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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML12152A409 + (PVNGS-2012-03-Final-Operating-Test)
- ML12156A058 + (PVNGS-2012-03-Public Forms)
- ML042960232 + (PVTS-01, Revision 8, SRP Approved Version Palo Verde Transmission System Interchange Scheduling and Congestion Management Procedure)
- ML19058A260 + (PWR & BWR Knowledge and Abilities Master Catalogs)
- L-PI-12-078, PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25 + (PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25)
- Information Notice 1988-67, PWR Auxiliary Feedwater Pump Turbine Overspeed Trip Failure + (PWR Auxiliary Feedwater Pump Turbine Overspeed Trip Failure)
- ML20052C952 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 162)
- ML20063C168 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 161)
- ML20063C189 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 163)
- ML20052C950 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 165)
- ML20052C864 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 171)
- ML20052D023 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 160)
- ML20052C869 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 177)
- ML20052B852 + (PWR Blowdown Heat Transfer SEPARATE-EFFECTS PROGRAM-THERMAL- Hydraulic Test Facility Experimental Data Report for Test 164R)
- ML20197B001 + (PWR Blowdown Heat Transfer Separate Effects Program Thermal-Hydraulic Test Facility Experimental Data Rept for Test 156)
- ML19317H192 + (PWR Blowdown Heat Transfer Separate Effects Program:Thermal-Hydraulic Test Facility Experimental Data Rept for Test 168R)
- ML20148D591 + (PWR Blowdown Heat Transfer Separate Effects Program, Thermal-Hydraulic Test Facility Experimental Data Rept for Test 155)
- ML19256A369 + (PWR Blowdown Heat Transfer Separate Effects Program Thermal-Hydraulic Test Facility Experimental Data Rept for Test 158)
- ML19282D136 + (PWR Blowdown Heat Transfer Separate Effects Program Data Evaluation Rept,Thtf Test Series II)
- ML20147J008 + (PWR Blowdown Heat Transfer Separate Effects Program Test 157)
- ML20148D609 + (PWR Blowdown Heat Transfer Separate Effects Program,Thermal Hydraulic Test Facility Experimental Data Rept for Test 154R)
- ML19309E392 + (PWR Blowdown Heat Transfer Separate-Effects Program:Thermal -Hydraulic Test Facility Experimental Data Rept for Test 167R)
- ML20148M852 + (PWR Blowdown Heat Transfer Separate-Effects Prog Data Eval Rept,Heat Transfer for Thtf Series 100)
- ML19309E398 + (PWR Blowdown Heat Transfer Separate-Effects Program:Thermal -Hydraulic Test Facility Experimental Data Rept for Test 152)
- ML021770166 + (PWR Chemistry Program Manager Interview Questions)
- ML20056B544 + (PWR Dry Containment Issue Characterization)
- ML20073M860 + (PWR Dry Containment Parametric Studies)
- ML20041D016 + (PWR FLECHT-SEASET Steam Generator Separate Effects Task Data Analysis and Evaluation Report.Nrc/Epri/Westinghouse Report No. 9)
- ML19321A887 + (PWR Flecht SEASET,21-Rod Bundle Flow Blockage Task,Task Plan Rept, Nrc/Epri/Westinghouse Rept 5)
- ML19338G382 + (PWR Flecht Seaset 161-ROD Bundle Flow Blockage Task)
- ML20086A142 + (PWR Flecht Seaset 163-ROD Bundle Flow Blockage.Task Data Report.Nrc/Epri/Westinghouse Report No. 13)
- ML20069H879 + (PWR Flecht Seaset 21-ROD Bundle Flow Blockage Task Data and Analysis Report,Nrc/Epri/Westinghouse Report No. 11)
- ML20069J053 + (PWR Flecht Seaset 21-ROD Bundle Flow Blockage Task Data and Analysis Report,Nrc/Epri/Westinghouse Report No. 11)
- ML19323A814 + (PWR Flecht Seaset Steam Generator Separate Effects Task Data Rept)
- ML20071D850 + (PWR Flecht Seaset Systems Effects Natural Circulation and Reflux Condensation.Task Plan Report.Nrc/Epri/Westinghouse Report No. 12)
- ML20093C164 + (PWR Flecht Seaset Systems Effects Natural Circulation and Reflux Condensation.Data Evaluation and Analysis Report Nrc/Epri/Westinghouse Report No. 14)
- ML20009A403 + (PWR Flecht Seaset Unblocked Bundle,Forced and Gravity Reflood Task Data Report.Appendix C - Date Tables and Plots)
- ML20069A807 + (PWR Flecht Seaset Unblocked Bundle,Forced and Gravity Reflood Task Data Evaluation and Analysis Report. Nrc/Epri/Westinghouse Report No. 10)
- ML20037D250 + (PWR Flecht Seaset Unblocked Bundle,Forced and Gravity Reflood Task Data Report.Main Report and Appendix A,B,D,E,F, G)
- LIC-03-0122, PWR Fuel Design Criteria & Statistical Setpoint Calculations for Fort Calhoun Station Measurement Uncertainty Recapture Power Uprate + (PWR Fuel Design Criteria & Statistical Setpoint Calculations for Fort Calhoun Station Measurement Uncertainty Recapture Power Uprate)
- ML14247A564 + (PWR ISI RFI 2014-005)
- ML19254D202 + (PWR Lateral Core Response Routine.Famrec(Fuel Assembly Mechanical Response Code))
- ML17346A351 + (PWR Lattice Physics Methods at Florida Power & Light Co)
- ML16274A001 + (PWR MSIP Analysis and Measurements)
- ML20065F295 + (PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),AR Nuclear One,Unit 1, Technical Evaluation Rept)
- ML20027B586 + (PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Rancho Seco Nuclear Generating Station, Technical Evaluation Rept)
- ML18047A570 + (PWR Main Steam Line Break W/Continued Feedwater Addition (B-69), Request for Addl Info)
- ML20086D381 + (PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Palisades Plant, Technical Evaluation Rept)
- ML20065F725 + (PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),Oconee Nuclear Station Units 1,2 & 3, Technical Evaluation Rept)
- ML20067D532 + (PWR Main Steam Line Break W/Continued Feedwater Addition, Re Ginna Nuclear Power Plant, Technical Evaluation Rept)
- ML17301A013 + (PWR Main Steam Line Break W/Continued Feedwater Addition (B-69),St Lucie Unit 1, Technical Evaluation Rept)