ML21278A123
| ML21278A123 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/07/2021 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21278A102 | List:
|
| References | |
| NEI 99-04 | |
| Download: ML21278A123 (5) | |
Text
APPENDIX 5A STRUCTURAL DESIGN BASIS TABLE OF CONTENTS PAGE 5A.0 STRUCTURAL DESIGN BASIS 5A.1-1 5A.1 GENERAL 5A.1-1 5A.1.1 RESPONSIBLE DESIGN ORGANIZATIONS 5A.1-1 5A.1.1.1 Design Control 5A.1-1 5A.1.2 SPECIFIC REQUIREMENTS FOR SAFETY-RELATED 5A.1-2 PURCHASES 5A.2 CLASSES OF STRUCTURES, SYSTEMS, AND EQUIPMENT 5A.2-1 5A.2.1 SEISMIC CATEGORY I 5A.2-1 5A.2.1.1 Typical Category I Structures 5A.2-1 5A.2.1.2 Typical Category I Equipment and Systems 5A.2-1 5A.2.2 SEISMIC CATEGORY II 5A.2-2 5A.3 DESIGN BASES 5A.3-1 5A.3.1 CATEGORY I STRUCTURE DESIGN 5A.3-1 5A.3.1.1 Time History 5A.3-1 5A.3.1.2 Ground Spectra Curves 5A.3-1 5A.3.1.3 Confidence Limits 5A.3-2 5A.3.1.4 Amplified Response Loading for Structure and Floors 5A.3-2 5A.3.1.5 Amplified Response Loading for Equipment and 5A.3-3 Components 5A.3.1.6 Amplified Response Loading for Piping and 5A.3-3 Instrumentation 5A.3.1.7 Normal Operation 5A.3-4 5A.3.1.8 Loss-of-Coolant Accident, Seismic and Tornado 5A.3-4 Loads 5A.3.1.9 Tornado Forces 5A.3-8 5A.3.1.10 Seismic Forces (E and E') 5A.3-10 5A.3.1.11 Torsional Modes of Vibration 5A.3-10 5A.3.1.12 Foundation Isolation Joints 5A.3-12 5A.3.1.13 Soil/Foundation Interaction 5A.3-12 5A.3.1.14 Design Code References 5A.3-12 5A.3.2 SEISMIC CATEGORY I SYSTEMS AND EQUIPMENT DESIGN 5A.3-12 5A.3.2.1 Piping 5A.3-13 5A.3.2.2 Routing of Seismic Category I Piping 5A.3-14 5A.3.2.3 Equipment, Personnel, and Escape Locks 5A.3-14 5A.3.2.4 Seismic Adequacy Verification of Equipment 5A.3-15 5A.3.3 CATEGORY II 5A.3-17 5A.3.3.1 Structure Design 5A.3-17 5A.3.3.2 Systems and Equipment Design 5A.3-17 5A.3.4 COUPLED CONTAINMENT, CONTAINMENT INTERNAL 5A.3-17 STRUCTURE, AND REACTOR COOLANT SYSTEM (RCS)
SEISMIC ANALYSIS 5A.3.4.1 Methodology 5A.3-18 CALVERT CLIFFS UFSAR 5A-i Rev. 50
APPENDIX 5A STRUCTURAL DESIGN BASIS TABLE OF CONTENTS PAGE 5A.3.4.2 Results 5A.3-20 5A.
3.5 REFERENCES
5A.3-20 5A.4 LOADINGS COMMON TO ALL STRUCTURES 5A.4-1 5A.5 FLOODING 5A.5-1 5A.6 MASONRY WALL DESIGN 5A.6-1 CALVERT CLIFFS UFSAR 5A-ii Rev. 50
APPENDIX 5A STRUCTURAL DESIGN BASIS LIST OF TABLES TITLE PAGE 5A-1 CONTAINMENT SEISMIC ANALYSIS MODEL POINTS 5A.3-21 5A-2 CONTAINMENT RESPONSES BY RESPONSE-SPECTRUM 5A.3-22 TECHNIQUE FOR OBE 5A-3 CONTAINMENT RESPONSES BY RESPONSE-SPECTRUM 5A.3-23 TECHNIQUE FOR SSE 5A-4 CONTAINMENT RESPONSES BY TIME HISTORY METHOD FOR 5A.3-24 OBE 5A-5 ASSESSMENT OF PROBABILITY OF EXPOSURES IN EXCESS OF 5A.3-25 10 CFR PART 100 FOR EQUIPMENT LOCATIONS WITHOUT TORNADO-GENERATED MISSILE RESISTANT BARRIERS 5A-6 TABLE OF LOADING COMBINATIONS AND PRIMARY STRESS 5A.3-26 LIMITS FOR NUCLEAR CLASS 2 AND 3 PIPING 5A-7 USE OF CODE CASE N-392-1 (12-11-89) - EVALUATION OF THE 5A.3-28 DESIGN OF HOLLOW CIRCULAR CROSS-SECTION WELDED ATTACHMENTS ON CLASS 2 AND 3 PIPING 5A-8 DAMPING VALUES FOR ALL SEISMIC CATEGORY I 5A.3-29 STRUCTURES, SYSTEMS, AND COMPONENTS 5A-9 DAMPING VALUES FOR CONTAINMENT SEISMIC CATEGORY I 5A.3-30 STRUCTURES, SYSTEMS, AND COMPONENTS (FOR USE WITH 3-D CONTAINMENT MODEL GENERATED TIME HISTORIES AND RESPONSE SPECTRA)
CALVERT CLIFFS UFSAR 5A-iii Rev. 50
APPENDIX 5A STRUCTURAL DESIGN BASIS LIST OF FIGURES FIGURE 5A-1 RESPONSE SPECTRA OPERATING BASIS EARTHQUAKE 5A-2 RESPONSE SPECTRA OPERATING BASIS EARTHQUAKE 5A-3 RESPONSE SPECTRA OPERATING BASIS EARTHQUAKE 5A-4 RESPONSE SPECTRA OPERATING BASIS EARTHQUAKE CALVERT CLIFFS UFSAR 5A-iv Rev. 47
APPENDIX 5A STRUCTURAL DESIGN BASIS LIST OF ACRONYMS ADV Atmospheric Dump Valve AEC Atomic Energy Commission AFW Auxiliary Feedwater ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers B&PV Boiler and Pressure Vessel BGE Baltimore Gas and Electric Company CCNPP Calvert Cliffs Nuclear Power Plant CE Combustion Engineering, Inc.
EDG Emergency Diesel Generator FOST Fuel Oil Storage Tank IEEE Institute of Electrical and Electronic Engineers LOCA Loss-of-Coolant Accident MSSV Main Steam Safety Valve NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System OBE Operating Basis Earthquake RCS Reactor Coolant System SG Steam Generator SQUG Seismic Qualification Utility Group SSE Safe Shutdown Earthquake UFSAR Updated Final Safety Analysis Report USI Unresolved Safety Issue CALVERT CLIFFS UFSAR 5A-v Rev. 50