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TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT

ANSI B31.1 +  and ANSI B31.1.0 +

Boron +, Iodine +, Iron +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +  and Platinum +

10 CFR 50.72 +, 10 CFR 100 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 20.1302 +, 10 CFR 50.4 +, 10 CFR 50.9 +, 10 CFR 50.32 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.34#b +, 10 CFR 50.59#b2 +, 10 CFR 50.59#b +, 10 CFR 50.71#e +  and 10 CFR 50.71#c +

Initiating Events +  and Mitigating Systems +

05000298  +  and 00298  +

FC-C-1 +, FP-PNL-OF +  and FP-CPSR-SACI +

Nebraska Public Power District +  and Swailes J +

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 81-06, Periodic Updating of Final Safety Analysis Reports (FSARS) +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification +

ML20196B385 +, ML20196B385 +, ML20196B385 +, ML20196B385 +, ML20196B385 +, ML20196B385 +, ML20196B385 +, ML20196B385 +, ML20196B385 +  and ML20196B385 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00308 d (0.0739 hours, 4.398148e-4 weeks, 1.01213e-4 months)  +, 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)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +

Westinghouse +, Limitorque +  and General Electric +

NRC Bulletin 80-14 +  and NRC Bulletin 80-17 +

NUREG-1433 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

MP +, SP +, RT +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +  and Regulatory Guide 1.9 +

SR-3.5.1.9 +, SR-3.3.1.1.2 +, SR-3.0.3 +, SR-3.0.4 +, SR-3.3.1.1 +, SR-3.6.1.3.2 +, SR-3.7.2.4 +, SR-3.5.3.5 +, SR-3.7.3.4 +  and SR-3.3.1.2.7 +

07-98-018 +, 07-97-100 +, 07-90-161 +, 07-94-029 +, 07-95-033 +, 5A-K1 +, 07-97-012 +, 07-98-008 +, 07-97-148 +, 07-97-150 +, 07-98-090 +, 07-98-023 +, 07-98-057 +, 07-80-138 +, 07-97-162 +, 07-97-168 +, 07-50-29f +, R1IR-921MV +, 6A-KI +, 1Iold-up +, R1IR-V-145 +  and R1IR-V-147 +

Washington +  and Nebraska +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Filtration System +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +, Core Standby Cooling System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +...

TS-3.5.1 +, TS-3.6 +, TS-3.3.6.1 +, TS-3.3.3 +, TS-3.0.4 +, TS-3.7.5 +, TS-3.6.3.1 +, TS-3.4.1 +, TS-3.9.7 +, TS-3.7.C +, TS-3.0.2 +, TS-3.7.D +, TS-3.0.5 +, TS-3.0.6 +, TS-5.6.5 +, TS-3.5.0 +, TS-4.1 +, TS-3.8.1.3 +  and TS-1.0.J +

Hot Short +, Safe Shutdown +, Time of Discovery +, High winds +, Reactor Vessel Water Level +, Grab sample +, Fire Barrier +, Stroke time +, Anticipated operational occurrence +, Post Accident Monitoring +, Hydrostatic +, Coatings +, Temporary Modification +, Emergency Lighting +, Incorporated by reference +, Condition Adverse to Quality +, High Energy Line Break +, Missed surveillance +, Abnormal operational transient +, Corrosion bonding +, Local Leak Rate Testing +, Design basis earthquake +, Notice of Violation +, Foreign Material Exclusion +, Scram Discharge Volume +, Feedwater Controller Failure +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Severe Accident Management Guideline +, Rod Drop Event +...