ML17305A194

0 to Updated Final Safety Analysis Report, Master Table of Contents

ML17305A194
Person / Time
Site:	Perry
Issue date:	10/23/2017
From:	FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17305A181	List: L-17-046, Technical Specification Bases, Rev. 11 ML17305A193 ML17305A194 ML17305A195 ML17305A197 ML17305A198 ML17305A199 ML17305A200 ML17305A201 ML17305A202 ML17305A203 ML17305A205 ML17305A207 ML17305A208 ML17305A210 ML17305A211 ML17305A212 ML17305A213 ML17305A214 ML17305A215 ML17305A216 ML17305A217 ML17305A218 ML17305A219 ML17305A220 ML17305A221 ML17305A222 ML17305A223 ML17305A224 ML17305A225 ML17305A226 ML17305A227 ML17305A228 ML17305A229 ML17305A230 ML17305A231 ML17305A232 ML17305A233 ML17305A234 ML17305A235 ML17305A236 ML17305A237 ML18022A830
References
L-17-046
Download: ML17305A194 (27)

Text

S e c t i o n

1. 0

1. 1 t. 2 t. 2. 1,

r. 2. 2

r. 2. 3

1. 3 t _. 3. 1 L. 3. 2 L. 4

1. 4. 1

r. 4. 2 1 d

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1. 4. 4 1 4 t r,

r. 4. 6 L. 4. 7 1. 5 1. 5. 1 I. 1 MASTER TABLE OF CONTENTS Titl-e Page INTRODUCTION AND G

1. O-1 TNTRODUCTTON 1 ' 1-1 GENERAL PLANT DESCRIPTION PRINCIPAL DESIGN CRITERIA PLANT DESCRIPTION SYMBOLS USED IN ENGINEERING DRAWINGS COMPARISON TABLES COMPARISONS WITH SIMILAR FACILITY DESIGNS COMPARISON OF FINAL AND PRELIMINARY TNFORMAT ION IDENTIFICATION OF AGENTS AND CONTRACTORS CURRENT DEVELOPMENT PROGRAMS REFERENCE MATERIALS THE CLEVELAND ELECTRIC ILLUM]NATING COMPANY OWNER L.4-1' G T L B E R T A S S O C T A T E S, r N C. - A R C H T T E C T / E N C r N n s n 1. 4 - 2 GENERAL ELECTRIC COMPANY NUCLEAR STEAM S U P P L Y S Y S T E M

\\. 4 - 3 R A Y M O N D K A T S E R E N G T N E E R S, r N C.

L. 4 - 4 GENERAL ELECTRIC COMPANY TURBINE GENERATOR V E N D O R 1.. 4 - 4 NUS CORPORATION ENVIRONMENTAL CONSULTANT 1.4.5 O T H E R C O N S U L T A N T S 1 ". 4 - 6 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5-1 t.2-r L. 2 - 1,

L. 2 - L 4 L. 2 - 4 5 t a a 1. 3 - 1 L. 5-/ "

L. 4-r 1. 5 - 1 L. 6 - L L. 7. 7 Revi-sion 13 Decemberr 2003 DRAWINGS AND OTHER DETAILED INFORMATION

Section I. 7. L 7. 7. 2 1. 7. 3 1. 8 1. 9 t _. 1 0 APPENDIX 1A APPENDIX ]-B 1. V

2. t

^ 1 1 Z. I. I 2.L.2 2.r.3 2. 1. 4 z. z

2. 2. 1,

2. 2. 2

2. 2. 3 2. 2. 4

2. 3 MASTER TABLE OF CONTENTS (CONtiNUCd)

T i t l e ELECTRICAL, INSTRUMENTATION/ AND CONTROL DRAWINGS PIPING AND INSTRUMENTATION DIAGRAMS OTHER DETAILED INFORMATION NRC REGULATORY GUIDE ASSESSMENT STANDARD DESIGNS EVALUATION OF UNIT ]- OPERATTONS RESULTING FROM UNIT 2 CONSTRUCTION ACTIVITIES NUREG-O737 *TMr ACTTON PLAN REQUTREMENTS FOR APPLICANTS FOR NEW OPERATING LICENSES" PNPP LICENSE COMMITMENTS SITE CHARACTERISTIffi GEOGRAPHY AND DEMOGRAPHY SITE LOCATION AND DESCRIPTION EXCLUSION AREA AUTHORITY AND CONTROL POPULATION DISTRIBUTION REFERENCES FOR SECTION 2.I NEARBY INDUSTRIAL, TRANSPORTATION AND MILITARY F A C I L I T I E S LOCAT]ONS AND ROUTES DESCRIPTIONS EVALUATION OF POTENTIAL ACCIDENTS REFERENCES FOR SECTION 2.2 METEOROLOGY Paqe 7. 1 - 1,

I. 7 - L L. 7 - 7 t _. B - 1 1. 9 - 1 1. 1_0-1_

i n t ' \\ Y E.

I A TAB A P P. 1 8 TAB 2.0-r 2. L - 7 2. L - L z. L - 5 2.r-5 2.1-1"r 2.2-L z. z - r

2. 2-4 2. 2-27

2. 2-39 2. 3-L Revision 14 O c t o b e r, 2 0 0 5 l_1

Section

2. 3. 7

2. 3. 2

2. 3. 3

2. 3. 4

2. 3. 6

2. 4

2. 4. 1 z. +. 2 2. 4. 3 2. 4. 4 2. 4. 5 2. 4. 6 2. 4. 7 2. 4. B 2. 4. 9 2.4.r0 2. 4. I L 2. 4. L 2

2. 4. 1, 3

2. 4. 14 MASTER TABLE OF CONTENTS (Continued)

'1'rcl-e REGIONAL CLIMATOLOGY LOCAL METEOROLOGY ONSITE METEOROLOGICAL MEASUREMENT PROGRAM SHORT TERM (ACCIDENT) DIFFUSION ESTIMATES LONG TERM (ROUTINE RELEASE) DIFFUSION ESTIMATES REFERENCES FOR SECTION 2.3 HYDROLOGIC ENGINEERING HYDROLOGIC DESCRIPTION FLOODS PROBABLE MAXIMUM FLOOD ( PMF) ON STREAMS AND RIVERS POTENTIAL DAM FAILURES, SEISMICALLY INDUCED PROBABLE MAXIMUM SURGE FLOODING PROBABLE MAXIMUM TSUNAMI FLOODING ICE EFFECTS COOLING WATER TUNNELS AND OFFSHORE STRUCTURES CHANNEL DIVERSIONS FLOODING PROTECTION REQUIREMENTS LOW WATER CONSIDERATTONS DISPERSION,

