous 3.8.2.1 PPL Rev. 1 rr
MOTOR OPERATED TABLE 3.8.2.1-1 (Page 4 of 4)
VALVES THERMAL OVERLOAD PROTECTION - CONTINUOL SYSTEM(S)
VALVE NUMBER AFFECTED HV-144F004 RWCU HV-14182A RWCU HV-14182B RWCU HV-143F031A RX RECIRC HV-143F031B RX RECIRC HV-143F032A RX RECIRC HV-143F032B RX RECIRC
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SUSQUEHANNA - UNIT 1 TRM I 3.8-1 0 EFFECTIVE DATE 12/03/2004
Motor Operated Valves Thermal Overload Protection - Automatic 3.8.2.2 PPL Rev. 2
-3.8.2 Motor Operated Valves Thermal Overload Protection 3.8.2.2 Motor Operated Valves (MOV) Thermal Overload Protection - Automatic TRO 3.8.2.2 APPLICABILITY:
Thermal overload protection for each valve in Table 3.8.2.2-1 shall have automatic bypass capability.
When diesel generator (DG) E is not aligned to the Class 1 E distribution system and the valve is open.
ACTIONS NOTE Separate condition entry is allowed for each valve.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more MOVs Iswith MOmE bypass
/--
A
-- of thermal overload protection inoperable.
A.1 Continuously bypass the thermal overload protection.
OR A.2.1 Verify DG E is not running.
AND A.2.2 Verify the affected ESW flow path is isolated.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8 hours 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.8.2.2.1 Verify automatic bypass of MOV thermal overload protection is OPERABLE.
24 months I I
1 1 - I... - 1 1-1.1- -
- 1 1 -
-I.,-
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I
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_ _. II-I--,
-. y,.-
~
SUSQUEHANNA - UNIT I TRM 1 3.8-11 EFFECTIVE DATE 09/03/2004
Motor Operated Valves Thermal Overload Protection - Automatic 3.8.2.2 PPL Rey. 2 TABLE 3.8 2.2-1 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION - AUTOMATIC SYSTEM VALVE NUMBER AFFECTED HV01110E ESW HV01 120E ESW HV01112E ESW HV01 122E ESW
- - ---
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12 EFFECTIVE DATE 12/03/2004 SUSQUEHANNA - UNIT 1 TRM /13.8-'
Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 PPL Rey. 1 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation TRO 3.11.1.4 APPLICABILITY:
The Radioactive Liquid Radwaste Effluent Monitoring Instrumentation channels shown in Table 3.11.1.4-1 shall be OPERABLE with their setpoints established in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of TRO 3.11.1.1.
At all times.
ACTIONS
I------__------- NOTE-----
- 1.
Separate condition entry is allowed for each channel
- 2.
The provisions of TRO 3.0.4 are not applicable W
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more A.1 Suspend the release of Immediately radioactive liquid radioactive liquid effluent monitoring effluents monitored by instrumentation the affected channel alarm/trip channels setpoint less OR conservative than the limits allowed by TRO A.2 Declare the channel Immediately 3.11.1.1 inoperable (continued) gm
.:~
r II
- --~I I I -
I I~
SUSQUEHANNA - UNIT 1 TRM / 3.1 1-8 EFFECTIVE DATE 8/31/1998
Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 PPL Rev. 1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Liquid Radwaste releases are necessary and Effluent Line Gross Radioactivity Monitoring Instrumentation inoperable.
B. 1 Analyze at least two independent samples in accordance with TRO 3.11.1.1 AND B.2 Independently determine release rates for samples analyzed per Action B.1 AND B.3 Perform and independently verify discharge valve lineup AND B.4 Restore monitoring instrumentation Prior to initiating each release.
Prior to initiating each release.
Prior to initiating each release.
14 days
-- --- - ---- --
-- --.0.,,-M w
.1- ---
- 4.
4 C. Liquid Radwaste releases are not in progress and the Gross Radioactivity Monitoring instrumentation is inoperable because the inoperable channel is caused by a discharge valve interlock in an off-normal condition or not functioning.
C.1 Maintain at least one isolation valve closed between each source of release and the liquid radwaste discharge valve.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of securing from release or discovery of inoperable instrument.
(continued) 11 I I- - gm -woll 1.6
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- -- -
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-1 .1 SUSQUEHANNA - UNIT 1 TRM /3.11-9 EFFECTIVE DATE 8/31/1998 If
Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 PPL Rev. 1
_w r__--M" WMWT-,
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Liquid Radwaste releases D.1 Estimate Flow Rate.
Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> are necessary and Effluent during releases.
Line or Cooling Tower AND Blowdown Flow Monitoring Instrumentation inoperable.
D.2 Restore Monitoring 30 days Instrumentation.
E. Liquid Radwaste releases are not in progress and cooling tower blowdown flow monitoring instrumentation is inoperable because the inoperable channel is a discharge valve interlock in an off-normal condition or pflf f
>~-,
n~uncti'oning.
E.1 Maintain at least one isolation valve closed between each source of release and the liquid radwaste discharge valve.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of securing release or discovery of inoperable instrument 4
4 F. Required Action and Associated Completion Time of Conditions B, C, D, or E not met.
F.1
-NOTE--
Only applicable to Condition B*
Suspend release of radioactive effluents via this pathway AND F.2 Explain why the inoperability was not corrected in a timely manner.
Immediately In the next Radioactive Effluent Release Report per TS Section 5.6 I
V SUSQUEHANNA - UNIT I TRM 1 3.1 1-10 EFFECTIVE DATE 12/03/2004
Liquid Radwaste Effluent Monitoring Instrumentation PPL Ray. 1 3.11.1.4 TE HNIA~LRE b-AR-ENT SURVELLAN
~~~NOTE--------
Refer to Table 3.11.1.4-1 to determine which TRSs apply for each Monitoring Function.
SURVEILLANCE FREQUENCY TRS 3.11.1.4.1 Perform CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 3.11.1.4.2 Perform CHANNEL CHECK including a Prior to commencing source check.
release TRS 3.11.1.4.3 Perform CHANNEL FUNCTIONAL TEST 92 days Z~RS 3.11.1.4.4 Perform CHANNEL CALIBRATION 24 months SUSQUEHANNA - UNIT 1 TRM / 3.1 1 -11 SUSQEHANA
- NIT TRM/3.1-11EFFECTIVE DATE 8/31/1 998
Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 PPL Rey. 1
.111-
.1 -
I., *W-0 TABLE 3.11.1.4-1 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line 1
-TRS 3.11.1.4.2 TRS 3.11.1.4.3 TRS 3.11.1.4.4
- 2. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line 1
TRS 3.11.1.4.1(a)
TRS 3.11.1.4.3 TRS 3.11.1.4.4 TRS 3.11.1.4.1(a)
TRS 3. 1>.1.4.3 TRS 3.11.1.4.4
- b. Cooling Tower Blowdown
-1 e WI S ~
c of: is, I
(a) Only required when performing batch releases.
1--'
I I
-1 1
SUSQUEHANNA - UNIT 1 TRM /3.11-12 EFFECTIVE DATE 8131/1998
Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 PPL Rey. 1 I
-iA 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation TRO 3.11.1.5 APPLICABILITY:
The Radioactive Liquid Process Monitoring Instrumentation channels shown in Table 3.11.1.5-1 shall be OPERABLE with their setpoints established in accordance with the ODCM to ensure the alarm will occur prior to exceeding the limits of TRO 3.11.1.1.
As specified in Table 3.11.1.5-1.
ACTIONS NOTE -------
- 1.
Separate condition entry is allowed for each channel
- 2.
The provisions of TRO 3.0.4 are not applicable
-
I I
-CONDITION REQUIRED ACTION COMPLETION TIME
+
A. One or more Radioactive Liquid Process Monitoring Instrumentation alarm/trip channels setpoint less conservative than the limits allowed by TRO 3.11.1.1.
A.1 Suspend the release of liquid effluents monitored by the affected:-
channel Immediately OR A.2 Declare the channel inoperable Immediately I
(continued)
= -..
=-
j z
-:x SUSQUEHANNA - UNIT I 3.11-13 EFFECTIVE DATE 9/01/1998
Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 PPL Rey. 1 W.-
11 I I ;
I "
11 110 IN i
AtTicN S7 (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Radioactive Liquid Process B.1.1 Suspend the release of Immediately Monitoring Instrumentation liquid effluents monitored otherwise inoperable.
by the affected channel.
