ML21307A204
| ML21307A204 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/28/2021 |
| From: | Energy Harbor Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21307A174 | List:
|
| References | |
| L-21-018 | |
| Download: ML21307A204 (27) | |
Text
MASTER TABLE OF CONTENTS
Section Titl-e Page
1.0 INTRODUCTION
AND 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
taa 1.3 COMPARISON TABLES
t_.3.1 COMPARISONS WITH SIMILAR FACILITY DESIGNS 1.3-1
L.3.2 COMPARISON OF FINAL AND PRELIMINARY TNFORMAT ION 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 RAYMOND KATSER ENGTNEERS, rNC. 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 EVALUATION OF UNIT ]- OPERATTONS RESULTING FROM UNIT 2 CONSTRUCTION ACTIVITIES 1. 1_0-1_
APPENDIX 1A NUREG-O737 *TMr ACTTON PLAN REQUTREMENTS FOR
in APPLICANTS FOR NEW OPERATING LICENSES" 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
^11Z.I.I SITE LOCATION AND DESCRIPTION 2.L-L
2.L.2 EXCLUSION AREA AUTHORITY AND CONTROL z. L-5
2.r.3 POPULATION DISTRIBUTION 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, LOCAT]ONS AND ROUTES z.z-r
2.
2.2 DESCRIPTION
S 2.2-4
2.2.3 EVALUATION OF POTENTIAL ACCIDENTS 2.2-27
2.
2.4 REFERENCES
FOR SECTION 2.2 2.2-39
2.3 METEOROLOGY 2.3-L
Revision 14 l_1 October,2005 MASTER TABLE OF CONTENTS (Continued)
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 METEOROLOGICAL MEASUREMENT PROGRAM 2.3 2.3.4 SHORT TERM (ACCIDENT) DIFFUSION ESTIMATES 2.3-40
LONG TERM (ROUTINE RELEASE) DIFFUSION ESTIMATES 2.3-43
2.
3.6 REFERENCES
FOR SECTION 2.3 2.3-41
2.4 HYDROLOGIC ENGINEERING 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-rr
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
11-OPERATION REQUIREMENTS 2.4-LLt
Revision 12 1a l_ January l 2403 MASTER TABLE OF CONTENTS (Continued)
Section Title Page
2.4.L5 LIST OF PERSONS AND 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
APPENDIX 29 MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS FOR PNPP, lO-M WINDS APP. 2B TAB
APPENDIX 2C MONTHLY AND ANNUAL JOINT FREQUENCY
^a DISTRIBUTIONS FOR PNPP, 6O-M WINDS AEE. /.V TAB
APPENDIX 2D BEDROCK DEFORMATION IN THE COOLING WATER TUNNEL APP. 2D TAB
APPEND]X 2E SOIL AND ROCK BORINGS APP. 2E TAB
DESIGN OF STRUCTUR AND SYSTEMS 3.1-1
3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.l_-1
Revi-sion t2 l_v January l 2043 MASTER TABLE OF CONTENTS (Continued)
Section '.t-'t_ t l-e Page
3.1.1
SUMMARY
DESCR]PTION 3. 1_-1
3.L.2 CRITERION CONFORMANCE 3.L-2
3.t CLASSIFICATION OF STRUCTURES COMPONENTS AND SYSTEMS 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 TORNADO LOADS 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 STRUCTURES, SYSTEMS AND COMPONENTS TO BE 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 SUBSYSTEM ANALYSIS 3.1-25
3.1.4 SEISMIC INSTRUMENTATION 3.'7 -44
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
Revi-sion 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/
COMPONENT SUPPORTS 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
^n1-AJ.Y-IlU 3.9.6 INSERVICE TESTING OF PUMPS AND VALVES
3.
9.7 REFERENCES
FOR SECTION 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 REFERENCES
FOR SECTION 3.10 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 MASTER TABLE OF CONTENTS (Continued)
Section Title Page
-n APPENDIX 3A HYDRODYNAMIC LOADS FOR PNPP 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
- q. r-r4Ii 1 1A 4.
