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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

• ML20078C782  + (Cajun Electric Power Cooperative,Inc Concise Statement of Matl Facts to Which Genuine Issue Exists Accompanying & Supporting Answer to Gulf State Utilities Company Motion for Summary Disposition.W/Certificate of Svc)
• ML20024J308  + (Cajun Electric Power Cooperative,Inc Motion to Compel Responses to Interrogatories & Production of Documents.* Requests Board to Issue Order Against Gsu Compelling Production of Listed Items.W/Certificate of Svc)
• ML20138M764  + (Cajun Electric Power Cooperative,Inc,1984 Annual Rept)
• ML15176A701  + (Cal OES Letter to FEMA Regional Administrator (Karen Armes) Dated June 11, 2015)
• ML15176A716  + (Cal OES Letter to SCE Vice President/Chief Nuclear Officer (Tom Palmisano) Dated June 11, 2015)
• ML20034H202  + (Cal,Suppl 1 Responding to Arnold Re Resumption of Mfg & Distribution of Model NCI-21PF-1 Packagings.Advises That as Part of Items 1 & 2,index by Title/Subj of SOPs & Schedule for Training of Personnel Should Be Provided)
• ML16092A036  + (Calc Control Sheet Attachment 22 ENTR-078-CALC-003, Rev 4 Page 216 of 219)
• ML17363A086  + (Calc No. NEE-323-CALC-001, Primary Containment Radiation EAL Threshold Determination)
• ML17363A079  + (Calc No. NEE-323-CALC-002, Dose Rate Evaluation of Reactor Vessel Water Levels During Refueling for EAL Thresholds)
• ML17363A085  + (Calc No. NEE-323-CALC-002, Dose Rate Evaluation of Reactor Vessel Water Levels During Refueling for EAL Thresholds)
• ML17363A075  + (Calc No. NEE-323-CALC-003, Documentation of the RU1 Emergency Action Levels)
• ML17363A078  + (Calc No. NEE-323-CALC-004, Revised Liquid Radiological EALs Per NEI 99-01)
• ML17363A076  + (Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 6)
• ML17363A082  + (Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06)
• ML17363A088  + (Calc No. NEE-323-CALC-006, Correlation of Drywell Radiation Monitors for 300 Uci/Gm Dose Equivalent Iodine)
• ENS 44181  + (Calcium Chloride Spilled on Site)
• ML20260D979  + (Calcium Fluoride Dewatering General Plan. Sheet 1)
• U-602613, Calcs for Functional Requirements for First & Second Level Undervoltage Relays at 4kV 1A1,1B1 & 1C1  + (Calcs for Functional Requirements for First & Second Level Undervoltage Relays at 4kV 1A1,1B1 & 1C1)
• ML12214A553  + (Calculated Peak Containment Internal Pressure LAR Acceptance Review Results TAC No. ME9081-82)
• ML061390077  + (Calculation - Areva - Meteorology Document, PNPS)
• ML14324A322  + (Calculation - DC00040-118 - Main Steam Line Break - TSC)
• RC-14-0179, Calculation - DC00040-118 - Main Steam Line Break - TSC  + (Calculation - DC00040-118 - Main Steam Line Break - TSC)
• ML14324A323  + (Calculation - DC00040-119 - Reactor Coolant Pump Locked Rotor - TSC)
• RC-14-0179, Calculation - DC00040-119 - Reactor Coolant Pump Locked Rotor - TSC  + (Calculation - DC00040-119 - Reactor Coolant Pump Locked Rotor - TSC)
• ML14324A324  + (Calculation - DC00040-120 - Fuel Handling Accident -TSC)
• RC-14-0179, Calculation - DC00040-120 - Fuel Handling Accident -TSC  + (Calculation - DC00040-120 - Fuel Handling Accident -TSC)

• ML14324A325  + (Calculation - DC00040-121 - Steam Generator Tube Rupture - TSC)
• RC-14-0179, Calculation - DC00040-121 - Steam Generator Tube Rupture - TSC  + (Calculation - DC00040-121 - Steam Generator Tube Rupture - TSC)

• ML14324A327  + (Calculation - DC00040-122 - Loss of Coolant Accident - TSC)
• RC-14-0179, Calculation - DC00040-122 - Loss of Coolant Accident - TSC  + (Calculation - DC00040-122 - Loss of Coolant Accident - TSC)
• RC-14-0179, Calculation - DC00040-123 - Rod Ejection Accident - TSC  + (Calculation - DC00040-123 - Rod Ejection Accident - TSC)
• L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac)  + (Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac))
• ML20216E689  + (Calculation 0067-000-84-C-020 (PS-0920), Clipped A-46 Spectra for Radwaste/Turbine Building. W/14 Oversize Drawings)
• ML20216E716  + (Calculation 0067-00084-C-011 PS-0912, LAR of Raceways)
• ONS-2018-016, Calculation 0079-0191-CALC-002, Induced Differential Voltage in Control Cables  + (Calculation 0079-0191-CALC-002, Induced Differential Voltage in Control Cables)
• ML070871112  + (Calculation 0108-0342-JFL-01, Rev 0, Analysis of CCW Supply Temperature During LOCA Recirculation)
• ML040640734  + (Calculation 02-E-0004-01, Rev. 0, Zone 99-M PSA Analysis for Operator Action SDP)
• L-MT-13-019, Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer  + (Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer)
• ML16279A052  + (Calculation 0326-0062-CLC-01, Rev. 0, Evaluation of ACI Equation for Elastic Modulus)
• ML16279A051  + (Calculation 0326-0062-CLC-03, Rev. 2, Correlation Between Through-Thickness Expansion and Elastic Modulus in Concrete Test Specimens Affected by Alkali-Silica Reaction (Asr))
• SBK-L-16153, Calculation 0326-0062-CLC-04, Rev. 0, Calculation of Through-Wall Expansion from Alkali-Silica Reaction To-Date at Seabrook Station  + (Calculation 0326-0062-CLC-04, Rev. 0, Calculation of Through-Wall Expansion from Alkali-Silica Reaction To-Date at Seabrook Station)
• ML16279A053  + (Calculation 0326-0074-CLC-02, Rev. 0, Compressive Strength Values for Concrete at Seabrook Station)
• ML090260121  + (Calculation 07Q3691-CAL-003, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Supply Line Diesel Generator 1A Unit 1)
• ML090260122  + (Calculation 07Q3691-CAL-004, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Return Line Diesel Generator 1A Unit 1)
• ML090260123  + (Calculation 07Q3691-CAL-005, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Supply Line Diesel Generator 1B Unit 1)
• ML090260124  + (Calculation 07Q3691-CAL-006, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Return Line Diesel Generator 1B Unit 1)
• ML090260125  + (Calculation 07Q3691-CAL-007, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Supply Line Diesel Generator 2A Unit 2)
• ML090260126  + (Calculation 07Q3691-CAL-008, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Return Line Diesel Generator 2A Unit 2)
• ML090260127  + (Calculation 07Q3691-CAL-009, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Supply Line Diesel Generator 2B Unit 2)
• ML090260128  + (Calculation 07Q3691-CAL-010, Revision 0, Analysis of Buried Hdpe Piping System - Nuclear Service Water (NSW) Return Line Diesel Generator 2B Unit 2)
• L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis  + (Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis)
• L-09-122, Calculation 0900354.301, Rev. 0, Flaw Evaluation for N6A and C Nozzle to Safe End Welds  + (Calculation 0900354.301, Rev. 0, Flaw Evaluation for N6A and C Nozzle to Safe End Welds)