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ML042010289 +
10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.12 +, 10 CFR 50.81 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 73.21 +, 10 CFR 50.54#o +, 10 CFR 50.54#p +, 10 CFR 50.36#c2ii +, 10 CFR 73.55#51 +, 10 CFR 50.46#b1 +, 10 CFR 50.46#a3ii +, 10 CFR 50.46#b5 +, 10 CFR 50.46#b2 +, 10 CFR 2.390#b1 + and 10 CFR 50.92#c +
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>.
ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 +, ML042010289 + and ML042010289 +
July 9, 2004 +
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07:21:15, 16 January 2025 +
NUREG-1493 +, NUREG/CR-3332 +, NUREG-0036 +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0841, Responds to Constituent K Karan Ltr Re Decommissioning Costs & Evacuation Plan for Plant That Would Be Implemented in Event of Accident.More Detailed Info on Decommissioning May Be Found in 1979 Environ Rept & NUREG-0841 + and NUREG-0857, Supplement No. 8 Safety Evaluate on Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 +
182 +
TAC:MA5660 +, TAC:MB1035 +, TAC:MB6328 +, TAC:MB3373 +, TAC:MB6726 +, TAC:MC0870 +, TAC:MB2291 +, TAC:MB3695 + and TAC:M95687 +
Request +
SR-3.0.3 +, SR-3.3.1.1 +, SR-3.0.2 +, SR-3.3.1.8 +, SR-3.3.2.5 +, SR-3.3.1 +, SR-3.3.2.1 +, SR-3.3.1.6 +, SR-3.3.1.9 +, SR-3.3.2.3 + and SR-3.3.2.4 +
July 9, 2004 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Steam Bypass Control System +, Fuel Pool Cooling and Cleanup +, Main Steam Safety Valve +, Qualified Safety Parameter Display System +, Spray Pond +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam + and Containment Spray +
Request for a License Amendment to Support Replacement of Steam Generators & Uprated Power Operations in Units 1 and 3, and Associated Administrative Changes for Unit 2 +
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, High Energy Line Break +, Local Leak Rate Testing +, Feedwater Heater +, Large early release frequency +, Loss of Offsite Power +, Integrated leak rate test +, Safeguards Contingency Plan +, Earthquake +, Pressure boundary leak +, Fire Protection Program +, Flow Induced Vibration +, Power Uprate +, Affidavit +, Loss of condenser vacuum +, Control Room Habitability + and Leak-Before-Break +
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