1.5 REFERENCES
FOR SECTION 4.L
+.2 FUEL SYSTEM DESIGN 4.2-L
4.2.1 GENERAL AND DETAILED DESIGN BASES 4.2-t
4.
2.2 DESCRIPTION
AND DESIGN DRAWINGS 4.2-7
4.2.3 DESIGN EVALUATIONS 4.2-5
4.2.4 TESTING, INSPECTION AND SURVEILLANCE PLANS 4.2-6
4.2.5 OPERATING AND DEVELOPMENTAL EXPERIENCE 4.2-6
4.
2.6 REFERENCES
FOR SECTION 4.2 4.2-6
4.3 NUCLEAR DESIGN 4.3-1
4.3.r DESIGN BASES 4.3-r
4.
3.2 DESCRIPTION
A '2. -1
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 MASTER TABLE OF CONTENTS (Continued)
Section Titl-e Page
4.4 THERMAL AND HYDRAULIC DESIGN 4.4-L
4.4.L DESIGN BASIS 4.4-r
4.
4.2 DESCRIPTION
OF THERMAL.HYDRAULIC DESIGN OF THE REACTOR CORE
4.
4.3 DESCRIPTION
OF THE THERMAL AND HYDRAULIC DESIGN OF THE REACTOR COOLANT SYSTEM 4.4-4
4.4.4 EVALUAT ION 4.4-r0
4.4.5 TESTING AND VERIFICATION 4.4-1r
4.4.6 INSTRUMENTAT ION REQUI REMENTS 4.4-r2
/q. REACTOR MATERIALS 4 q-l
A q 1 CONTROL ROD DRIVE SYSTEM STRUCTURAL MATERIALS 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 CONTROL SYSTEMS 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 REFERENCES
FOR SECTION 4.6 4.6-6r
REACTOR COOLANT SY 5.1-1
5.1
SUMMARY
DESCRIPTION 5.1-1_
Revisi-on 1,'l 1X October, 201,1" MASTER TABLE OF CONTENTS (CONIiNUEd)
Section TitIe Page
q11 5.L-4 J.l-.J-SCHEMATIC FLOW DIAGRAM
5.1.2 PIPING AND INSTRUMENTATION DIAGRAM 5.1-4
\\l 5. 1-5 ELEVATION DRAWINGS
5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 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 5.2-1 9
q? REACTOR VESSEL 5. 3-1
q?1 REACTOR VESSEL MATERIALS 5.3-1
5.3.2 PRESSURE-TEMPERATURE LIMTTS 5.3-13
REACTOR VESSEL INTEGRITY 5.3-16
5.
3.4 REFERENCES
FOR SECTION 5.3 5.3-28
C,A 5.4-1 COMPONENT AND SUBSYSTEM DESIGN
\\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 REMOVAL SYSTEM 5.4-39
5.4.8 REACTOR WATER CLEANUP SYSTEM 5.4-55
5.4.9 MAIN STEAM LINE AND FEEDWATER PIPING 5.4-60
q A 1n 5.4-62 J. ?.IV PRESSURI ZER
tr-A 11 5.4-62
J. A.II PRESSURIZER RELIEF DISCHARGE SYSTEM
5.4.12 VALVES 5.4-62
5.4.13 SAFETY AND RELIEF VALVES 5.4-65
5.4.14 COMPONENT SUPPORTS 5.4-66
5.4.15 REFERENCES FOR SECTION 5.4 5.4-68
6.0 ENGINEERED SAFETY 6.1-1
6.r ENGINEERED SAFETY FEATURE MATERIALS 6. r--1
6.1.1 METALLIC MATERIALS 6,1-1
6.L.2 ORGANIC MATERIALS 6.L-7
6'1? REFERENCES FOR SECTION 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 ^ a1^
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 EMERGENCY CORE COOLING SYSTEM 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 REQU I REMENTS 6.3-57
5.
