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ANSI B31.1 +, ANSI N45.2.6 +, ANSI B30.2-1976 +, ANSI B30.2 +  and ANSI N101.4-1972 +

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

Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Hydrogen +, Chloride +  and Lead +

BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-116 +, BWRVIP-25 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-139 +, BWRVIP-190 +, BWRVIP-74 +, BWRVIP-29 +, BWRVIP-05 +, BWRVIP-16 +, BWRVIP-78 +, BWRVIP-1 +, BWRVIP-35 +  and BWRVIP-86-A +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.55 +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 54.21 +, 10 CFR 50.55a +, 10 CFR 54.3#a +, 10 CFR 50.49#e +, 10 CFR 50.49#f +, 10 CFR 50.49#e5 +, 10 CFR 54.3#a6 +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +  and 10 CFR 54.21#b +

NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, 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 +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +, L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +  and L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction +

IEEE P1205-2000 +  and IEEE P1205 +

General Electric +  and Westinghouse +

Information Notice 87-67 +, Information Notice 89-64 +  and Information Notice 2000-14, Non-vital Bus Fault Leads to Fire and Loss of Offsite Power +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5643 +, 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-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-1865, Safety Evaluation Report Related to the License Renewal of the Monticello Nuclear Generating Plant +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

TAC:MD9990 +, TAC:MA9891 +, TAC:ME7930 +, TAC:MB3819 +  and TAC:M93925 +

Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.190 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.89 +

NEDO-32205 +, NEDO-21888 +, NEDC-32983P +, NEDO-32205A +  and NEDO-24576 +

Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Fire Barrier +, Anticipated operational occurrence +, Hydrostatic +, Coatings +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Maintenance Rule Program +, Biofouling +, EVT-1 +, Fire Protection Program +, Power Uprate +, Thermography +  and Thermal fatigue +