OR B.1.2 Analyze grab samples for Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> isotopic activity to the when the associated required LLDs for liquid pathway is in service effluents (Table 3.11.1.1-1).
AND B.2 Restore monitoring 30 days instrumentation
_r_
/.
-C.
Required Action and_
Associated Completion Time of Conditions B not met.
C.1 Explain why the inoperability was not corrected in a timely manner In the next Radioactive Effluent I
Release Report per TS Section 5.6 D. RHR Heat Exchanger to be D.1 Analyze grab samples from Prior to draining RHR drained to the spray pond.
the RHR Heat Exchanger for Heat Exchanger to isotopic activity to the required the spray pond.
LLDs for liquid effluents (Table 3.11.1.1-1).
I I _W_
! 7
-
-
I
- Z =-*Ai f=4
_=-a-AL______
SUSQUEHANNA - UNIT 1 TRM /3.11-14 EFFECTIVE DATE 12/03/2004
PPL Rey. 1 Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 TECHNICAL REQUIREMENT SURV-LLANCE
---a-----NOTE--a----
Refer to Table 3.11.1.5-1 to determine which TRSs apply for each Monitoring Function.
U SURVEILLANCE FREQUENCY TRS 3.11.1.5.1 Perform CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 3.11.1.5.2 Perform a Source Check 31 days TRS 3.11.1.5.3 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.11.1.5.4 Perform CHANNEL CALIBRATION 24 months p
-.-.------..--.---.---.--,-------.-.--.---
----.----..-.-..-----.
SUSQUEHANNA - UNIT I 3.1 1-15 EFFECTIVE DATE 9/01/1998
Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 PPL Rey. 1 H
RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION CHANNELS APPLICABILITY REQUIREMENTS GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- 1. Service Water System Effluent Line
- 2. Supplemental Decay Heat Removal Service Water 1
(a)
I (a)
TRS 3.11.1.5.1 TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4 TRS 3.11.1.5.1 TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4 TRS 3.11.1.5.1 TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4
- 3. RHR Service Water System Effluent 1/Loop
._ Line.
(b)
(a)
System aligned through Fuel Pool Cooling Heat Exchanger. Alignment change between Service Water System Effluent Line and Supplemental Decay Heat Removal Service Water is not considered to be a change in the applicable condition.
(b)
At all times SUSQUEHANNA - UNIT 1 3.1 1-16 EFFECTIVE DATE 9/01/1998
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2
- 3. 11 Ra lMoacti'Ve Mluents 3.11.2 Gaseous Effluents 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation TRO 3.11.2.6 APPLICABILITY:
The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.11.2.6-1 shall be OPERABLE with their setpoints established in accordance with the ODCM to ensure that the limits of Requirement 3.11.2.1 are not exceeded.
According to Table 3.11.2.6-1 ACTIONS g
- NOTE -
Separate condition entry is allowed for each channel.
r meCONDITI-ON; VI--
REQUIRED ACTION COMPLETION TIME
+
A.
Radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than,.--,
required to ensure that the limits of Requirement 3.11.2.1 are not exceeded A.1 Suspend the release of radioactive gaseous effluents monitored by the affected channel Immediately Immediately OR A.2 Declare the channel inoperable (continued)
__v SUSQUEHANNA - UNIT 1 3.11-25 EFFECTIVE DATE 9/01/1998
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2
- 1. -- - -
- 11 F -- -
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- cl ' -
; --'- -- -- I- -
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I 1. I ACTIONS (continue CONDITION REQUIRED ACTION COMPLETION TIME B. Reactor Building Ventilation System Noble Gas Activity Monitor low range channel inoperable B. 1.Take grab samples AND B.2 Analyze grab samples for isotopic activity to the required LLDs for principal noble gas gamma emitters (Table 3.11.2.1-1)
AND B.3 Restore monitoring instrumenta ton Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while release is in progress.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of grab sample 30 days
-t I
-0t
' -C.-
Deleted
- `
D. Reactor Building DA IEstimrate flow rate
-Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ventilation Monitoring while release is System Effluent System in progress Flow Rate Monitor or AND Sampler Flow Rate Monitor inoperable D.2 Restore monitoring 30 days instrumentation (continued)
----------
SUSQUEHANNA - UNIT 1 TRM / 3.11-26 SUSQ EHA NA UNT I RM 3.1
-26EFFECTIVE DATE 01/21/2004
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2
.=_
=- -
-ACTIONS (continued) w ,<
CONDITION- -- -
REQUIRED ACTION COMPLETION TIME E. Turbine Building Ventilation System Noble Gas Activity Monitor low range channel inoperable E.1 Verify mechanical vacuum pump is not in operation AND E.2 Take grab samples AND E.3 Analyze grab samples for isotopic activity to the required LLDs for the principal noble gas gamma emitters (Table 3.11.2.1-1)
AND E.4 Restore monitoring instrumentation Immediately Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while release is in progress Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after sample 30 days 4
4-F. Deleted G. Turbine Building G.1 Estimate flow rate Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ventilation Monitoring while release is System Effluent System in progress.
Flow Rate Monitor or AND Sampler Flow Rate Monitor inoperable G.2 Restore monitoring 30 days instrumentation (continued)
SUSQUEHANNA - UNIT I TRM I 3. 11-27 EFFECTIVE DATE 01/21/2004
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. Standby Gas Treatment H.1 Take grab samples Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> System Noble Gas while release is Activity Monitor low in progress range channel AND inoperable H.2 Analyze grab samples for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> isotopic activity to the of grab sample required LLDs for being taken principal noble gas gamma emitters (Table 3.11.2.1-1)
AND H.3 Restore monitoring 30 days instrumentation
.I.
Deleted I
J.
SGTS Ventilation J.1 Estimate flow rate Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Monitoring System while release is Effluent flow rate in progress.
monitor or sample flow AND rate monitor inoperable J.2 Restore monitoring 30 days instrumentation (continued) 1=0_;=M I 11 1111 1 1111 1 1 1 r-
. I I I
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00%"00,401 N 4 ---- --- --
rm5wwov, ! I-,- II-I'll
I M-SUSQUEHANNA - UNIT 1 TRM / 3.11-28 EFFECTIVE DATE 01/2112004
rn-
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rev. 2 A.
me
- _vE.
9MIM
-a ACTIONS (continf e
QF CONDITION REQUIRED ACTION COMPLETION TIME K.
Required Actions and K.1 Explain why this inoperability In the next Completion Times not met was not corrected in a timely Radioactive Effluent for Conditions B through J manner Release Report per TS Section 5.6 TECHNICAL REQUIREMENT SURVEILLANCE
--- NOTE--
Refer to Table 3.11.2.6-1 to determine which TRSs apply for each Monitoring Function.
SURVEILLANCE FREQUENCY TRS 3.11.2.6.1 Perform CHANNEL CHECK 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
TRS 3.11.2.6.2 Deleted
.7r_-M e
-a-nem.......-45 TRS 3.11.2.6.3 Perform Source Check 31 days TRS 3.11.2.6.4 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.11.2.6.5 Perform CHANNEL CALIBRATION 24 months SUSQUEHANNA - UNIT I TRM 1 3.11-29 EFFECTIVE DATE 12/03/2004'
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2
-Z;V7A.R
- ...O.
1-ce w I
-f:.
3 i _,.ff-_iz-1-l' TABuff P1
&Page"iof3-RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS
- 1. REACTOR BUILDING VENTILATION MONITORING SYSTEM
- a. Noble Gas Activity Monitor (Low Range)
At all Times 1
TRS 3.11.2.6.1 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5
- b. Deleted
- c.
Deleted
-7
==
d.
Effluent System Flow Rate Monitor At all Times 1
TRS 3.11.2.6.1 TRS 3.11.2.6.4 IRS 3.11.2.6.5
- e. Sampler Flow Rate Monitor At all Times I
TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 (continued)
- 1 -. *_.
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I I I-j I
-II SUSQUEHANNA - UNIT I TRM / 3. 11-30 EFFECTIVE DATE 01/21/2004
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2
~TABLE 3. 1.2.6-1 (Page 2 of 3)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS
- 2.
