ML21361A215
ML21361A215 | |
Person / Time | |
---|---|
Site: | Perry ![]() |
Issue date: | 12/20/2021 |
From: | Energy Harbor Nuclear Corp |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML21361A235 | List:
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References | |
L-21-287 | |
Download: ML21361A215 (27) | |
Text
MA S TE RTA B LE OF C ON TE N TS Section Titl-e Page 1.0 I N T R O D U C T I O NA N D G 1. O-1 1.1 TNTRODUCTTON 1 ' 1-1 t.2 GENERAL PLANT DESCRIPTION t .2-r t.2.1, PRINCIPAL DESIGN CRITERIA L.2-1, r.2.2 PLANT DESCRIPTION L.2-L4 r.2.3 SYMBOLS USED IN ENGINEERING DRAWINGS L.2-45 1.3 t a a COMPARISON TABLES t_.3.1 COMPARISONSWITH SIMILAR FACILITY DESIGNS 1.3-1 L.3.2 COMPARISON OF FINAL AND PRELIMINARY TNFORMATION L . 5-/"
L.4 IDENTIFICATION OF AGENTS AND CONTRACTORS L.4-r 1.4.1 THE CLEVELAND ELECTRIC ILLUM]NATING COMPANY OWNER L .4-1' r.4.2 GTLBERT ASSOCTATES, rNC. - ARCHTTECT/ENCrNnsn 1.4-2 1d ? GENERAL ELECTRIC COMPANY NUCLEAR STEAM SUPPLY SYSTEM \.4-3 1.4 .4 R A Y M O N DK A T S E R E N G T N E E R S , r N C . L.4-4 14tr, GENERAL ELECTRIC COMPANY TURBINE GENERATOR VENDOR 1..4-4 r.4.6 NUS CORPORATION ENVIRONMENTAL CONSULTANT 1.4.5 L.4 .7 OTHER CONSULTANTS 1".4-6 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1 1.5.1 CURRENT DEVELOPMENT PROGRAMS 1.5-1 REFERENCE MATERIALS L.6-L I.1 DRAWINGS AND OTHER DETAILED INFORMATION L.7.7 Revi-sion 13 Decemberr 2003
MASTER TABLE OF CONTENTS (CONtiNUCd)
Section Title Paqe I.7 .L ELECTRICAL, INSTRUMENTATION/ AND CONTROL DRAWINGS 7 .1-1, 7.7 .2 PIPING AND INSTRUMENTATION DIAGRAMS I.7 -L 1.7.3 OTHER DETAILED INFORMATION L.7 -7 1.8 NRC REGULATORY GUIDE ASSESSMENT t _ .B - 1 1.9 STANDARD DESIGNS 1.9-1 t_.10 EV AL U AT ION OF U N IT ]- OP E R A TTON SR E S U LTIN G F R O MU N I T 2 C O N S T R U C T I O A NC T I V I T I E S 1 . 1_0-1_
APPENDIX 1A N U R EG-O7 37
- TMr A C TTON P LA N R E QU TR E ME N TS FOR A PP L IC A N T S FOR N E W OP E R A TIN GLIC E N S E S "
i n t'\YE. IA TAB APPENDIX ]-B PNPP LICENSE COMMITMENTS APP. 18 TAB 1.V SITE CHARACTERISTIffi 2.0-r 2.t GEOGRAPHY AND DEMOGRAPHY 2.L-7
^ 1 1 Z.I.I S I T E L O C A T I O NA N D D E S C R I P T I O N 2.L-L 2.L.2 E XC L U S IO N A R E A A U TH OR ITY A N D C ON TR OL z. L-5 2.r.3 P O P U L A T I O ND I S T R I B U T I O N 2.r-5 2.
1.4 REFERENCES
FOR SECTION 2.I 2.1-1"r z.z NEARBY INDUSTRIAL, TRANSPORTATION AND MILITARY FACILITIES 2.2-L 2.2.1, L O C AT ]ON SA N D R OU TE S z.z-r 2.
2.2 DESCRIPTION
S 2.2-4 2.2.3 E VA L U A T IO N OF P OTE N TIA L A C C ID E N TS 2.2-27 2 .2.4 REFERENCEF SO R S E C T I O N2 . 2 2.2-39 2.3 METEOROLOGY 2 .3-L Revision 14 l_1 October,2005
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section '1'rcl-e Page 2.3.7 REGIONAL CLIMATOLOGY 2.3-1, 2.3.2 LOCAL METEOROLOGY 2.3-L7 2.3.3 ONSITE METEOROLOGICALMEASUREMENTPROGRAM 2 .3 2.3.4 S H O R TT E R M ( A C C I D E N T ) D I F F U S I O N E S T I M A T E S 2.3-40 L O N G T E R M ( R O U T I N ER E L E A S E ) D I F F U S I O N E S T I M A T E S 2 . 3 - 4 3 2.
3.6 REFERENCES
FOR SECTION 2.3 2.3-41 2.4 H Y D R O L OGICE N GIN E E R IN G 2.4-L 2.4.1 HYDROLOGIC DESCRIPTION 2.4-1, z.+.2 FLOODS 2.4-4 2.4.3 PROBABLE MAXIMUM FLOOD ( PMF) ON STREAMS AND RIVERS 2.4-1 2.4.4 POTENTIAL DAM FAILURES, SEISMICALLY INDUCED 2. 4 - r r 2.4 .5 PROBABLE MAXIMUM SURGE FLOODING 2.4-1-2 2.4.6 PROBABLE MAXIMUM TSUNAMI FLOODING 2.4-45 2.4.7 ICE EFFECTS 2.4-45 2.4 .B COOLING WATER TUNNELS AND OFFSHORE STRUCTURES 2.4-41 2.4.9 CHANNEL DIVERSIONS 2.4-50 2.4.r0 FLOODING PROTECTION REQUIREMENTS 2.4-50 2.4.IL LOW WATER CONSIDERATTONS 2.4-5L 2.4.L2 DISPERSION, DILUTION, AND TRAVEL TIMES OF ACCIDENTAL RELEASES OF RADIOACTIVE EFFLUENTS IN LAKE ERIE 2.4-62 2.4.1,3 GROUNDWATER 2.4-65 2.4.14 TECHNICAL SPECIFICATION AND EMERGENCY 1 1 -
OPERATION REQUIREMENTS 2.4-LLt Revision 12 1a l_ January l 2403
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section Title Page 2.4 .L5 LIST OF PERSONSAND AGENCIES INTERVIEWED 2.4-L11 2.4.L6 REFERENCES FOR SECTION 2.4 2 .4-120 2.5 GEOLOGY, SEISMOLOGY AND GEOTECHNICAL ENGINEERING 2.5-r 2.5.7 BASIC GEOLOGIC AND SEISMIC INFORMATION 2.5-7 2.5.2 V]BRATORY GROUND MOTION 2 .5-LL1 2.5.3 SURFACE FAULTING 2.5-161 2.5.4 STABILITY OF SUBSURFACE MATERIALS AND FOUNDATIONS 2.5-181 2.5.5 STABILITY OF SLOPES 2.5-265 2.5.6 EMBANKMENTS AND DAMS 2 .5-21 0 2.
