ML19263C105

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Srp,Revision 1 to Table of Contents
ML19263C105
Person / Time
Issue date: 11/24/1975
From:
Office of Nuclear Reactor Regulation
To:
References
NUREG-75-087, NUREG-75-087-ERR-R01, NUREG-75-87, NUREG-75-87-ERR-R1, SRP-NUREG-75-087, SRP-NUREG-75-87, NUDOCS 7902070051
Download: ML19263C105 (12)
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Text

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e-Enclosure TRANSM.lTTAL SHEET REVISION TO NUREG-75/ 087

" Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants" (LWR Edition)

Section No. Table of Centents Revision No.

1 Filing Instructions Pages to be removed New pages to be inserted Page Number Date Page Number Date v thru xiii 11/24/75 i thru x l

O U.S. Nuclea r Regu latory Commission Office of Nuclear Reactor Regulation

STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS App.'e-Revis 1

INTRODUCTION 1

Table of Contents CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 0

1.8 Interfaces for Standard Desien CHAPTER 2 SITE CHARACTERISTICS 1

2.1.1 Site Location and Description 11/24/75 Appendix A i

2.1.2 Exclusion Area Authority and Control 1

2.1.3 Population Distribution 2.2.1-2.2.2 Identification of Potential Hazards in Site Vicinity 1

1 2.2.3 Evaluation of Potential Accidents 1

2.3.1 Regional Climatology 1

2.3.2 Local Meteorology 1

2.3.3 Onsite Meteorological Measurements Programs 1

Appendix A 11/24/75 2.3.4 Short Term Diffusion Estimates 1

2.3.5 Long-Term Diffusion Estimates 1

2.4.1 Hydrologic Description 1

Appendix A.

1 2.4.2 Floods 1

2.4.3 Probable Maximum Flood (PMF) on Streams mnd Rivers 1

2.4.4 Potential Dam Failures (Seismically-Induced) 1 2.4.5 Probsble Maximum Surge and Seiche Flooding i

2.4.6 Probable Maximum ~sunami Flooding 1

2.4.7 Ice Effects 1

2.4.8 Cooling Water Canals and Reservoirs 1

2.4.9 Channel Diversions 1

2.4.10 Flood Protectioa Requirements 1

2.4.11 Low Water Considerations 2.4.12 Dispersion, Dilution, and Travel Times of Accidental 1

Releases of Liquid Effluents in Surface Waters i

Rev. 1

TABLE OF CONTENTS (Continued)

Applicable Revision 2.4.13 Groundwater 1

BIP HMB/GSB 1 I

2.4.14 Technical Specifications and Emergency Operation Requirements 1

2.5.1 Basic Geologic and Seismic Information 1

2.5.2 Vibratory Ground Motion 11/24/75 2.5.3 Surface Faulting i

2.5.4 Stability of Subsuriace Materials and Foundations 1

2.5.5 Stability of Slopes 1

CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.2.1 Seismic Classification 11/24/75 3.2.2 System Quality Group Classification 11/24/75 BTP RSB 3-i 11/24/75 BIP RSS 3-2 11/24/75 3.3.1 Wind Loadings 1

3.3.2 Tornado loadings 1

3.4.1 Flood Protectico 1

3.4.2 Analysis Procedures 11/24/75 3.5.1.1 Internally Generated Missiles (Outside Containment) 1 3.5.1.2 Internally Generated Missiles (Inside Containment) 1 3.5.1.3 Turbine Missiles 1

Appendix A 11/24/75 3.5.1.4 Missiles Generated by Natural Phenomena 11/24/75 BTP AAB 3-2 11/24/75 3.5.1.5 Site Proximity Missiles (Except Aircraft) 11/24/75 3.5.1.6 Aircraft Hazards 11/24/75 3.5.2 Structures, Systems, and Components to be Protected from Externally Generated Missiles 1

3.5.3 Barrier Design Procedures 11/24/75 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment 11/24/75 BTP APCSB-3-1 11/24/75 3.6.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping 11/24/75 BIP MEB-3-1 11/24/75 3.7.1 Seismic Input 11/24/75 3.7.2 Seismic System Analysis 11/24/75 3.7.3 Seismic Subsystem Analysis 11/24/75 3.7.4 Seismic Instrumentation 11/24/75 3.8.1 r icrete Containment