3.6 REFERENCES
FOR SECTION 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 INSTRUMENTAT ION REQUIREMENTS 6.4-1"9a
5.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5-1
- 6. 5. 1_ ENGINEERED SAFETY FEATURES (ESF) FILTER SYSTEMS 6.5-1
6.5.2 CONTAINMENT SPRAY SYSTEM 6.5-9
6.5.3 FISSION PRODUCT CONTROL SYSTEMS 6.5-15
6.5.4 ICE CONDENSER AS A FISSION PRODUCTCLEANUP SYSTEM 6.5-24
6.
5.5 REFERENCES
FOR SECTION 6.5 6.5-24
INSERVICE INSPECTION OF CLASS 2 AND3 COMPONENTS 6.6_7
6.6.1. COMPONENTS SUBJECT TO EXAMINATION 6.6-7
Revision L7 x11 October, 2011 MASTER TABLE OF CONTENTS (Continued)
Section m.i +-1^IILIC 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_
hxl 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 INSTRUMENTAT ION REQUIREMENTS 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 IDENTIFICATION OF SAFETY-RELATED SYSTEMS 7.7-L
7.1.2 IDENTIFICATION OF SAFETY CRITERIA 1.I-1
7.1.3 PLANT PROTECT]ON SYSTEM-ELECTRONIC TRIP SYSTEM 1.1"-L1
1.2 REACTOR TRIP SYSTEM REACTOR PROTECTION SYSTEM (RPS) 1.2-t
-4nt.z-L 1.2.r DESCRI PT ION
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 PT ION 1.4-1,
'1 A) ANALYSIS "7.4-27
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 MASTER TABLE OF CONTENTS (Continued)
Section 't_'r_ t l-e Page
B.l_ INTRODUCTION 8.1-1
- 8. 1.1 SAFETY LOADS B.T-2
d.L.z REFERENCES FOR SECTION 8.1 8.1-3
8.2 OFFSITE POWER SYSTEM 8.2-t
n41o.z.t DESCRIPTION I.2-1
d.z.z ANALY S I S 8.2-6
8.3 ONSITE POWER SYSTEMS 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 REFERENCES
FOR SECTION 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
AN 9.1.3 SPENT FUEL POOL COOLING AND CLEANUP SYSTEM 9. L-ZY
9.1,.4 FUEL HANDLING SYSTEM 9.1,- 41,
CONTROL OF HEAVY LOADS OVER OR NEAR SPENT FUEL AND OTHER CRITICAL PLANT SYSTEMS/COMPONENTS 9.1-82
9la-\\ o 1-a?
REFERENCES FOR SECTION 9.I J.L
9.2 WATER SYSTEMS 9.2-r
9.2.r EMERGENCY SERVICE WATER SYSTEM 9.2-r
9.2.2 EMERGENCY CLOSED COOLING SYSTEMS 9.2-23
9.2.3 DEMINERALIZED WATER MAKEUP SYSTEM 9.2-35
Revision 1'2 January, 2003 MASTER TABLE OF CONTENTS (ContiNUEd)
Section m.: r'l ^I.L L.LC Page
9.2.4 POTABLE WATER SYSTEM 9.2-37
9.2.5 ULTIMATE HEAT SINK 9.2-39
9.2.6 CONDENSATE STORAGE FACILITIES 9.2-43
9.2.7 SERVICE WATER SYSTEM 9.2-46
9.2.8 NUCLEAR CLOSED COOLING SYSTEM 9.2-50
o)o TURBINE BUILDING CLOSED COOLING SYSTEM 9.2-60
9.2.L0 ALTERNATE DECAY HEAT REMOVAL SYSTEM 9.2-64
PROCESS AUXILIARIES 9.3-1
9.3.1 COMPRESSED AIR 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 HYDROGEN WATER CHEMISTRY SYSTEM 9.3-43
9.4 ArR CONDITTONTNG, HEATTNG, COOLTNG AND 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 TURBINE BUILDING AREA VENTILATION SYSTEM 9.4-44