TURBINE BUILDING VENTILATION MONITORING SYSTEM
- a. Noble Gas Activity Monitor (Low Range)
At all Times 1
TRS 3.11.2.6.1 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5
- b. Deleted
- c. Deleted
- d. Effluent System Flow Rate
- e. Sampler Flow Rate Monitor At all Times At all Times I
I TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 (continued)
- ~v:-
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- ;- _7
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^'L 1121/2004 SUSQUEHANNA - UNIT I TRM I 3.11-31 EFFECTIVE DATE 01
Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 PPL Rey. 2 wi T
ABLE 3.11.2.6-1 (Page 3 o 3-f 3) )-- ----
~
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS
- 3. STANDBY GAS TREATMENT SYSTEM (STGS) MONITOR
- a. Noble Gas Activity Monitor (Low Range)
During operation of SGTS I
TRS 3.11.2.6.1 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5
- b. Deleted
- c. Deleted
=
- d. Effluent System Flow Rate
-~ - " ~- - I -
nitor
<e.
Sm Flow Ra
-te Monito
-r
I TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 4
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I::r I-IU 11M SUSQUEHANNA - UNIT 1 TRM / 3.11-32 EFFECTIVE DATE 01/21/2004
Monitoring Program 3.11.4.1 PPL Rev. 1 tdio actio tve Effluents R
3.11.4 Radiological Environmental Monitoring 3.11.4.1 Monitoring Program TRO 3.11.4.1 APPLICABILITY:
The radiological environmental monitoring program shall be conducted as specified in Table 3.11.4.1-1.
At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological environmental monitoring program not being conducted as specified in
_ able 3.11.4.1-1 A.1 Report and describe the events and any actions taken to prevent their recurrence in the Annual Radiological Environmental Operating Report Annually
+
B. The average level of radioactivity over any calendar quarter as the result of an individual radionuclide in plant effluents in a particular environmental exposure pathway in a particular environmental sampling medium, at a specified location exceeds the applicable reporting level of Table 3.11.4.1-2 B. Prepare and submit a Special Report to the Commission 30 days (continued)
__I-
--- 1 II'l
=
I_
- ~
II
~-
1 -
I
- ~ -
-I ~
SUSQUEHANNA - UNIT 1 3.1 1-35 EFFECTIVE DATE 8131/1998
Monitoring Program PPL Rev. 1 3.11.4.1 ACTIONS (continued)
.m mo-CONDITION REQUIRED ACTION COMPLETION TIME C. More than one of the C. A Prepare and submit a Special 30 days radionuclides in Table Report to the Commission 3.11.4.1-2 are detected in a particular environmental exposure pathway at a specified monitoring location and are the result of plant effluents AND The sum of the ratios of the quarterly average activity levels to their corresponding reporting levels of each detected radionuclide, from Table 3.11.4.1-2, is > 1.0 iRe a
x 7.7-77s oC~ic A=7_
N5o s
m-s s>rwa:rSAe(continued) us us ~
m u
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...
nvj...
-.
71zF-`L I7 SUSQUEHANNA - UNIT 1 3.11-36 EFFECTIVE DATE 8/31/1998 I-..
ON
Monitoring Program PPLRev. 1 3.11.4.1
~ACTIONS (conti~nuedi)
CONDITION REQUIRED ACTION COMPLETION TIME D. One or more Radionuclide(s) other than those in Table 3.11.4.1-2 are detected in a particular environmental exposure pathway at a specified location and are the result of plant effluents AND The potential annual dose to a MEMBER OF THE PUBLIC from all detected radionuclides that are the result of plant effluents is greater than or equal to the calendar year limits of TROs 3.11.1.2, 3. 11.2.2 and 3.11.2.3 D.A Prepare and submit a Special Report to the Commission 30 days E. The requirements for a E. 1 Report and discuss the Annually Special Report per reasons for not attributing Conditions B, C, or D are identified radionuclides to plant met, but the radionuclides effluents in the Annual that are detected are not the Radiological Environmental result of plant effluents Operating Report (continued)
_=-===
!7 -Ae
=-
SUSQUEHANNA - UNIT 1 3.1 1-37 EFFECTIVE DATE 8/31/1998 I~
Monitoring Program 3.11.4.1 PPL Rev.: I
~-
N. !MP Z
-~
~~- ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F. Milk or fresh leafy vegetable samples are unavailable
,-,from one or more of the sample locations required by Table 3.11.4.1-1 NOTE The specific locations from which samples were unavailable may then be deleted from the monitoring program.
F.1 Identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program AND F.2 Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report 30 days Annually I
7 - I
-, I I---- - - -
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- -- 1 Z, - -,1-,"-- - --
I I - . ?7
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Monitoring Program PPL Rey. 1 3.11.4.1 I.
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FREQUENCY TRS 3.11.4.1.1 Collect the radiological environmental As required by monitoring samples pursuant to Table 3.11.4.1-1 Table 3.11.4.1-1 TRS 3.11.4.1.2 Analyze samples pursuant to the As required by requirements of Table 3.11.4.1-1 with Table 3.11.4.1-1 equipment meeting the detection capabilities required by Table 3.11.4.1-3 TRS 3.11.4.1.3 Determine annual cumulative potential dose Annually contributions from radionuclides detected in environmental samples in accordance with the methodology and parameters in the ODCM.
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE -
SAMPLING AND EXPOSURE PATHWAY SAMPLES AND COLLECTION TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS FREQUENCY OF ANALYSIS
- 1. DIRECT RADIATION 40 routine monitoring stations with two or more dosimeters or with one instrument for measuring and recording dose rate continuously placed as follows:
Quarterly Gamma dose quarterly
- 1. An inner ring of stations, one in each meteorological sector, in the general area of the SITE BOUNDARY 2 An outer ring of stations, one in each meteorological sector, in the 3 to 9 mile range from the site
- 3. The balance of the stations placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations
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- 2. AIRBORNE Radioiodine and Particulates Samples from 5 locations
- a. 1 sample from close to each of the 3 SITE BOUNDARY locations (in different sectors) with the highest calculated annual average groundlevel %/Q
- b. I sample from the vicinity of the community having one of the highest calculated annual ground level XIQ Continual sampler operation with sample collection weekly, or more frequently if required by dust loading Radioiodine Canister:
1-131 Analysis weekly Particulate Samoler: -
Gross Beta radio activity analysis following filter change"' Gamma isotopic analysis of composite (by location) quarterly
- c. I sample from a control location, between 15 and 30 km distant and in the least prevalent wind direction of wind blowing from the plant (continued)
(a) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thom daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
SUSQUEHANNA - UNIT 1 3.1 1-40 EFFECTIVE DATE 8/31/1998
Monitoring Program 3.11.4.1 PPL Rev-1
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TABLE 3.11.4.1-1 (Page 2 of 3)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS
- 3. WATERBORNE
- a. Surface I sample upstream I sample downstream Composite sample over one-month period Gamma isotopic analysis monthly.
Composite for tritium analyses quarterly
- b.
Ground Samples from I or 2 sources only if likely to be affected Quarterly Gamma isotopic and tritium analyses quarterly
- c.
Drinking 1 sample from each of 1 to 3 of the nearest water supplies that could be affected by its discharge 1 sample from a control location 1
-. _M Composite sample over 2-week period when 1-131 analysis is performed,
-MM f5nthly
.. I composite otherwise 1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year. Composite for gross beta and gamma isotopic analyses monthly.
Composite for tritium analyses quarterly
- d. Sediment from shoreline I sample from downstream area with existing or potential recreational value Semiannually Gamma isotopic analyses semiannually (continued)
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-IM RI~l 14 SUSQUEHANNA - UNIT 1 3.11-41 EFFECTIVE DATE 8/31/1998
Monitoring Program 3.11.4.1 PPL Rev. I TABLE3.111.4.1-1 (Page 3 of 3)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND EXPOSURE PATHWAY SAMPLES AND COLLECTION TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS FREQUENCY OF ANALYSIS
- 4.
INGESTION
- a. Milk
- a. Samples from milking animals in 3 locations within 5km from the plant having the highest dose potential. If there are none, then, 1 sample from milking animals in each of 3 areas between 5 and 8km distant where doses are calculated to be greater than 1 mrem per year.
Semimonthly when animals are on pasture, monthly at other times.
Gamma isotopic and 1-131 analysis semimonthly when animals are on pasture; monthly at other times.