'I'24/75 3.8.2 Steel Containment 11/24/75 Pev. 1 ii

TABLE OF CONTENTS (Continued)

Applicable Revision 3.8.3 Concrete and Steel Internal Structures of Steal or Concrete Containments 11/24/75 3.8.4 Other Seismic Category I Structures 11/24/75 3.8.5 Foundations 11/24/75 1

3.9.1 Special Topics for Mechanical Component, 3.9.2 Dynamic Testing and Analysis of Systems, Components, i

and Equipment 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures 11/24/75 3.9.4 Control Rod Drive Systems 11/24/75 3.9.5 Reactor Pressure Vessel Internals 1

3.9.6 Inservice Testing of Pumps and Valves 1

3.10 Seismic Qualification of Category I Instrumentation and Electrical Equipment i

3.11 Environmental Design of Mechanical and Electrical i

Equipment CHA_PTER 4 REACTOR 1

4.2 Fuel System Design 1

4. 3 Nuclear Design BTP CPB 4.3-1 1

4.4 Thermal and Hydraulic Design 11/24/75 Appendix 11/24/75 4.5.1 Control Rod Drive Structural Materials 1

4.5.2 Reactor Internals Materials 1

4.6 Functional Design of Reactivity Control System 11/24/75 CHAPTER 5 REACTOR COGLANT SYSTEM AND CONNECTED SYSTEMS 1

5.2.1.1 Compliance with 10 CFR K 50.55a 1

5.2.1.2 Applicable Code Cases 5.2.2 Overpressurization Protection 11/24/75

5. 2. 3 Reactor Coolant Pressure Boundary Materials 1

BTP MTEB 5-7 1

5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing 11/24/75

5. 2. 5 Reactor Coolant Pressure Boundary Leakage Detection 11/24/75 5.3.1 Reactor Vessel Materials 11/24/75 5.3.2 Pressure-Temperature Limits 11/24/75 BIP MTEB 5-2 11/24/75 5.3.3 Reactor Vessel Integrity 11/24/75 iii Rev. 1

TABLE OF CONTENTS (Continued)

Appilcable Revision 5.4 Preface 11/24/75 5.4.1.1 Pump Flywheel Integrity (PWR) 11/24/75 5.4.2.1 Steam Generator Materials 1

BIP MTEB 5-3 1

5.4.2.2 Steam Generator Inservice Inspection 11/24/75 5.4.6 Reactor Core Isolation Cooling System (BWR) 1

5. 4. 7 Residual Heat Removal (RHR) System 1

BTP RSB 5-1 1

5.4.8 Reactor Water Cleanuo System (BWR) 1 5.4.11 Pressurizer Relief Tank 1

CHAPTER 6 ENGINEERED SAFETY FEATURES 6.1.1 Engineered Safety Features Metallic Materials 1

BTP MTEB 6-1 1

6.1.2 Organic Materials 1

6.1.3 Post-Accident Chemistry 11/24/75 6.2.1 Containment functional Design 1

6.2.1.1.A PWR Dry Containments, including Subatmospheric Containments I

6.2.1.1.B Ice Condenser Containments I

6.2.1.1.C Pressure-Suppression Type BWR Containments 3

6.2.1.2 Subcompartment Analysis 1

6.2.1.3 Mass and Energy Release Analysis for Fostulated Loss-of-Coolant Accidents 11/24/75 6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures 11/24/75 6.2.1.5 Minimum Containment Pressure Analysis for Emergency Core Cooling System Performance Capability Studies 1

BTP CSB 6-1 1

6.2.2 Containment Heat Removal Systems 2

6.2.3 Secondary Continament Functional Design 1

BTP CSB 6-3 I

6.2.4 Containment Isolation System 1

BTP CSB 6-4 1

6.2.5 Combustible Gas Control in Containment 1

Appendix A 1

BTP CSB 6-2 1

6.2.6 Containment Leakage Testing 1

6.3 Emergency Core Cooling System 11/24/75 BTP RSB 6-1 11/24/75 O

Rev. 1 iv

TABLE OP CONTENTS (Continued)

Applicable Revision 1

6.4 Habitability Systems......

1 Appendix A 1

6.5.1 ESF Atmosphere Cleanup Systems 11/24/75 6.5.2 Containment Spray as a Fission Product Cleanup System.

1 6.5.3 Fission Product Control Systems.....