DILUTION, AND TRAVEL TIMES OF ACCIDENTAL RELEASES OF RADIOACTIVE EFFLUENTS IN LAKE ERIE GROUNDWATER TECHNICAL SPECIFICATION AND EMERGENCY OPERATION REQUIREMENTS Page 2.3-1, 2. 3-L7 2.3 2. 3-40

2. 3-43 2. 3-41 2. 4-L 2. 4-1, 2. 4-4 2. 4-1 2.4-rr 2. 4-1-2 2. 4-45 2. 4-45 2. 4-41

2. 4-50

2. 4-50 2. 4-5L 2. 4 - 6 2 2. 4 - 6 5 1 1 -

2. 4 - L L t Revision 12 January l 2403 1a l_

S e c t i o n 2. 4. L 5 2. 4. L 6 2. 5 2. 5. 7 2. 5. 2 2. 5. 3 2. 5. 4 2. 5. 5 2. 5. 6 2. 5. 7 APPENDIX 2A APPENDIX 29 APPENDIX 2C APPENDIX 2D APPEND]X 2E

3. 1 MASTER TABLE OF CONTENTS (Continued)

T i t l e LIST OF PERSONS AND AGENCIES INTERVIEWED REFERENCES FOR SECTION 2.4 GEOLOGY, SEISMOLOGY AND GEOTECHNICAL ENGINEERING BASIC GEOLOGIC AND SEISMIC INFORMATION V]BRATORY GROUND MOTION SURFACE FAULTING STABILITY OF SUBSURFACE MATERIALS AND FOUNDATIONS STABILITY OF SLOPES EMBANKMENTS AND DAMS REFERENCES FOR SECTION 2.5 ANNUAL JOINT FREQUENCY DISTRIBUTIONS FOR CLEVELAND AND ERIE MONTHLY AND ANNUAL JOINT FREQUENCY D I S T R I B U T I O N S F O R P N P P, l O - M W I N D S MONTHLY AND ANNUAL JOINT FREQUENCY D I S T R I B U T I O N S F O R P N P P, 6 O - M W I N D S BEDROCK DEFORMATION IN THE COOLING WATER TUNNEL SOIL AND ROCK BORINGS DESIGN OF STRUCTUR AND SYSTEMS CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA Page 2. 4 - L 1 1 2. 4 - 1 2 0 2.5-r 2. 5 - 7 2. 5 - L L 1 2. 5 - 1 6 1 2. 5 - 1 8 1 2. 5 - 2 6 5 2. 5 - 2 1 0 2. 5 1 0 A P P. 2 A TAB A P P. 2 B TAB

^ a A E E.

/. V TAB A P P.

TAB A P P.

TAB 3. 1 - 1 3. l _ - 1 Revi-sion t2 January l 2043 2D 2E l_v

Section

3. 1. 1

3. L. 2 3. t

3. 2. 1,

3. 2. 2

3. 2. 3

3. 2. 4

3. 2. s

3. 3

3. 3. 2

3. 3. 3

? A

3. 4. L

3. 4. 2

3. 4. 3

3. 5

3. 5. 1

3. 5. 2

3. 5. 3

3. 5. 4 MASTER TABLE OF CONTENTS (Continued)

'.t-'t_ t l-e

SUMMARY

DESCR]PTION CRITERION CONFORMANCE CLASSIFICATION OF STRUCTURESCOMPONENTS AND SYSTEMS SEISMIC CLASSIFICATION SYSTEM QUALITY GROUP CLASSIFICATIONS SYSTEM SAFETY CLASSIFICATIONS QUALITY ASSURANCE CORRELATION OF SAFETY CLASSES WITH INDUSTRY U\\JLJT-J WIND AND TORNADO LOADS WIND LOADINGS TORNADO LOADINGS REFERENCES FOR SECTION 3.3 WATER LEVEL (FLOOD) DESIGN FLOOD PROTECTION ANALYTICAL AND TEST PROCEDURES FLOOD FORCE APPLICATION M I S S I L E P R O T E C T I O N M I S S I L E S E L E C T I O N A N D D E S C R I P T I O N STRUCTURES, SYSTEMS AND COMPONENTS TO BE PROTECTED FROM EXTERNALLY GENERATED MISSILES BARRIER DESIGN PROCEDURES REFERENCES FOR SECTION 3.5 Page

3. 1_-1

3. L-2 3. 2-t

3. 2-1, 3. 2-3 3. 2-3

3. 2-9

3. 2-10

3. 3-1

3. 3-1

3. 3-3 3. 3-1

3. 4-1 3. 4-L

3. 4-3

3. 4-4

3. 5-1

3. 5-1

3. 5-19

3. 5-20 3. 5-22 R e v i s i o n L 2 J a n u a r y, 2 0 0 3

S e c t i o n

3. 6

3. 6. 1

3. 6. 2 3. 6. 3 3. 7. 1 3. 1. 2

< l 3. 1. 4 3. 7. 5 3. 8 3. 8. 0 3. 8. 1 3. 8. 2 3. 8. 3 3. 8. 4 3. 8. 5 3. 8. 6 3. 9 3. 9. 1 3. 9. 2 MASTER TABLE OF CONTENTS (CONI1NUEd) m. i f ' l

^

PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING POSTULATED PIPING FAILURES IN FLUID SYSTEMS DETERMINATION OF BREAK LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING REFERENCES FOR SECTION 3.5 S E I S M I C D E S I G N S E I S M I C I N P U T SEISMIC SYSTEM ANALYSIS SEISMIC SUBSYSTEM ANALYSIS SEISMIC INSTRUMENTATION REFERENCES FOR SECTION 3.1 DESIGN OF CATEGORY I STRUCTURES GENERAL DESCRIPTION CONCRETE CONTAINMENT STEEL CONTAINMENT INTERNAL CONCRETE AND STEEL STRUCTURES OTHER SEISMIC CATEGORY I STRUCTURES FOUNDATIONS AND CONCRETE SUPPORTS REFERENCES FOR SECTION 3.8 MECHANICAL SYSTEMS AND COMPONENTS SPECIAL TOPICS FOR MECHANICAL COMPONENTS DYNAMIC TESTING AND ANALYSIS Page 3. 6 - 1 3. 5 - 1 3. 6 - 9 3. 6 - 8 3 3. 7 - r _