5.7 REFERENCES
FOR SECTION 2.5 2 .5-2-10 APPENDIX 2A ANNUAL JOINT FREQUENCY DISTRIBUTIONS FOR CLEVELAND AND ERIE APP. 2A TAB A P P E N D I X2 9 MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS FOR PNPP, lO-M WINDS APP. 2B TAB A P P E N D I X2 C MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS FOR PNPP, 6O-M WINDS
^ a AEE. /.V TAB APPENDIX 2D BEDROCK DEFORMATION IN THE COOLING WATER TUNNEL A P P . 2D TAB A P P E N D ] X2 E SOIL AND ROCK BORINGS A P P . 2E TAB DESIGN OF STRUCTUR AN D SY ST E MS 3.1-1 3.1 C O N F O R M A N C EW I T H N R C G E N E R A L D E S I G N C R I T E R I A 3.l_-1 Revi-sion t2 l_v January l 2043
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section '.t-'t_
t l- e Page 3.1.1 S U MMA R YD E S C R ]P TION 3. 1_-1 3.L.2 CRITERION CONFORMANCE 3.L-2 3.t C L A S S I F I C A T I O N O F S T R U C T U R E SC O M P O N E N T S A N D S YS T EMS 3.2-t 3.2.1, SEISMIC CLASSIFICATION 3.2-1, 3.2.2 SYSTEM QUALITY GROUP CLASSIFICATIONS 3.2-3 3.2.3 SYSTEM SAFETY CLASSIFICATIONS 3.2-3 3.2.4 QUALITY ASSURANCE 3.2-9 3.2.s CORRELATION OF SAFETY CLASSES WITH INDUSTRY U\JLJT-J 3.2-10 3.3 WIND AND TORNADOLOADS 3.3-1 WIND LOADINGS 3.3-1 3.3.2 TORNADO LOADINGS 3.3-3 3.
3.3 REFERENCES
FOR SECTION 3.3 3.3-1
?A WATER LEVEL (FLOOD) DESIGN 3.4-1 3.4.L FLOOD PROTECTION 3.4-L 3.4.2 ANALYTICAL AND TEST PROCEDURES 3.4-3 3.4.3 FLOOD FORCE APPLICATION 3.4-4 3.5 MISSILE PROTECTION 3.5-1 3.5.1 MISSILE SELECTION AND DESCRIPTION 3.5-1 3.5.2 S T R U C T U R E S , S Y S T E M S A N D C O M P O N E N T ST O B E PROTECTED FROM EXTERNALLY GENERATED MISSILES 3.5-19 3.5.3 BARRIER DESIGN PROCEDURES 3.5-20 3.
5.4 REFERENCES
FOR SECTION 3.5 3.5-22 Revision L2 January,2003
MASTER TABLE OF CONTENTS (CONI1NUEd)
Section m.i f'l ^
Page 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3. 6-1 3.6.1 POSTULATED PIPING FAILURES IN FLUID SYSTEMS 3. 5-1 3.6.2 DETERMINATION OF BREAK LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3. 6-9 3.
6.3 REFERENCES
FOR SECTION 3.5 3. 6-83 SEISMIC DESIGN 3.7-r_
3.7.1 SEISMIC INPUT 3.7-1 3.1 .2 SEISMIC SYSTEM ANALYSIS 3 .1-5
<l SEISMIC SUBSYSTEMANALYSIS 3 .1-25 3.1 .4 SEISMIC INSTRUMENTATION 3 . ' 7- 4 4 3.
7.5 REFERENCES
FOR SECTION 3.1 3.7-53 3.8 DESIGN OF CATEGORY I STRUCTURES 3.8-1 3.8.0 GENERAL DESCRIPTION 3. B-1 3.8.1 CONCRETE CONTAINMENT 3.8.4 3.8.2 STEEL CONTAINMENT 3.8-95 3.8.3 INTERNAL CONCRETE AND STEEL STRUCTURES 3.8-1,47 3.8.4 OTHER SEISMIC CATEGORY I STRUCTURES 3. B-199 3.8.5 FOUNDATIONS AND CONCRETE SUPPORTS 3 .8-213 3.
8.6 REFERENCES
FOR SECTION 3.8 3.8-291 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3. 9-1 3.9.1 SPECIAL TOPICS FOR MECHANICAL COMPONENTS 3.9-1_
3.9.2 DYNAMIC TESTING AND ANALYSIS 3.9-50 R evi -si on 1'2 vl_ January, 2A03
MASTER TABLE OF CONTENTS (CONtiNUCd)
Section Titl-e Page 3.9.3 ASME CODE CLASS L, 2, AND 3 COMPONENTS/
COMPONENTSUPPORTS AND CORE SUPPORT STRUCTURES 3. 9-99 3.9.4 CONTROL ROD DRIVE SYSTEM 3.9-148 3.9.s REACTOR PRESSURE VESSEL INTERNALS 3. 9-151
^ n 1 - A 3.9.6 INSERVICE TESTING OF PUMPS AND VALVES J.Y-IlU 3.9.7 R E F E R E N C E SF O R S E C T I O N 3 . 9 3.9-170 3.10 SEISMIC AND DYNAMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.1_0 ? 1n 1 SEISMIC AND DYNAMIC QUALIFICAITON CRITERIA 3.10-3 3.L0.2 METHODS AND PROCEDURES FOR SEISMIC AND DYNAMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT J. IU-Y
< ttl METHODS AND PROCEDURES FOR SE]SMIC AND DYNAMIC QUALIFICATION OF SUPPORTS OF MECHANICAL AND ELECTRICAL EQUIPMENT 3.10-17 3.10.4 SEISMIC AND DYNAMIC QUATIFICATION RESULTS 3. r0-22 3.10.5 R E F E R E N C E SF O R S E C T I O N 3 . 1 0 3.10-23 3.11 ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT 3 . 11-l_
3.11.1 EQUIPMENT IDENTIFICATION AND ENVIRONMENTAL CONDITIONS 3.11-1 3 . 1 , L. 2 ENVIRONMENTAL QUALIFICATION PROGRAM ACCEPTANCE CRITERIA 3.11_-6 3.11.3 QUALIFICATION TESTS RESULTS 3.11-33 3.11.4 LOSS OF VENTILATION 3.1_1-36 3.11.5 ESTIMATED CHEMICAL AND RADIATION ENVIRONMENT 3.11-40 3.