1 6.5.4 Ice Condenser as a Fission Product cleanup System.....

11/24/75 6.6 Inservice Inspection of Class 2 and 3 Components Main Steam Isolation valve Leakage Control 6.7 1

System (BWR)..........................

CHAPTER 7 INSTRUMENTATION AND CONTROLS 1

Instrumentation and Controls - Introduction.........

7.1 Table 7-1 Acceptance Criteria for Instrumentation 1

and Controls...

1 7.2 Reactor Trip System......

1 Appendix A.

1 7.3 Engineered Safety Features Systems.................

1 Appendix A................................

1 7.4 Systems Required for Safe Shutdown......

1 7.5 Safety-Related Display Instrumentation.........

1 All Other Instrumentation Systems Required for Safety.

7.6 1

77 Control Systems Not Required for Safety 1

Appendix 7-A Branch Technical Positions (ICSB).......

1 BTP ICSB 1 (DOR) 1 BTP ICSB 3 1

BTP ICSB 4 (PSB) 1 BTP ICSB 5 1

BTP ICSB 9................................

1 BTP ICSB 12.............

1 BTP ICSB 13.....................

1 BTP ICSB 14.

1 BTP ICSB 16.....

1 BTP ICSB 19..............

1 BTP ICSB 20................................

1 BTP ICSB 21...................................

1 BTP ICSB 22.............

1 BTP ICSB 25............................

1 BTP ICSB 26............

11/24/75 Appendix 7-B Ceneral Agenda, Station Site Visits...

Rev. 1 v

TABLE OF CONTENTS (Continued)

Applicable Revision CHAPTER 8 ELECTRIC POWER 8.1 Electric Power-Introducti a 1

Table 8-1 Acceptance Criteria for Electric Power 1

8.2 Offsite Power System 1

8.3.1 A-C Power Systems (Onsite) 1 8.3.2 D-C Power Systems (Onsite; 1

Appendix 8A Branch Technical Positions (PSB) 1 BTP ICSB 2 (PSB) 1 BTP ?CSR 4 (P5B) 1 BTP ICSB 8 (PSb) 1 STP ICSB 11 (PSB) 1 BTP ICSB 15 (PSB) 1 BTP ICSB 17 (PSB) 1 BTP ICSB 18 (PSB) 1

'HAPTE R 9 AUXILIARY SYSTEMS 9.1.1 Ne. Fuel Storage 1

9.1.2 Spent Fuel Storage 1

9.1. 3 Spent Fuel Pool Cooling and Cleanup System 11/24/75 9.1.4 Fuel Mandling System 1

BTP ASB 9-1 1

9.2.1 Station Service Water System 1

9.2.2 Reactor Auxiliary Cooling Water Systems 11/24/75 9.2.3 Demineralized Water Makeup System 1

9.2.4 Potable and Sanitary Water Systets 1

9.2.5 Ultimate Heat Sink l

BTP ASB 9-2 1

9.2.6 Condensate Storage Facilities 1

9.3.1 Compressed Air System 11/24/75 9.3.2 Process Sampling System 1

9.3.3 Equipment and Floor Drainage System 1

9.3.4 Chemical and Volume Contrcl System (PWR)

(Including Boron Recovery System) 1 9.3.5 Standby Liquid Control System (BWR) 1 9.4.1 Control Room Area Ventilation System 1

9.4.2 Spent Fuel Pool Area Ventilation System 1

9.4.3 Auxiliary and Radwa,te a na Ventilation System 1

9.4.4 Turbine Area Ventilation System 1

O Rev. 1 vi

TABLE OF CONTENTS (Continued)