3. 7 - 1 3. 1 - 5 3. 1 - 2 5 3. ' 7 - 4 4 3. 7 - 5 3 3. 8 - 1 3. B - 1 3. 8. 4 3. 8 - 9 5 3. 8 - 1, 4 7 3. B - 1 9 9 3. 8 - 2 1 3 3. 8 - 2 9 1 3. 9 - 1 3. 9 - 1 _

3. 9 - 5 0 Revi-sion 1'2

January, 2A03 vl_

Section 3. 9. 3 3. 9. 4 3.9.s 3. 9. 6 3. 9. 7 3. 1 0

? 1 n 1 3. L 0. 2 t t l

3. 10. 4

3. 10. 5

3. 11

3. 11. 1 3. 1, L. 2

3. 11. 3

3. 11. 4

3. 11. 5

3. 11. 6 MASTER TABLE OF CONTENTS (CONtiNUCd)

Titl-e ASME CODE CLASS L, 2,

AND 3 COMPONENTS/

COMPONENT SUPPORTS AND CORE SUPPORT STRUCTURES CONTROL ROD DRIVE SYSTEM REACTOR PRESSURE VESSEL INTERNALS INSERVICE TESTING OF PUMPS AND VALVES R E F E R E N C E S F O R S E C T I O N 3. 9 SEISMIC AND DYNAMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT SEISMIC AND DYNAMIC QUALIFICAITON CRITERIA METHODS AND PROCEDURES FOR SEISMIC AND DYNAMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT METHODS AND PROCEDURES FOR SE]SMIC AND DYNAMIC QUALIFICATION OF SUPPORTS OF MECHANICAL AND ELECTRICAL EQUIPMENT SEISMIC AND DYNAMIC QUATIFICATION RESULTS R E F E R E N C E S F O R S E C T I O N 3. 1 0 ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT EQUIPMENT IDENTIFICATION AND ENVIRONMENTAL CONDITIONS ENVIRONMENTAL QUALIFICATION PROGRAM ACCEPTANCE CRITERIA QUALIFICATION TESTS RESULTS LOSS OF VENTILATION ESTIMATED CHEMICAL AND RADIATION ENVIRONMENT REFERENCES FOR SECTION 3. ]-1 Page 3. 9 - 9 9 3. 9 - 1 4 8 3. 9 - 1 5 1

^ n 1 - A J. Y - I l U

3. 9-170

3. 1_0 3. 10-3 J. I U - Y

3. 10-17 3. r0-22

3. 10-23 3. 11-l_

3. 11-1

3. 11_-6

3. 11-33

3. 1_1-36

3. 11-40 J. I I - 4 J Revi-sion L2

January, 2003 v1l_

S e c t i o n APPENDIX 3A APPENDIX 38 4. U 4. I 4. L. 1,

4. L. 2 4. 1,. 4 4. 1. 5

+. 2 4. 2. 1 4. 2. 2 4. 2. 3 4. 2. 4 4. 2. 5 4. 2. 6 4. 3

4. 3. r

4. 3. 2

4. 3. 3

4. 3. 4

4. 3. 5 MASTER TABLE OF CONTENTS (Continued)

T i t l e HYDRODYNAMIC LOADS FOR PNPP CONTAINMENT LOADS BEASIAB

SUMMARY

DESCRIPTION REACTOR VESSEL REACTOR INTERNAL COMPONENTS REACTIVITY CONTROL SYSTEMS ANALYSIS TECHNIQUES R E F E R E N C E S F O R S E C T I O N 4. L FUEL SYSTEM DESIGN GENERAL AND DETAILED DESIGN BASES DESCRIPTION AND DESIGN DRAWINGS DESIGN EVALUATIONS TESTING, INSPECTION AND SURVEILLANCE PLANS OPERATING AND DEVELOPMENTAL EXPERIENCE REFERENCES FOR SECTION 4.2 NUCLEAR DESIGN DESIGN BASES DESCRIPTION ANALYTICAL METHODS CHANGES REFERENCES FOR SECTION 4.3 Page

- n A Y E.

J A TAB A P P. 3 8 TAB 4. L - L 4. L - T 4. L-1, 4. 1 - B 4.r-9 i

1 1 A q.

r - r 4 I 4. 2 - L 4. 2 - t 4. 2 - 7 4. 2 - 5 4. 2 - 6 4. 2 - 6 4. 2 - 6 4. 3 - 1 4.3-r A '2. -1 4. 5 - L Z 4. 3 - ! 2 4. 3 - 1 3 Revision L2

January, 2003 vt_ l-.]-

MASTER TABLE OF CONTENTS (Continued)

Titl-e THERMAL AND HYDRAULIC DESIGN Page 4. 4 - L 4.4-r Section 4. 4 4. 4. L 4. 4. 2 4. 4. 3 4. 4. 4 4. 4. 5 4. 4. 6

/ q.

A q

1

4. 5. 2

4. 5. 3 t

^ 4.

4. 6 4. 6. L 4. 6. 2 4. 6. 3 4. 6. 4 4. 6. 5 4. 6. 6 5. 1 DESIGN BASIS D E S C R I P T I O N O F REACTOR CORE D E S C R I P T I O N O F DESIGN OF THE EVALUAT ION THE THERMAL AND REACTOR COOLANT HYDRAULIC SYSTEM THERMAL.HYDRAULIC DESIGN OF THE TESTING AND VERIFICATION INSTRUMENTAT ION REQUI REMENTS REACTOR MATERIALS CONTROL ROD DRIVE SYSTEM STRUCTURAL MATERIALS REACTOR INTERNAL MATERIALS CONTROL ROD DRIVE HOUSING SUPPORTS REFERENCES FOR SECTION 4.5 FUNCTIONAL DESIGN OF REACTIVITY C O N T R O L S Y S T E M S 4. 6. 1 4. 4 - 4 4.4-r0 4.4-1r 4.4-r2 4

q - l 4. 5 - 1 4. 5 - 8 4. 5 - L 4 4. 5 - 1 5 INFORMATION FOR CRDS EVALUATIONS OF THE CRDS TESTING AND VERIFICATION OF THE CRDS INFORMATION FOR COMBINED PERFORMANCE OF REACTIVITY CONTROL SYSTEMS EVALUATION OF COMBINED PERFORMANCE R E F E R E N C E S F O R S E C T I O N 4. 6 REACTOR COOLANT SY

SUMMARY

DESCRIPTION 4. 5 - L 4. 6 - 2 5 4. 6 - 4 3 4. 6 - 5 0 4. 6 - 5 1 4. 6 - 6 r 5. 1 - 1 5. 1 - 1 _

Revisi-on 1,'l

October, 201,1" 1 X

MASTER TABLE OF CONTENTS (CONIiNUEd)

S e c t i o n q 1 1 J. l -. J -

5. 1. 2

\\ l

5. 2 5. 2. 1,

5. 2. 2

5. 2. 3

5. 2. 5

5. 2. 6 q ?

q ? 1

5. 3. 2

5. 3. 4 C, A

\\ A 1 q. / a 5. 4. 4 C - 4 t r.

