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ML18347B330 +
10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 20 Appendix B +, 10 CFR 50 Appendix B +, 10 CFR 51 +, 10 CFR 20.1301 +, 10 CFR 50.44 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.68 +, 10 CFR 50.90 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 51.21 +, 10 CFR 100.11 +, 10 CFR 20.106 +, 10 CFR 50.54#p +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2 +, 10 CFR 50.36#b +, 10 CFR 50.61#b2 +, 10 CFR 73.55#c7 +, 10 CFR 50.46#b +...
Regulatory Guide 1.183 +, Regulatory Guide 1.195 +, Regulatory Guide 1.99 +, Regulatory Guide 8.32 +, ML050120209 +, ML11277A148 +, Regulatory Guide 1.24 +, ML070570006 +, ML12324A013 +, ML070100635 +, ML070740002 +, ML15006A035 +, ML16125A114 +, ML072640413 +, ML070710376 +, ML110620086 +, ML070550057 +, ML050250061 +, ML052350118 +, ML052350149 +, ML052350158 +, CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations +, CNL-17-112, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule +, ML16077A093 +, ML022540925 +, ML15345A424 +, ML16159A057 +, ML13141A564 +, RIS 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components +, ML18040A434 +...
84 FR 3259 + and 83 FR 26709 +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +, ML18347B330 +...
May 22, 2019 +
05000390/LER-1917-014, Regarding Main Control Room Boundary Door Left Open Leading to a Loss of Safety Function +, CAC:MG0207 +, CNL-15-192, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Response to NRC Request for Additional Information - Radiation Protection and Consequence Branch +, ML11269A064 +, CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) + and CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) . +
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>.
13:31:08, 5 January 2025 +
NUREG-1431 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-1764 +, NUREG-0711 +, NUREG/CR-6698 +, NUREG-1672 +, NUREG-084 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, 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-0713, Vol.43, Occupation Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2021: Fifty-Fourth Annual Report + and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
94 +
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Approval +
May 22, 2019 +
Tennessee + and Washington +
Steam Generator +, Reactor Coolant System +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Shield Building +, Fuel Pool Cooling and Cleanup +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod + and Main Steam +
Issuance of Amendment Regarding Revision to Watts Bar Unit 2 Technical Specification 4.2.1 Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage +
Safe Shutdown +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Operator Manual Action +, Cyber Security +, Loss of Offsite Power +, Safeguards Contingency Plan +, Tritium Producing Burnable Absorber Rods +, Control of Heavy Loads +, Fuel cladding +, Fire Protection Program +, Basic Component +, Spent fuel rack + and Pressure Temperature Limits Report +
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