Applicable Revision 9.4.5 Engineered Safety Feature Ventilation System 1

9.5.1 Fire Protection Program 2

6TP ASB 9.5.1 1

Appendix A 11/18/76 1

.5.2 Communications Systems 1

9.5.3 Lighting Systems 9.5.4 Emergency Diesel Engine Fuel Oil Storage and 1

Transfer System 9.5.5 Emergency Diesel Engine Cooling Water System 1

9.5.6 Emergency Diesel Engine Starting System 1

9.5.7 Emergency Diesel Engine Lubrication System 1

9.5.8 Emergency Diesel Engine Combustion Air Intake and 1

Exhaust System CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 10.2 Turbine Generator 1

10.2.3 Turbine Disk Integrity 11/24/75 1

10.3 Main Steam Supply System 10.3.6 Steam and Feedwater System Materials 1

10.4.1 Main Condensers 1

10.4.2 Main Condenser Evacuation System 1

i 10.4.3 Turbire Gland Sealing System 1

10.4.4 Turbine Bypass System 1

10.4.5 Circulating Water System 1

10.4.6 Condensate Cleanup Syste;a 10.4.7 Condensate and Feedwater System i

1 BTP ASB 10-2 10.4.8 Steam Generator Blawdown System (PWR) 1 1

10.4.9 Auxiliary feedwater System (PWR) 1 BTP ASB 10-1 CHAPTER 11 RADI0 ACTIVE WASTE MANAGEMENT 11.1 Source Terms 1

1 11.2 Liquid Waste Management Systems BTP ETSB 11-1 11/24/75 i

11.3 Gaseous Waste Management Systems 1

11.4 Solid Waste Management Systems BTP ETSB 11-3 1

vii Rev. 1

TABLE OF CONTENTS (Continued)

Applicable Revision 11.5 Process and Effluent Radiological Monitoring and Sampling Systems I

CHAPTER 12 RADIATION PROTECTION 12.1 Assuring That Occupational Radiation Exposures are As Low As Is Reasonably Achievable 1

12.2 Radiation Sources 1

12.3 Radiation Protection Design Features 1

12.4 Dose Asses;4 cat I

12.5 Heaith Physics Program 1

C_HADTtR 13 CONDUC; 0F OPERATIONS 13.1.1 Management and Technical Support Organization 11/24/75 13.1.2 Operating Organization 11/24/75 13.1.3 Qualifications of Nuclear Plant Personnel 11/24/75 13.2 Training I

13.3 Emergency Planning 1

Appendix A 11/24/75 13.4 Review and Audit.

11/24/75 13.5 Plant Procedures 1

13.6 Industrial Security 11/24/75 CHAPTER 14 INITIAL TEST PROGRAM 14.1 Initial Plant Test Programs - PSAR 11/24/75 14.2 Initial Plant Test Programs - FSAR 11/24/75 CHAPTER 15 ACCIDENT ANALYSIS 15.0 Introduction I

15.1 INCREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM 15.1.1-15.1.4 Decrease in Feedwater Temperature, Increase in Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve 11/24/75 15.1.5 Steam System Piping Failures Inside and Outside of Containment (PWR) 1 Appendix 1

O Rev. 1 Vili

TABLE OF CONTENTS (Continued)

Applicable Revision 15.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM 15.2.1-15.2.5 Loss of External Load, Turbine Trip, Loss of Condenser Vacuum, Closure of Main Steam Isolation Valve (BWR), and Steam Pressure Regulator Failure (Closed) 11/24/75 15.2.6 Loss of Non-Emergency A-C Power to the Station Auxiliaries 11/24/75 15.2.7 Loss of Normal Feedwater Flow 11/24/75 15.2.8 Feedwater System Pipe Breaks Inside and Outside Containment (PWR) 11/24/75 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE 15.3.1-15.3.2 Loss of Forced Reactor Coolant Flow Including Trip of Pump and Flow Contrc11er Malfunctions 11/24/75 15.3.3-15.3.4 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break i

15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES 15.4.1 Uncontrolled Control Rod Assembly Withdrawal from a Subcr~tical or Low Power Startup Condition i

