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10 CFR 50.72 +, 10 CFR 26 +, 10 CFR 50.46 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 50.68 +, 10 CFR 50.90 +, 10 CFR 50.109 +, 10 CFR 54.3 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.55a +, 10 CFR 70.24 +  and 10 CFR 50.65#a4 +

Nuclear Energy Institute +  and Schoppman M +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 06-01 +, NRC Generic Letter 83-11, Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +

ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +, ML072130165 +...

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)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

NEI 96-07 +, NEI 91-06 +  and NEI 06-02, License Amendment Request (LAR) Guidelines +

LIC-500 +  and LIC-101 +

NUREG/BR-0058 +, NUREG-1536, Responds to Re Transfer of Spent Fuel.Nrc Has Approved Applications for Sierra Nuclear VSC-24 Storage Sys. Description of Approved Sys & Acceptance Criteria Located in NUREG-1571 & NUREG-1536 Respectively.W/O NUREGs +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

John Lubinski +  and Daniel Frumkin +

Regulatory Guide 1.9 +, Regulatory Guide 1.187 +  and Regulatory Guide 1.152 +

RIS 2005-08, Endorsement of Nuclear Energy Institute (NEI) Position Paper Range of Protective Actions for Nuclear Power Plant Incidents +, RIS 2005-05, Regulatory Issues Regarding Criticality Analyses for Spent Fuel Pools and Independent Spent Fuel Storage Installations +, RIS 2005-20, Rev. 1: Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety +  and RIS 2005-28, Scope of For-Cause Fitness-For-Duty Testing Required by 10 CFR 26.24(a)(3) +

Washington +  and California +

Steam Generator +, Reactor Protection System +, Emergency Diesel Generator +, Decay Heat Removal +  and Main Steam +

TSTF-493 +  and TSTF-449 +

Westinghouse +, Tennessee Valley Authority +, Exelon +, Southern California Edison +, Southern Nuclear +, Luminant +, Electric Power Research Institute +, Nuclear Energy Institute +, Nuclear Management Co +, John Lubinski +, FirstEnergy Corp +, Daniel Frumkin +, Marion A +, Roe J +, Miller D +, Jeffrey Riley +, Excel Services Corp +, Butler J +, Key J +, Eterl J +, Houghton J +, Wollard J +  and Plant Licensing Branch III-2 +

Fitness for Duty +, Ultimate heat sink +, Tornado Missile +, Significance Determination Process +, Tornado Missile Protection +, Operability Determination +, TORMIS +, Fuel cladding +, Pressure Boundary Leakage +, Backfit +, Inattentive +, Power Uprate +, Operational leakage +  and Control Room Habitability +