aAq, ENGINEERED SAFETY FEATURES VENTILATION SYSTEM 9.4-55
9.4.6 REACTOR BUILDING VENTILATION SYSTEMS 9.4-68
Revision 18 xvi October, 2AL3 MASTER TABLE OF CONTENTS (COntiNUCd)
Section TitIe Page
Oi4 1 INTERMEDIATE BUILDING VENTILATION SYSTEM 9.4-90
9.4.8 TURBINE POWER COMPLEX VENTILATION SYSTEM 9.4-99
9.4.9 CHILLED WATER SYSTEMS 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? DIESEL GENERATOR LUBRICATION SYSTEM 9. s-63
9.5.8 DIESEL GENERATOR COMBUSTION AIR INTAKE AND EXHAUST SYSTEM 9.5-58
9.5.9 HIGH PRESSURE CORE SPRAY DIESEL GENERATOR 9.5-71
n - tn vtttlJ. J. LV AUXIL]ARY STEAM SYSTEM 9.5-107
q q 11 REFERENCES FOR SECTION 9.5 9.5-109
APPENDIX 9A FIRE PROTECTION EVALUATION REPORT APP. 9A TAB
10.0 STEAM AND POWER CONV 10. l_-1
10.1
SUMMARY
DESCRIPTION 10.1-1
IU.Z TURBINE GENERATOR L0.2-1,
Revision L4 xval_ October' 2005 MASTER TABLE OF CONTENTS (CONtiNUCd)
Dr na Secti-on J. -L L.LE ! qYv
I0.2.L DESIGN BASES L0.2-L
IN r0.2.2 DESCRI PT ION LU. Z-Z
10.2.3 TURBINE DISK INTEGRITY LO.2-LI
10.2.4 EVALUAT ION t0.2-L7
10.2.5 HYDROGEN AND CARBON DIOXIDE SYSTEMS L0.2-1,9
n-L0.
2.6 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
70.3.2 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
IU. J-4^,
r_0.3. 6 STEAM AND FEEDWATER SYSTEM MATERIALS
10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1
in A a IU. {.I MAIN CONDENSER 10.4-1
tnrv.Ll.l MAIN CONDENSER EVACUATION SYSTEM 10.4-9
70.4.3 TURBINE GLAND SEALING SYSTEM 1"0.4-12
I0.4.4 TURBINE BYPASS SYSTEM 1,Q.4-16
1n 4 q CIRCULATING WATER SYSTEM L0.4-2r
10.4.6 CONDENSATE CLEANUP SYSTEM 10.4-30
L0.4.1 CONDENSATE AND FEEDWATER SYSTEM 10.4-35
10.4. B STEAM GENERATOR BLOWDOWN SYSTEM 10.4-45
10.4.9 AUXILIARY FEEDWATER SYSTEM t0.4-46
Revisi-on 1,2 xvrLl_ January, 2003 MASTER TABLE OF CONTENTS (CONtiNUCd)
D: rra Section Title r sYv
10.4.10 REFERENCES FOR SECTION 10.4 t0.4-46
11.0 nenroecrrvE wasrE m 11.1-1
r_1.1-SOURCE TERMS 11.1-1
11.1.1 FISSION PRODUCTS 1,1". L-2
II.L.2 ACTIVATION PRODUCTS 11.1-10
44 4 n1
- 11. t_.3 TRITIUM II.I-II
11.1.4 FUEL FISSION PRODUCTION INVENTORY AND FUEL EXPERIENCE l_11-15
11.1.5 PROCESS LEAKAGE SOURCES 11 1-1 6
11.1.6 LIQUID RADWASTE SYSTEM 11 L-1"1
IL.1_.1 RADIOACTIVE SOURCES IN THE GAS TREATMENT SYSTEM 11_.7-1,1
1 1'1 11.1. B SOURCE TERMS FOR COMPONENT FAILURES 11.I-I /
11.
1.9 REFERENCES
FOR SECTION 11.1 11.1-1B
1,r.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.2-L
L7.2.L DESIGN BASES 11.2-L
11 A-Lr.2.2 SYSTEM DESCRIPTION LL.t'l
II.2.3 RADIOACTIVE RELEASES 1r.2-2L
tL.
2.4 REFERENCES
FOR SECTION 1,I.2 LL.2-22
11.3 GASEOUS WASTE MANAGEMENT SYSTEMS 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
^ Ar 11.
