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ASME Section XI +, ASME Section III +  and ASME Section VIII +

Boron +, Iron +, Nitrogen +, Carbon +, Chloride +, Aluminum +  and Manganese +

BWRVIP-75 +, BWRVIP-41 +, BWRVIP-48 +, BWRVIP-27 +, BWRVIP-116 +, BWRVIP-25 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-190 +  and BWRVIP-05 +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.37#b +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +  and 10 CFR 50.71#e +

RS-11-159, Updated Final Safety Analysis Report, Revision 11 +, 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 +

05000254  +  and 05000265  +

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 +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +, RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +  and RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Appendix a +

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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-1796, (2:2) Chpt 3 - End, Safety Evaluation Report: Related to the License Renewal of Dresden Nuclear Power Station, Units 2 & 3 and Quad Cities Nuclear Power Station, Units 1 & 2 +

RT +  and ISP +

RS-11-159, Updated Final Safety Analysis Report, Revision 11 +, 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 1.99 +  and Regulatory Guide 1.54 +

Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, 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 +  and Main Steam +

Ultimate heat sink +, Fire Barrier +, Coatings +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Main Steam Line Radiation Monitor +, License Renewal +, Biofouling +  and Thermal fatigue +