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IWB-3600 +, IWB-3514 +, IWB-3500 +, IWB-2500 +, IWB-3522 +, IWB-5222 +, IWB-2412 +, IWB-5221 +, IWB-3515 +, IWC-3516 +, IWB-2400 +, IWB-3512 +, IWB-3400 +, IWB-3520 +, IWB-4000 +, IWB-3100 +, IWB-7000 +, IWB-3140 +, IWB-3519 +, IWB-3200 +, IWB-522 +, IWA-5000 +, IWA-2200 +, IWA-4000 +, IWA-3300 +, IWA-5240 +, IWA-7000 +  and IWA-3400 +

ASME Section XI +, ASME Section III +  and ASME Section X +

Nickel +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Manganese +, Palladium +, Tin +  and Platinum +

BWRVIP-75 +, BWRVIP-61 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-25 +, BWRVIP-03 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-76 +, BWRVIP-74 +, BWRVIP-29 +, BWRVIP-45 +, BWRVIP-62 +, BWRVIP-42 +, BWRVIP-05 +, BWRVIP-16 +, BWRVIP-78 +, BWRVIP-271 +, BWRVIP-19 +, BWRVIP-44 +, BWRVIP-50 +, BWRVIP-51 +, BWRVIP-57 +, BWRVIP-14 +, BWRVIP-07 +, BWRVIP-4 +, BWRVIP-28 +, BWRVIP-53 +...

10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.55a +, 10 CFR 54.21#a1i +  and 10 CFR 50.55a#1 +

ASME Code Case N-481 +  and ASME Code Case N-307-1 +

PROJ0690  +  and 00249  +

NRC/NRR/DRIP/RLSB +  and Dozier I +

SIL 409 +  and SIL 455 +

NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +  and NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +

ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +, ML003729453 +  and ML003729453 +

NRC Bulletin 82-02 +  and NRC Bulletin 80-13 +

Information Notice 82-39 +, Information Notice 84-41 +, Information Notice 94-42 +, Information Notice 88-03 +, Information Notice 92-57 +, Information Notice 97-02 +, Information Notice 97-46 +, Information Notice 93-21 +  and Information Notice 95-17 +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG-1705 +, NUREG/CR-6583 +, NUREG-1544 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +  and NUREG-1344, Advises That Util 890710 Response to Generic Ltr 89-08 Re Pipe Wall Thinning Induced by Erosion &/Or Corrosion Acceptable,Based on Confirmation That Erosion/Corrosion Program Meets or Exceeds App a to NUREG-1344 Requirements +

Jerry Dozier +  and Allen Hiser +

Regulatory Guide 1.45 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.43 +

NEDE-21821 +  and NEDE-2182 +

07-97-171 +, T0AT-0 +  and B7WRVIP-14 +

Maryland +, Washington +, Arkansas +  and Vermont +

Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +, Low Pressure Coolant Injection +  and Extraction steam +

Nuclear Energy Institute +  and Walters D +

Weld Overlay +, Hydrostatic +, Nondestructive Examination +, VT-2 +, Aging Management +, Feedwater Heater +, Stress corrosion cracking +, Eddy Current Testing +, License Renewal +, Dissimilar Metal Weld +  and Thermal fatigue +