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Report  and Miscellaneous

ANSI B31.1 +  and ANSI B31.1.0 +

ASME Section III +  and ASME Section XI +

Iron +, Oxygen +, Hydrogen +, Lead +  and Tin +

10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1302 +, 10 CFR 50.49 +, 10 CFR 50 Appendix I +  and 10 CFR 50.55a +

SECY 11-0014 +  and RS-001 +

H.2(u) +  and P.0(o) +

ML083230111 +, ML12192A104 +, ML091410120 +, ML092260436 +, ML12207A541 +, ML092090219 +, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information +, L-MT-08-052, Response to Request for Additional Information on Extended Power Uprate: Updates to Enclosures 1, 3, 5 and 7 of L-MT-08-052, and 3 of L-MT-09-047 +, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009 +, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009 +, L-MT-09-048, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Request for Additional Information (RAI) Dated March 19, 2009, and March 26,2009 +, L-MT-09-042, Extended Power Uprate: Response to NRC Reactor Inspection Branch Request for Additional Information (RAI) Dated March 20, 2009 +, L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009 +, L-MT-08-043, Extended Power Uprate, Acceptance Review Supplemental Information Package 6 +, L-MT-08-039, Extended Power Uprate (USNRC TAC MD8398); Acceptance Review Supplemental Information +, L-MT-08-036, Extended Power Uprate - Acceptance Review Supplement Regarding Radiological Analysis +  and L-MT-12-082, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure +

GDC 33 +, GDC 10 +, GDC 60 +, GDC 9 +, GDC 67 +, GDC 69 +, GDC 68 +, GDC 70 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 95-06, Changes in the Operator Licensing Program +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 06-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +, ML13039A200 +  and ML13039A200 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

Nitrogen-16 +  and N-16 +

Valcor +  and General Electric +

NUREG-1865, Safety Evaluation Report Related to the License Renewal of the Monticello Nuclear Generating Plant +  and 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 +

115KV +, 4kV +, 115kV +  and 345kV +

AOP +, Emergency Operating Procedure +  and Emergency Plan +

TAC:MD9990 +, TAC:ME3145 +  and TAC:MD8398 +

Regulatory Guide 1.174 +  and Regulatory Guide 1.200 +

50E-03 +, 655E-07 +, 115kV-4 +, 115kV-13 +, E8A-20 +, E8B-20 +, E7A-10 +, E7B-10 +, V2A-8 +, V2B-8 +, 07-07-25P +, 12J-f14 +  and 5S-Hreff +

Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Main Transformer +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Stator Water Cooling +, Standby Liquid Control +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Extraction steam +  and Main Turbine Bypass System +

Stroke time +, Anticipated operational occurrence +, Internal Flooding +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, High Energy Line Break +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, MELLLA +, Stress corrosion cracking +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Time Critical Operator Action +, License Renewal +, Earthquake +, GOTHIC +, Power Uprate +, Failure to Scram +  and Manual Operator Action +