ML21257A254

2 to Updated Final Safety Analysis Report, Chapter 01, Appendix 1C, AEC Proposed General Design Criteria for Nuclear Power Plants, Table of Contents

ML21257A254
Person / Time
Site:	Calvert Cliffs
Issue date:	09/07/2021
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
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References
NEI 99-04
Download: ML21257A254 (4)

Text

APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS PAGE 1C.0 AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR 1C.1-1 POWER PLANTS 1C.1 INTRODUCTION 1C.1-1 1C.2 OVERALL PLANT REQUIREMENTS 1C.2-1 1 QUALITY STANDARDS 1C.2-1 2 PERFORMANCE STANDARDS 1C.2-1 3 FIRE PROTECTION 1C.2-1 4 SHARING OF SYSTEMS 1C.2-1 5 RECORDS REQUIREMENTS 1C.2-1 1C.3 PROTECTION BY MULTIPLE FISSION PRODUCT BARRIERS 1C.3-1 6 REACTOR CORE DESIGN 1C.3-1 7 SUPPRESSION OF POWER OSCILLATIONS 1C.3-1 8 OVERALL POWER COEFFICIENT 1C.3-1 9 REACTOR COOLANT PRESSURE BOUNDARY 1C.3-1 10 CONTAINMENT 1C.3-1 1C.4 NUCLEAR AND RADIATION CONTROLS 1C.4-1 11 CONTROL ROOM 1C.4-1 12 INSTRUMENTATION AND CONTROL SYSTEMS 1C.4-1 13 FISSION PROCESS MONITORS AND CONTROLS 1C.4-1 14 CORE PROTECTION SYSTEMS 1C.4-1 15 ENGINEERED SAFETY FEATURES PROTECTION SYSTEMS 1C.4-1 16 MONITORING REACTOR COOLANT PRESSURE BOUNDARY 1C.4-1 17 MONITORING RADIOACTIVITY RELEASES 1C.4-1 18 MONITORING FUEL AND WASTE STORAGE 1C.4-1 1C.5 RELIABILITY AND TESTABILITY OF PROTECTION SYSTEMS 1C.5-1 19 PROTECTION SYSTEMS RELIABILITY 1C.5-1 20 PROTECTION SYSTEMS REDUNDANCY AND INDEPENDENCE 1C.5-1 21 SINGLE FAILURE DEFINITION 1C.5-1 22 SEPARATION OF PROTECTION AND CONTROL INSTRUMENTATION 1C.5-1 SYSTEMS 23 PROTECTION AGAINST MULTIPLE DISABILITY FOR PROTECTION 1C.5-1 SYSTEMS 24 EMERGENCY POWER FOR PROTECTION SYSTEMS 1C.5-1 25 DEMONSTRATION OF FUNCTIONAL OPERABILITY OF PROTECTION 1C.5-1 SYSTEMS 26 PROTECTION SYSTEMS FAIL-SAFE DESIGN 1C.5-1 1C.6 REACTIVITY CONTROL 1C.6-1 27 REDUNDANCY OF REACTIVITY CONTROL 1C.6-1 28 REACTIVITY HOT SHUTDOWN CAPABILITY 1C.6-1 29 REACTIVITY SHUTDOWN CAPABILITY 1C.6-1 CALVERT CLIFFS UFSAR 1C-i Rev. 50

APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS PAGE 30 REACTIVITY HOLDDOWN CAPABILITY 1C.6-1 31 REACTIVITY CONTROL SYSTEMS MALFUNCTION 1C.6-1 32 MAXIMUM REACTIVITY WORTH OF CONTROL RODS 1C.6-1 1C.7 REACTOR COOLANT PRESSURE BOUNDARY 1C.7-1 33 REACTOR COOLANT PRESSURE BOUNDARY CAPABILITY 1C.7-1 34 REACTOR COOLANT PRESSURE BOUNDARY RAPID PROPAGATION 1C.7-1 FAILURE PREVENTION 35 REACTOR COOLANT PRESSURE BOUNDARY BRITTLE FRACTURE 1C.7-1 PREVENTION 36 REACTOR COOLANT PRESSURE BOUNDARY SURVEILLANCE 1C.7-1 1C.8 ENGINEERED SAFETY FEATURES 1C.8-1 A. GENERAL REQUIREMENTS 1C.8-1 37 ENGINEERED SAFETY FEATURES BASIS FOR DESIGN 1C.8-1 38 RELIABILITY AND TESTABILITY OF ENGINEERED SAFETY 1C.8-1 FEATURES 39 EMERGENCY POWER FOR ENGINEERED SAFETY FEATURES 1C.8-1 40 MISSILE PROTECTION 1C.8-1 41 ENGINEERED SAFETY FEATURES PERFORMANCE CAPABILITY 1C.8-1 42 ENGINEERED SAFETY FEATURES COMPONENTS CAPABILITY 1C.8-1 43 ACCIDENT AGGRAVATION PREVENTION 1C.8-1 B. EMERGENCY CORE COOLING 1C.8-2 44 EMERGENCY CORE COOLING SYSTEMS CAPABILITY 1C.8-2 45 INSPECTION OF EMERGENCY CORE COOLING SYSTEMS 1C.8-2 46 TESTING OF EMERGENCY CORE COOLING SYSTEMS 1C.8-2 COMPONENTS 47 TESTING OF EMERGENCY CORE COOLING SYSTEMS 1C.8-2 48 TESTING OF OPERATIONAL SEQUENCE OF EMERGENCY CORE 1C.8-2 COOLING SYSTEMS C. CONTAINMENT 1C.8-2 49 CONTAINMENT DESIGN BASIS 1C.8-2 50 NIL-DUCTILITY TEMPERATURE REQUIREMENT FOR CONTAINMENT 1C.8-2 MATERIAL 51 REACTOR COOLANT PRESSURE BOUNDARY OUTSIDE 1C.8-3 CONTAINMENT 52 CONTAINMENT HEAT REMOVAL SYSTEMS 1C.8-3 53 CONTAINMENT ISOLATION VALVES 1C.8-3 54 CONTAINMENT LEAKAGE RATE TESTING 1C.8-3 55 CONTAINMENT PERIODIC LEAKAGE RATE TESTING 1C.8-3 56 PROVISIONS FOR TESTING OF PENETRATIONS 1C.8-3 57 PROVISIONS FOR TESTING OF ISOLATION VALVES 1C.8-3 CALVERT CLIFFS UFSAR 1C-ii Rev. 50

APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS PAGE D. CONTAINMENT PRESSURE REDUCING 1C.8-3 58 INSPECTION OF CONTAINMENT PRESSURE-REDUCING SYSTEMS 1C.8-3 59 TESTING OF CONTAINMENT PRESSURE-REDUCING SYSTEMS 1C.8-3 COMPONENTS 60 TESTING OF CONTAINMENT SPRAY SYSTEMS 1C.8-4 61 TESTING OF OPERATIONAL SEQUENCE OF CONTAINMENT 1C.8-4 PRESSURE-REDUCING SYSTEMS E. AIR CLEANUP 1C.8-4 62 INSPECTION OF AIR CLEANUP SYSTEMS 1C.8-4 63 TESTING OF AIR CLEANUP SYSTEMS COMPONENTS 1C.8-4 64 TESTING OF AIR CLEANUP SYSTEMS 1C.8-4 65 TESTING OF OPERATION SEQUENCE OF AIR CLEANUP SYSTEMS 1C.8-4 1C.9 FUEL AND WASTE STORAGE SYSTEMS 1C.9-1 66 PREVENTION OF FUEL STORAGE CRITICALITY 1C.9-1 67 FUEL AND WASTE STORAGE DECAY HEAT 1C.9-1 68 FUEL AND WASTE STORAGE RADIATION SHIELDING 1C.9-1 69 PROTECTION AGAINST RADIOACTIVITY RELEASE FROM SPENT 1C.9-1 FUEL AND WASTE STORAGE 1C.10 PLANT EFFLUENTS` 1C.10-1 70 CONTROL OF RELEASES OF RADIOACTIVITY TO THE 1C.10-1 ENVIRONMENT 1C.11 REFERENCES 1C.11-1 CALVERT CLIFFS UFSAR 1C-iii Rev. 50

APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS LIST OF ACRONYMS ASTM American Society for Testing and Materials GDC General Design Criteria LOCA Loss-of-Coolant Accident NDTT Nil-Ductility Transition Temperature SACM Societe Alsacienne De Constructions Mecaniques De Mulhouse CALVERT CLIFFS UFSAR 1C-iv Rev. 49