3.4 REFERENCES
FOR SECTION 11.3 r r. 5'/.3
Revisi-on t_3 XAX December, 2003 MASTER TABLE OF CONTENTS (Continued)
Section m.i {-'l ^I. -L LIE D: rra
II.4 SOLID RADIOACTTVE WASTE MANAGEMENT SYSTEM LL.4-L
11.4.1 DESIGN BASES 1,r.4-L
]-7.4.2 SYSTEM DESCRIPTION L1,.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
11 - rI I --h rL.5.2 SYSTEM DESCRIPTION
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^ 1 '1 l / t-l 12.L.I POLICY CONSIDERATIONS
i^ n ^
L2.r.2 DESIGN CONSIDERATIONS LZ. L-Z
44 1 1 12.1,.3 OPERATIONAL CONS IDERAT IONS LZ. L. I
12.2 RADIATION SOURCES L2.2-1"
1,2.2.r CONTAINED SOURCES L2.2-L
12.2.2 AIRBORNE RADIOACTIVE MATERIAL SOURCES T2.2-TI
1,2.2.3 REFERENCES FOR SECTION 72.2 L2.2-14
4A ^ i 1,2.3 RADIATION PROTECTION DESIGN FEATURES LZ.J-L
L2.3.L FACI],ITY DESIGN FEATURES L2.3-r
12.3.2 SHIELDING L2.3-B
72.3.3 VENTILATION L2.3-L9
Revision 13 Decemberr 2003 MASTER TABLE OF CONTENTS (Continued)
Section Titl-e Page
12.3.4 AREA RADIATION AND AIRBORNE RADIOACTIVITY MON ITORING INSTRUMENTAT ION 1,2.3-24
12.
3.5 REFERENCES
FOR SECTION L2.3 12.3-68
12.4 DOSE ASSESSMENT 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
12.4.3 ESTIMATED INHALATION DOSES 1,2.4-3
72.4.4 ESTIMATED ANNUAL DOSE OUTSIDE THE NUCLEAR FACILITY AT THE BOUNDARY OF THE RESTRICTED AREA t2.4-5
12.
4.5 REFERENCES
FOR SECTION L2.4 1,2.4-t0
1,2.5 RADIATION PROTECTION PROGRAM 12.5-1,
12.5.1_ ORGANIZATION 1"2.5-r
72.5.2 EQUIPMENT, INSTRUMENTATION AND FACILITIES 12.5-2
12.5.3 HEALTH PHYSICS INSTRUCTIONS L2.5-9
12.6 DESIGN REVIEW OF PLANT SH]ELDING FOR SPACES/
SYSTEMS WH]CH MAY BE USED IN POSTACCIDENT OPERATIONS OUTSIDE CONTAINMENT L2.6-L
12.5.L INTRODUCTION 12.6-r
1 -^
12.6.2 RADIOACTIVE SOURCE RELEASES LZ. O-Z
44-^LZ.O-J RADIOACTIVE SOURCE DISTRIBUTION 1,2.6-3
12.6.4 SYSTEMS CONTAINING RADIOACTIVE SOURCES L2.6-6
1,2.6.5 SHIELDING REVIEW 1,2.6-8a
12.6.6 AREAS REQUIRING PERSONNEL ACCESS 1,2.6-9
12.6.1 POSTACCIDENT RADIATION ZONE DRAWINGS AND
SUMMARY
t2.6-LL
Revision !7 XXI October, 20LL MASTER TABLE OF CONTENTS (Continued)
Section.L -L L.LC Page
1,2.
6.8 REFERENCES
FOR SECTION 12.6 12.6.II
13.0 CONDUCT OF OPERATION 13.1-1
13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT IJ.I.-I
13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION 13.1-1
1,3.r.2 OPERAT ING ORGAN I ZAT ION 13.1-14
4 A-1?'t ? QUALIFICATIONS OF PERSONNEL r5. r-1f,
4 da 13.
