ML21361A215

Supplemental Information for Revision 22 to Updated Safety Analysis Report, Master Table of Contents

ML21361A215
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Site:	Perry
Issue date:	12/20/2021
From:	Energy Harbor Nuclear Corp
To:	Office of Nuclear Reactor Regulation
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ML21361A235	List: L-21-287, Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter) ML21361A187 ML21361A188 ML21361A189 ML21361A190 ML21361A191 ML21361A192 ML21361A193 ML21361A194 ML21361A195 ML21361A196 ML21361A197 ML21361A198 ML21361A199 ML21361A200 ML21361A201 ML21361A202 ML21361A203 ML21361A205 ML21361A206 ML21361A207 ML21361A208 ML21361A209 ML21361A211 ML21361A212 ML21361A213 ML21361A215 ML21361A216 ML21361A217 ML21361A218 ML21361A219 ML21361A220 ML21361A221 ML21361A222 ML21361A223 ML21361A224 ML21361A225 ML21361A226 ML21361A227 ML21361A228 ML21361A229
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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. 6.4 S T EA M S YS TE M P IP IN G B R E A K OU TS ID E C ON TA IN ME N T 15. 5-B

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