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ANSI code: ANS-3.1-1993
accession number: ML083450028
atomic element: Lead
CFR: 10 CFR 26
CFR: 10 CFR 50
CFR: 10 CFR 52
CFR: 10 CFR 2.802
CFR: 10 CFR 26.3
CFR: 10 CFR 26.4
CFR: 10 CFR 26.5, Definitions
CFR: 10 CFR 26.29
CFR: 10 CFR 26.33, Behavioral Observation
CFR: 10 CFR 26.201, Applicability
CFR: 10 CFR 26.203
CFR: 10 CFR 26.205
CFR: 10 CFR 26.207
CFR: 10 CFR 26.209
CFR: 10 CFR 50.57
CFR: 10 CFR 50.54
CFR: 10 CFR 26.211
CFR: 10 CFR 26.27#a
CFR: 10 CFR 50.54#m2iv
CFR: 10 CFR 50.54#k
CFR: 10 CFR 50.54#m
CFR: 10 CFR 50.54#m2iii
CFR: 10 CFR 26.207#a
CFR: 10 CFR 26.205#d
CFR: 10 CFR 26.205#d1
CFR: 10 CFR 26.205#d4
CFR: 10 CFR 26.205#d3
CFR: 10 CFR 26.205#c
CFR: 10 CFR 26.205#b3
CFR: 10 CFR 26.205#b
CFR: 10 CFR 26.205#d2
CFR: 10 CFR 26.205#e
CFR: 10 CFR 26.4#a
CFR: 10 CFR 26.4#a1
CFR: 10 CFR 26.4#a4
CFR: 10 CFR 26.4#a5
CFR: 10 CFR 26.205#b1
CFR: 10 CFR 52.103#g
CFR: 10 CFR 26.211#b
CFR: 10 CFR 26.211#a1
CFR: 10 CFR 26.207#a1ii
CFR: 10 CFR 26.3#c
CFR: 10 CFR 26.205#d5i
CFR: 10 CFR 26.29#a10
CFR: 10 CFR 26.27#b8
CFR: 10 CFR 26.211#c2
CFR: 10 CFR 26.203#c
CFR: 10 CFR 26.203#b1
CFR: 10 CFR 26.203#b4
CFR: 10 CFR 26.203#c2
contact: http://kanterella.com/Special:URIResolver/Orr_M/RES/415-2D6373
cornerstone: Emergency Preparedness
document: ML083110161
document: ML090080163
document: L-2008-237, Comment (2) of Robert J. Hughes for Point Beach
document: L-HU-08-022, Nuclear Industry Comments on Draft Regulatory Guide DG-5026, Fatigue Management for Nuclear Power Plant Personnel
document: ML083100592
document: ML090080138
document: ML083100594
document: ML083220199
document: ML083190386
document: ML082960428
document: ML083100595
document: LR-N08-0256, Comment (3) of Jeffrie Keenan, on Behalf of PSEG Nuclear LLC, on Draft Regulatory Guide DG-5026, Fatigue Management for Nuclear Power Plant Personnel
document: NL-08-1705, And Vogtle Electric Generating Plant, Comments on Draft Regulatory Guide DG-5026
emergency facility: Technical Support Center
emergency facility: Emergency Operations Facility
FR: 54 FR 3424
FR: 73 FR 56618
FR: 73 FR 16988
from: Office of Nuclear Regulatory Research

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