1.4 REFERENCES
FOR SECTION 13.1 LJ. L-IO
13.2 TRAINING PROGRAM L3.2-L
L3.2.I PERRY STAFF TRAINING PROGRAM 13.2-L
L3.2.2 LICENSED OPERATOR TRAINING PROGRAM L3.2-2
13.2.3 TRAINING PROGRAMS FOR NON-LICENSED PERSONNEL LJ. I-Y
L3.2.4 PLANT ACCESS TRAINING LJ. Z_ LI
Alt 13.2.5 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 REVIEW COMMITTEE 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 FENOC OVERSIGHT DEPARTMENT 13.4-3
l_3.5 PLANT PROCEDURES 13.5-1
13.5.1 PROCEDURES AND INSTRUCTIONS 13.5-2
13.5.2 OPERATING AND MAINTENANCE INSTRUCTIONS 13.5-5
Revision 11 xxt_ r-October, 20L1' MASTER TABLE OF CONTENTS (Continued)
Secti-on t'r_ t re Page
13.6 INDUSTRIAL SECURITY 13.6-1
13.6.1_ SECUR]TY PLAN 1_3.6-1
4^-1IJ. b-I L3.6.2 SECURITY ORGANIZATION
- 13. 6.3 SECURITY PROCEDURES t3.6-2
14.0 INIT IAL TEST PROGMM t4.t-L
1A 1 ra. 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 UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCES IN THE DEVELOPMENT OF 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 PROGRAM SCHEDULE )-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 MASTER TABLE OF CONTENTS (Continued)
Section Title Page
t_5.0.1 ANALYTICAL OBJECTIVE 15.0-2
15.0.2 ANALYTICAL CATEGORIES 15.0-3
15.0.3 EVENT EVALUATION 15.0-s
15.0.4 NUCLEAR SAFETY OPERATIONAL ANALYSIS (NSOA)
RELATIONSHIP I5.U-r/a II
15.0. s EXTENDED OPERATING DOMAINS AND MODES OF OPERATION 15.0-1_B
15.0.6 RELOAD SAFETY ANALYSIS 15.0-21
15.
0.7 REFERENCES
FOR SECTION 15.0 15.0-23
15.1 DECREASE IN REACTOR COOLANT TEMPERATURE l_5. r_-1
- 15. 1.1 LOSS OF FEEDWATER HEATING 1-5.1-1
15.1,.2 FEEDWATER CONTROLLER FAILURE MAXIMUM DEMAND 15.1-8
15.1.3 PRESSURE REGULATOR FAILURE OPEN I5. I-IJ
1tr 1 A 15.1-20 J-J. l_..t INADVERTENT SAFETY/RELIEF VALVE OPENING
15.1.5 SPECTRUM OF STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT IN A PWR 1,5.1,-23
15.1. 6 INADVERTENT RHR SHUTDOWN COOLING OPERATION 1,5. L-23
l5 l-,/\\
15.
1.7 REFERENCES
FOR SECTION 15.1
75.2 INCREASE IN REACTOR PRESSURE L5.2-1,
1,5.2.L PRESSURE REGULATOR FAILURE CLOSED L5.2-7
1-^nL3. Z' I 15.2.2 GENERATOR LOAD REJECTION
t5.2.3 TURBINE TRIP L3.I-LJ
L5.2.4 MSIV CLOSURE 1,5.2-21.
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 LOSS OF FEEDWATER FLOW 15.2-41,
15.2.8 FEEDWATER LINE BREAK 1"5.2-45
75.2.9 FAILURE OF RHR SHUTDOWN COOLING 1,5.2-45
15.2.10 LOSS OF INSTRUMENT AIR 15.2-53
1,5.2. L1, REFERENCES FOR L5.2 15.2-55
15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE 15.3-1
]_s.3.1 RECIRCULATION PUMP TRIP 15.3-1
L5.3.2 RECIRCULATION FLOW CONTROL FAILURE DECREASING FLOW 15.3-6
15.3.3 RECIRCULATION PUMP SEIZURE 15.3-11
15.3.4 RECIRCULATION PUMP SHAFT BREAK 15.3-15
15.
