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Boron +, Cesium +, Oxygen +, Hydrogen +  and Lead +

L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +, L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +  and L-MT-10-003, Mellla+ Risk Assessment, Attachment 6 of L-MT-10-003 +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +

NUREG/CR-5750 +, NUREG/CR-4550 +, NUREG/CR-4551 +, NUREG-5500 +, NUREG-1560, Forwards Draft NUREG-1560 Public Workshop Summary Rept from Workshop Held on 970407-09 in Austin,Texas.Rept Summarizes Discussions Held During Workshop & Documents All of Presentation Matl Distributed to Workshop by Attendees +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

AOP +, SP +  and Emergency Operating Procedure +

Regulatory Guide 1.174 +  and Regulatory Guide 1.200 +

NEDC-32424P +, NEDC-33006P +, NEDC-32523P +  and NEDC-33004P +

1E-5 +, 2E-5 +, 3E-4 +, I1E-b(Mech) +  and 10Q-7 +

Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +  and Low Pressure Coolant Injection +

Xcel Energy +  and Office of Nuclear Reactor Regulation +

High winds +, Mission time +, Internal Flooding +, Probabilistic Risk Assessment +, Job Performance Measure +, Large early release frequency +, MELLLA +, Loss of Offsite Power +, Severe Accident Management Guideline +, Flow Induced Vibration +, Power Uprate +, Failure to Scram +  and Loss of condenser vacuum +