ML23110A245
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PBAPS UFSAR APPENDIX H - CONFORMANCE TO AEC (NRC) CRITERIA TABLE OF CONTENTS SECTION TITLE H.1
SUMMARY
DESCRIPTION H.1.1 Restatement of Proposed General Design Criteria (GDC)
(July 1967)
H.2 CRITERIA CONFORMANCE H.2.1 Group I - Overall Plant Requirements (Criteria 1-5, Table H.2.1)
H.2.2 Group II - Protection by Multiple Fission Product Barriers (Criteria 6-10, Table H.2.2)
H.2.3 Group III - Nuclear and Radiation Controls (Criteria 11-18, Table H.2.3)
H.2.4 Group IV - Reliability and Testability of Protection Systems (Criteria 19-26, Table H.2.4)
H.2.5 Group V - Reactivity Control (Criteria 27-32, Table H.2.5)
H.2.6 Group VI - Reactor Coolant Pressure Boundary (Criteria 33-36, Table H.2.6)
H.2.7 Group VII - Engineered Safety Features (Criteria 37-65, Table H.2.7)
H.2.8 Group VIII - Fuel and Waste Storage Systems (Criteria 66-69, Table H.2.8)
H.2.9 Group IX - Plant Effluents (Criterion 70, Table H.2.9)
H.3 EXTENDED POWER UPRATE (EPU) GENERAL DESIGN AND OTHER CRITERIA CONFORMANCE H.3.1 MATERIALS AND CHEMICAL ENGINEERING H.3.1.1 Reactor Vessel Material Surveillance Program H.3.1.2 Pressure-Temperature Limits and Upper-Shelf Energy H.3.1.3 Reactor Internal and Core Support Materials H.3.1.4 Reactor Coolant Pressure Boundary Materials H.3.1.5 Protective Coating Systems (Paints) - Organic Materials H.3.1.6 Flow-Accelerated Corrosion H.3.1.7 Reactor Water Cleanup System H.3.2 MECHANICAL AND CIVIL ENGINEERING H.3.2.1 Pipe Rupture Locations and Associated Dynamic Effects H.3.2.2 Pressure-Retaining Component and Component Supports H.3.2.3 Reactor Pressure Vessel Internals and Core Supports H.3.2.4 Safety-Related Valves and Pumps APPENDIX H H-i REV. 26, APRIL 2017
PBAPS UFSAR H.3.2.5 Seismic and Dynamic Qualification of Mechanical and Electrical Equipment H.3.2.6 Replacement Steam Dryer Structural Integrity H.3.3 ELECTRICAL ENGINEERING H.3.3.1 Environmental Qualification of Electrical Equipment H.3.3.2 Offsite Power System H.3.3.3 Alternating Current Onsite Power System H.3.3.4 Direct Current Onsite Power System H.3.3.5 Station Blackout H.3.4 INSTRUMENTATION AND CONTROLS H.3.4.1 Reactor Protection, Safety Features Actuation, and Control Systems H.3.5 PLANT SYSTEMS H.3.5.1 Internal Hazards H.3.5.1.1 Flooding H.3.5.1.1.2 Equipment and Floor Drains H.3.5.1.1.3 Circulating Water Systems H.3.5.1.2 Missile Protection H.3.5.1.2.1 Internally Generated Missiles H.3.5.1.2.2 Turbine Generator H.3.5.1.3 Pipe Failures H.3.5.1.4 Fire Protection H.3.5.2 Fission Product Control H.3.5.2.1 Fission Product Control Systems and Structures H.3.5.2.2 Main Condenser Evacuation System H.3.5.2.3 Turbine Gland Sealing System H.3.5.3 Component Cooling and Decay Heat Removal H.3.5.3.1 Spent Fuel Pool Cooling and Cleanup System H.3.5.3.2 Station Service Water Systems H.3.5.3.3 Reactor Auxiliary Cooling Water Systems H.3.5.3.4 Ultimate Heat Sink H.3.5.4 Balance-of-Plant Systems H.3.5.4.1 Main Steam H.3.5.4.2 Main Condenser H.3.5.4.3 Turbine Bypass H.3.5.4.4 Condensate and Feedwater H.3.5.5 Waste Management Systems H.3.5.5.1 Gaseous Waste Management System H.3.5.5.2 Liquid Waste Management System H.3.5.5.3 Solid Waste Management System H.3.5.6 Additional Considerations H.3.5.6.1 Emergency Diesel Engine Fuel Oil Storage and Transfer System H.3.5.6.2 Light Load Handling System (Related to Refueling)
APPENDIX H H-ii REV. 26, APRIL 2017