5. 4. 6 T i t I e SCHEMATIC FLOW DIAGRAM PIPING AND INSTRUMENTATION DIAGRAM ELEVATION DRAWINGS INTEGRITY OF REACTOR COOLANT PRESSURE COMPLIANCE WITH CODES AND CODE CASES OVERPRESSURIZATION PROTECTION REACTOR COOLANT PRESSURE BOUNDARY MATERIALS INSERVICE EXAMINATION AND PRESSURE TESTING OF REACTOR COOLANT PRESSURE BOUNDARY DETECTION OF LEAKAGE THROUGH REACTOR COOLANT PRESSURE BOUNDARY REFERENCES FOR SECTION 5.2 REACTOR VESSEL REACTOR VESSEL MATERIALS PRESSURE-TEMPERATURE LIMTTS REACTOR VESSEL INTEGRITY REFERENCES FOR SECTION 5.3 COMPONENT AND SUBSYSTEM DESIGN REACTOR RECIRCULATION PUMPS STEAM GENERATORS ( PWR)

REACTOR COOLANT PIPING MAIN STEAM LINE FLOW RESTRICTORS MAIN STEAM LINE ISOLATION SYSTEM REACTOR CORE ISOLATION COOLING SYSTEM Page 5. L - 4 5. 1 - 4 5. 1 - 5 BOUNDARY 5.2.I 5. 2-1,

5. 2-4 5.2-25

5. 2-43

5. 2-53 5. 2-1 9

5. 3-1

5. 3-1

5. 3-13

5. 3-16

5. 3-28

5. 4-1 5. 4-r

5. 4-B

5. 4-B

5. 4-B

5. 4-11 5. 4-20 Revision L2

January, 2003

Section 5. 4. 7 5. 4. 8 5. 4. 9 q

A 1 n J.

?

. I V t r - A 1 1 J.

A

. I I 5. 4. 1 2 5. 4. 1 3 5. 4. 1 4 5. 4. 1 5 6. 0 6.r 6. 1. 1 6. L. 2 6 ' 1 ?

5. 2 6. 2. 1 _

6. 2. 2 6. 2. 3 6. 2. 4 6. 2. 5 6. 2. 6 6. 2. 1 6. 2. 8 MASTER TABLE OF CONTENTS (CONtiNUCd)

T i t l e RESIDUAL HEAT REMOVAL SYSTEM REACTOR WATER CLEANUP SYSTEM MAIN STEAM LINE AND FEEDWATER PIPING PRESSURI ZER PRESSURIZER RELIEF DISCHARGE SYSTEM VALVES SAFETY AND RELIEF VALVES COMPONENT SUPPORTS REFERENCES FOR SECTION 5.4 ENGINEERED SAFETY ENGINEERED SAFETY FEATURE MATERIALS METALLIC MATERIALS ORGANIC MATERIALS R E F E R E N C E S F O R S E C T I O N 6. 1 CONTAINMENT SYSTEMS CONTAINMENT FUNCTIONAL DESIGN CONTAINMENT HEAT REMOVAL SYSTEM SECONDARY CONTAINMENT FUNCTIONAL DESIGN CONTAINMENT ISOLATION SYSTEM COMBUSTIBLE GAS CONTROL TN CONTAINMENT CONTAINMENT LEAKAGE TESTING SUPPRESSION POOL MAKEUP SYSTEM HYDROGEN CONTROL SYSTEM Page 5. 4 - 3 9 5. 4 - 5 5 5. 4 - 6 0 5. 4 - 6 2 5. 4 - 6 2 5. 4 - 6 2 5. 4 - 6 5 5. 4 - 6 6 5. 4 - 6 8 6. 1 - 1

6. r--1 6, 1 - 1 6. L - 7 6.r-9 6.2-r 6. 2 - L 6. 2 - 5 9 6. 2 - 7 0 6. 2 - 1 I a

^

a 1 ^

o. z - L L z

6. 2-126 6. 2-L32

6. 2-1, 42 Revision 1,2 Januaryr 2003 xt_

Section

6. 2. 9

6. 3 b. J. t -

6. 3. 2 A ? ?

6. 3. 4 6. 3. 5 5. 3. 6 6. 4 6.4.r 6. 4. 2 6. 4. 3 6. 4. 4 6. 4. 5 6. 4. 6 5. 5 6. 5. 1 _

6. 5. 2 6. 5. 3 6. 5. 4 6. 5. 5 6. 6. 1.

MASTER TABLE OF CONTENTS (CONI1NUCd)

Titl-e REFERENCES FOR SECTION 6.2 EMERGENCY CORE COOLING SYSTEM DESIGN BASES AND

SUMMARY

DESCRIPTION S Y S T E M D E S I G N PERFORMANCE EVALUAT ]ON TESTS AND INSPECTIONS INSTRUMENTAT ION REQU I REMENTS R E F E R E N C E S F O R S E C T I O N 6. 3 HABITABILITY SYSTEMS DESIGN BASES SYSTEM DESIGN SYSTEM OPERATIONAL PROCEDURES DESIGN EVALUATION TESTING AND INSPECTION INSTRUMENTAT ION REQUIREMENTS FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS ENGINEERED SAFETY FEATURES (ESF) FILTER SYSTEMS CONTAINMENT SPRAY SYSTEM Page 6. 2 - L 5 0 6. 3 - 1 6. 3 - 1 6. 3 - 9 6. 3 - 3 9 6. 3 - 5 2 6. 3 - 5 7 6. 3 - 5 8 6. 4 - r 6.4-r 6. 4 - 4 6. 4 - L 2 6. 4 - L 4 6. 4 - 1, 8 6. 4 - 1 " 9 a 6. 5 - 1 6. 5 - 1 6. 5 - 9 6. 5 - 1 5 FISSION PRODUCT CONTROL SYSTEMS ICE CONDENSER AS A FISSION PRODUCT SYSTEM R E F E R E N C E S F O R S E C T I O N 6. 5 INSERVICE INSPECTION OF CLASS 2 AND CLEANUP 6. 5 - 2 4 6. 5 - 2 4 3 COMPONENTS 6.6_7 COMPONENTS SUBJECT TO EXAMINATION 6. 6 - 7 Revision L7