1 sample from milking animals at a control location (between 15 and 30km from the plant preferably in the least prevalent direction for wind blowing from the plant).
- b. Fish and/or Invertebrates
- c.
Food Products
- b. 1 sample of each of two recreationally important species in vicinity of plant discharge area, 1 sample of same species in areas not influenced
.a by plant discharge.
- c.
1 sample of each prncipal cIass of food products from any area which is irrigated by water in which liquid plant wastes have been discharged.
Sample in season, or semiannually if they are not seasonal.
Gamma isotopic analysis on edible portions.
At time of harvest Gamma isotopic analysis on edible portions.
Samples of 3 different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.
1 sample of each of the similar broad leaf vegetation grown between 15 to 30km from the plant, preferably, in the least prevalent direction for wind blowing from the plant if milk sampling is not performed.
Monthly when available Monthly when available Gamma isotopic and 1-131 analysis.
Gamma isotopic and 1-131 analysis.
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Monitoring Program PPLRey. 1 3.11.4.1
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TABLE 3.11.4.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels K
Analysis H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-1 40 Water Airborne Particulate Fish Milk Food Products (pCiA) or Gases (pCi/M3 )
(pCi/kg, wet)
(pCi/I)
(pCi/kg, wet)
-a 20,000(a) 1,000 400 1,000 300 300 400(b) 30,000 10,000 30,000 10,000 20,000 zrX 2
30 50 200(b)
N 0.9 20 2,000 3
100 70 2,000 300 (a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
(b) Total for parent and daughter.
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EFFECTIVE DATE 8/31/1998 SUSQUEHANNA - UNIT 1 3.1 1-43
Monitoring Program 3.11.4.1 PPL Rev. 1 TABLE 3.11.4.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)
Food Airborne Products Sendiments Water Particulate Or Fish Milk (pCi/kg, (Ci/kg, Analysis (pCi/I)
Gases (pCi/m3 )
(pCi/kg, wet)
(pCi/)
wet) dry)
Gross Beta H-3 Mn-54 Fe-59 Co-58, 60 Zn-65
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2000 15 30 15 30 30 15 1 (a) 15 18 60 15 0.01 130 260 130 260
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C I DATE 8/31/1 998 EFFECTIVE DATE 8/31/1998 SUSQUEHANNA - UNIT 1
Land Use Census 3.11.4.2 PPL Rev. I 3.11.4 Radiological Environmental Monitoring 3.11.4.2 Land Use Census TRO 3.11.4.2 APPLICABILITY:
A land use census shall be conducted.
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Land use census identifies a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Requirement A.1 Identify the new location(s) in the next Radioactive Effluent Release Report As defined by the Radioactive Effluent Release Report
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B. Land use census identifies a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Requirement 3.11.4.1 B. 1 Add the new location(s) to the radiological environmental monitoring program AND 8.2 Identify the new location(s) in the next Radioactive Effluent Release Report per TS Section 5.6 30 days As defined in Radioactive Effluent Release Report M
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SUSQUEHANNA - UNIT 1 TRM 3.11-45 EFFECTIVE DATE 12/03/2004
Land Use Census 3.11.4.2 PPL Rey. 1 a -..
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SUSQUEHANNA - UNIT 1 3.11-46 EFFECTIVE DATE 8/31/1998 I
TRM Isolation Actuation Instrumentation PPL Rey. 2 B 3.3.6
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B 3.3.6 TRM Isolation Actuation Instrumentation BASES TRO The TRM Actuation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Reference 1). The TRM Isolation Actuation Instrument has been relocated from the Technical Specifications because the identified Function is not credited in the plant design basis to mitigate any plant event, but does provide a diverse means to initiate an Isolation Actuation.
The isolation instrumentation includes the sensors, relays, and instruments that are necessary to cause initiation of primary containment and reactor coolant pressure boundary (RCPB) isolation. When the setpoint is reached, the sensor actuates, which then outputs an isolation signal to the isolation logic. Monitoring a wide range of independent parameters provides functional diversity. The input parameters to the isolation logic are:
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Reactor Building Main Steam Differential Temperature - High, (c)
Turbine Building Main Steam Line Tunnel Temperature - High, (d)
HPCI Pipe Routing Area Differential Temperature - High, (e) HPCI Equipment Room Differential Temperature - High, (ff
'-RCIC Pipe-Routi'ng Area Differential Temperature - High, (g)
RCIC Equipment Room Differential Temperature - High, (h)
RWCU Penetration Area Differential Temperature - High, (i)
RWCU Pump Area Differential Temperature - High, (I)
RWCU Heat Exchanger Area Differential Temperature - High, and (k)
RHR Flow - High.
The valves associated with these trip channels are identified in Table B 3.3.6-1. Each of these valves is also associated with other trip channels as identified in LCO Bases B 3.6.1.3.
Functions (d) and (f) trips will occur only after a 15 minute time delay; the other trips occur after a one second delay. See Tech Spec Basis B 3.3.6-1.
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TRM Isolation Actuation Instrumentation PPL Rev. 2 B 3.3.6 7
B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. The Actions are modified by Note 2, which identifies that if the degradation of any TRM Isolation Actuation Instrumentation impacts the OPERABILITY of any Technical Specification Isolation Instruments identified in LCO 3.3.6.1, "Primary Containment Isolation Instrumentation", the appropriate Technical Specification Actions must be taken. This Note is necessary because the TRM Isolation Actuation Instrumentation can impact the capability of the Technical Specification Isolation Instrumentation. If this occurs, both the TRM and Technical Specification Required Actions must be taken to ensure proper compensatory actions are taken.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRM Isolation Actuation Instrumentation Functions are maintained OPERABLE. TRM Isolation Actuation Instrumentation Surveillances are performed consistent with the Bases for LCO 3.3.6.1 "Isolation Activation Instrumentation."
TRS 3.3.6.5 TLTEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform portions of this surveillance -under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the surveillance when performed at the 24 month Frequency.
TRS 3.3.6.6 Response time testing for the Function 1.a and Function 2.a < 10 second requirement per FSAR Table 7.3-29 is met by testing the channel for the < 1 second channel response time requirement per FSAR Table 7.3-29 for Function 1.a.
(continued)
SUSQUEHANNA - UNIT I TRM I B 3.3-11 EFFECTIVE DATE 08/31/1998 M
TRM Isolation Actuation Instrumentation B 3.3.6 PPL Rey. 2 B 3.3.6 TRM Isolation Actuaon n Instrumentation BASES (continued)
REFERENCES
- 1.
FSAR Section 7.3.1
- 2.
NRC Inspection and Enforcement Manual, Part 9900: Technical Guidance, Standard Technical Specification Section 1.0 Definitions, Issue dated 12/8196.
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TRM Isolation Actuation Instrumentation PPL Rey. 2 B 3.3.6 Table B 3.3.6-1 Primary Containment Isolation Valves Isolation Signal Plant systems Valve Number Valve Description Function No.
Nuclear HV-141F022A MSIV 1.a, 1.b Boiler HV-141F022B MSIV 1.a, 1.b HV-1 41 F022C MSIV 1.a, 1.b HV-141F022D MSIV 1.a, 1.b HV-141F028A MSIV 1.a, 1.b HV-141F028B MSIV 1.a, 1.b HV-141F028C MSIV 1.a, 1.b HV-141F028D MSIV 1.a, 1.b HV-141F016 MSL Drain Isolation Valve 1.a, 1.b HV-141F019 MSL Drain Isolation Valve 1.a, 1.b Reactor HV-143F019 Reactor Coolant Sample Valve 2.a Recirculation HV-143F020 Reactor Coolant Sample Valve 2.a HPCI HV-155F002 HPCI Steam Supply Valve 3.a, 3.b HV-155F003 HPCI Steam Supply Valve 3.a, 3.b HV-155F100 HPCI Steam Supply Valve 3.a, 3.b HV-155F042 HPCI Suction Valve 3.a, 3.b RCIC HV-149F007 RCIC Steam Supply Valve 4.a, 4.b HV-149F008 RCIC Steam Supply Valve 4.a, 4.b HV-149F088 RCIC Steam Supply Valve 4.a, 4.b RWCU HV-144F001 RWCU Suction Valve 5.a, 5.b, 5.c HV-144F004 RWCU Suction Valve 5.a, 5.b, 5.c RHR HV-151F022 RHR - Reactor Vessel Head Spray Valve 6.a I 14"r RHR HV-151 F022 RHR - Reactor Vessel Head Spray Valve 6.a HV-151 F023 RHR - Reactor Vessel Head Spray Valve 6.a HV-151 F008 RHR Shutdown Cooling Valve 6.a HV-1 51 F009 RHR Shutdown Cooling Valve 6.a
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Primary Containment Closed System Boundaries PPL Rey. I B 3.6.4 B 3.6.4 Primary Containment Closed System Boundaries BASES TRO A closed system used as a primary containment isQiation boundary is defined as a piping system outside primary containment that does not communicate directly with the atmosphere outside primary containment, meets the design requirements of NUREG-75/087, (Reference 1), as described in FSAR Section 6.2.4 (Reference 2), and is considered an extension of primary containment.
