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Regulatory Guide  and Draft

Boron +, Iodine +, Hydrogen +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 51 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50 Appendix E +, 10 CFR 100.21 +  and 10 CFR 50.34#a1ii +

Reactor Trip +  and Turbine Trip +

GDC 20 +, GDC 15 +, GDC 10 +, GDC 55 +, GDC 61 +, GDC 35 +, GDC 60 +, GDC 13 +, GDC 31 +, GDC 25 +, GDC 28 +, GDC 29 +, GDC 27 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 26, Reactivity control system redundancy and capability +

NRC Generic Letter 80-19, Resolution of Enhanced Fission Gas Release Concern +, NRC Generic Letter 83-32, NRC Staff Recommendations Regarding Operator Action for Reactor Trip and ATWS +, NRC Generic Letter 83-22, Safety Evaluation of "Emergency Response Guidelines" +, NRC Generic Letter 83-11, Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 86-16, Westinghouse ECCS Evaluation Models +, NRC Generic Letter 86-13, Potential Inconsistency Between Plant Safety Analyses and Technical Specifications +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications +, NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +  and NRC Generic Letter 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition +

ML061640491 +, ML061640491 +, ML061640491 +, ML061640491 +, ML061640491 +  and ML061640491 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0718, Forwards Final Rule on Licensing Requirements for Pending CP & Mfg License Applications & NUREG-0718,Revision 2.SER Comparison to New Requirements Revealed Util Commitments & CP Conditions Conform to Nureg.W/O NUREG +  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 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Core Spray +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +  and Containment Spray +

Anticipated operational occurrence +, Loss of Offsite Power +, Fuel cladding +  and Loss of condenser vacuum +