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IWB-2500 +, IWB-3522 +, IWB-3142 +  and IWA-2500 +

ASME Section XI +, ASME Section III +, ASME Section IX +, ASME Section IV +  and ASME Section VI +

Boron +, Uranium +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Lead +, Chromium +  and Tin +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 26.73 +, 10 CFR 21 +, 10 CFR 26 +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 34 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 31.5 +, 10 CFR 71 +, 10 CFR 35.41 +, 10 CFR 2 +, 10 CFR 25 +, 10 CFR 31 +, 10 CFR 171 +, 10 CFR 2.201 +, 10 CFR 2.202 +, 10 CFR 2.204 +, 10 CFR 2.205 +, 10 CFR 20.2003 +, 10 CFR 26.3 +, 10 CFR 30.10 +, 10 CFR 35.40 +, 10 CFR 50.7 +, 10 CFR 50.47 +, 10 CFR 50.71 +...

Emergency Preparedness +  and Barrier Integrity +

SECY-92-223 +, NRC 2001-01 +, 1CAN090102 +, RS-01-182 +, STC 10 +  and STC 10-08 +

S.2(b) +, S.4(f) +  and S.1(z) +

05000346  +, 00346  +, 00269  +  and 00313  +

56 FR 56251 +, 61 FR 6765 +, 72 FR 63974 +, 62 FR 52187 +, 67 FR 67099 +, 53 FR 50317 +, 63 FR 66492 +, 61 FR 65172 +, 69 FR 68046 +, 70 FR 61887 +  and 158 FR 52410 +

GDC 14 +, GDC 31 +  and GDC 32 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +

ML093100167 +, ML093100167 +, ML093100167 +, ML093100167 +, ML093100167 +, ML093100167 +, ML093100167 +, ML093100167 +  and ML093100167 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 0.00162 d (0.0389 hours, 2.314815e-4 weeks, 5.327e-5 months)  +

Tritium +, Cesium-137 +, Iridium-192 +  and Cobalt-60 +

NRC Form 3 +, NRC Form 241 +  and NRC Form 33 +

Information Notice 94-63 +  and Information Notice 2001-05, Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station Unit 3 +

NUREG/CR-6245 +  and NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +

AM +, ES +, EAP +, TOP +, Emergency Operating Procedure +  and TP-IIQ-219P +

Regulatory Guide 1.174 +  and Regulatory Guide 1.45 +

1A-05-052 +, 1Q-306 +, S14D-0 +, 7t-3 +, 5G-346 +, 06-84S-01-EA +, 11A-05-052 +, 00J006-0 +, 1A-QS-QS2 +, 1A-oS-oS2 +, S14D-04664 +, 14D-04665 +, S14D-04667 +, S14D-04668 +, 182J-groove +, S14D-04671 +, S14D-04672 +, S14D-04673 +, S14D-046 +, S14D-04676 +, S14D-04677 +, S14D-04678 +, 514D-04679 +, 1A-OS-OS2 +, 1WA-2500-1 +, 8V-t +, 32t-8337 +, 3F0801-06 +, 8aD-38 +, 1Q-219P +...

STC 10 +  and STC 10-08 +

Davis Besse +  and DPR-51 +

Ohio +, Washington +, New York +, Florida +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Primary containment +, Reactor Pressure Vessel +, Emergency Core Cooling System +  and Control Rod +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Non-Destructive Examination +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, VT-2 +, Finite Element Analysis +, Significance Determination Process +, Notice of Violation +, Stress corrosion cracking +, Maintenance Rule Program +, Liquid penetrant +, Pressure Boundary Leakage +, Through-Wall Leakage +, Backfit +, Unidentified leak +, Overexposure +, Affidavit +, Eddy-Current Testing +, Regulatory Conference +  and Basic Component +