11.6 REFERENCES
FOR SECTION 3. ]-1 J.II-4J Revi-sion L2 v1l_ January, 2003
MA ST E RTA B LE OF C ON TE N TS (C onti nued)
Section Title Page APPENDIX 3A HYDRODYNAMIC LOADS FOR PNPP
- n AYE. JA TAB APPENDIX 38 CONTAINMENT LOADS APP. 38 TAB 4.U BEASIAB 4.I
SUMMARY
DESCRIPTION 4.L-L 4 .L.1, REACTOR VESSEL 4.L-T 4.L.2 REACTOR INTERNAL COMPONENTS 4 . L-1, REACTIVITY CONTROL SYSTEMS 4.1-B 4.1,.4 ANALYSIS TECHNIQUES 4.r-9 i 1 1A 4.1.5 R E F E R E N C E SF O R S E C T I O N 4 . L q. r-r4I
+.2 FUEL SYSTEM DESIGN 4.2-L 4.2.1 GE N E R A LAN D D E TA ILE D D E S IGN B A S E S 4.2-t 4.2.2 D E S C R I P T I O NA N D D E S I G N D R A W I N G S 4.2-7 4.2.3 D ES IG N E VA LU A TION S 4.2-5 4 .2.4 T E S T I N G , I N S P E C T I O NA N D S U R V E I L L A N C EP L A N S 4.2-6 4.2.5 O P ER AT IN GA N D D E V E LOP ME N TAE L X P E R IE N C E 4.2-6 4 .2.6 REFERENCEF SO R S E C T I O N 4 . 2 4.2-6 4.3 N U C L E A RD E S I G N 4.3-1 4.3.r DESIGN BASES 4. 3 - r A '2.-1 4.
3.2 DESCRIPTION
4.3.3 ANALYTICAL METHODS 4.5-LZ 4.3.4 CHANGES 4 .3-!2 4.
3.5 REFERENCES
FOR SECTION 4.3 4.3-13 Revision L2 vt_ l- .]- January, 2003
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section Titl-e Page 4.4 T H ER M ALA ND H Y D R A U LIC D E S IGN 4 .4-L 4.4.L DESIGN BASIS 4. 4 - r 4.4.2 D E S C R I P T I O N O F THERMAL.HYDRAULIC DESIGN OF THE REACTOR CORE 4.4.3 D E S C R I P T I O N O F THE THERMAL AND H Y D R A U LIC D E S I G N O F T H E REACTOR COOLANT S Y S T E M 4.4-4 4.4.4 EVALUAT ION 4. 4 - r 0 4.4.5 TESTING AND VERIFICATION 4. 4 - 1 r 4.4.6 INSTRUMENTAT ION REQUI REMENTS 4. 4 - r 2 4 q-l
/q.
REACTOR MATERIALS A q 1 CONTROLROD DRIVE SYSTEM STRUCTURALMATERIALS 4.5-1 4.5.2 REACTOR INTERNAL MATERIALS 4.5-8 4.5.3 CONTROL ROD DRIVE HOUSING SUPPORTS 4.5-L4 t ^4. REFERENCES FOR SECTION 4.5 4.5-15 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROLSYSTEMS 4.6.1 4.6.L INFORMATION FOR CRDS 4 .5-L 4 .6.2 EVALUATIONS OF THE CRDS 4 .6-25 4 .6.3 TESTING AND VERIFICATION OF THE CRDS 4 .6-43 4.6.4 INFORMATION FOR COMBINED PERFORMANCE OF REACTIVITY CONTROL SYSTEMS 4 . 6-50 4.6.5 EVALUATION OF COMBINED PERFORMANCE 4 . 6-51 4.6.6 R E F E R E N C E SF O R S E C T I O N 4 . 6 4 .6-6r REACTOR COOLANT SY 5.1-1 5.1
SUMMARY
DESCRIPTION 5.1-1_
R evi si -on 1,'l 1X October, 201,1"
MASTER TABLE OF CONTENTS (CONIiNUEd)
Section TitIe Page q11 J . l - . J - SCHEMATIC FLOW DIAGRAM 5.L-4 5.1.2 PIPING AND INSTRUMENTATION DIAGRAM 5.1-4
\ l ELEVATION DRAWINGS 5. 1-5 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE B O U N D A R Y 5 . 2 . I 5.2 .1, COMPLIANCE WITH CODES AND CODE CASES 5.2-1, 5.2.2 OVERPRESSURIZATION PROTECTION 5.2-4 5.2.3 REACTOR COOLANT PRESSURE BOUNDARY MATERIALS 5.2-25 INSERVICE EXAMINATION AND PRESSURE TESTING OF REACTOR COOLANT PRESSURE BOUNDARY 5.2-43 5.2.5 DETECTION OF LEAKAGE THROUGH REACTOR COOLANT PRESSURE BOUNDARY 5.2-53 5.
2.6 REFERENCES
FOR SECTION 5.2 5.2-19 q? REACTOR VESSEL 5. 3-1 q?1 REACTORVESSEL MATERIALS 5.3-1 5.3.2 PR ES SU R E - TE MP E R A TU R LIMTTS E 5.3-13 R EA C T ORVE S S E L IN TE GR ITY 5.3-16 5.3.4 REFERENCEF SO R S E C T I O N5 . 3 5.3-28 C,A C O M P O N E NATN D S U B S Y S T E MD E S I G N 5.4-1
\A1 REACTOR RECIRCULATION PUMPS 5.4-r q./a STEAM GENERATORS ( PWR) 5.4-B REACTOR COOLANT PIPING 5.4-B 5.4.4 MAIN STEAM LINE FLOW RESTRICTORS 5.4-B C-4tr.
MAIN STEAM LINE ISOLATION SYSTEM 5.4-11 5.4.6 REACTOR CORE ISOLATION COOLING SYSTEM 5.4-20 Revision L2 January, 2003
MASTER TABLE OF CONTENTS (CONtiNUCd)
Section Title Page 5.4.7 RESIDUAL HEAT REMOVALSYSTEM 5.4-39 5.4.8 REACTORWATER CLEANUP SYSTEM 5.4-55 5.4.9 M AIN ST E AM LIN E A N D FE E D W A TE RP IP IN G 5.4-60 q
J .
A
? . I V 1n P R E S S U RZI E R 5.4-62 tr- A J . A . I I 11 P R E S S U R I Z E RR E L I E F D I S C H A R G ES Y S T E M 5 .4-62 5.4.12 VALVES 5.4-62 5.4.13 SA F ET Y A N D R E LIE F V A LV E S 5.4-65 5.4 .14 C OMP O N EN T S U P P OR TS 5 .4-66 5.4 .15 REFERENCES FOR SECTION 5.4 5.4-68 6.0 EN G IN EE R E DS A FE TY 6.1-1 6.r EN G IN EE R E DS A FE TY FE A TU R EMA TE R IA LS 6.r--1 6.1.1 METALLIC MATERIALS 6,1-1 6.L.2 ORGANIC MATERIALS 6.L-7 6'1? R E F E R E N C E SF O R S E C T I O N 6 . 1 6.r-9 5.2 CONTAINMENT SYSTEMS 6. 2 - r 6.2.1_ CONTAINMENT FUNCTIONAL DESIGN 6 .2-L 6.2.2 CONTAINMENT HEAT REMOVAL SYSTEM 6.2-59 6.2.3 SECONDARY CONTAINMENT FUNCTIONAL DESIGN 6.2-7 0 6.2.4 CONTAINMENT ISOLATION SYSTEM 6.2-1 I a ^ a 1 ^
6.2.5 COMBUSTIBLE GAS CONTROL TN CONTAINMENT o.z-LLz 6.2.6 CONTAINMENT LEAKAGE TESTING 6.2-126 6.2.1 SUPPRESSION POOL MAKEUP SYSTEM 6.2-L32 6.2.8 HYDROGEN CONTROL SYSTEM 6.2-1,42 Revision 1,2 xt_ Januaryr 2003
MASTER TABLE OF CONTENTS (CONI1NUCd)
Section Titl-e Page 6.
