public meetings 247 state discussions 175, 247 Westinghouse plutonium fabrication 125 Defects, noncompliance reporting 155, 204 Clinch River Breeder Reactor 98 Federal Radioactive Waste Study 146 TMI accident assistance 15, 16, 18 8, 140 information exchange 183-186 technical exchanges 186 3D program, research 222, 223 International Atomic Energy Agency (IAEA) safety assistance 185, 186 technical assistance 186 transportation standards 129 International Nuclear Fuel Cycle Evaluation (INFCE) 98, 187, 188 Investigations by IA 277 Investigations by IE 168-172 Judicial review 262-271 cases concluded 264-267 cases pending 268-271 Kemeny Commission -see President's Commission Legislation civil penalties amendment 168 NRC Authorization Act (1979) 242 State participation in waste management 147 License revocation, suspension -see Enforcement description (reactors) 64 Liquid Pathway Generic Study 99, 100 Liquid display watches 130 Liquid Metal Fast Breeder Reactor (LMFBR) Litigation-see Judicial review Load combinations study 237 LOCA-see Loss-of-coolant accident LOFT-see Loss-of-Fluid Test Facility Low-level radiation effects 199, 200, 208, 238 234, 235 inspections 157-159 installation nonconformance 90, 91 interagency coordination 104-107 international safety standards 185, 186, 189, 216, 217 investigations 169-171 licensing process 64, 107-115 licensing status 63, 65 loose parts detection 231 loss of containment integrity 89, 171 loss of electric power 86 loss-of-feedwater transient 171 materials, components standards 201, 202 occupational exposure 104, 210, 211 operating experience evaluation 5, 6, 275 operator licenses 65, 204 pipe cracks 82-85, 88, 89 pipe support loading 90 piping system installation 90, 91 pressure suppression containments 71-73 80 purge-valve operability 89 quality assurance 90, 91, 113, 114, 202 qualification tests 79, 80, 203 radiation safety training 213 radiological impact 100, 101 reactor vessel integrity 75, 76, 80 regulatory priorities 1, 2 research to improve safety 242-244 resident inspectors 6, 153, 154, 159, 277 residual heat removal (post-shutdown) 80, 81 respiratory protection 210 risk assessment 66 rulemaking 107, 108 safeguarding 138, 139, 144 safety overview 3, 4 seismic design 82, 191-194 simulation 198 siting policy 102-104, 108-110 siting problems 101-104 socioeconomic impacts 110-112 spent fuel storage 81, 82, 117, 118 standard plants 95-98 standard review plans 110 standard technical specifications 101 standards 200-204 station blackout 86 status 63 steam generator supports 76, 77 steam generator tube integrity 69, 70, 230 Systematic Evaluation Program 81, 114, 115 tabulations 63, 65, 96, 97, 301-311 technical problems 86-95 technical specifications (environmental) 102 water hammer 67, 68, 237 |