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Letter, Annual Report  and Occupational Exposure Record

ASME Section III +  and ASME Section XI +

ASTM D3803-1989 +  and ASTM D3803 +

Department of Natural Resources +  and Federal Emergency Management Agency +

Boron +, Iodine +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Lead +, Aluminum +  and Calcium +

10 CFR 50 Appendix R +  and 10 CFR 50 Appendix B +

05000266  +, 05000301  +, 07200005  +, 00266  +  and 00301  +

Turbine Trip +  and Reactor Trip +

Nuclear Management Co +  and Cayia A +

NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 86-12, Criteria for Unique Purpose Exemption From Conversion From the Use of HEU Fuel +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +, ML010670316 +  and ML010670316 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +

IEEE 344-1987 +, IEEE C37 +  and IEEE 317 +

DPR-024  +  and DPR-027  +

Westinghouse +, Limitorque +  and Farr +

NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +  and NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +

OP-2A +, OP-4D +, OP-3C +  and OP-9C +

RO-04008 +  and RO-04015 +

4.16KV +, 4kV +  and 345kV +

EOP-1 +, AOP-2 +, AOP-10A +, AOP-10B +, EOP-1.3 +, AOP-1OA +  and AOP-1OB +

Regulatory Guide 1.181 +  and Regulatory Guide 1.35 +

2P-29 +, 2A-01 +, 2A-02 +, 2B-02 +, 2A-05 +, 2B-32 +, 2PR-49 +, 07-72-005 +, 1DY-01 +, 2RC-430 +, 2N-31 +, 2B-42 +, 1DY-02 +, 2DY-01 +, 2DY-02 +, 2HX-15D +, 2HX-15A +, 2HX-15C +, 2HX-15B +, 1HX-15C +, 2A-03 +, 2A-04 +, 2N-32 +, 2B-11 +, 1C-157 +, 2C-20 +, 2PR-3 +, 2N-40 +, 1A52-17 +, 1HX-15A +...

DPR-24 +  and DPR-27 +

Washington +  and Wisconsin +

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

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, Boric Acid +, High Radiation Area +, Fire Barrier +, Hydrostatic +, Temporary Modification +, VT-2 +, Zebra Mussel +, Emergency Lighting +, Notice of Violation +, Foreign Material Exclusion +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Exemption Request +, Fire Watch +, Core Exit Thermocouple +, Manual Operator Action +, Control Room Habitability +, Seal weld +, Spill +  and Restart +

WO 9818976 +, WO 9931040 +  and WO 9914124 +