October, 2011 x 1 1

S e c t i o n 6. 6. 2 6. 6. 3 6. 5. 4 6. 6. 5 6. 6. 6 6. 6. 1 5. 6. 8 6 ' 7 6. 8 h x l 6. 8. 2 5. 8. 3 6. 8. 4 6. 8. 5 6. 9 5. 9. 1 6. 9. 2 6. 9. 3 6. 9. 4 6. ' q q 1. 0

1. 7 MASTER TABLE OF CONTENTS (Continued) m. i + - 1 ^

I I L I C A C C E S S I B I L I T Y EXAMINATION TECHNIQUES AND PROCEDURES INSPECTION INTERVALS EXAMINATION CATEGORIES AND REQUIREMENTS EVALUATION OF EXAMINATION RESULTS SYSTEM PRESSURE TESTS AUGMENTED INSERVICE INSPECTION TO PROTECT AGAINST POSTULATED PIPING FAILURES MAIN STEAM LINE ISOLATION VALVE LEAKAGE CONTROL SYSTEM SAFETY-RELATED INSTRUMENT AIR SYSTEM DESIGN BASES S Y S T E M D E S I G N DESIGN EVALUATION TESTS AND INSPECTIONS INSTRUMENTAT ION REQUIREMENTS FEEDWATER LEAKAGE CONTROL SYSTEM DESIGN BASES SYSTEM DESCRIPTION DESIGN EVALUATION TESTS AND INSPECTIONS INSTRUMENTATION REQUIREMENTS INSTRUMENTATION A INTRODUCTION Page 6. 6 - L 6. 6 - 1 6. 6 - 2 6. 6 - 2 6. 6 - 2 6. 6 - 3 6. 6 - 3 6. 1 - 1 6. B - 1 _

6. 8 - 1 _

6. B - 1 _

6. B - 3 6. 8 - 4 6. 8 - 5 6. 9 - L 6. 9 - 1,

6. 9 - 2 6. 9 - 5 6. 9 - 6 6. 9 - 6 7.7-r 7.1-r Revision L2 J a n u a r y, 2 0 0 3 xl_ t_ l_

Section 1. 7. L 7. 1. 2 7. 1. 3 1. 2 1.2.r 1.2.2 1.3 1. 3. L t. 5. 2 1. 4 1.4.r

' 1 A )

1 t r 1. 5. 2 1. 6 1. 6. 1,

7. 6. 2 1. 1 7. 7. I 1. 1. 2 a n MASTER TABLE OF CONTENTS (CONTiNUCd)

Titl-e IDENTIFICATION OF SAFETY-RELATED SYSTEMS IDENTIFICATION OF SAFETY CRITERIA PLANT PROTECT]ON SYSTEM-ELECTRONIC TRIP SYSTEM REACTOR TRIP SYSTEM REACTOR PROTECTION S Y S T E M ( R P S )

DESCRI PT ION ANALYS I S ENGINEERED SAFETY FEATURE SYSTEMS D E S C R I P T I O N ANALYS IS SYSTEMS REQUIRED FOR SAFE SHUTDOWN DESCRI PT ION ANALYSIS SAFETY-RELATED DISPLAY INSTRUMENTATTON DESCRIPTION ANALYS I S ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY D E S C R I P T I O N ANALYS IS CONTROL SYSTEMS NOT REQUIRED FOR SAFETY D E S C R I P T I O N ANALYS I S ELECTRIC POWER Page 7. 7 - L 1. I - 1 1. 1 " - L 1 1. 2 - t

- 4 n t. z - L 7. 2 - 2 2

?. 3 - 1 7. 3 - 1 7. 3 - 6 8 7. 4 - I 1. 4 - 1,

" 7. 4 - 2 7 7. 5 - 1 7. 5 - 1 7. 5 - 1 _ 1 7. 6 - 1,

7. 6 - I 1. 6 - 4 8 1. 1 - L 1. 1 - 1,

7. 7 - 5 0 8. 1 - 1 Revision L2

January, 2043 XI-V

Section B. l _

8. 1. 1 d. L. z

8. 2 n 4 1 o. z. t d. z. z

8. 3 R ? 1 8. 3. 2 8. 3. 3 8. 3. 4 9. 1 9. 1. 1 9. 1,. 2 9. 1. 3 9. 1,. 4 9 l a - \\

9. 2 9. 2. r

9. 2. 2 9. 2. 3 MASTER TABLE OF CONTENTS (Continued)

't_'r_ t l-e INTRODUCTION SAFETY LOADS R E F E R E N C E S F O R S E C T I O N 8. 1 OFFSITE POWER SYSTEM DESCRIPTION ANALY S I S ONSITE POWER SYSTEMS AC POWER SYSTEMS DC POWER SYSTEMS FIRE PROTECTION FOR CABLE SYSTEMS R E F E R E N C E S F O R S E C T I O N 8. 3 AUXILIARY SYSTEMS FUEL STORAGE AND HANDLING NEW FUEL STORAGE SPENT FUEL STORAGE SPENT FUEL POOL COOLING AND CLEANUP SYSTEM FUEL HANDLING SYSTEM CONTROL OF HEAVY LOADS OVER OR NEAR SPENT FUEL AND OTHER CRITICAL PLANT SYSTEMS/COMPONENTS REFERENCES FOR SECTION 9.I WATER SYSTEMS EMERGENCY SERVICE WATER SYSTEM EMERGENCY CLOSED COOLING SYSTEMS DEMINERALIZED WATER MAKEUP SYSTEM Page 8. 1 - 1 B. T - 2 8. 1 - 3 8. 2 - t I. 2 - 1 8. 2 - 6 8. 3 - 1 8. 3 - 1 U. J - Y U 8. 3 - 1 0 0 8. 3 - 1 0 1 9. 1 - 1 9. 1 - 1 9. 1 - 1 9. 1 - B A N 9. L - Z Y 9.1,- 41, 9. 1 - 8 2 o 1 - a ?