2.9 REFERENCES
FOR SECTION 6.2 6.2-L50 6.3 EME R GE N C Y C OR E C OOLIN G S Y S TE M 6.3-1 b.J.t- DESIGN BASES AND
SUMMARY
DESCRIPTION 6.3-1 6.3.2 SYSTEM DESIGN 6.3-9 A?? PERFORMANCE EVALUAT ]ON 6.3-39 6.3.4 TESTS AND INSPECTIONS 6 .3-52 6.3.5 INSTRUMENTAT ION REQUI REMENTS 6.3-57 5.3.6 R E F E R E N C E SF O R S E C T I O N 6 . 3 6.3-58 6.4 HABITABILITY SYSTEMS 6.4-r 6 . 4. r DESIGN BASES 6.4-r 6.4 .2 SYSTEM DESIGN 6.4-4 6.4.3 SYSTEM OPERATIONAL PROCEDURES 6.4-L2 6.4.4 DESIGN EVALUATION 6.4-L4 6.4.5 TESTING AND INSPECTION 6.4-1,8 6.4 .6 I N S T R U M E N T A TI O N R E Q U I R E M E N T S 6 .4-1"9a 5.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5-1
- 6. 5. 1_ E N G I N E E R E DS A F E T Y F E A T U R E S( E S F ) F I L T E R S Y S T E M S 6 . 5 - 1 6.5.2 C O N T AIN M EN TS P R A Y S Y S TE M 6.5-9 6.5.3 FISSION PRODUCT CONTROL SYSTEMS 6.5-15 6.5.4 I C E C O N D E N S E RA S A F I S S I O N P R O D U C T CLEANUP SYSTEM 6 .5-24 6.5.5 R E F E R E N C E SF O R S E C T I O N 6 . 5 6.5-24 INSERVICE I N S P E C T I O N O F C L A S S 2 A N D 3 C O M P O N E N T6S .6_7 6.6 .1. C O MP O N EN TS S U B JE C T TO E X A MIN A TION 6.6-7 Revision L7 x11 October, 2011
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section m.i +-1^
I I L I C Page 6.6 .2 ACCESSIBILITY 6.6-L 6.6 .3 EXAMINATION TECHNIQUES AND PROCEDURES 6.6-1 6.5.4 INSPECTION INTERVALS 6.6-2 6.6.5 EXAMINATION CATEGORIES AND REQUIREMENTS 6.6-2 6.6.6 EVALUATION OF EXAMINATION RESULTS 6.6-2 6.6.1 SYSTEM PRESSURE TESTS 6. 6-3 5.6.8 AUGMENTED INSERVICE INSPECTION TO PROTECT AGAINST POSTULATED PIPING FAILURES 6 .6-3 6'7 MAIN STEAM LINE ISOLATION VALVE LEAKAGE CONTROL SYSTEM 6.1-1 6.8 SAFETY-RELATED INSTRUMENT AIR SYSTEM 6. B-1_
h x l DESIGN BASES 6.8-1_
6.8.2 SYSTEM DESIGN 6. B-1_
5.8.3 DESIGN EVALUATION 6. B-3 6.8.4 TESTS AND INSPECTIONS 6.8-4 6.8.5 I N S T R U M E N T A TI O N R E Q U I R E M E N T S 6.8-5 6.9 FEEDWATER LEAKAGE CONTROL SYSTEM 6 .9-L 5.9.1 DESIGN BASES 6.9-1, 6.9.2 SYSTEM DESCRIPTION 6.9-2 6.9.3 DESIGN EVALUATION 6.9-5 6.9.4 TESTS AND INSPECTIONS 6.9-6 6.'qq INSTRUMENTATION REQUIREMENTS 6.9-6 1.0 INSTRUMENTATION A 7. 7 - r
1.7 INTRODUCTION
7.1-r Revision L2 xl_ t_l_ January,2003
MASTER TABLE OF CONTENTS (CONTiNUCd)
Section Titl-e Page 1 .7.L I D E N T I F I C A T I O N O F S A F E T Y - R E L A T E DS Y S T E M S 7 .7-L 7 .1.2 IDENTIFICATION OF SAFETYCRITERIA 1.I-1 7.1.3 P L AN T PR O TE C T]ONS Y S TE M-E LE C TR ON IC TR IP SYSTEM 1 .1"-L1 1.2 REACTOR TRIP SYSTEM REACTOR PROTECTION SYSTEM (RPS) 1 .2-t
- 1. 2 . r DESCRI PTION
- 4 n t.z-L
- 1. 2 . 2 ANALYS I S 7 .2-22 1.3 ENGINEERED SAFETY FEATURE SYSTEMS ?.3-1 1 .3.L DESCRIPTION 7.3-1 t.5.2 ANALYS IS 7 . 3-68 1.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7 .4-I 1.4.r DESCRI PTION 1 .4-1,
'1 " 7. 4 - 2 7 A) ANALYSIS 1tr SAFETY-RELATED DISPLAY INSTRUMENTATTON 7.5-1 DESCRIPTION 7.5-1 1 .5.2 ANALYS I S 7.5-1_1 1.6 ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 7 .6-1, 1.6.1, DESCRIPTION 7.6-I 7.6.2 ANALYS IS 1 .6-48 1.1 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 1 .1-L 7.7.I DESCRIPTION 1 .1-1, 1.1.2 ANALYS I S 7.7-50 an ELECTRIC POWER 8.1-1 Revision L2 XI-V January, 2043
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
't_'r_ Page Section t l- e B.l_ INTRODUCTION 8.1-1
- 8. 1.1 SAFETY LOADS B.T-2 d.L.z R E F E R E N C E SF O R S E C T I O N 8 . 1 8.1-3 8.2 OFFSITE POWERSYSTEM 8.2-t o.z.t n 4 1 DESCRIPTION I .2-1 d.z.z ANALY S I S 8.2-6 8.3 ONSITE POWERSYSTEMS 8.3-1 R?1 AC POWER SYSTEMS 8.3-1 8.3.2 DC POWER SYSTEMS U . J-YU 8.3.3 FIRE PROTECTION FOR CABLE SYSTEMS 8.3-100 8.3.4 R E F E R E N C E SF O R S E C T I O N 8 . 3 8.3-101 AUXILIARY SYSTEMS 9.1-1 9.1 FUEL STORAGE AND HANDLING 9.1-1 9.1.1 NEW FUEL STORAGE 9.1-1 9.1,.2 SPENT FUEL STORAGE 9.1-B 9.1.3 SPENT FUEL POOL COOLING AND CLEANUP SYSTEM A N 9 . L-ZY 9.1,.4 FUEL HANDLING SYSTEM 9 .1,-41, CONTROL OF HEAVY LOADS OVER OR NEAR SPENT F U E L A N D O T H E R C R I T I C A L P L A N T S Y S T E M S / C O M P O N E N T S9 . 1 - 8 2 o 1-a?