The design of several containment penetrations relies upon a single Primary Containment Isolation Valve (PCIV) and a closed piping system outside primary containment (Primary Containment Closed System) as the two isolation barriers, as identified in Technical Specification (TS) Bases, Table B 3.6.1.3-1. For a given containment penetration that relies upon a closed system as the redundant containment isolation barrier, the closed system boundary is essentially equivalent to the ASME Class 2 boundary for the system/loop which contains the penetration. The closed system boundaries are defined by the Leakage Rate Test Program.
As a special case, the containment penetrations for the H202 analyzer lines also rely upon a closed system as the redundant containment isolation barrier, even though two PCIVs are provided for each of these penetrations. The PCIVs associated with these penetrations are identified in TS Bases Table B 3.6.1.3-1. The PCIVs in each H202 analyzer penetration are redundant to each other with regard to mechanical operation, but are not redundant with regard to electrical operation. Both PCIVs in each of these penetrations are powered from the same electrical division in order to prevent a single electrical failure from resulting in a loss of both divisions of H202 analyzers. This results in the valves being susceptible to a single electrical failure which could result in both valves failing open or failing to remain closed.
Because of this unique design consideration, the H20.2 penetrations are equivalent to penetrations having a single PCIV, with the closed system providing the redundant isolation barrier.
Each division of the H202 analyzer piping has multiple flowpaths (e.g., upper drywell, lower drywell, drywell return). These multiple flowpaths are interrelated and make up one closed system for each division. The tested closed system for each division is shown in the Leakage Rate Test Program.
For penetrations with a single PCIV, alteration of the corresponding closed system boundary during power operation is permitted provided that alteration does not impact the containment isolation function of the PCIV, [i.e., able to be closed (automatically or manually) or remain closed, and maintain leakage within that assumed in the design basis loss of coolant accident dose analysis.]
Conversely, if a PCIV is in a configuration where it is not capable of performing its containment isolation function (e.g., stuck open), then closed system integrity must be maintained in order to have at least one containment isolation barrier operable. These requirements also apply to the H202 analyzer penetrations.
SUSQUEHANNA - UNIT 1 TRM I B 3.6-6 EFFECTIVE DATE 12/0312004 am
Primary Containment Closed System Boundaries B 3.6.4 PPL Rey. 1 B 3.6.4 Primary Containment Closed System Boundaries
-BASES (continued)
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The APPLICABILITY is modified by a Note allowingPrimary Containment Closed System boundaries to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communications with the control room. In this way, the Primary Containment Closed System can be rapidly isolated when a need for primary containment isolation is indicated.
Opening of closed system boundary valve periodically for specific activities that l require the valve to be opened (e.g., testing, venting) is not considered a breach of a closed system, provided the valve is operated under administrative control. Examples include the opening of a high point vent in the Core Spray system to verify that the system is filled with water or the opening of a H202.analyzer boundary valve to perform a functional test of the Post Accident Sampling System. Similarly, stroking of a boundary valve as part of restoration from maintenance activities associated with that valve does not constitute a breach of the closed system. Examples of this would be the stroking of a valve where the work that was done was replacement of the motor actuator, or other work where the pressure boundary of the valve was not violated. Also, the opening of a valve as a result of normal system operation/testing does not constitute a breach of the closed system.
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. - 1 SUSQUEHANNA - UNIT 1 TRM / B 3.6-7 EFFECTIVE DATE 12/31/2002
Primary Containment Closed System Boundaries PPL Rev. 1 B 3.6.4 B 3.6.4 Primary Containment Closed System Boundaries BASES (continued)
ACTIONS These ACTIONS are provided to address Conditions where Primary Containment Closed System boundaries are inoperable. When the Primary Containment Closed System boundaries are OPERABLE, but the associated PCIV(s) is inoperable, LCO 3.6.1.3, Primary Containment Isolation Valves (PCIVs)," Condition C or Condition D would apply.
Note 1 has been added to provide clarification that, for the purpose of the TRO, separate Condition entry is allowed for each closed system. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable closed system. Complying with Required Actions may allow for continued operation, and subsequent inoperable PCIVs or closed systems are governed by subsequent Condition entry and application of associated Required Actions.
The ACTIONS are modified by Notes 2 and 5. Note 2 ensures that appropriate remedial actions are taken, if necessary, if the affected system(s) are rendered inoperable by an inoperable closed system (e.g., an Emergency Core Cooling System subsystem is inoperable due to a failed open drain valve). Note 5 ensures appropriate remedial actions are taken when the primary containment leakage limits are exceeded. Pursuant to TRO 3.0.6, these actions are not
--required even when the associated TRO is not met Therefore, Notes 2 and 5 are added to require the proper actions be taken when Pnmary Containment ClosedSystem'Boundaries are inoperable.
Note 3 has been added to provide clarification that failing to complete the Required Actions results in a condition that could compromise Primary Containment Integrity and thus, place the plant in an unanalysed condition.
The ACTIONS are modified by Note 4 allowing penetration flow path(s) to be unisolated intermittently under administrative controls. This note applies to a condition where the closed system is inoperable. It does not apply to a situation where a penetration flowpath is normally open and the closed system is OPERABLE (such as the RHR and Core Spray minimum flow return lines),
since that represents the normal design configuration. Administrative controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. In this way, the penetration can be rapidly isolated when a need for primary containment isolation is indicated.
SUvEHNA-UNI I TR I B- -
EFCiVE DATE 12/31/2002 SUSQUEHANNA - UNIT I TRM / B 3.64 3
EFFECTIVE DATE 1213112002
Primary Containment Closed System Boundaries B 3.6.4 PPL Rev. I B 3.6.4 Primary Containment Closed System Boundaries BASES (continued)
ACTION (continued)
A.1.1. A.1.2. A.2.1. and A.2.2 With one or more penetration flow paths with its Primary Containment Closed System boundary inoperable, the affected portion of the closed system piping must be isolated from the rest of the closed system and the primary containment. This Condition only applies when the associated PCIV for the penetration flow path is OPERABLE. For the penetration flow paths associated with the H202 analyzers, both PCIVs must be OPERABLE. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. Closing an intervening valve between the breach in the closed system and the open penetration is permitted when the penetration PCIV is OPERABLE. If no intervening valve exists between the closed system breach and the PCIV, then the PCIV must be closed and deactivated to ensure compliance with LCO 3.6.1.1, "Primary Containment." For the penetration flow paths associated with the H202 analyzers, one PCIV must be closed and deactivated. Deactivation of the H202 analyzer PCIVs is discussed in the TS Bases for LCO 3.6.1.3, Condition D.
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The Required Actions to isolate the closed system breach, or the penetration, must be completed within the 4-hour Completion Time. The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is consistent with LCO 3.6.1.3, Condition A, which applies to penetration flow paths with two PCIVs. The Primary Containment Closed System boundary is considered to be the functional equivalent to the ASME Class 2 boundary for the system/loop which contains the penetration. Because this boundary serves as the second barrier required by General Design Criteria 55 and 56 (Ref. 3) in lieu of a second isolation valve, the same Required Actions and associated Completion Times are appropriate.
For inoperable closed system boundaries where the breach has been isolated from the rest of the closed system and primary containment (Required Action A.1.1), or where the penetration has been isolated by a closed and deactivated PCIV (Required Action A. 1.2), the affected penetration flow path(s) must be verified to be isolated on a periodic basis. This is necessary to ensure that primary containment penetrations required to be isolated following an accident, and no longer capable of being automatically isolated, will be in the isolation position should an event occur. This Required Action does not require any testing or device manipulation. Rather, it involves verification that those devices outside containment and capable of potentially being mispositioned are in the correct position.
