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ML11206A499 +
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 21.3 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 2.390 +, 10 CFR 50.34 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.50 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 73.54 +, 10 CFR 50.54 +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.55a +, 10 CFR 50.49#l +, 10 CFR 50.54#f +, 10 CFR 50.54#w +, 10 CFR 50.34#f +, 10 CFR 140.11#a4 +, 10 CFR 50.34#f2xix +, 10 CFR 50.34#b6iii +...
ML072060688 +, ML080320443 +, ML110260025 +, ML072060473 +, ML101720050 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, ML073551056 +, ML072190047 +, ML103480708 +, ML101940236 +, ML103120711 +, ML101200155 +, ML072570676 +, SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, ML072060488 +, ML092151155 +, ML073230681 +, ML103200146 +, ML003708056 +, ML083310185 +, ML110140103 +, ML022540925 +, ML032880062 +, ML073520546 +, ML090920506 +, ML100710442 +, ML090700378 +, ML072060469 +, ML072060479 +, ML072060486 +...
GDC 20 +, GDC 41 +, GDC 44 +, GDC 34 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 56 +, GDC 35 +, GDC 14 +, GDC 18 +, GDC 21 +, GDC 24 +, GDC 11 +, GDC 13 +, GDC 46 +, GDC 31 +, GDC 39 +, GDC 45 +, GDC 40 +, GDC 25 +, GDC 64 +, GDC 23 +, GDC 28 +, GDC 22 +, GDC 29 +, GDC 37 +, GDC 42 +, GDC 43 +, GDC 27 +...
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 81-07, Control of Heavy Loads +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, 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 83-22, Safety Evaluation of "Emergency Response Guidelines" +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products +, 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 91-05, Licensee Commercial-Grade Procurement and Dedication Programs +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, 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 95-02, Use of Numarc/epri Report TR-102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 +, 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 +...
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ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 +, ML11206A499 + and ML11206A499 +
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months) +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months) +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months) +, 2.199074e-4 d (0.00528 hours, 3.141534e-5 weeks, 7.2295e-6 months) +, 5.324074e-4 d (0.0128 hours, 7.60582e-5 weeks, 1.7503e-5 months) + and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months) +
IEEE 384 +, IEEE 344 +, IEEE 323 +, IEEE 279 +, IEEE 603-1991 +, IEEE 279-1971 +, IEEE 603 +, IEEE 379 +, IEEE 308 +, IEEE 344-1975 +, IEEE 384-1992 +, IEEE 384-1981 +, IEEE 344-2004 +, IEEE 829 +, IEEE 1012 +, IEEE 1028 +, IEEE 1012-1998 +, IEEE 1028-1997 +, IEEE 830 +, IEEE 1012-1986 +, IEEE 1028-1988 +, IEEE 352 + and IEEE 829-1998 +
June 30, 2011 +
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23:29:31, 10 March 2020 +
NUREG-1431 +, NUREG/CR-6101 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-847 +, NUREG/CR-6303 +, NUREG-0085 +, NUREG-01 +, 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-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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 +, NUREG-0718, Forwards Final Rule on Licensing Requirements for Pending CP & Mfg License Applications & NUREG-0718,Revision 2.SER Comparison to New Requirements Revealed Util Commitments & CP Conditions Conform to Nureg.W/O NUREG +, NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +, NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +, NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 + and NUREG-0460 +
354 +
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Request +
Regulatory Guide 1.97 +, Regulatory Guide 1.180 +, Regulatory Guide 1.27 +, Regulatory Guide 1.75 +, Regulatory Guide 1.9 +, Regulatory Guide 1.147 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.70 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.100 +, Regulatory Guide 1.105 +, Regulatory Guide 1.181 +, Regulatory Guide 1.53 +, Regulatory Guide 1.8 +, Regulatory Guide 1.99 +, Regulatory Guide 1.29 +, Regulatory Guide 1.41 +, Regulatory Guide 3.54 +, Regulatory Guide 1.133 +, Regulatory Guide 1.152 +, Regulatory Guide 1.168 +, Regulatory Guide 1.89 +, Regulatory Guide 1.153 +, Regulatory Guide 1.68 +, Regulatory Guide 1.69 +, Regulatory Guide 1.11 +, Regulatory Guide 1.40 +, Regulatory Guide 9.3 +...
June 30, 2011 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Emergency Response Data System +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Intermediate Range Monitor +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Turbine Gland Sealing System +...
NUREG-0847 Supp 23, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2. +
Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Fire Barrier +, Anticipated operational occurrence +, Commercial Grade Dedication +, Weld Overlay +, Post Accident Monitoring +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, Operator Manual Action +, Cyber Security +, Incorporated by reference +, Condition Adverse to Quality +, High Energy Line Break +, Tornado Missile Protection +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Safeguards Contingency Plan +, Battery sizing +, Hemyc +, Earthquake +, Commercial Grade +...
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.
WCAP-9401 +, WCAP-8584 +, WCAP-13869 +, WCAP-13191 +, WCAP-16097-P-A +, WCAP-16096-NP-A +, WCAP-16097-NP-A +, WCAP-8691-P + and WCAP-16096 +