15.4.2 Uncontrolled Control Rod Assembly Withdrawal at Power 1

15.4.3 Control Rod Misoperation (System Malfunction 1

or Operator Error) 15.4.4-15.4.5 Startup of an Inactive Loop or ?ecirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow 11/24/75 Rate 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant (PWR) 11/24/75 15.4.7 Inadvertent Loauing and Operation of a Fuel Assembly in an Improper Position 11/24/75 15.4.8 Spectrum of Rod Ejection Accidents (PWR) 1 11/24/75 Appendix 15.4.9 Spectrum of Rod Drop Accidents (BWR) 1 1

Appendix 15.5 INCREASE IN REACTOR COOLANT INVENTORY 15.5.1-15.5.2 Inadvertent Operation of ECCS and Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory 11/24/75 ix Rev. 1

TABLE OF CONTENTS (Continued)

Applicable Revision 15.6 DECREASE IN REACTOR COOLANT INVENTORY 15.6.1 Inadvertent Opening of a PWR Pressurizer Safety / Relief Valve or a BWR Safety / Relief Valve 11/24/75 15.6.2 Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant O'4tside Containment 1

15.6.3 Radiological Consequences of Steam Generator Tube Failure (PWR) 1 15.6.4 Radiological Consequences of Main Steam Line Failure Outside Containment (BWR)

I 15.6.5 Loss-of-Coolant Accidents Resulting ' rom Spectrum of Postulated Piping Breaks Within the Reactor Cr-lant Pressure Boundary 1

pendix A 11/24/75 Appendix P 11/24/75 Appendix C 1

Appendix 0 11/24/75 15.7 RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT 15.7.1 Waste Gas System Failure 11/24/75 15.7.2 Radioactive Liquid Waste System Leak or Failure (Release to Atmosphere) 11/24/75 15.7.3 Postulated Radioactive Release Due to Liquid-Containing Tank Failures 1

15.7.4 Radiological Consequences of Fuel Handling Accidents 11/24/75 15.7.5 Spent Fuel Cask Drop Accidents 1

15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM 15.8 Anticipated Transients Without Scram 11/24/75 Appendix 11/24/75 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.0 Technical Specifications 11/24/75 CHAPTER 17 QUALITY ASSURANCE 17.1 Quality Assurance During the Design and Construction 11/24/75 17.2 Quality Assurance During the Operations Phase 11/24/75 O

Rev. 1

e U.S. NUCLE AR REGUL ATORY COMMISSION 17 77)

BIBLIOGRAPHIC DATA SHEET NUREG-75/087

4. TITLE AND SUBTITLE LAdd Volume No. of avorterestel 2 lleeve blek)

STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS," REVISION NO. 1 TO 3 RECIPIENT'S ACCESSION NO.

SECTION TABLE OF CONTENTS

7. AUTHORGJ
5. DATE REPORT COMPLETED MONTH lvtan December 1978
9. PE RFORMING ORGANIZATION N AME AND M AILING ADDRESS (include l<c Codel DATE REPORT ISSUED

' Y9N Office of Nuclear Reactor Regulation December U. S. Nuclear Regulatory Commission 6"""''

Washington, D. C.

20555

8. (Leeve bienki
12. SPONSORING ORGANIZ ATION N AME AND M AILING ADDRESS (lactode Isp Codel 10 PROJECT /T ASKfWORK tJNIT NO.

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission ii. CONTR ACT NO.

Washington, D. C.

20555 13 TYPE OF REPORT PE RIOD COVE RE D (inclus,re detest GU10E

15. SUPPLEVENTARY NOTES
14. (Leeve birk /

Revision 1 to Section Table of Contents 5. ABSTR ACT Q00 words or lessi E6 g

Revision No. 1 to Section

/

of the Standard Review Plan incorporates changes that have been developed since the original issuance in September 1975, many of which are editorial in nature, to reflect current staff practice in the review of safety analysis reports for nuclear power plants.

17. KEY WORDS AND DOCUMENT AN ALYSIS 17a DESCRl(TORS 1

17b. IDENTIFIERS /OPEN-ENDE D TERMS 4 AV A.ABILtTY STATEMENT

19. SECURITY CLASS (This reportl
21. NO. OF P AGE S Un1imited 2c. SE CuRiTY CLASS (Thes papel
22. PRICE s

wmccomu 335(777)

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