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EFFECTIVE DATE 12/31/2002 SUSQUEHANNA - UNIT 1 TRM / B 3.6-9
Primary Containment Closed System Boundaries PPL Rey. I B 3.6.4 B 3.6.4 Primary Containment Closed System Boundaries BASES (continued)
ACTION The Completion Time of "once per 31 days" is consistent with LCO 3.6.1.3, (continued)
Condition A, and is appropriate because the devices are operated under administrative controls and the probability of their misalignment is low.
B.1 and B.2 With one or more penetration flow paths with its Primary Containment Closed System boundary inoperable, the affected penetration flow path must be isolated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> when the corresponding PCIV for the penetration flow path is also inoperable. For the penetration flow paths associated with the
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H202 analyzers, this Condition applies when one or both PCIVs are inoperable.
The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 1-hour Completion Time is consistent with the LCO 3.6.1.3, Condition B, which applies to penetration flow paths with two PCIVs, both of which are inoperable. Alternatively, immediate entry into the applicable Conditions and Required Actions of LCO 3.6.1.1 is permitted.
C.1 7If the Required Actions and associated Completion Times of Conditions A or B cannot be met, immediate entry into LCO 3.6.1.3, Condition G or H, is directed.
The appropriate Condition to enter is determined by the operating MODE of the unit at the time of entry.
TRS TRS 3.6.4.1 The boundaries for water filled closed systems are verified to be intact by direct observation, during operator rounds, of the lack of leakage from the system (which is under pressure from the keepfill system), or by observed integrity during functional testing as required by the applicable LCO; and by the system boundary administrative controls (i.e., by procedure and checkoff lists for evolutions that affect the system boundary). The integrity of a closed system boundary, verified in accordance with the methodologies described above, is not compromised throughout the effective surveillance period by the subsequent isolation of the keepfill system and/or depressurization of the closed system.
=L SUQEAN-NT T.
B 3.-0EFCIE AE11120 SUSQUEHANNA - UNIT 1 TRM / B 3.6-1 0 EFFECTIVE DATE 12/3112002
Primary Containment Closed System Boundaries B 3.6.4 PPL Rev. 1 B 3.6.4 Primary Containment Closed System Boundaries BASES TRS (continued)
The boundaries for air filled closed systems are verified to be intact by verification that no work has been performed since the last leak rate test in accordance with TRS 3.6.4.2, and by the system boundary administrative controls (i.e., procedure and checkoff lists for evolutions that affect the system boundary).
The Frequency corresponds to the Inservice Testing Program requirements for performing valve testing at least once every 92 days.
TRS 3.6.4.2 When restoring a closed system, testing must be performed to verify system integrity. Explicit quantification of the leakage is not required for water filled closed systems. However, testing must be sufficient to assure that an essentially leaktight barrier exists (no gross leakage). For air filled closed systems, explicit leakage quantification is required, and is performed in accordance with the Leakage Rate Test Program.
The Frequency of testing is in accordance with the Leakage Rate Test Program.
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REFERENCES
- 1. NUREG-75/087, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants", September 1975.
- 2.
FSAR Section 6.2.4, "Containment Isolation System."
I
- 3.
10 CFR 50, Appendix A, "General Design Criteria for Nuclear Power Plants."
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SUSQUEHANNA - UNIT I TRM / B 3.6-11 EFFECTIVE DATE 12/31/2002
Snubbers B 3.7.8 PPL Rev. 1 BASES TRO All snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
Snubbers are required to be OPERABLE whenever they are considered necessary to support equipment for the systems on which they are installed.
"Type" of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity. For example, mechanical snubbers utilizing the same design features of the 2-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by company "B" for the purposes of this Technical Requirement would be of a different type, as would hydraulic snubbers from either manufacturer.
-1'snr-"9P
-A list of indivda snuberswith detailed information of snbe lcto and size and of system affected shall be available at the plant in accordance with Section 50.71 (c) of 10 CFR part 50. The controlled list of plant snubbers is maintained by the ISI Program. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
(continued)
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'B 3.7-24 EFFECTIVE DATE 08/31/1
Snubbers PPL Rey. I B 3.7.8 B 7.
nuers BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
Condition A The removal or inoperability of one or more snubbers or one or more sets of parallel pair snubbers on an OPERABLE system requires the supported system to be immediately declared inoperable.
For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached. The-purose--of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
If prior to the removal or inoperability of one snubber or one set of parallel pair snubbers on an OPERABLE system, an engineering evaluation has been performed on the system to which the snubber is attached and the
, Eengineerngevaluation determines that there are no adverse affects on the system with the snubber either removed or inoperable, then the removed or inoperable snubber must be repaired or replaced within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Replacement snubbers and snubbers which have repairs which might affect the functional test shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom of motion test must have been performed within 12 months before being installed in the unit.
Condition D Potentially damaging transients are determined from a review of operational data and a visual inspection of the systems.
(continued)
SUSQUEHANNA - UNIT I TRM / B 3.7-25 EFFECTIVE DATE 12/03/2004
Snubbers PPL Rev. 1 B 3.7.8 BASES (continued)
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the snubbers are maintained OPERABLE. Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
TRS 3.7.8.1 The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Generic Letter 90-09 provides a method for determining the next interval for the visual inspection of snubbers based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval.
The visual inspeci eval for a snubber population shall be determned based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 3.7.8-1. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 3.7.8-1.
(continued)
SUSQUEHANNA - UNIT 1 B 3.7-26 EFFECTIVE DATE 08/31/1998
Snubbers B 3.7.8 PPL Rev. 1 B 3.7.8 Snubbers BASES TRS (continued)
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible, and are inspected on that basis.
The snubber population, for the purpose of visual inspection, is determined either separately or jointly for accessible and inaccessible units. The results of snubber examinations are judged, per Table 3.7.8-2, in accordance with that population. The decision whether to combine the category populations or keep them separate must be documented before any inspection, and that decision shall be used as the basis upon which to determine the subsequent inspection interval for that category.
The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.,., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
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v-Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component, and to the snubber anchorage are functional.
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SUSQUEHANNA - UNIT 1 B 3.7-27 EFFECTIVE DATE 08/31/1998
Snubbers B 3.7.8 PPL Rev. 1 B 3.1.8 Snubbers i
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BASES TRS (continued)
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per TRS 3.7.8.2. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
TRS 3.7.8.2 A representative sample of snubbers shall be tested for each type of snubber. The representative sample selected for the functional test sample plans shall be randomly selected-from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity oF sncuboers ot each type.
Functional Test Acceptance Criteria
/
The snubber functional test shall verify that:
- 1) Activation (restraining action) is achieved within the specified range in both tension and compression;
- 2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; (continued)
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SUSQUEHANNA - UNIT B
B 3.7-28
Snubbers PPL Rey. 1 B 3.7.8 B3.7.8 Snu bebrers BASES TRS
- 3) Where required, the force required to initiate or maintain motion of the (continued) snubber is within the specified range in both directions of travel; and
- 4)
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
TRS 3.7.8.3 The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with FSR17.2.17.
The, service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.); The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
(continued)
SUSQUEHANNA - UNIT 1 B 3.7-29 EFFECTIVE DATE 08/31/1998 i
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TRS 3.7.8.5 The required inspection consists of the following elements:
- 1. Perform a visual inspection of all affected snubbers.
- 2.
Verify freedom of motion of mechanical snubbers by manually induced snubber movement, or
- 3.
Verify freedom of motion of mechanical snubbers by evaluation of in-place snubber piston setting, or Verify freedom of motion of mechanical snubbers by stroking the mechanical snubber through its full range of travel.
REFERENCES
- 1. Generic Letter 90-09 r
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SUSQUEHANNA - UNIT 1 B 3.7-30 EFFECTIVE DATE 08/31/1998 I
Control Structure HVAC PPL Rev. 1 B 3.7.9
-B 3.7.9 ~Control Structure HVAC BASES TRO Control structure HVAC systems have safety related functions to maintain the required air pressure control in the building and maintain the heating and cooling of support equipment required to mitigate a Loss of Coolant Accident. The Control Structure and Computer Room ventilation fans are required to maintain the habitability envelope at a positive pressure (i.e.,
>0" wc) and also to perform a heating and/or cooling function. The operation and surveillance requirements of the ventilation fans to maintain the habitability envelope at a positive pressure during CREOAS operation are discussed in TS 3.7.3. The heating and/or cooling function is addressed in this TRO. At least one train of each system is required for these purposes Technical Specification LCOs 3.7.3 and 3.7.4 address operating and surveillance requirements for the Control Room Emergency Outside Air Supply System and the Control Room Floor Cooling System.
