ML21257A254
| ML21257A254 | |
| 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: ML21257A254 (4) | |
Text
APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 1C-i Rev. 50 1C.0 AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS 1C.1-1 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 SYSTEMS 1C.5-1 23 PROTECTION AGAINST MULTIPLE DISABILITY FOR PROTECTION SYSTEMS 1C.5-1 24 EMERGENCY POWER FOR PROTECTION SYSTEMS 1C.5-1 25 DEMONSTRATION OF FUNCTIONAL OPERABILITY OF PROTECTION SYSTEMS 1C.5-1 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
APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 1C-ii Rev. 50 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 FAILURE PREVENTION 1C.7-1 35 REACTOR COOLANT PRESSURE BOUNDARY BRITTLE FRACTURE PREVENTION 1C.7-1 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 FEATURES 1C.8-1 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 COMPONENTS 1C.8-2 47 TESTING OF EMERGENCY CORE COOLING SYSTEMS 1C.8-2 48 TESTING OF OPERATIONAL SEQUENCE OF EMERGENCY CORE COOLING SYSTEMS 1C.8-2 C.
CONTAINMENT 1C.8-2 49 CONTAINMENT DESIGN BASIS 1C.8-2 50 NIL-DUCTILITY TEMPERATURE REQUIREMENT FOR CONTAINMENT MATERIAL 1C.8-2 51 REACTOR COOLANT PRESSURE BOUNDARY OUTSIDE CONTAINMENT 1C.8-3 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
APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 1C-iii Rev. 50 D.
CONTAINMENT PRESSURE REDUCING 1C.8-3 58 INSPECTION OF CONTAINMENT PRESSURE-REDUCING SYSTEMS 1C.8-3 59 TESTING OF CONTAINMENT PRESSURE-REDUCING SYSTEMS COMPONENTS 1C.8-3 60 TESTING OF CONTAINMENT SPRAY SYSTEMS 1C.8-4 61 TESTING OF OPERATIONAL SEQUENCE OF CONTAINMENT PRESSURE-REDUCING SYSTEMS 1C.8-4 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 FUEL AND WASTE STORAGE 1C.9-1 1C.10 PLANT EFFLUENTS`
1C.10-1 70 CONTROL OF RELEASES OF RADIOACTIVITY TO THE ENVIRONMENT 1C.10-1 1C.11 REFERENCES 1C.11-1
APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS LIST OF ACRONYMS CALVERT CLIFFS UFSAR 1C-iv Rev. 49 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