3.5 REFERENCES
FOR SECTION 15.3 15.3-19
15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES t_5.4-1
1q, A 1 15.4-1 lJ..l. -LROD WITHDRAWAL ERROR LOW POWER
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 SPECTRUM OF ROD EJECTION ASSEMBLIES 1.5.4-22
L5.4.9 CONTROL ROD DROP ACCIDENT (CRDA) L5.4-23
15.4.10 REFERENCES FOR SECTION 15.4 15.4-31
Revision 1'2 XXV January, 2003 MASTER TABLE OF CONTENTS (CONtiNUCd)
Section 'l-'r_ c _L e Page
15.5 INCREASE IN REACTOR COOLANT INVENTORY 15.5-1
'r q q-1 15.5.1 INADVERTENT HPCS STARTUP
15.5.2 CHEMICAL VOLUME CONTROL SYSTEM MALFUNCTION (oR OPERATOR ERROR) 15.5-4
15.5.3 BWR TRANSIENTS WHICH INCREASE REACTOR COOLANT INVENTORY 15.5-4
r-5. 6 DECREASE IN REACTOR COOLANT INVENTORY 15. 6-1
l_5. 6. 1 INADVERTENT SAFETY/RELIEF VALVE OPENING 1q A-1
75.6.2 INSTRUMENT LINE PIPE BREAK 15.6-1
- 15. 6.3 STEAM GENERATOR TUBE FAILURE 15.6-8
- 15. 6.4 STEAM SYSTEM PIPING BREAK OUTSIDE CONTAINMENT 15. 5-B
- 15. 6.5 LOSS-OF-COOLANT ACCTDENTS (RESULTTNG FROM SPECTRUM OF POSTULATED PIPING BREAKS WITHIN THE REACTOR COOLANT PRESSURE BOUNDARY)
INSIDE CONTAINMENT 15.6-16
- 15. 6.6 FEEDWATER LINE BREAK OUTSIDE CONTAINMENT 15.6-38
L5.
6.1 REFERENCES
FOR SECTION 15.6 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 RADIOACTIVE LIQUID WASTE SYSTEM FAILURES (RELEASE TO ATMOSPHERE) 15.7-15
1q 1 ? POSTULATED RADIOACTIVE RELEASES DUE TO LIQUID-CONTAINING TANK FAILURES 1,5.7 -t"l
1tr 1 A FUEL HANDLING ACCIDENT OUTSIDE CONTAINMENT L5.1-2r
15.7.5 SPENT FUEL CASK DROP ACCIDENTS 1_5.7-30
16 7 6 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 15.7-31
Revision 1"4 xxv-l_ October' 2005 MASTER TABLE OF CONTENTS (ContiNUCd)
Secti-on Page
1,5.1.1 REFERENCES FOR SECTION 15.7 1-5.7-37
- 15. B OTHER EVENTS t_5. B-1
15.8.1_ ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) 15.8-1
- 15. B.2 STATION BLACKOUT (SBO) 15.B-2
APPENDIX 15A PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS APP. 15A i Nq1-')A \\ TAB
\\!rvv'r/
APPENDIX 158 RELOAD SAFETY ANALYSIS APP. 158 TAB
APPENDIX 15C ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) APP. 15C TAB
APPENDIX 15D PARTIAL FEEDWATER HEATING OPERATION ANALYSIS APP. 1.5D TAB
APPENDIX 15E PNPP MAXIMUM EXTENDED OPERATING DOMAIN ANALYSIS APP. 15E TAB
I -fi APPENDIX 15F PNPP SINGLE LOOP OPERATION ANALYSIS AEY. I3T TAB
APPENDIX 1-5G CONTROL SYSTEM INTERACTIONS APP. 15G TAB
APPENDIX 15H STATION BLACKOUT (SBO) APP. ]-5H TAB
aa n 1 16.0 TECHNICAL SPECIFI lo.u-r
17.0 OUALITY ASSURANCE 1_7.0-1
1'7 1 ( DELETED) r/.1-
I1.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE L'7.2-r
Revisi-on 13 xxvl-l-Decemberr 2003