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ML15033A041 +
10 CFR 50 +, 10 CFR 2.390 +, 10 CFR 50.21 +, 10 CFR 50.49 +, 10 CFR 50.68 +, 10 CFR 50 Appendix I +, 10 CFR 50.54 +, 10 CFR 50.49#l +, 10 CFR 50.49#i +, 10 CFR 50.49#k +, 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 50.36#c1 + and 10 CFR 50.55a#h2 +
ML12054A735 +, ML12054A679 +, ML12312A167 +, ML14163A658 +, IR 05000391/2014604 +, ML14289A222 +, IR 05000391/2013604 +, IR 05000391/2014608 +, IR 05000391/2011605 +, IR 05000391/2011607 +, IR 05000391/2013610 +, IR 05000391/2013612 +, IR 05000391/2014603 +, IR 05000391/2011604 +, IR 05000391/2012602 +, ML101720050 +, IR 05000391/2014602 +, IR 05000391/2011609 +, ML14085A009 +, ML073551056 +, ML110980637 +, ML101200155 +, ML072570676 +, SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, ML112232205 +, ML092151155 +, ML13351A314 +, ML11306A193 +, ML11293A365 +, ML042360586 +...
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 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 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS 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 +, NRC Generic Letter 2003-01, Control Room Habitability +, NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems + and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +
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ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 +, ML15033A041 + and ML15033A041 +
IR 05000390/2014003 +, IR 05000391/2014604 +, IR 05000391/2013604 +, IR 05000391/2014608 +, IR 05000391/2011605 +, IR 05000391/2011607 +, IR 05000391/2013610 +, IR 05000391/2013612 +, IR 05000391/2014603 +, IR 05000391/2011604 +, IR 05000391/2012602 +, IR 05000391/2014602 + and IR 05000391/2011609 +
Tritium + and Iodine-131 +
January 31, 2015 +
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19:50:12, 5 February 2020 +
NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting + and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
121 +
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ML15033A041 + and ML15033A041 +
Request +
SR-3.8.1.7 + and SR-3.8.1.2 +
January 31, 2015 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, 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 Supplement 27, Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2. +
Safe Shutdown +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Safe Shutdown Earthquake +, Hydrostatic +, Operator Manual Action +, Cyber Security +, Multiple Spurious Operation +, Finite Element Analysis +, Condition Adverse to Quality +, Open Phase Condition +, Stress corrosion cracking +, Spent Fuel Pool Instrumentation +, Hemyc +, Earthquake +, Core Exit Thermocouple +, Power Uprate +, Control Room Habitability +, Gas accumulation +, Leak-Before-Break + and Pressure Temperature Limits Report +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.