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ML13205A136 +
10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50.68 +, 10 CFR 50 Appendix I +, 10 CFR 73.54 +, 10 CFR 50.54 +, 10 CFR 50.49#l +, 10 CFR 73.54#a1iii +, 10 CFR 73.54#a1ii +, 10 CFR 50.54#f +, 10 CFR 50.54#w +, 10 CFR 140.11#a4 +, 10 CFR 50.55a#h +, 10 CFR 50.48#a +, 10 CFR 50.48#a1 +, 10 CFR 50.48#a2 +, 10 CFR 50.48#a3 + and 10 CFR 50.71#e +
ML11206A499 +, IR 05000391/2011605 +, IR 05000391/2011607 +, IR 05000391/2013612 +, IR 05000391/2011604 +, IR 05000391/2012602 +, ML101720050 +, IR 05000391/2011609 +, ML073551056 +, ML103480708 +, ML103120711 +, ML101200155 +, ML072570676 +, SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, ML112232205 +, ML092151155 +, ML102360283 +, ML111960228 +, ML111960300 +, ML093631061 +, ML100130227 +, ML100190443 +, ML100539515 +, ML100200375 +, ML100260594 +, ML100270076 +, ML100120052 +, ML101200035 +, ML100480062 +, ML102080017 +...
NRC Generic Letter 04-02 +, NRC Generic Letter 07-01 +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 2006-03 +, NRC Generic Letter 80-77, Refueling Water Level +, NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves +, NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 82-21, Fire Protection Audits +, NRC Generic Letter 83-33, NRC Positions on Certain Requirements of Appendix R to 10 CFR 50 +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, 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 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition +, NRC Generic Letter 06-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +...
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ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 +, ML13205A136 + and ML13205A136 +
2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months) +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months) +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 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) +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months) +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months) +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months) + and 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months) +
Tritium + and Iodine-131 +
June 30, 2013 +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
08:08:38, 6 February 2020 +
NUREG-1793 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 + and NUREG-1852, G20070440 - William J. Shack Ltr Re Draft Final NUREG-1852, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire +
207 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML13205A136 + and ML13205A136 +
Request +
Regulatory Guide 1.97 +, Regulatory Guide 1.189 +, Regulatory Guide 1.180 +, Regulatory Guide 1.75 +, Regulatory Guide 1.70 +, Regulatory Guide 1.100 +, Regulatory Guide 1.8 +, Regulatory Guide 1.133 +, Regulatory Guide 1.152 +, Regulatory Guide 1.168 +, Regulatory Guide 1.153 +, Regulatory Guide 1.209 + and Regulatory Guide 1.169 +
June 30, 2013 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Emergency Response Data System +, HVAC +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray + and Turbine Gland Sealing System +
NUREG-0847 Supp 26 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +
Hot Short +, Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Anticipated operational occurrence +, Commercial Grade Dedication +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Enforcement Discretion +, Operating Basis Earthquake +, Operator Manual Action +, Cyber Security +, Zebra Mussel +, Multiple Spurious Operation +, Emergency Lighting +, Finite Element Analysis +, Condition Adverse to Quality +, B.5.b +, Thermoset +, Stress corrosion cracking +, Loss of Offsite Power +, Hemyc +, Earthquake +, Commercial Grade +, Fuel cladding +...
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