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Hydrogen +  and Lead +

05000282  +, 05000306  +, 00282  +  and 00306  +

ML003691712 +  and L-PI-06-063, Supplement to License Amendment Request (LAR) to Technical Specification (TS) 5.5.14 for One-Time Extension of Containment Lntegrated Leakage Rate Test Interval +

NRC Generic Letter 04-02 +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +, ML083440696 +  and ML083440696 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

L-PI-08-022, Prairie Lsland, Units 1 and 2, Annual Report of Personnel Radiation Exposure +, L-PI-09-055, Enclosure 4 - H4, Offsite Dose Calculation Manual (Odcm), Revision 22 +  and 05000282/LER-1997-013, :on 971018,inoperability of AFW & Entry Into TS 3.0.C Was Noted Due to AFW Manual Start During Planned & Orderly Shutdown.Lar Will Be Prepared +

NUREG/CR-6595 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1570, Summary of ACRS Subcommittees on Matls & Metallurgy and Severe Accidents Meeting on 970304-05 in Rockville,Md Re Staff Draft NUREG-1570, Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture +, NUREG-1488, Notice of Draft NUREG 1488, Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of Rocky Mountains +, 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 +  and NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +

AM +  and Emergency Operating Procedure +

1E-6 +, 1E-8 +, 1E-4 +, 1E-7 +, 1E-9 +, 6E-8 +, 2E-2 +, 2E-7 +, 2E-5 +, 2E-8 +, 2E-6 +, 5E-4 +, 8E-7 +, 5E-5 +, 1E-2 +, 1E-1 +, 2X-XX-X +, 2L-XX-X +, 2L-DH-L +, 2L-CC-L +, 2L-SR-E +, 2X-H2-E +, 2H-DH-L +, 2L-H2-E +, 2H-XX-X +, 2H-OT-L +, 2X-CI-E +, 2L-CI-E +, 2H-H2-E +, 2H-CI-E +...

Wolf Creek +  and Prairie Island +

Minnesota +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

Hot Short +, Safe Shutdown +, Boric Acid +, High winds +, Loop seal +, Mission time +, Internal Flooding +, Probabilistic Risk Assessment +, B.5.b +, Seismically rugged +, Large early release frequency +, Loss of Offsite Power +, Severe Accident Management Guideline +, License Renewal +, Earthquake +, Maintenance Rule Program +, Fire Watch +, Scaffolding +, Power Uprate +, Overspeed trip +, Overspeed +, Pressure locking +  and Restart +

WCAP-10541 +, WCAP-16341-P +, WCAP-15341-P +  and WCAP-10451 +

WCAP-10541 +, WCAP-16341-P +, WCAP-15341-P +  and WCAP-10451 +