The SGTS Room Cooling and Heating systems are essential to maintain the normal and post accident environment of the Control Structure Elevation 806 within acceptable design temperature limits. CREOASS, SGTS, and Control Structure Chilled Water equipment is located on Control XX tructr Eevation 86 The Computer Room Floor Cooling System's function is to maintain the computer room environment within acceptable design temperature limits.
The system also maintains the habitability envelope pressure within limits.
The Computer Room Floor Cooling System consists of two independent, redundant -subsystems that provide cooling of recirculated computer room air. Each subsystem consists of cooling coils, fans, chillers, compressors, ductwork, dampers and instrumentation and controls to provide computer room temperature control.
The Control Structure Heating and Ventilation System serves all elevations of the control structure except the control room, TSC, and elevation 697'.
The system's function is to maintain temperature and habitability envelope pressure within acceptable limits. The Control Structure Heating and Ventilation System consists of two independent, redundant subsystems that provide SUSQUEHANNA - UNIT 1 TRM I B 3.7-31 EFFECTIVE DATE 12/03/2004
Control Structure HVAC B 3.7.9 PPL Rey. 1
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3.7.9 Contrlf Structure HVAC BASES TRO (continued) cooling of recirculated control structure air. Each subsystem consists of cooling coils, fans, chillers, compressors, ductwork, dampers and instrumentation and controls to provide temperature control.
The Control Structure Chilled Water System functions to transfer heat from the Control Room Floor Cooling System, Computer Room Floor Cooling System, Control Structure Heating and Ventilation System, and the Unit I ESGRC units to the ESW system. The Control Structure Chilled Water System consists of two independent, redundant subsystems consisting of a centrifugal compressor, a chilled water pump, one emergency condenser water pump, cooling coils, closed expansion tank, air separator, interconnecting piping, valves and instrumentation and controls.
The Battery Room Exhaust System functions to maintain the battery room design temperature, design pressure, and hydrogen concentration within limits. The Battery Room Exhaust System consists of two independent, redundant subsystems consisting of fans, ductwork, dampers and instrumentation and controls.
- 3Vi.?
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ACTIONS The Actions are defined to ensure proper corrective measures are taken in rn compo nents. With one of the HVAC subsystems inoperable, the inoperable HVAC subsystem must be restored to OPERABLE status within 30 days. With the unit in this condition, the remaining OPERABLE HVAC subsystem is adequate to perform the cooling and/or heating function. However, the overall reliability is reduced because a -single failure in the OPERABLE subsystem results in the loss of the HVAC function. The 30 day Completion Time is based on the consideration that the remaining subsystem can provide the required protection, and the availability of alternate nonsafety cooling methods.
TRS The TRS assures sufficient system functionality to ensure operation when called upon to perform its safety related function.
REFERENCES
- 1. FSAR Section 9.4.1
- 2.
FSAR Section 9.2.12.1
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SUSQUEHANNA - UNIT 1 TRM / B 3.7-32 EFFECTIVE DATE 03/09/2001
Spent Fuel Storage Pools B 3.7.10 PPL Rey. I Iy -
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B 3.7.1 Spent Fuel Storage Pools BASES TRO The design and licensing basis of SSES assumes that the Unit 1 and Unit 2 Spent Fuel Storage Pools (SFSP) are cross-connected through the Cask Storage Pit. This allows either Unit's Fuel Pool Cooling system and RHR Fuel Pool Cooling subsystem to provide cooling to the spent fuel stored in both units SFSP. In addition, cross-connected SFSP's allow make up water to be added to either unit's SFSP. If the SFSP are not cross-connected through the Cask Storage Pit, certain conditions must be maintained to assure the fuel pools remain within analyzed conditions. This TRO defines the required conditions and the actions required should the conditions not be met The conditions applicable to SFSP's that are not cross-connected are:
- a. The Unit 1 SFSP water temperature is less than or equal to 1 150F. The I Fuel Pool Cooling system analyses assume the fuel pool temperature is less than orequal to I150F. Normally, the Fuel Pool Cooling system is<<r used to maintain the fuel pool temperature less than or equal to 1 150F.
- b. Both subsystems of the ESW system must have at least one pump and the respective flow path to the SFSP to be considered OPERABLE for the ESW system fuel pool supply function. The ESW system provides the only safety-related source of make-up water to the SFSP.
- c. The RHR Fuel Pool Cooling subsystem provides a safety-related source of cooling to the SFSP. The RHR Fuel Pool Cooling subsystem is considered OPERABLE when one of the pumps, one of the heat exchangers, associated piping, valves, instrumentation and controls are OPERABLE. Note that this cannot be the same set of equipment (pump, heat exchanger, piping, valves etc.) credited for an OPERABLE RHR Suppression Pool Cooling subsystem.
(continued)
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SUSQUEHANNA - UNIT 1 TRM / B 3.7-33 EFFECTIVE DATE 04/15/2003
Spent Fuel Storage Pools B 3.7.10 PPL Rev. 1 B 3.7.10 Spent Fuel Storage Pools BASES TRO (continued)
- d. RHR must have one subsystem of Suppression Pool Cooling OPERABLE. One subsystem of RHR Suppression Pool Cooling is considered OPERABLE when one of the pumps, one of the heat exchangers, associated piping, valves, instrumentation and controls are OPERABLE. Note that this cannot be the same set of equipment (pumps, heat exchanger, piping, valves etc.) credited for an OPERABLE RHR Fuel Pool Cooling subsystem. A subsystem of RHR Suppression Pool Cooling is required to be available post accident to provide cooling for the reactor vessel while RHR Fuel Pool Cooling is providing cooling to the fuel pool.
- e. Zone I is capable of being aligned to the Recirculation Plenum.
Alignment of the Unit 1 Reactor Building to the recirculation plenum is assumed in the analyses. This assures adequate distribution of the
'refueling floor environment should the fuel pool temperature exceed 1 150F.
APPLICABILITY The APPLICABILITY is modified to permit isolating SFSPs from the cask storage pit when theanalyzed nominal decay heat in one SFSP is < 5.1 x 106 Btu/hr, concurrent with a nominal decay heat of < 4.0 x 106 Btu/hr in the other SFSP. For example, if the Unit 1 SFSP analyzed nominal decay heat is 4.5 X106 Btu/hr, then the Unit 2 SFSP analyzed nominal decay heat must be < 4.0 x 106 Btu/hr in order for the SFSPs to not be cross-connected through the cask storage pit. The manner in which this value is determined is specified in Reference 1, and is consistent with the SSES design and licensing basis. With a SFSP nominal decay heat less than this value, sufficient time will exist to implement the actions required to cross-connect the SFSPs and prevent boiling in the event of a Design Basis Loss of SFP Cooling event. This also ensures compliance with licensing bases requirements regarding the evaluation of this event prior to isolating the SFSPs.
I (continued)
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SUSQUEHANNA - UNIT 1 TRM / B 3.7-34 EFFECTIVE DATE 12/03/2004
Spent Fuel Storage Pools B 3.7.10 PPL Rev. I 3.7.10 spent Fuel storage Pools BASES (continued)
ACTIONS The listed ACTIONS ensure that should the required conditions not be maintained, the required conditions be restored in sufficient time to preclude fuel pool boiling and to minimize the impact of a fuel pool with water temperatures greater than 11 50F.
The completion time for Condition A of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is a reasonable time to restore adequate cooling to the SFSP and restore the fuel pool temperature less than or equal to the 115OF limit. This 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> completion time takes into account the low probability of an event occurring during this period that could prevent reestablishing adequate fuel pool cooling.
The completion times specified for the Conditions B, C, D, and E account for the low probability of an event occurring during the period that could cause the loss of adequate fuel pool cooling. The completion time for Condition B is more restrictive since ESW is required to raise fuel pool level so that cooling systems can be operated.
Action F is required to be taken to cross-connect the SFSP's so that a
m7.
cooling can be provided should an event result in loss of fuel pool cooling.
