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ACI-318 +, ACI-349 +  and ACI-201 +

Boron +, Iron +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +, Aluminum +, Manganese +  and Chromium +

10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix I +, 10 CFR 54.4 +, 10 CFR 54.21 +, 10 CFR 50.48 Appendix R +, 10 CFR 54.4#a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +, 10 CFR 54.4#a1 +, 10 CFR 54.4#b +, 10 CFR 54.4#a1i +, 10 CFR 54.37#a +, 10 CFR 50.62#c1 +, 10 CFR 50.62#c2 +, 10 CFR 54.21#a1 +, 10 CFR 54.21#a1i +, 10 CFR 54.21#a +, 10 CFR 54.21#a1ii +, 10 CFR 54.21#a2 +, 10 CFR 50.48#b +, 10 CFR 50.63#a1 +  and 10 CFR 54#a1 +

FP-FO +  and FC-00-127 +

Turbine Trip +  and Reactor Trip +

NRC/NRR/DRIP/RLEP +  and Kuo P +

ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +, ML032481257 +  and ML032481257 +

LIC-03-0090, Report of Full Compliance with the Compensatory Measures of the Order for Compensatory Measures Related to Access Authorization +, LIC-02-0141, November 2002 Monthly Operating Report for Calhoun Station Unit 1 +, LIC-03-0035, Response to Potential Open Items for Review of License Renewal Application, Table 3.1.1 - Conclusion +, LIC-02-0133, Responses to Request for Additional Information (RAI) for the Review of the License Renewal Application for Fort Calhoun Station, Unit 1 +, LIC-01-0095, Part 2 of 2 - Responses to Request for Additional Information (RAI) for the Review of the License Renewal Application for Fort Calhoun Unit 1, Attachment Enclosures LIC-91-0003L, LIC-01-0095, LIC-02-0007, & Calculation Number FC006608 +, ML030500413 +  and ML022840179 +

Information Notice 93-95 +  and Information Notice 2001-09, Main Feedwater System Degradation in Safety-Related ASME Code Class 2 Piping Inside the Containment of a Pressurized Water Reactor +

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-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

4kV +, 4.16kV +, 345kV +  and 600V +

CH-131 +  and CH-134 +

Regulatory Guide 1.155 +, Regulatory Guide 1.127 +  and Regulatory Guide 1.154 +

Missouri +  and Nebraska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Circulating Water System +, Main Steam Safety Valve +, Qualified Safety Parameter Display System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Main Steam +  and Containment Spray +

Omaha Public Power District +  and Ridenoure R +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Fire Barrier +, Anticipated operational occurrence +, Internal Flooding +, Probabilistic Risk Assessment +, Emergency Lighting +, Aging Management +, Loss of Offsite Power +, Integrated leak rate test +, Frazil ice +, License Renewal +, Control of Heavy Loads +, Fire Protection Program +  and Spent fuel rack +