9la-\ REFERENCES FOR SECTION 9.I J . L 9.2 WATER SYSTEMS 9. 2 - r 9.2.r E M ER G E N C Y S E R V IC E W A TE R S Y S TE M 9. 2 - r 9.2.2 E M ER G E N C Y C LOS E D C OOLIN G S Y S TE MS 9.2-23 9.2.3 DEMINERALIZED WATER MAKEUP SYSTEM 9.2-35 R evi si on 1'2 January, 2003
MASTER TABLE OF CONTENTS (ContiNUEd)
Section m.: r'l I .L L.LC
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Page 9.2.4 P O T A BL E WA TE R S Y S TE M 9.2-37 9.2.5 U L T IM AT E H E A T S IN K 9.2-39 9.2.6 C O N D E N S ATES TOR A GEFA C ILITIE S 9.2-43 9.2.7 S E R V I C E W A T E RS Y S T E M 9.2-46 9.2.8 N U C L E ARC LOS E DC OOLIN G S Y S TE M 9.2-50 o)o T U R B I N E B U I L D I N G C L O S E DC O O L I N GS Y S T E M 9.2-60 9.2.L0 ALTERNATE DECAY HEAT REMOVALSYSTEM 9.2-64 P R O C E S SA U X I L I A R I E S 9.3-1 9.3.1 C O M P R E S S E DA I R SYSTEMS 9.3-1 9.3.2 PROCESS SAMPLING SYSTEM 9.3-4 9.3.3 EQUIPMENT AND FLOOR DRAINAGE SYSTEM 9 . 3 9.3.4 CHEMICAL AND VOLUME CONTROL SYSTEM 9 .3-23 9.3.5 STANDBY LIQUID CONTROL (SLC) SYSTEM 9.3-23 q?6 POST ACCIDENT SAMPLING SYSTEM 9.3-37 9.3.1 ZINC INJECTION SYSTEM 9.3-42 v<x HYDROGENWATER CHEMISTRY SYSTEM 9.3-43 9.4 A r R C O N D I T T O N T N GH , E A T T N G , C O O L T N GA N D VENTILATING SYSTEMS 9.4-L 9.4.7 CONTROL COMPLEX HVAC SYSTEMS 9.4-L Y.+.2 FUEL HANDLING AREA VENT]LATION SYSTEM 9.4-20 9.4.3 AUXILIARY AND RADWASTE AREA VENTILATION SYSTEMS 9.4-27 9.4.4 T U R B I N E B U I L D I N G A R E A V E N TILA TION S Y S TE M 9.4-44 aAq, EN G IN EE R E DS A FE TY FE A TU R E SV E N TILA TION SYSTEM 9.4-55 9.4.6 R EA C T ORBU ILD IN G V E N T I L A T I O N S Y S T E M S 9.4-68 Revision 18 xvi October, 2AL3
MASTER TABLE OF CONTENTS (COntiNUCd)
Section TitIe Page Oi4 1 IN T E R ME D IA TE B U ILD IN G V E N TILA TION S Y S TE M 9.4-90 9.4.8 T U R B IN E POW E RC OMP LE XV E N TILA TION S Y S TE M 9.4-99 9.4.9 C H IL L E D WA TE RS Y S TE MS 9.4-103 9.4 .10 BUILDING HEATING SYSTEM 9.4-7L1 9.4.Lr OFFGAS CHARCOAL VAULT REFRIGERATION SYSTEM 9.4-121 9 .4 .L2 MISCELLANEOUS NONSAFETY HVAC SYSTEMS 9.4-L42 9.5 OTHER AUXILIARY SYSTEMS 9.5-1 9.5.1 FIRE PROTECTION SYSTEM 9.5-1 COMMUNICATIONS SYSTEMS 9.5-30 LIGHTING SYSTEMS 9.5-35 9.5.4 DIESEL GENERATOR FUEL OIL STORAGE AND TRANSFER SYSTEM 9.5-41 9.5.5 DIESEL GENERATOR COOLING WATER SYSTEM 9.5-51 9.5.6 DIESEL GENERATOR STARTING AIR SYSTEM 9.5-58 qq?
D IE SE L GE NE R A TORLU B R IC A TION S Y S TE M 9. s-63 9.5.8 D IE SE L G E NE R A TORC OMB U S TIONA IR IN TA K E AN D EX H A US TS Y S TE M 9.5-58 9.5.9 H IG H PR ES S U R EC OR E S P R A Y D IE S E L GE N E R A TOR 9.5-71 n
v t t t l J .
J .
t n L V AU XIL ]A R Y S TE A M S Y S TE M 9.5-107 q q 11 REFERENCES FOR SECTION 9.5 9.5-109 APPENDIX 9A F IR E P R OT E C TIONE V A LU A TION R E P OR T APP. 9A TAB 10.0 STEAM AND POWER CONV 10. l_-1 10.1
SUMMARY
DESCRIPTION 10.1-1 IU.Z T U R B IN E GE N E R A TOR L0.2-1, Revision L4 xval_ October' 2005
MASTER TABLE OF CONTENTS (CONtiNUCd)
Secti-on J. -L L.LE Dr
! qYv na I0.2.L DESIGN BASES L 0. 2 - L r0 .2 .2 D E S C R IP TI O N I N LU . Z-Z 10.2.3 TURBINE DISK INTEGRITY L O. 2 - L I 10.2.4 EVALUAT ION t0.2-L7 10.2.5 HYDROGENAND CARBON DIOXIDE SYSTEMS L0.2-1,9 L 0. 2 . 6 n -
REFERENCES FOR SECTION 1.0.2 LU-Z-25 10.3 MAIN STEAM SUPPLY SYSTEM 10.3-1 10.3.1 DESIGN BASES 10.3-1 7 0. 3 . 2 DESCRIPTION LU. J-I 10.3.3 EVALUAT ION L0.3-2 10.3.4 INSPECTION AND TESTING REQUIREMENTS 10.3-3 10.3.5 WATER CHEMISTRY ( PWR) 10.3-4
^,
r_0.36 . S T EA M AN D FE E D W A TE RS Y S TE MMA TE R IA LS IU. J-4 10.4 OT H ER F EA TU R E SOF S TE A M A N D P OW E RC ON V E R S ION SYSTEM 10.4-1 i n IU.
