Browse wiki

Letter  and Inspection Report

ASME Section XI +  and ASME Section V +

Iron +, Copper +, Nitrogen +, Carbon +, Hydrogen +, Lead +, Aluminum +  and Manganese +

BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +  and BWRVIP-03 +

10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50 Appendix H +  and 10 CFR 50.55#a +

Benny Jose +, T. Hanley +, M. Wagner +, K. Ohr +, W. Beck +, T. Petersen +, D. Luebbe +, M. Rice +, B. Stedman +, K. OShea +, M. Dunlay +, N. Howard +, T. Rushing +, P. Yost +  and A. Burress +

Initiating Events +  and Mitigating Systems +

05000254  +, 05000265  +, 00254  +  and 00265  +

ML12291A831 +  and IR 05000265/2012008 +

05000254/FIN-2012010-01 +, 05000265/FIN-2012010-01 +, 05000254/FIN-2012010-02 +  and 05000265/FIN-2012010-02 +

Ann Marie Stone +  and NRC/RGN-III/DRS/EB2 +

IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +, IR 05000254/2012010 +...

IR 05000249/2010010 +, IR 05000237/2009007 +, IR 05000265/2012008 +, IR 05000254/2012010 +  and IR 05000265/201210 +

NUREG/CR-6260 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, 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-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 +

Regulatory Guide 1.127 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.99 +

Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Intermediate Range Monitor +, Residual Heat Removal Service Water +, Stator Water +, Steam Jet Air Ejector +, Control Rod +  and Main Steam +

Pacilio M +  and Exelon +

Safe Shutdown +, Ultimate heat sink +, Non-Destructive Examination +, Coatings +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Main Steam Line Radiation Monitor +, License Renewal +, Fire Protection Program +  and Power Uprate +