J. L 9.2-r 9.2-r 9.2-23 9.2-35 Revision 1'2

January, 2003

Section 9. 2. 4 9. 2. 5 9. 2. 6 9. 2. 7 9. 2. 8 o ) o 9. 2. L 0 9. 3. 1 9. 3. 2 9. 3. 3 9. 3. 4 9. 3. 5 q ? 6 9. 3. 1 v < x 9. 4 9. 4. 7 Y. +. 2 9. 4. 3 9. 4. 4 a A q,

9. 4. 6 MASTER TABLE OF CONTENTS (ContiNUEd) m. : r ' l

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I. L L. L C POTABLE WATER SYSTEM ULTIMATE HEAT SINK CONDENSATE STORAGE FACILITIES SERVICE WATER SYSTEM NUCLEAR CLOSED COOLING SYSTEM TURBINE BUILDING CLOSED COOLING SYSTEM ALTERNATE DECAY HEAT REMOVAL SYSTEM PROCESS AUXILIARIES COMPRESSED AIR SYSTEMS PROCESS SAMPLING SYSTEM EQUIPMENT AND FLOOR DRAINAGE SYSTEM CHEMICAL AND VOLUME CONTROL SYSTEM STANDBY LIQUID CONTROL (SLC) SYSTEM POST ACCIDENT SAMPLING SYSTEM ZINC INJECTION SYSTEM HYDROGEN WATER CHEMISTRY SYSTEM ArR CONDITTONTNG, HEATTNG, COOLTNG AND VENTILATING SYSTEMS CONTROL COMPLEX HVAC SYSTEMS FUEL HANDLING AREA VENT]LATION SYSTEM AUXILIARY AND RADWASTE AREA VENTILATION SYSTEMS TURBINE BUILDING ENGINEERED SAFETY SYSTEM REACTOR BUILDING AREA VENTILATION SYSTEM FEATURES VENTILATION VENTILATION xvi Page 9. 2 - 3 7 9. 2 - 3 9 9. 2 - 4 3 9. 2 - 4 6 9. 2 - 5 0 9. 2 - 6 0 9. 2 - 6 4 9. 3 - 1 9. 3 - 1 9. 3 - 4 9. 3 9. 3 - 2 3 9. 3 - 2 3 9. 3 - 3 7 9. 3 - 4 2 9. 3 - 4 3 9. 4 - L 9. 4 - L 9. 4 - 2 0 9. 4 - 2 7 9. 4 - 4 4 9. 4 - 5 5 9. 4 - 6 8 Revision 18 O c t o b e r, 2 A L 3 SYSTEMS

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q 1 1 APPENDIX 1 0. 0 1 0. 1 I U. Z MASTER TABLE OF CONTENTS (COntiNUCd)

T i t I e INTERMEDIATE BUILDING VENTILATION SYSTEM TURBINE POWER COMPLEX VENTILATION SYSTEM CHILLED WATER SYSTEMS BUILDING HEATING SYSTEM OFFGAS CHARCOAL VAULT REFRIGERATION SYSTEM MISCELLANEOUS NONSAFETY HVAC SYSTEMS OTHER AUXILIARY SYSTEMS FIRE PROTECTION SYSTEM COMMUNICATIONS SYSTEMS LIGHTING SYSTEMS DIESEL GENERATOR FUEL OIL STORAGE AND TRANSFER SYSTEM DIESEL GENERATOR COOLING WATER SYSTEM DIESEL GENERATOR STARTING AIR SYSTEM DIESEL GENERATOR LUBRICATION SYSTEM DIESEL GENERATOR COMBUSTION AIR INTAKE AND EXHAUST SYSTEM HIGH PRESSURE CORE SPRAY DIESEL GENERATOR AUXIL]ARY STEAM SYSTEM REFERENCES FOR SECTION 9.5 9A FIRE PROTECTION EVALUATION REPORT STEAM AND POWER CONV

SUMMARY

DESCRIPTION Page 9. 4 - 9 0 9. 4 - 9 9 9. 4 - 1 0 3 9. 4 - 7 L 1 9. 4 - 1 2 1 9. 4 - L 4 2 9. 5 - 1 9. 5 - 1 9. 5 - 3 0 9. 5 - 3 5 9. 5 - 4 1 9. 5 - 5 1 9. 5 - 5 8 9. s - 6 3 9. 5 - 5 8 9. 5 - 7 1 9. 5 - 1 0 7 9. 5 - 1 0 9 A P P. 9 A TAB 1 0. l _ - 1 1 0. 1 - 1 L 0. 2 - 1,

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J. - L L. L E DESIGN BASES DESCRI PT ION TURBINE DISK INTEGRITY EVALUAT ION HYDROGEN AND CARBON DIOXIDE REFERENCES FOR SECTION 1.0.2 MAIN STEAM SUPPLY SYSTEM SYSTEMS DESIGN BASES D E S C R I P T I O N EVALUAT ION INSPECTION AND TESTING REQUIREMENTS WATER CHEMISTRY ( PWR)

STEAM AND FEEDWATER SYSTEM MATERIALS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM MAIN CONDENSER MAIN CONDENSER EVACUATION SYSTEM TURBINE GLAND SEALING SYSTEM TURBINE BYPASS SYSTEM CIRCULATING WATER SYSTEM CONDENSATE CLEANUP SYSTEM CONDENSATE AND FEEDWATER SYSTEM STEAM GENERATOR BLOWDOWN SYSTEM AUXILIARY FEEDWATER SYSTEM D r n a

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11. 3. 4 MASTER TABLE OF CONTENTS (CONtiNUCd)

T i t l e REFERENCES FOR SECTION 10.4 nenroecrrvE wasrE m SOURCE TERMS FISSION PRODUCTS ACTIVATION PRODUCTS TRITIUM FUEL FISSION PRODUCTION INVENTORY AND FUEL EXPERIENCE PROCESS LEAKAGE SOURCES LIQUID RADWASTE SYSTEM RADIOACTIVE SOURCES IN THE GAS TREATMENT SYSTEM SOURCE TERMS FOR COMPONENT FAILURES REFERENCES FOR SECTION 11.1 LIQUID WASTE MANAGEMENT SYSTEMS DESIGN BASES SYSTEM DESCRIPTION RADIOACTIVE RELEASES REFERENCES FOR SECTION 1,I.2 GASEOUS WASTE MANAGEMENT SYSTEMS DESIGN BASES S Y S T E M D E S C R I P T I O N RADIOACTIVE RELEASES R E F E R E N C E S F O R S E C T I O N 1 1. 3 D : r r a r s Y v t 0. 4 - 4 6 1 1. 1 - 1 1 1. 1 - 1 1,1"