A
{ .I a
MA IN C O N DE N S E R 10.4-1 t n rv.Ll .l MA IN C O N DE N S E R E V A C U A TIONS Y S TE M 10.4-9 70.4.3 T U R B I N E G L A N DS E A L I N G S Y S T E M 1 " 0. 4 - 1 2 I0 .4 .4 T U R B I N E B Y P A S SS Y S T E M 1,Q .4-16 1n 4 q C IR C U L A T ING W A TE R S Y S TE M L0.4-2r 10.4.6 C O N D E N S ATE C LE A N U P S Y S TE M 10.4-30 L0.4 .1 C O N D E N S ATE A N D FE E D W A TE RS Y S TE M 10.4-35 10.4 . B STEAM GENERATORBLOWDOWN SYSTEM 10.4-45 10.4 .9 AU XIL IA R Y FE E D W A TE RS Y S TE M t0 .4-46 R evi si -on 1,2 xvrLl_ January, 2003
MASTER TABLE OF CONTENTS (CONtiNUCd)
Section Title D r :s Yr rva 10.4.10 R E F E R E N C EF SO R S E C T I O N 1 0 . 4 t0 .4-46 11.0 nenroecrrvEwasrEm 11.1-1 r_1.1- SOURCE TERMS 11.1-1 11.1.1 FISSION PRODUCTS 1,1" . L- 2 II.L.2 AC T IVA T IO N P R OD U C TS 11.1-10
- 11. t_.3 TRITIUM 4 4 4 n 1 II.I-II 11.1.4 F U EL F ISS IO N P R OD U C TIONIN V E N TOR YA N D FU E L EXPERIENCE l_1 1 - 1 5 11.1.5 PR O C ES SL EA K A GE S OU R C E S 11 1-1 6 11.1.6 L IQ U ID R AD W A S TES Y S TE M 1 1 L-1"1 IL.1_.1 RADIOACTIVE SOURCESIN THE GAS TREATMENT SYSTEM 11_. 7-1,1 11.1. B SOURCETERMS FOR COMPONENTFAILURES 1 1 . 1I - I 1'1
/
11.1.9 REFERENCEF SO R S E C T I O N 1 1 . 1 11. 1-1B 1 , r. 2 L IQ U ID W A S TE MA N A GE ME N S T Y S TE MS 11. 2-L L7.2.L DESIGN BASES 11. 2-L Lr .2 .2 S Y S T E MD E S C R I P T I O N 1 1 A -
LL.t'l II .2 .3 R AD IO A C T IV E R E LE A S E S 1r .2-2L tL.
2.4 REFERENCES
FOR SECTION 1,I.2 LL.2-22 11.3 GASEOUSWASTE MANAGEMENTSYSTEMS 11.3-1 11.3.1 DESIGN BASES 11.3-1 1 , L. 3 . 2 SYSTEM DESCRIPTION tl 11.3.3 RADIOACTIVE RELEASES 1L.3-23 11.3.4 r r . 5'/.3
^ A r R E F E R E N C E SF O R S E C T I O N 1 1 . 3 R e v i s i - o n t_3 XAX December, 2 0 0 3
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section m.i {-'l ^
I. -L LIE D: rra II .4 S O L ID R AD I OA C TTV EW A S TEMA N A GE ME N S T Y S TE M LL.4-L 11.4.1 DESIGN BASES 1 , r. 4 - L
]-7.4.2 SYSTEM DESCRIPTION L 1 ., 4 - 4 11.
4.3 REFERENCES
FOR SECTION 17.4 Lr.4-1,6 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5-1 1-1.5.1 DESIGN BASES 11.5-1 rL .5.2 1 1 - r SYSTEM DESCRIPTION I I - - h 11.5.3 EFFLUENT MONITORING AND SAMPLING LL.3-II 11.5.4 PROCESS MONITORING AND SAMPLING Lr.5-tt 1 , 2. 0 RADIATION PROTECTIoN L2 . L-L 12.1, ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS REASONABLY ACHIEVAqLE (ALARA) L2. L_I
' 1 12.L.I 1 ^ 1 POLICY CONSIDERATIONS l / t - l L2.r.2 i ^ n ^
DESIGN CONSIDERATIONS LZ. L-Z 1 2. 1 ., 3 4 4 1 1 O P E R A T I O N A L C O N SI D E R A T I O N S LZ. L. I 12.2 RADIATION SOURCES L 2. 2 - 1 "
1,2.2.r CONTAINED SOURCES L 2. 2 - L 1 2. 2 . 2 AIRBORNE RADIOACTIVE MATERIAL SOURCES T 2. 2 - T I 1 , 2. 2 . 3 REFERENCES FOR SECTION 72.2 L2.2-14 1,2.3 PROTECTION DESIGN FEATURES 4 A ^ i RADIATION LZ.J-L L2.3.L F A C I],IT Y D E S IGN FE A TU R E S L 2. 3 - r 1 2. 3 . 2 SHIELDING L 2. 3 - B 72.3.3 VENTILATION L2.3-L9 Revision 13 Decemberr 2003
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section Titl-e Page 12.3.4 AREA RADIATION AND AIRBORNE R A D IOA C TIV ITY MONIT O R IN G IN S TR U ME N TAION T 1,2.3-24 12.3.5 REFERENCEF SO R S E C T I O N L 2 . 3 12.3-68 1 2. 4 D O S EA S S E S S M E N T 12.4-r 1 , 2 . 4. 1 , ESTIMATES OF PERSONNEL OCCUPANCY REQUIREMENTS 1 - 2. 4 - L 1 , 2 . 4. 2 ESTIMATES OF ANNUAL PERSON-REM DOSES 72.4-2 1 2. 4 . 3 ESTIMATED INHALATION DOSES 1,2.4-3 7 2. 4 . 4 ESTIMATED ANNUAL DOSE OUTSIDE THE NUCLEAR FACILITY AT THE BOUNDARY OF THE RESTRICTED AREA t2 .4-5 12.4.5 R E F E R E N C E SF O R S E C T I O N L 2 . 4 1 , 2. 4 - t 0 1 , 2. 5 RADIATION PROTECTION PROGRAM 1 2. 5 - 1 ,
12.5.1_ ORGANIZATION 1 " 2. 5 - r 72.5.2 EQUIPMENT, INSTRUMENTATION AND FACILITIES 1 2. 5 - 2 12.5.3 HEALTH PHYSICS INSTRUCTIONS L 2. 5 - 9 1 2. 6 DESIGN REVIEW OF PLANT SH]ELDING FOR SPACES/
S YS T EMSWH ]C H MA Y B E U S E D IN P OS TA C C ID E N T OPERATIONS OUTSIDE CONTAINMENT L2.6-L 12.5.L IN T R OD U C TION 1 2. 6 - r 12.6.2 R A D IOA C T IV E S OU R C ER E LE A S E S 1 - ^
LZ . O-Z 4 4 - ^