PBAPS UFSAR H.3.6 CONTAINMENT REVIEW CONSIDERATIONS H.3.6.1 Primary Containment Functional Design H.3.6.2 Sub-compartment Analysis H.3.6.3 Mass and Energy Release Analysis for LOCA H.3.6.4 Combustible Gas Control in Containment H.3.6.5 Containment Heat Removal H.3.6.6 Secondary Containment Functional Design H.3.6.7 Containment Review Considerations H.3.6.7.1 Containment Isolation H.3.6.7.2 Generic Letter 89-13 H.3.6.7.3 Generic Letter 89-16 H.3.6.7.4 Generic Letter 96-06 H.3.7 HABITABILITY, FILTRATION AND VENTILATION H.3.7.1 Control Room Habitability System H.3.7.2 Engineered Safety Feature Atmospheric Cleanup H.3.7.3 Control Room Area Heating, Ventilation and Air Conditioning System H.3.7.4 Spent Fuel Pool Area Ventilation System H.3.7.5 Reactor, Turbine, Drywell and Radwaste Area Ventilation Systems H.3.7.6 Engineered Safety Feature Heating, Ventilation and Air Conditioning Systems H.3.8 REACTOR SYSTEMS H.3.8.1 Fuel System Design H.3.8.2 Nuclear Design H.3.8.3 Thermal and Hydraulic Design H.3.8.4 Emergency Systems H.3.8.4.1 Functional Design of Control Rod Drive System H.3.8.4.2 Overpressure Protection During Power Operations H.3.8.4.3 Reactor Core Isolation Cooling System H.3.8.4.4 Residual Heat Removal System H.3.8.4.5 Standby Liquid Control System H.3.8.5 Accident and Transient Analyses H.3.8.5.1 Decrease on Feedwater Temperature, Incr4ease in Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Main Steam or Safety Valve H.3.8.5.2 Decrease in Heat Removal by the Secondary System H.3.8.5.2.1 Loss of External Load; Turbine Trip; Loss of Condenser Vacuum; Closure of Main Steam Isolation Valve; and Steam Pressure Regulator Failure (Closed)
H.3.8.5.2.2 Loss of Non-Emergency AC Power to the Station Auxiliaries H.3.8.5.2.3 Loss of Normal Feedwater Flow H.3.8.5.3 Decrease in Reactor Coolant System Flow H.3.8.5.3.1 Loss of Forced Reactor Coolant Flow H.3.8.5.3.2 Reactor Recirculation Pump Rotor Seizure and Reactor Recirculation Pump Shaft Break APPENDIX H H-iii REV. 26, APRIL 2017
PBAPS UFSAR H.3.8.5.4 Reactivity and Power Distribution Anomalies H.3.8.5.4.1 Uncontrolled Control Rod Assembly Withdrawal from a Subcritical of Low Power Startup Condition H.3.8.5.4.2 Uncontrolled Control Rod Assembly Withdrawal at Power H.3.8.5.4.3 Startup of a Recirculation Loop at an Incorrect Temperature and Flow Controller Malfunction Causing an Increase in Core Flow Rate H.3.8.5.4.4 Spectrum of Rod Drop Accidents H.3.8.5.5 Inadvertent Operation of ECCS or Malfunction that Increases Reactor Coolant Inventory H.3.8.5.6 Decrease in Reactor Coolant Inventory H.3.8.5.6.1 Inadvertent Opening of a Pressure Relief Valve H.3.8.5.6.2 Emergency Core Cooling System and Loss-of-Coolant Accidents H.3.8.5.7 Anticipated Transients Without Scrams H.3.8.6 Fuel Storage H.3.8.6.1 New Fuel Storage H.3.8.6.2 Spent Fuel Storage H.3.9 SOURCE TERMS AND RADIOLOGICAL CONSEQUENCES ANALYSES H.3.9.1 Source Terms for Radwaste Systems Analyses H.3.9.2 Radiological Consequences Using Alternate Source Term H.3.10 HEALTH PHYSICS H.3.10.1 Occupational and Public Radiation Doses H.3.11 HUMAN PERFORMANCE H.3.11.1 Human Factors APPENDIX H H-iv REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX H - CONFORMANCE TO AEC (NRC) CRITERIA LIST OF TABLES TABLE TITLE H.2.1 AEC (NRC) General Design Criteria - Group I (Overall Plant Requirements)
H.2.2 AEC (NRC) General Design Criteria - Group II (Protection by Multiple Fission Product Barriers)
H.2.3 AEC (NRC) General Design Criteria - Group III (Nuclear and Radiation Controls)
H.2.4 AEC (NRC) General Design Criteria - Group IV (Reliability and Testability of Protection Systems)
H.2.5 AEC (NRC) General Design Criteria - Group V (Reactivity Control)
H.2.6 AEC (NRC) General Design Criteria - Group VI (Reactor Coolant Pressure Boundary)
H.2.7 AEC (NRC) General Design Criteria - Group VII (Engineered Safety Features)
H.2.8 AEC (NRC) General Design Criteria - Group VIII (Fuel and Waste Storage Systems)
H.2.9 AEC (NRC) General Design Criteria - Group IX (Plant Effluents)
APPENDIX H H-v REV. 26, APRIL 2017