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ASME Section XI +  and ASME Section III +

Boron +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Hydrogen +, Chloride +, Lead +, Aluminum +, Titanium +  and Manganese +

BWRVIP-75 +, BWRVIP-41 +, BWRVIP-79 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-116 +, BWRVIP-25 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-74 +, BWRVIP-29 +, BWRVIP-05 +, BWRVIP-104 +  and BWRVIP-78 +

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 50.65 +, 10 CFR 54.4#a2 +, 10 CFR 54.3#a +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 54.21#b +  and 10 CFR 50.55#a +

RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-03-131, Additional Information Supporting Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program +  and RS-03-099, Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program +

05000237  +, 05000249  +, 05000254  +, 05000265  +, 00237  +, 00249  +, 00254  +  and 00265  +

Exelon +  and Simpson P +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, 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 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 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +, 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 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +  and RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, 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 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

RS-04-039, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations +, RS-03-131, Additional Information Supporting Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program +  and RS-03-099, Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.89 +

Dresden +  and Quad Cities +

Quad Cities +, DPR-19 +  and DPR-25 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Stator Cooling Water +, Stator Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Ultimate heat sink +, Fire Barrier +, Weld Overlay +, Coatings +, Nondestructive Examination +, VT-2 +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Main Steam Line Radiation Monitor +, Moisture barrier +, License Renewal +, Biofouling +, Pressure Boundary Leakage +, Power Uprate +  and Thermal fatigue +