TRS The TRS's are defined to be performed at the specified frequency to ensure that the required conditions are maintained while the SFSP's are not cross-connected.
REFERENCES
- 1. Safety Evaluation NL-00-029
- 2. FSAR Section 9.1.3
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PPL Rey. 1 Dose Rate B 3.11.2.1
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-r-BASES TRO This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public either within or outside the Site Boundary, in excess of the design objectives of Appendix I to 10 CFR 50. It provides operational flexibility for releasing gaseous effluents while satisfying section lI.B and ll.C design objectives of Appendix I. For individuals who may at times be within the Site Boundary, the occupancy of the individual will usually be sufficiently low to compensate for any increase in atmospheric diffusion factor above that for the Site Boundary. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mremlyr to the total body or to less than or equal to 3000 mremlyr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an individual via the inhalation pathway to less than or equal to 1500 mrem/yr. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20. (Reference 3)
-This Requirement applies to the release of gaseous effluents from all reactors at the site.
This section of the TRM is also part of the ODCM (Reference 2).
(continued)
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= I SUSQUEHANNA - UNIT 1 TRM I B3.11-12 EFFECTIVE DATE 2/01/99
Dose Rate PPL Rev. 1 B 3.11.2.1 B 3.11.2.1 Dose Rate BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the limits being exceeded.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the dose rates are maintained within limits. Dose rates are determined in accordance with the methodology and parameters of the ODCM.
Table 3.11.2.1-1 defines Radioactive Gaseous Waste Sampling A Analysis Program. The lower limit of detection (LLD) is defined, for purposes of these requirement, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation:
LLD =
E
- V
- 2.22E6
- Y
- exp(-XAt)
Where:
LLD is the a priori lower limit of detection as defined above (as microcunes per unit mass or volume),
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency, as counts per disintegration, V is the sample size, in units of mass or volume, 2.22 E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
(continued)
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SUSQUEHANNA - UNIT 1 TRM/83-11-13 EFFECTIVE DATE 2/01/99
Dose Rate PPLRev. I B 3.11.2.1 B 3.11.2.1 Dose Rate BASES TRS The value of Sb used in the calculation of the LLD for a detection system (continued) shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and At shall be used in the calculation.
The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-1 35, Xe-135m and Xe-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks which are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.
The design of the systems for the sampling of particulates and iodines provide for sample nozzle entry velocities which are approximately isokinetic with instack air velocities. Gaseous particulate and iodine
-samrip~les are gathered continuousy, wif5I tne sa e size proportonal to the stack emissions; a composite gaseous sample is a combination of all the particulate filters gathered in a sampling period.
Particulate or iodine sampling required to be in continuous service will be considered to remain and have been in continuous service when its service is interrupted for a time period not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per sampling period.
For particulate and iodine sampling, this is a small fraction of the normal minimum analysis frequency.
The minimum Analysis Frequency as listed for the Composite Samples shall mean the minimum frequency for initiation of the required analyses, not completion of the analysis and evaluation of the results. Since the analysis involves sending the samples to an offsite laboratory and performance of involved sample preparation and wet chemical analyses, there will be a delay between initiation of the analysis and receipt of the results. The analysis initiation shall normally be done on-a calendar quarter for a 92 day frequency.
(continued)
SUSQUEHANNA - UNIT 1 TRM /B 3.11-14 EFFECTIVE DATE 12/03/2004
Dose Rate PPL Rev. 1 B 3.11.2.1 I - I I -
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REFERENCES 1.
2.
3.
Technical Specification 5.5.4 - Radioactive Effluent Controls Program Technical Specification 5.5.1 - Offsite Dose Calculation Manual 10 CFR Part 20 I4 01*0 1
SUSQUEHANNA - UNIT 1 TRM I B 3.1 1-15 EFFECTIVE DATE 2/01/99
Monitoring Program PPL Ray.
B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES TRO The radiological environmental monitoring program required by this Requirement provides representative measurements of radiation and of radioactive materials in those environmental exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Changes to the radiological environmental monitoring program specified in Table 3.11.4.1-1 may be made based on expected SSES operation and the results of radiological environmental monitoring during SSES operation.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 3.11.4.1-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit
_preenting the ap-abilIty of a measurement system and not as an a
'~posteroi (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually); Currie, L. A.,
"Limits for Qualitative Detection and Quantitative Determination -
Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968); and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques,"
Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
(Reference 1)
This section of the TRM is also part of the ODCM (Reference 2).
ACTIONS The Actions are defined to ensure proper corrective measures are taken when requirements are not met.
(continued)
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Monitoring Program PPL Rev. I B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES ACTIONS Per Action A.1, the Annual Radiological Environmental Operating Report (continued) shall provide a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
The Special Report submitted per Action B. 1 shall identify the cause(s) for exceeding the limit(s) and define the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Requirements 3.11.1.2, 3.11.2.2 and 3.11.2.3.
Include revised figure(s) and table for the ODCM reflecting the new locations for obtaining samples per Action F. I in the next Radioactive Effluent Release Report.
TRS The TRSs are defined to be performed at the specified frequency to ensure that the requirements are implemented. Monitoring samples collected per TRS 3.11.4.1.1 shall be from the specific locations given in the table and fiuein the ODCM. (Referene;2)
Table 3.11.4.1-1 Sample Locations Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in this Table and in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (Reference 3) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling (continued)
SUSQUEHANNA - UNIT I TRM / B 3.11-29 EFFECTIVE DATE 12103/2004
Monitoring Program PPLRev. 1 B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES TRS period. All deviations from the sampling schedule shall be documented in (continued) the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.
Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).
Direct Radiation One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. r badges shall not be used as dosimeters for mesring direct radiatioan.
Radioiodine and Particulates - Sampling and Collection Frequency The charcoal cartridges used in the airborne radioiodine sampling conducted as part of the radiological environmental monitoring program are designed and tested by the manufacturer to assure a high efficiency in the capture of radioiodine. Certificates from the manufacturer of the cartridges are provided with each batch of cartridges certifying the percent retention of the radiodine for stated air flows.
Radioiodine and Particulates - Particulate Sample: Waterbome -Surface.
Ground, Sediment: Food Products Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
Waterbome - Surface The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in the discharge line.
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Monitoring Program B 3.11.4.1 PPL Rev. 1 B 3.11.4.1 Monitoring Program BASES TRS (continued)
Waterbome - Drinking - Sampling and Collection Frequency A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite samples shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
Waterborne - Ground - Samples and Sample Locations Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
Drinking Water-1-131 Analyses Calculation of the dose projected from I-131 in drinking water to determine if 1-131 analyses of the water are required shall be performed for the maximum organ and age group using the methodology and parameters of
'the ODC"M.'
Food Products - Sampling and Collection Frequency If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly.
Attention shall be paid to including samples of tuborous and root food products.
Table 3.11.4.1-3 This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable at 95% confidence level together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating report.
Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
(Reference 4)
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SUSQUEHANNA - UNIT I B 3.1 1-31 EFFECTIVE DATE 08/30/98
Monitoring Program B 3.11.4.1 PPL Rev. 1 BA3.1.4.1 Monitoring Program BASES TRS (continued)
The LLD is defined, for purpose of these Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD = E
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- exp(-2At)
Where:
LLD is the a priori lower limit of detection as defined above (as picrocuries per unit mass or volume),
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- countingrate-of a bank sa'mple as appropriate (as counts per minute),
E is the counting efficiency, as counts per disintegration, V is the sample size, in units of mass or volume, 2.22 is the number of disintegrations per minute per picrocurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
Typical values of E, V, Y, and At should be used in the calculation.
(continued)
SUSQUEHANNA - UNIT 1 B 3.11-32 EFFECTIVE DATE 08130/98
Monitoring Program B 3.11.4.1 PPL ReY. 1
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B 3.11.4.1 Monitoring Program BASES TRS (continued)
It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posterori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDS unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
REFERENCES
- 1. HASL Procedures Manual, HASL-300 (revised annually); Curie, L.A.,
"Limits for Qualitative Detection and Quantitative Determination -
Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968); and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975) Offsite Dose Calculation Manual.
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- 3.
NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.
- 4.
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SUSQUEHANNA - UNIT I B 3.11-33 EFFECTIVE DATE 08/30/98