LZ.O-J R A D I O A C T I V E S O U R C ED I S T R I B U T I O N 1 , 2. 6 - 3 12.6.4 S YS T EMSC ON TA IN IN G R A D IOA C TIV E S OU R C E S L2.6-6 1,2.6.5 SHIELDING REVIEW 1 , 2. 6 - 8 a 12.6 .6 AR EA S R EQU IR IN G P E R S ON N E LA C C E S S 1 , 2. 6 - 9 12.6 .1 P O S T AC C ID E N TR A D IA TION ZON E D R A W IN GSA N D
SUMMARY
t2 .6-LL Revision !7 XXI October, 20LL
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section .L -L L.LC Page 1 , 2. 6 . 8 R E F E R E N C EF SO R S E C T I O N 1 2 . 6 12.6.II 13.0 C ON D U C TO F OP E R A TION 13.1-1 13.1 O R G A N IZ A TION A LS TR U C TU R EOF A P P LIC A N T IJ.I.-I 13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION 13.1-1 1,3.r.2 OPERATING ORGANI ZAT ION 13.1-14 1?'t ? OF PERSONNEL r5. r-1f, 4 A -
QUALIFICATIONS 13.1.4 R E F E R E N C E SF O R S E C T I O N 1 3 . 1 4 d a LJ. L-IO 1 3. 2 TRAINING PROGRAM L 3. 2 - L L 3. 2 . I PERRY STAFF TRAINING PROGRAM 1 3. 2 - L L 3. 2 . 2 LICENSED OPERATOR TRAINING PROGRAM L 3. 2 - 2 13.2.3 TRAINING PROGRAMSFOR NON-LICENSED PERSONNEL LJ. I-Y L 3. 2 . 4 PLANT ACCESS TRAINING LJ. Z_ LI 13.2.5 A l t FIRE PROTECTION TRAINING LJ.I_LJ 13.3 EMERGENCY PLANNING 13.3-1 13.3.1 REFERENCE FOR SECTION ].3.3 r3. J-Z 13.4 REVIEW AND AUDIT 13.4-1 13.4.1 PLANT OPERATIONS R E V IE W C OMMITTE E 73.4-2 1,3.4.2 COMPANY NUCLEAR REVIEW BOARD 13.4-2 13.4.3 ( DELETED) 13.4-3 1,3.4.4 F E N O C O V E R S I G H T DEPARTMENT 13.4-3 l_3.5 PLANT PROCEDURES 13.5-1 13.5.1 P R O C E D U R E SA N D I N S T R U C T I O N S 13.5-2 13.5.2 OPERATING AND MAINTENANCE INSTRUCTIONS 13.5-5 Revision 11 xxt_ r- October, 20L1'
MA ST E R TA B LE OF C ON TE N TS (C onti nued)
Secti-on t ' r _t r e Page 13.6 IN D U ST R IAL S E C U R ITY 13.6-1 13.6.1_ SECUR]TY PLAN 1_3.6-1 L3.6.2 4 ^ - 1 SECURITY ORGANIZATION IJ. b-I 13.6.3 SECURITY PROCEDURES t3 .6-2 1 4. 0 INIT IAL TEST PROGMM t4.t-L 1A ra.
1 r SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORTS 14.1-1 1,4.2 PERRY NUCLEAR POWER PLANT TEST PROGRAM 1 , 4. 2 - 1 ,
1,4.2.L
SUMMARY
OF TEST PROGRAM AND OBJECTTVES L4.2-1, L4.2.2 ORGANIZATION AND STAFFING L4.2-5 14.2.3 TEST PROCEDURES L4.2-23 1 " 4. 2 . 4 CONDUCT OF TEST PROGRAM 14.2-25 r4.2.5 REVIEW, EVALUATION AND APPROVAL OF TEST RESULTS 14.2-28 L4.2 .6 TEST RECORDS 1,4.2-30 L4.2.1 CONFORMANCE OF THE TEST PROGRAM WITH REGULATORY GUIDES 1,4.2-30 L4.2.8 U T I L I Z A T I O N O F R E A C T O RO P E R A T I N GA N D T E S T I N G E X P E R I E N C E SI N T H E D E V E L O P M E NO TF THE TEST PROGRAM L4.2-30 L4.2.9 TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES 1,4.2-37 74.2. 10 INTTIAL FUEL LOADING AND INITIAL CRITICALITY 1,4.2-3r
^ - a 14.2. t1 TEST PROGRAMSCHEDULE )-4. t-JJ 1 , 4. 2 . 1,2 INDIVIDUAL TEST DESCRIPTIONS 1,4.2-34 15.0 ACCIDENT ANALYSIS 15.0-1 15.0 GENERAL 15.0-1 Revision 1'2 xx]--r_l- January, 2003
M A S T E RT A B L E O F C O N T E N T S( C o n t i n u e d )
Section Title Page t_5.0.1 A N A L YT IC AL OB JE C TIV E 1 5. 0 - 2 15.0.2 AN AL Y T IC A L C A TE GOR IE S 15.0-3 15.0.3 EVENT EVALUATION 15.0-s 15.0.4 N U C L E ARS AFE TY OP E R A TION A LA N A LY S IS (N S OA )
I RELATIONSHIP I5.U-r/a I 15.0. s EXTENDED OPERATING DOMAINS AND MODES OF OPERATION 15.0-1_B 15.0.6 R E L O A D S AFE TY A N A LY S IS 15.0-21 15.0.7 REFERENCEF SO R S E C T I O N 1 5 . 0 15.0-23 15.1 DECREASEIN REACTORCOOLANTTEMPERATURE l _ 5 r. _ - 1
- 15. 1.1 LOSS OF FEEDWATER HEATING 1-5.1-1 1 5 . 1 ,. 2 FEEDWATER CONTROLLER FAILURE MAXIMUM DEMAND 15.1-8 15.1.3 PRESSURE REGULATOR FAILURE OPEN I5. I-IJ 1tr J-J.
1 A l_ ..t INADVERTENT SAFETY/RELIEF VALVE OPENING 15.1-20 15.1.5 SPECTRUMOF STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT IN A PWR 1,5.1,-23 15.1. 6 I N A D V E R T E N T R H R S H U T D O W NC O O L I N G O P E R A T I O N 1 , 5. L - 2 3 15.1.7 R E F E R E N C E SF O R S E C T I O N 1 5 . 1 l 5 l - , / \
75.2 INCREASE IN REACTOR PRESSURE L5.2-1, 1,5.2.L PRESSURE REGULATOR FAILURE CLOSED L5.2-7 15.2 .2 1 - ^ n GENERATOR LOAD REJECTION L3. Z' I t5 .2 .3 TURBINE TRIP L3.I-LJ L5.2.4 MSIV CLOSURE 1 , 5. 2 - 2 1 .