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I. - L L I E SOLID RADIOACTTVE WASTE MANAGEMENT SYSTEM DESIGN BASES SYSTEM DESCRIPTION REFERENCES FOR SECTION 17.4 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS DESIGN BASES S Y S T E M D E S C R I P T I O N EFFLUENT MONITORING AND SAMPLING PROCESS MONITORING AND SAMPLING RADIATION PROTECTIoN ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS REASONABLY ACHIEVAqLE (ALARA)

POLICY CONSIDERATIONS DESIGN CONSIDERATIONS OPERATIONAL CONS IDERAT IONS RADIATION SOURCES CONTAINED SOURCES AIRBORNE RADIOACTIVE MATERIAL SOURCES REFERENCES FOR SECTION 72.2 RADIATION PROTECTION DESIGN FEATURES FACI],ITY DESIGN FEATURES SHIELDING VENTILATION D : r r a L L. 4 - L 1, r. 4 - L L 1,. 4 - 4 L r. 4 - 1, 6 1 1. 5 - 1 1 1. 5 - 1 1 1 r

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i L Z. J - L L2.3-r L2.3-B L 2. 3 - L 9 Revision 13 Decemberr 2003

Section

12. 3. 4

12. 3. 5 12. 4 1, 2. 4. 1, 1, 2. 4. 2 12. 4. 3 72. 4. 4

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L Z. O - J 1 2. 6. 4 1, 2. 6. 5 1 2. 6. 6 1 2. 6. 1 MASTER TABLE OF CONTENTS (Continued)

Titl-e AREA RADIATION AND AIRBORNE MON ITORING INSTRUMENTAT ION REFERENCES FOR SECTION L2.3 DOSE ASSESSMENT RADIOACTIVITY ESTIMATES OF PERSONNEL OCCUPANCY REQUIREMENTS ESTIMATES OF ANNUAL PERSON-REM DOSES ESTIMATED INHALATION DOSES ESTIMATED ANNUAL DOSE OUTSIDE THE NUCLEAR FACILITY AT THE BOUNDARY OF THE RESTRICTED AREA R E F E R E N C E S F O R S E C T I O N L 2. 4 RADIATION PROTECTION PROGRAM ORGANIZATION EQUIPMENT, INSTRUMENTATION AND FACILITIES HEALTH PHYSICS INSTRUCTIONS DESIGN REVIEW OF PLANT SH]ELDING FOR SPACES/

SYSTEMS WH]CH MAY BE USED IN POSTACCIDENT OPERATIONS OUTSIDE CONTAINMENT INTRODUCTION RADIOACTIVE SOURCE RELEASES RADIOACTIVE SOURCE DISTRIBUTION SYSTEMS CONTAINING RADIOACTIVE SOURCES SHIELDING REVIEW AREAS REQUIRING PERSONNEL ACCESS POSTACCIDENT RADIATION ZONE DRAWINGS AND

SUMMARY

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13. 5. 2 MASTER TABLE OF CONTENTS (Continued)

. L - L L. L C REFERENCES FOR SECTION 12.6 CONDUCT OF OPERATION ORGANIZATIONAL STRUCTURE OF APPLICANT MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION OPERAT ING ORGAN I ZAT ION QUALIFICATIONS OF PERSONNEL R E F E R E N C E S F O R S E C T I O N 1 3. 1 TRAINING PROGRAM PERRY STAFF TRAINING PROGRAM LICENSED OPERATOR TRAINING PROGRAM TRAINING PROGRAMS FOR NON-LICENSED PERSONNEL PLANT ACCESS TRAINING FIRE PROTECTION TRAINING EMERGENCY PLANNING REFERENCE FOR SECTION ].3.3 REVIEW AND AUDIT Page 1 2. 6. I I 1 3. 1 - 1 I J. I. - I 1 3. 1 - 1 1 3. 1 - 1 4 4

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FENOC OVERSIGHT PLANT PROCEDURES REVIEW COMMITTEE REVIEW BOARD DEPARTMENT PROCEDURES AND INSTRUCTIONS OPERATING AND MAINTENANCE INSTRUCTIONS Revision 11 O c t o b e r, 2 0 L 1 '

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1, 4. 2.

1 5. 0 1 5. 0 10 t 1 1,2 MASTER TABLE OF CONTENTS (Continued) t'r_ t re INDUSTRIAL SECURITY SECUR]TY PLAN SECURITY ORGANIZATION SECURITY PROCEDURES INIT IAL TEST PROGMM SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY SAFETY ANALYSIS REPORTS PERRY NUCLEAR POWER PLANT TEST PROGRAM

SUMMARY

OF TEST PROGRAM AND OBJECTTVES ORGANIZATION AND STAFFING TEST PROCEDURES CONDUCT OF TEST PROGRAM REVIEW, EVALUATION AND APPROVAL OF TEST RESULTS TEST RECORDS CONFORMANCE OF THE TEST PROGRAM WITH REGULATORY G U I D E S UTILIZATION OF REACTOR OPERATING AND TESTING EXPERIENCES IN THE DEVELOPMENT OF THE TEST PROGRAM TRIAL USE OF PLANT OPERATING AND EMERGENCY PROCEDURES INTTIAL FUEL LOADING AND INITIAL CRITICALITY TEST PROGRAM SCHEDULE INDIVIDUAL TEST DESCRIPTIONS ACCIDENT ANALYSIS GENERAL Page 1 3. 6 - 1 1 _ 3. 6 - 1 4 ^ - 1 I J.

