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ML16242A111 +
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.49 +, 10 CFR 50.57 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 100.11 +, 10 CFR 50.49#b +, 10 CFR 50.67#b2 +, 10 CFR 50.67#b2i +, 10 CFR 50.67#b1 +, 10 CFR 50.54#0 +, 10 CFR 50.34#b +, 10 CFR 50.34#b2 +, 10 CFR 50.34#a1 +, 10 CFR 50.34#a4 +, 10 CFR 50.48#c +, 10 CFR 50.48#a +, 10 CFR 51.22#b + and 10 CFR 51.22#c9 +
Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +, Regulatory Guide 1.23 +, ML051400209 +, ML15029A022 +, ML041040063 +, ML040420012 +, ML053460347 +, ML003734190 +, ML021720780 +, ML003740205 +, ML063600394 +, ML070730398 +, ML070550069 +, ML070190178 +, ML070820123 +, ML051390358 +, ML12045A149 +, ML011210348 +, ML012190402 +, ML063460464 +, Regulatory Guide 1.203 +, ML16242A111 +, ML15323A434 +, ML16169A129 +, ML070250176 +, ML110730473 +, ML12039A201 +...
80 FR 17091 + and 72 FR 12838 +
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>.
ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +, ML16242A111 +...
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months) +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months) +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months) +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months) +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months) +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months) +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +, 0.00139 d (0.0333 hours, 1.984127e-4 weeks, 4.566e-5 months) + and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months) +
October 20, 2016 +
ML022980619 +, AEP-NRC-2016-56, Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term +, ML15323A433 +, AEP-NRC-2015-80, Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term + and AEP-NRC-2015-19, Supplemental Information for the License Amendment Request to Adopt TSTF-490, Rev 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and Implement Full-Scope +
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01:44:06, 10 January 2025 +
NUREG/CR-5950 +, NUREG/CR-2858 +, NUREG/CR-6189 +, NUREG/CR-5966 +, NUREG/CR-0009 +, NUREG/CR-5175 +, NUREG-0917 +, NUREG/CR-7220 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, 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 + and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
76 +
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Approval +
October 20, 2016 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam + and Containment Spray +
DC Cook, Units 1 and 2 - Issuance of Amendments Adoption of TSTF-490,REV.0,Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and Implementation of Full-Scope Alternative Source Ter +
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