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Letter  and Safety Evaluation

IWB-3600 +, IWB-2500 +, IWC-2500 +, IWB-2420 +, IWB-2430 +, IWA-2300 +, IWA-5000 +, IWA-2211 +, IWA-5244 +, IWA-5241 +, IWA-4000 +, IWA-2210 +, IWA-2213 +, IWA-2232 +, IWA-2212 +, IWA-3300 +, IWA-4500 +, IWA-4221 +, IWA-221 +, IWA-4132 +  and IWA-4100 +

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

Iron +  and Tungsten +

BWRVIP-108 +  and BWRVIP-05 +

10 CFR 50 +, 10 CFR 50.5S#a +, 10 CFR 55.55a#a3 +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g6i +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#b2xvG +, 10 CFR 50.55a#3i +, 10 CFR 50.55a#g6 +, 10 CFR 50.55a#b2xxiv +  and 10 CFR 50.55a#b2xvi +

ASME Code Case N-504-2 +, ASME Code Case N-460 +, ASME Code Case N-702 +, ASME Code Case N-700 +, ASME Code Case N-686 +, ASME Code Case N-653 +  and ASME Code Case N-686-1 +

05000331  +  and 00331  +

05000331/LER-2007-003, Re Linear Indications Found During UT Examination of Safe-End to Nozzle Welds +, ML020160532 +, ML013330156 +, ML073600374 +, ML081680709 +, ML11237A105 +, ML13051A266 +, ML13051A049 +, ML070090357 +, ML043270051 +, ML071380183 +, ML082480680 +, ML101680600 +, ML071110007 +, ML082040046 +, ML11235A935 +, ML070030S16 +, ML0700903S7 +, ML1124SA240 +, ML010920009 +, ML023530046 +, ML022610353 +, ML061B70230 +, ML07010457 +, NG-12-0489, Response to NRC Requests for Additional Information Regarding the Fourth 10-Year Inservice Inspection Plan +, NG-11-0320, Fourth 10-Year Inservice Inspection Plan +, NG-10-0328, Response to Supplemental Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations +, NG-10-0094, Response to Request for Additional Information Related to Relief Request for 1st Period Limited Weld Examinations +, NG-09-0539, Relief Request for 1st Period Limited Weld Examinations +, NG-08-0557, Response to Request for Additional Information Regarding Revised Request to Allow Use of the Provisions of IWA-4132 for Remainder of the Fourth Ten-Year Inservice Inspection Interval +...

Robert Carlson +  and Plant Licensing Branch III +

ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +, ML13051A266 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

ML023530046 +, ML022610353 +, ML13002A333 +, NG-11-0320, Fourth 10-Year Inservice Inspection Plan +, ML092120496 +, NG-08-0557, Response to Request for Additional Information Regarding Revised Request to Allow Use of the Provisions of IWA-4132 for Remainder of the Fourth Ten-Year Inservice Inspection Interval +, NG-08-0201, Revised Request to Allow Use of the Provisions of IWA-4132 for Remainder of the Fourth Ten-Year Inservice Inspection Interval +, ML080710422 +, NG-08-0093, Response to Request for Additional Information Related to the Relief Request for Seal Weld Procedure Qualification +, NG-07-0588, Relief Request for Seal Weld Procedure Qualification +, NG-07-0176, Alternative to ASME Section XI Requirements to Use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center +, NG-06-0856, Response to Request for Additional Information Related to Relief Request NDE-R001 +, ML061860692 +, ML040510181 +  and ML020880204 +

Target Rock +  and General Electric +

Robert Wolfgang +, John Tsao +  and Carolyn Fairbanks +

TAC:ME7246 +, TAC:MD3177 +  and TAC:MD8192 +

Regulatory Guide 1.174 +, Regulatory Guide 1.147 +  and Regulatory Guide 1.178 +

Feedwater +, Service water +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Residual Heat Removal Service Water +, Safety Relief Valve +, Control Rod +  and Main Steam +

Duane Arnold +  and Richard Anderson +

Reactor Vessel Water Level +, Weld Overlay +, Internal Flooding +, Probabilistic Risk Assessment +, Nondestructive Examination +, VT-2 +, Incorporated by reference +, Intergranular Stress Corrosion Cracking +, Large early release frequency +, Loss of Offsite Power +, Exemption Request +, Liquid penetrant +, Pressure Boundary Leakage +, Through-Wall Leakage +  and Scaffolding +