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A J - J. l _.. t 1 5. 1. 5 1 5. 1. 6 1 5. 1. 7 7 5. 2 1, 5. 2. L 1 5. 2. 2 t 5. 2. 3 L 5. 2. 4 1 5. 2. 5 L 5. 2. 6 MASTER TABLE OF CONTENTS (Continued)

T i t l e ANALYTICAL OBJECTIVE ANALYTICAL CATEGORIES EVENT EVALUATION NUCLEAR SAFETY OPERATIONAL ANALYSIS (NSOA)

RELATIONSHIP EXTENDED OPERATING DOMAINS AND MODES OF OPERATION RELOAD SAFETY ANALYSIS REFERENCES FOR SECTION 15.0 DECREASE IN REACTOR COOLANT TEMPERATURE LOSS OF FEEDWATER HEATING FEEDWATER CONTROLLER FAILURE MAXIMUM DEMAND PRESSURE REGULATOR FAILURE OPEN INADVERTENT SAFETY/RELIEF VALVE OPENING SPECTRUM OF STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT IN A PWR INADVERTENT RHR SHUTDOWN COOLING OPERATION R E F E R E N C E S F O R S E C T I O N 1 5. 1 INCREASE IN REACTOR PRESSURE PRESSURE REGULATOR FAILURE GENERATOR LOAD REJECTION T U R B I N E T R I P MSIV CLOSURE LOSS OF CONDENSER VACUUM LOSS OF AC POWER CLOSED Page 15. 0-2

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15. 2-35 Revision 13 December, 2003 xxiv

Section L 5. 2. 1 1 5. 2. 8 7 5. 2. 9 1 5. 2. 1 0 1,5.2. L1, 1 5. 3

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L - L E LOSS OF FEEDWATER FLOW FEEDWATER LINE BREAK FAILURE OF RHR SHUTDOWN COOLING LOSS OF INSTRUMENT AIR REFERENCES FOR L5.2 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE RECIRCULATION PUMP TRIP RECIRCULATION FLOW CONTROL FAILURE DECREASING FLOW RECIRCULATION PUMP SEIZURE RECIRCULATION PUMP SHAFT BREAK REFERENCES FOR SECTION 15.3 REACTIVITY AND POWER DISTRIBUTION ANOMALIES ROD WITHDRAWAL ERROR LOW POWER ROD WITHDRAWAL ERROR AT POWER CONTROL ROD MALOPERATION (SYSTEM MALFUNCTION OR OPERATOR ERROR)

ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP RECIRCULATION FLOW CONTROL FAILURE WITH INCREAS ING FLOW CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTIONS MISPLACED BUNDLE ACCIDENT SPECTRUM OF ROD EJECTION ASSEMBLIES CONTROL ROD DROP ACCIDENT (CRDA)

R E F E R E N C E S F O R S E C T I O N 1 5. 4 Dr rra 1 5. 2 - 4 1,

1 " 5

. 2 - 4 5 1, 5. 2 - 4 5 1 5. 2 - 5 3 1 5. 2 - 5 5 1 5. 3 - 1 1 5. 3 - 1 1 5. 3 - 6 1 5. 3 - 1 1 1 5. 3 - 1 5 1 5. 3 - 1 9 t _ 5. 4 - 1 1 5. 4 - 1 1, 5. 4 - 6 1 5. 4 - 1 0 1 5. 4 - 1 0 L 5. 4 - 1, 4 1 5. 4 - 1 9 1 5. 4 - 1 9 1. 5. 4 - 2 2 L 5. 4 - 2 3 1 5. 4 - 3 1 Revision 1'2 January, 2003 XXV

Section 1 5. 5 1 5. 5. 1 1 5. 5. 2 1 5. 5. 3 r-5. 6 l _ 5. 6. 1 7 5. 6. 2 1 5. 6. 3 1 5. 6. 4 1 5. 6. 5 1 5. 6. 6 L 5. 6. 1 1 5. 7 1 5. 7. 1 1, 5. 1. 2 1 q 1 ?

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6 MASTER TABLE OF CONTENTS (CONtiNUCd)

'l-'r_ c _L e INCREASE IN REACTOR COOLANT INVENTORY INADVERTENT HPCS STARTUP CHEMICAL VOLUME CONTROL SYSTEM MALFUNCTION (oR OPERATOR ERROR)

BWR TRANSIENTS WHICH INCREASE REACTOR COOLANT INVENTORY DECREASE IN REACTOR COOLANT INVENTORY INADVERTENT SAFETY/RELIEF VALVE OPENING INSTRUMENT LINE PIPE BREAK STEAM GENERATOR TUBE FAILURE STEAM SYSTEM PIPING BREAK OUTSIDE CONTAINMENT LOSS-OF-COOLANT ACCTDENTS (RESULTTNG FROM SPECTRUM OF POSTULATED PIPING BREAKS WITHIN THE REACTOR COOLANT PRESSURE BOUNDARY)

INSIDE CONTAINMENT FEEDWATER LINE BREAK OUTSIDE CONTAINMENT REFERENCES FOR SECTION 15.6 RADIOACTIVE RELEASE FROM SUBSYSTEMS AND COMPONENTS RADIOACTIVE GAS WASTE SYSTEM LEAK OR FAILURE RADIOACTIVE LIQUID WASTE SYSTEM FAILURES (RELEASE TO ATMOSPHERE)

POSTULATED RADIOACTIVE RELEASES DUE TO LIQUID-CONTAINING TANK FAILURES FUEL HANDLING ACCIDENT OUTSIDE CONTAINMENT SPENT FUEL CASK DROP ACCIDENTS FUEL HANDLING ACCIDENT INSIDE CONTAINMENT Page 1 5. 5 - 1

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APPENDIX 158 RELOAD SAFETY ANALYSIS APPENDIX 15C APPENDIX 15D APPENDIX 15E APPENDIX 15F APPENDIX 1-5G APPENDIX 1 6. 0 1 7. 0 1 ' 7 1

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I 1. 2 MASTER TABLE OF CONTENTS (ContiNUCd)

R E F E R E N C E S F O R S E C T I O N 1 5. 7 OTHER EVENTS ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS)

STATION BLACKOUT (SBO)

PLANT NUCLEAR SAFETY OPERATIONAL ANALYSIS Page 1 - 5. 7 - 3 7 t _ 5. B - 1 1 5. 8 - 1 1 5. B - 2 A P P. 1 5 A TAB A P P. 1 5 8 TAB A P P. 1 5 C TAB APP. 1.5D TAB A P P. 1 5 E TAB I

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PARTIAL FEEDWATER HEATING OPERATION ANALYSIS PNPP MAXIMUM EXTENDED OPERATING DOMAIN ANALYSIS PNPP SINGLE LOOP OPERATION ANALYSIS CONTROL SYSTEM INTERACTIONS 15H STATION BLACKOUT (SBO)

TECHNICAL SPECIFI OUALITY ASSURANCE

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QUALITY ASSURANCE DURING THE OPERATIONS PHASE xxvl-l-