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ACI-318 +, ACI-301 +, ACI-349 +  and ACI-201 +

IWB-3600 +, IWB-3500 +, IWC-3000 +, IWB-2500 +, IWB-3000 +, IWC-2500 +, IWC-3600 +, IWB-1220 +, IWC-1220 +, IWB-1100 +, IWC-1100 +, IWC-2430 +, IWC-3400 +, IWB-2400 +, IWB-2430 +, IWC-2400 +, IWB-3400 +, IWC-3500 +, IWB-31 +, IWC-31 +, IWB-3100 +, IWB-241 +, IWC-2410 +, IWA-2240 +, IWA-3000 +, IWA-4000 +  and IWA-2000 +

ASME Section XI +  and ASME Section III +

Boron +, Iron +, Nickel +, Potassium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Cadmium +, Molybdenum +, Zirconium +, Chloride +, Lead +, Beryllium +, Magnesium +, Aluminum +, Silicon +, Calcium +, Titanium +, Zinc +, Manganese +, Chromium +, Tin +  and Hafnium +

BWRVIP-75-A +, BWRVIP-61 +, BWRVIP-03 +, BWRVIP-27A +, BWRVIP-190 +, BWRVIP-62 +, BWRVIP-57 +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-49-A +, BWRVIP-14-A +, BWRVIP-60-A +, BWRVIP-59-A +, BWRVIP-57-A +  and BWRVIP-53-A +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 0 +, 10 CFR 54.2#a1 +, 10 CFR 50.490 +, 10 CFR 50.55a +, 10 CFR 50.49#e +, 10 CFR 50.49#f +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#a1 +, 10 CFR 54.21#C +, 10 CFR 54.21#a1ii +  and 10 CFR 50.55a#b2viii +

05000286  +, 05000247  +, 00247  +  and 00286  +

LP-33 +, LP-25 +, LP-34 +, LP-35 +, LP-39 +  and LP-3S +

NRC Generic Letter 80-95, Generic Activity A-10 +, NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" +, 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 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +

ML12334A655 +, ML12334A655 +, ML12334A655 +, ML12334A655 +, ML12334A655 +, ML12334A655 +, ML12334A655 +, ML12334A655 +  and ML12334A655 +

Westinghouse +  and General Electric +

NRC Bulletin 82-02 +, NRC Bulletin 80-13 +, NRC Bulletin 88-08 +  and NRC Bulletin 89-01 +

Information Notice 82-39 +, Information Notice 84-41 +, Information Notice 88-03 +, Information Notice 92-57 +, Information Notice 98-11 +, Information Notice 2006-27, Circumferential Cracking in the Stainless Steel Pressurizer Heater Sleeves of Pressurized Water Reactors +, Information Notice 97-46 +, Information Notice 04-08 +, Information Notice 94-63 +, Information Notice 97-19 +, Information Notice 84-18 +, Information Notice 80-38 +, Information Notice 91-05 +, Information Notice 97-88 +, Information Notice 82-37 +, Information Notice 85-65 +, Information Notice 90-04 +, Information Notice 90-10 +, Information Notice 96-11 +, Information Notice 89-33 +, Information Notice 94-87 +, Information Notice 2007-37, Buildup of Deposits in Steam Generators +, Information Notice 2005-02, Pressure Boundary Leakage Identified on Steam Generator Bowl Drain Welds +, Information Notice 2004-11, Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle +, Information Notice 2004-08, Reactor Coolant Pressure Boundary Leakage Attributable to Propagation of Cracking in Reactor Vessel Nozzle Welds +, Information Notice 2003-11, Leakage Found on Bottom-Mounted Instrumentation Nozzles +, Information Notice 99-10 +, Information Notice 96-09 +, Information Notice 89-80 +, Information Notice 95-17 +...

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG-1760 +, NUREG-1833 +, NUREG-1544 +, NUREG/CR-5385 +, NUREG/CR-6001 +, NUREG/CR-4652 +, 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-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-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

ES +, RT +, SP-4 +, SP-45 +, ES-1 +, SP-2 +, SP-1 +, SP-61 +, SP-5 +, SP-58 +, SP-88 +, SP-98 +, SP-71 +, ES.AP-281 +, ES.AP-273 +, ES.AP-280 +, ES.AP-278 +, ES.AP-272 +, ES.AP-270 +, SP-84 +, SP-83 +, SP-82 +, SP-90 +, SP-73 +, SP-12 +, SP-118 +, SP-127 +, SP-87 +, SP-27 +, SP-95 +...

Regulatory Guide 1.26 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.35.1 +

RIS 2003-09, Environmental Qualification of Low-Voltage Instrumentation and Control Cables +  and RIS 2008-30, Fatigue Analysis of Nuclear Power Plant Components +

2S00-1 +, 5P-27 +  and 5P-32 +

New York +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray +  and Extraction steam +

Boric Acid +, Fire Barrier +, Safe Shutdown Earthquake +, Weld Overlay +, Coatings +, Nondestructive Examination +, VT-2 +, Zebra Mussel +, Functionality Assessment +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Biofouling +, Liquid penetrant +, Pressure Boundary Leakage +, Eddy-Current Testing +, Thermal fatigue +  and Water hammer +