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ANSI B31.1 +, ANSI N45.2 +, ANSI 18.7-1976 +, ANSI N45.2.8 +, ANSI N13.2-1969 +, ANSI/ANS-3.1-1978 +, ANSI-N18.17-1973 +, ANSI N45.2.8 - 1975 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

ASME Section III +  and ASME Section XI +

Iodine +, Uranium +, Iron +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Chloride +, Lead +  and Mercury +

10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 20.1601 +, 10 CFR 50.44 +, 10 CFR 50 Appendix I +, 10 CFR 73.55 +, 10 CFR 70.24 +, 10 CFR 20.1501#c +  and 10 CFR 50.71#e +

ASME Code Case N-411 +, ASME Code Case N-240 +, ASME Code Case N-397 +, ASME Code Case N-315 +, ASME Code Case N-341 +, ASME Code Case N-356 +  and ASME Code Case N-413 +

05000461  +, 00461  +  and 00462  +

Drawing 1.7-1 +  and Drawing 1.9-1 +

EC-111 +  and EC-110 +

Turbine Trip +  and Circulating water pump trip +

GDC 19, Control room +  and GDC 1, Quality standards and records +

NRC Generic Letter 81-06, Periodic Updating of Final Safety Analysis Reports (FSARS) +  and NRC Generic Letter 2003-01, Control Room Habitability +

ML20105A245 +, ML20105A245 +, ML20105A245 +, ML20105A245 +, ML20105A245 +, ML20105A245 +, ML20105A245 +, ML20105A245 +, ML20105A245 +  and ML20105A245 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 384 +, IEEE 383 +, IEEE 344 +, IEEE 382 +, IEEE 323 +, IEEE 279 +, IEEE 484 +, IEEE 634 +, IEEE 379 +, IEEE 308 +, IEEE-450 +, IEEE 336 +, IEEE 387 +, IEEE 334 +, IEEE 317 +, IEEE 338 +, IEEE 622 +, IEEE 275 +, IEEE 381 +, IEEE 415 +  and IEEE 627 +

Tritium +, U-235 +, I-125 +  and I-131 +

NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +  and NUREG-1434 +

CP +  and TOP +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.25 +, Regulatory Guide 1.196 +, Regulatory Guide 1.27 +, Regulatory Guide 1.1 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.137 +, Regulatory Guide 1.63 +, Regulatory Guide 1.9 +, Regulatory Guide 1.147 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.3 +, Regulatory Guide 1.52 +, Regulatory Guide 1.76 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.33 +, Regulatory Guide 1.49 +, Regulatory Guide 1.121 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.182 +, Regulatory Guide 1.84 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.100 +...

NEDO-10329 +, NEDO-10905 +, NEDO-10174 +, NEDO-10173 +, NEDO-10505 +, NEDO-10751 +, NEDE-11146 +, NEDO-10734 +, NEDO-21506 +, NEDO-10802 +, NEDO-10527 +, NEDO-10585 +, NEDO-10320 +, NEDO-10899 +, NEDE-21821 +, NEDO-20533 +, NEDO-21231 +, NEDO-24154 +, NEDO-10349 +, NEDE-33284 +, NEDE-20943 +, NEDO-20340 +, NEDE-21156 +, NEDE-21354 +, NEDO-10739 +, NEDO-10801 +, NEDO-20377 +, NEDO-20566 +, NEDC-32975P +, NEDO-20944 +...

SR-3.0.2 +  and SR-3.8.3.6 +

1P-A +  and 126E-ffl6 +

Texas +, Ohio +, Illinois +, Maryland +, California +, Virginia +, Louisiana +, Missouri +  and Indiana +

Steam Generator +, 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 +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Shield Building +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +, Core Standby Cooling System +, Spray Pond +...

TS-3.8.1 +, TS-3.7.1 +, TS-3.8.3 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.6.1.3 +, TS-3.8.6 +, TS-3.4.7 +, TS-3.8 +, TS-5.5.14 +, TS-5.5.15 +, TS-3.3 +, TS-5.4 +, TS-5.3.1 +  and TS-5.6.3 +

Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, Temporary Modification +, Emergency Lighting +, Incorporated by reference +, Abnormal operational transient +, Flow Accelerated Corrosion +, Feedwater Heater +, Loss of Offsite Power +, Excess Flow Check Valve +, Integrated leak rate test +, Earthquake +, Turbine Missile +, Fuel cladding +, Liquid penetrant +, Pressure Boundary Leakage +, Pressure boundary leak +, Offsite Circuit +, Power change +, Unidentified leakage +, Power Uprate +...

Turbine bypass valve +  and Main Turbine Control Valve +