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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

Uranium +, Copper +, Nitrogen +, Sodium +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50.54#f +  and 10 CFR 50.61 +

05000282  +, 05000306  +, 00282  +  and 00306  +

SE-07 +  and SE-06 +

Wadley M +  and Northern States Power Company +

ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +, ML20106G410 +  and ML20106G410 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 0.00167 d (0.04 hours, 2.380952e-4 weeks, 5.4792e-5 months)  +, 0.101 d (2.433 hours, 0.0145 weeks, 0.00333 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 0.00417 d (0.1 hours, 5.952381e-4 weeks, 1.3698e-4 months)  +

NUMARC 87-00 +  and NUMARC 07-00 +

NUREG/CR-4550 +, NUREG/CR-4772 +, NUREG-1228 +, NUREG-4550 +, NUREG/CR-5039 +, NUREG/CR-4803 +, NUREG/CR-4905 +, NUREG/CR-1335 +, NUREG/CP-1278 +, NUREG-4803 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-1335, Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335 +, NUREG/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +  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 +

4.16KV +  and 4kV +

AOP +, PSP +, Emergency Operating Procedure +, SP-1100 +  and SP-1089 +

1E-6 +, 1E-8 +, 1E-3 +, 1E-7 +, 1E-9 +, 1E-06 +, 1E-07 +, 4E-09 +, 5E-08 +, 2E-07 +, 4E-05 +, 6E-10 +, 7E-08 +, 6E-07 +, 4E-08 +, 3E-06 +, 1E-09 +, 9E-06 +, 2E-08 +, 1E-02 +, 1E-05 +, 2E-10 +, 5E-06 +, 4E-06 +, 5E-5 +, 9E-2 +, 8E-08 +, 9E-08 +, 2E-05 +, 9E-10 +...

Wolf Creek +  and Prairie Island +

Minnesota +  and Washington +

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

TS-3.5.C +  and TS-3.13 +

Mission time +, Internal Flooding +, Hydrostatic +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Core Exit Thermocouple +  and Affidavit +