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ACI-318 +, ACI-349 +  and ACI-201 +

IWB-3640 +, IWB-3600 +, IWB-3500 +, IWB-2500 +, IWC-2500 +, IWB-3131 +, IWB-2400 +, IWB-2430 +, IWC-2400 +, IWB-3400 +, IWA-6230 +, IWA-6000 +, IWA-1400 +, IWA-2200 +, IWA-4000 +  and IWA-2210 +

ASME Section XI +, ASME Section IX +  and ASME Section V +

Federal Energy Regulatory Commission +  and American Society of Civil Engineers +

Boron +, Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Hydrogen +, Molybdenum +, Chloride +, Lead +, Aluminum +, Silicon +, Sulfur +, Titanium +  and Zinc +

BWRVIP-41 +, BWRVIP-25 +, BWRVIP-03 +, BWRVIP-183 +, BWRVIP-18 +, BWRVIP-38 +, BWRVIP-139 +, BWRVIP-190 +, BWRVIP-45 +, BWRVIP-62 +, BWRVIP-181 +, BWRVIP-2S +, BWRVIP-26-A +, BWRVIP-47-A +, BWRVIP-18-A +, BWRVIP-42-A +, BWRVIP-14-A +, BWRVIP-60-A +, BWRVIP-76-A +, BWRVIP-02-A +, BWRVIP-16-A +, BWRVIP-19-A +, BWRVIP-56-A +, BWRVIP-58-A +, BWRVIP-59-A +, BWRVIP-99-A +, BWRVIP-44-A +, BWRVIP-50-A +, BWRVIP-51-A +, BWRVIP-57-A +...

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21.21 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.4 +, 10 CFR 50.61a +, 10 CFR 50.55a +, 10 CFR 54.4#a1 +, 10 CFR 54.4#a1i +, 10 CFR 50.34#b6i +, 10 CFR 50.34#b6ii +, 10 CFR 50.36#c5 +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a2 +, 10 CFR 54.21#d +, 10 CFR 54.21#a1 +, 10 CFR 50.55a#b2 +, 10 CFR 50.55a#b2viii +  and 10 CFR 50.55a#b2ix +

ASME Code Case N-729-1 +, ASME Code Case N-722 +, ASME Code Case N-770 +  and ASME Code Case N-481 +

05000247  +  and 05000286  +

ML003717179 +, ML032880525 +, ML082410132 +, ML092120574 +, ML092750569 +, ML081140278 +, ML081230449 +, ML010430375 +, ML993490288 +, ML011080790 +, ML050730347 +, ML081500814 +, ML090930466 +, ML010780094 +, ML071840360 +, ML062770105 +, ML070400349 +, L-08-377, Supplemental Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 34 +  and Information Notice 2007-02, Recent Operating Experience with Failure of the Male Coupling of the Lead Screw on the Control Rod Drive Mechanism +

MRP-146 +, MRP-139 +, MRP-227 +, MRP-228 +  and MRP 146 +

NRC Generic Letter 04-02 +, NRC Generic Letter 07-01 +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, 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 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, 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 +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML11349A085 +, ML11349A085 +, ML11349A085 +, ML11349A085 +, ML11349A085 +, ML11349A085 +, ML11349A085 +, ML11349A085 +  and ML11349A085 +

IP 71111.01 +, IP 71111.06 +  and IP 71111.08 +

LR-ISG-2007-02 +, LR-ISG-2009-01 +  and LR-ISG-2006-01 +

NEI 97-06, Steam Generator Conditioning Monitoring Report +, NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NFPA 25 +  and NFPA 24 +

NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 80-11 +, NRC Bulletin 88-09 +, NRC Bulletin 82-02 +, NRC Bulletin 96-03 +, NRC Bulletin 87-01 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 88-02 +  and NRC Bulletin 89-01 +

Information Notice 97-45 +, Information Notice 94-28 +, Information Notice 87-44 +, Information Notice 87-67 +, Information Notice 98-36 +, Information Notice 99-19 +, Information Notice 94-42 +, Information Notice 97-17 +, Information Notice 88-03 +, Information Notice 92-57 +, Information Notice 97-02 +, Information Notice 07-28 +, Information Notice 86-99 +, Information Notice 89-79 +, Information Notice 97-10 +, Information Notice 97-46 +, Information Notice 2007-01, Recent Operating Experience Concerning Hydrostatic Barriers +, Information Notice 92-20 +, Information Notice 89-64 +, Information Notice 91-18 +, Information Notice 97-84 +, Information Notice 87-43 +, Information Notice 87-28 +, Information Notice 88-56 +, Information Notice 97-70 +, Information Notice 91-47 +, Information Notice 92-35 +, Information Notice 95-11 +, Information Notice 89-53 +, Information Notice 93-21 +...

NUREG-1432 +, NUREG-1431 +, NUREG-1705 +, NUREG/CR-4513 +, NUREG-1723 +, NUREG-1430 +, NUREG-1522 +, NUREG-1760 +, NUREG/CR-6923 +, NUREG-1823 +, NUREG/CR-5643 +, NUREG/CR-7000 +, NUREG-1544 +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG-1477, Discusses Technical Concerns W/Changes to Draft NUREG-1477 Re Probability of Leakage Curves +, 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-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, 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 +, NUREG-1915, Safety Evaluation Report, Related to the License Renewal of Wolf Creek Generation Station +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

AM +, ES-1 +, ES-2 +  and ES-3 +

TAC:MC2293 +, TAC:MB0468 +, TAC:MD6593 +  and TAC:M92442 +

Regulatory Guide 1.163 +, Regulatory Guide 1.137 +, Regulatory Guide 1.147 +, Regulatory Guide 1.121 +, Regulatory Guide 1.160 +, Regulatory Guide 1.26 +, Regulatory Guide 1.127 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +, Regulatory Guide 1.142 +, Regulatory Guide 1.35 +, Regulatory Guide 1.35.1 +  and Regulatory Guide 1.211 +

RIS 2000-22, Issues Stemming from NRC Staff Review of Recent Difficulties Experienced in Maintaining Steam Generator Tube Integrity +, RIS 2007-20, Implementation of Primary-To-Secondary Leakage Performance Criteria +, RIS 2009-04, Steam Generator Tube Inspection Requirements +  and RIS 2003-13, NRC Review of Responses to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +

1O-year +, 1S-S +, M16A-1 +, M16A-3 +, 1ISA-S7 +, M16A-2 +, M16A-4 +, M16A-S +, M16A-6 +, M16A-7 +, M16A-8 +, M21A-1 +, M21A-2 +, M21A-3 +, M2S-1 +, M2S-2 +  and M2S-3 +

Washington +, New York +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray +  and Extraction steam +

Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Hydrostatic +, Coatings +, Nondestructive Examination +, Incorporated by reference +, Condition Adverse to Quality +, Aging Management +, Local Leak Rate Testing +, Foreign Material Exclusion +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Earthquake +, Control of Heavy Loads +, Biofouling +, EVT-1 +, Liquid penetrant +, Pressure Boundary Leakage +, Through-Wall Leak +...