15.2.5 LOSS OF CONDENSER VACUUM 15.2-30 L5.2.6 LOSS OF AC POWER 15.2-35 Revision 13 xxiv December, 2003
MASTER TABLE OF CONTENTS (CONIiNUCd)
Section m.i +'l ^
I-.J- L-LE Dr rra L5.2.1 L O S S O F F E E D W A TE RFLOW 15.2-41, 15.2.8 FEEDWATERLINE BREAK 1 " 5. 2 - 4 5 75.2 .9 F A IL U R E O F R H R S H U TD OW N C OOLIN G 1,5.2-45 15.2.10 L O S S O F I N S T R U M E N TA I R 15.2-53 1 , 5. 2 . L 1 , REFERENCES FOR L5.2 15.2-55 15.3 DECREASEIN REACTORCOOLANT SYSTEM FLOW RATE 15.3-1
]_s.3.1 R EC IR C U L A TIONP U MP TR IP 15.3-1 L 5. 3 . 2 R EC IR C U L A TIONFLOW C ON TR OLFA ILU R E D EC R E AS INGFLOW 15.3-6 15.3.3 R E C I R C U L A T I O NP U M P S E I Z U R E 15.3-11 15.3.4 R EC IR C U L A TION P U MP S H A FT B R E A K 15.3-15 15.3.5 REFERENCEF SO R S E C T I O N 1 5 . 3 15.3-19 15.4 R E AC T IVIT Y A N D P OW E RD IS TR IB U TION A N OMA LIE S t_5.4-1 1q, l J .
A
. l 1
- L ROD WITHDRAWAL ERROR LOW POWER 15.4-1 L5.4 .2 ROD WITHDRAWAL ERROR AT POWER 1 , 5. 4 - 6 15.4.3 CONTROL ROD MALOPERATION (SYSTEM MALFUNCTION OR OPERATOR ERROR) 15.4-10 1 , 5. 4 . 4 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP 15.4-10 15.4.5 RECIRCULATION FLOW CONTROL FAILURE WITH INCREAS ING FLOW L5.4-1,4 15.4.6 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTIONS 15.4-19 L5.4 .1 MISPLACED BUNDLE ACCIDENT 15.4-19 15.4 . B SPECTRUMOF ROD EJECTION ASSEMBLIES 1 . 5. 4 - 2 2 L5.4.9 CONTROL ROD DROP ACCIDENT (CRDA) L5.4-23 15.4 .10 R E F E R E N C E SF O R S E C T I O N 1 5 . 4 15.4-31 R evi si on 1'2 XXV January, 2003
MASTER TABLE OF CONTENTS (CONtiNUCd)
'l-'r_ Page Section c _Le 15.5 INCREASE IN REACTOR COOLANT INVENTORY 15.5-1
'rq q-1 15.5.1 IN AD VE R T E N TH P C S S TA R TU P 15.5.2 C H EMIC AL VOLU MEC ON TR OLS Y S TE MMA LFU N C TION (o R O P ER ATORE R R OR ) 15.5-4 15.5.3 B WR T R A N S IE N TS W H IC H IN C R E A S E R E A C TORC OOLA N T INVENTORY 15.5-4 r - 5 .6 DECREASE IN REACTOR COOLANT INVENTORY 15. 6-1 l _ 5 .6 . 1 IN AD VE R T E N TS A FE TY /R E LIE F V A LV E OP E N IN G 1q A-1 75.6.2 IN S T R U M EN TLIN E P IP E B R E A K 15.6-1
- 15. 6.3 STEAM GENERATORTUBE FAILURE 15.6-8
- 15. 6.5 LOSS-OF-COOLANA T C C T D E N T S( R E S U L T T N GF R O M S P E C T R U MO F P O S T U L A T E DP I P I N G B R E A K SW I T H I N T H E R E AC TORC OOLA N TP R E S S U R EB OU N D A R Y )
INSIDE CONTAINMENT 15.6-16
- 15. 6.6 F EE D W A T ERLIN E B R E A K OU TS ID E C ON TA IN ME N T 15.6-38 L5.6.1 R E F E R E N C EF SO R S E C T I O N 1 5 . 6 15.6-43a 15.7 RADIOACTIVE RELEASE FROM SUBSYSTEMS AND COMPONENTS 15. /-l_
15.7.1 RADIOACTIVE GAS WASTE SYSTEM LEAK OR FAILURE 15. /-r 1 , 5 . 1. 2 R AD IO A C T IV E LIQU ID W A S TE S Y S TE M FA ILU R E S
( R E L E A S ET O A T M O S P H E R E ) 15.7-15 1q 1 ? P O S T U L A T EDR A D IOA C TIV E R E LE A S E S D U E TO L IQU ID -C O N TA IN IN G TA N K FA ILU R E S 1 , 5. 7 - t " l 1tr 1 A F U E L H AN DLIN G A C C ID E N T OU TS ID E C ON TA IN ME N T L5.1-2r 15.7.5 S PE N T F U E L C A S K D R OP A C C ID E N TS 1_5.7-30 16 7 6 F U E L H AN DLIN G A C C ID E N T IN S ID E C ON TA IN ME N T 15.7-31 Revision 1"4 xxv-l_ October' 2005
MASTER TABLE OF CONTENTS (ContiNUCd)
Secti-on Page 1 , 5 . 1. 1 R E F E R E N C E SF O R S E C T I O N 1 5 . 7 1-5.7-37
- 15. B OTHER EVENTS t _ 5 .B - 1 15.8.1_ ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) 15.8-1 1 5 . B. 2 STATION BLACKOUT (SBO) 15.B-2 APPENDIX 15A PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS APP. 15A i Nq1-')A \
\ ! r v v ' r /
TAB A P P E N D IX 1 5 8 R EL OA D S AFE TY A N A LY S IS APP. 158 TAB A P P E N D I X1 5 C ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) APP. 15C TAB A P P E N D I X1 5 D PARTIAL FEEDWATER HEATING OPERATION ANALYSIS A P P. 1 . 5 D TAB A P P E N D I X1 5 E PNPP MAXIMUM EXTENDED OPERATING DOMAIN ANALYSIS APP. 15E TAB A P P E N D I X1 5 F PNPP SINGLE LOOP OPERATION ANALYSIS I - f i AEY. I3T TAB APPENDIX 1-5G CONTROL SYSTEM INTERACTIONS A P P. 1 5 G TAB APPENDIX 15H S T A T I O N B L A C K O U T( S B O ) APP. ]-5H TAB 16.0 T E C H N I C A LS P E C I F I a a n 1 lo.u-r 17.0 O U AL IT Y A SS U R A N C E 1_7.0-1 1'7 r/.1-1 (DELETED)
I1 .2 Q U AL IT Y A SS U R A N C ED U R IN G TH E OP E R A TION SP H A S E L ' 7. 2 - r Revisi-on 13 xxvl-l- Decemberr 2003