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public meetings 247
standards 204, 205

state discussions 175, 247

Westinghouse plutonium fabrication 125

Defects, noncompliance reporting 155, 204
Department of Energy (DOE)

Clinch River Breeder Reactor 98
export licensing 186, 187

Federal Radioactive Waste Study 146
gas-cooled reactors 99, 233
high-level waste repository 148, 149
mill tailings, remedial action 152
national laboratories assistance 65
NFS Erwin SNM inventory difference
NFS West Valley, N. Y. facility study 125, 126
nuclear safety information coordination 233
research to improve reactor safety 244
spent fuel shipment 137

TMI accident assistance 15, 16, 18

8, 140

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IAEA-see International Atomic Energy Agency

IE Bulletins, Circulars, Information Notices 159-166

Immediate effectiveness rule 255

Improved in-plant accident response 243
Improved reactor safety research 242-244
Incident Response Program 153, 168
Indemnity financial protection 116-118
Independent Spent Fuel Storage Facility 124

In situ solution mining 151
Industrial radiography-see Radiography
Inspection 8, 153-166

bulletins, circulars, information notices 159-166
construction 155, 166

goals, initiatives 153, 155, 157

Incident Response Program 153, 168
Independent measurement verification 157

licensee quality assurance

NRC Staff 153-155

performance appraisal 157
power reactors

155-157

reactive inspections 166

155

reporting defects, noncompliance 155, 204

resident inspection program 159

resident inspectors (tabulation) 154
safeguards 155

TMI-2 accident 157-159

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NRC Authorization Act (1979) 242

State participation in waste management 147
Lewis Risk Assessment Review Group 240
License fees 279

License revocation, suspension

-see Enforcement
Licensing process

description (reactors) 64
improving procedures 107-115
Liquid effluent dispersion 239

Liquid Pathway Generic Study 99, 100

Liquid display watches 130

Liquid Metal Fast Breeder Reactor (LMFBR) 234, 235

Litigation-see Judicial review

Load combinations study 237

LOCA-see Loss-of-coolant accident

LOFT-see Loss-of-Fluid Test Facility

Loss-of-coolant accident (LOCA) codes 227

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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
manufacturing license 97-100

materials, components standards 201, 202
need-for-facility issue 111

occupational exposure 104, 210, 211
offsite explosion protection 235

operating experience evaluation 5, 6, 275
operating licenses 63, 65, 301-311

operator licenses 65, 204

pipe cracks 82-85, 88, 89

pipe support loading 90

piping system installation 90, 91

pressure suppression containments 71-73
pressure transients

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
system interaction 77

tabulations 63, 65, 96, 97, 301-311

technical problems 86-95

technical specifications (environmental) 102
unresolved safety issues 65-86

water hammer 67, 68, 237

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