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List of results

• ML13162A585  + (Reactor Oversight Program Info)
• ML20085A471  + (Reactor Performance Status Rept for Apr 1974.Answers Found Give Raise to New Questions.Confusion Exists on Higher Level)
• ML20054H830  + (Reactor Physics Design Calculations for the Acpr Upgrade)
• ML20266B830  + (Reactor Plant 3X3 Instrumented Fuel Assy General Assy)
• ML20266B816  + (Reactor Plant 3x3 Fuel Assembly for Instrumentation)
• ML041910310  + (Reactor Plant Event Notification Worksheet, EN 37839, Facility: Susquehanna LLC)
• ML20266B834  + (Reactor Plant Fuel Assembly)
• ML20262D426  + (Reactor Plant Heating & Ventilating System)
• ML20085D228  + (Reactor Plant Operating Experience Rept Apr 1962-1963)
• ML20262D444  + (Reactor Plant Piping Section K-K, as-built)
• ML20266B825  + (Reactor Plant Type L Assy)
• ML24355A140  + (Reactor Plenum Flow Meters License Amendment)
• ML24355A141  + (Reactor Plenum Flow Meters License Amendment)
• ENS 41085  + (Reactor Power Being Reduced Due to Entering Ts 3.0.3 Because of Inopeable Recirc Vent System)
• ML18151A894  + (Reactor Power Distribution Analysis Using Moveable In-Core Detection Sys & Tip/Cecor Computer Code Package)
• ENS 48402  + (Reactor Power Exceeded Fsar Analyzed Value)
• ENS 43830  + (Reactor Power Inadvertently Increased Above Accident Analysis Limit)
• ENS 42187  + (Reactor Power Operation in Excess of Operating License Condition)
• 05000313/FIN-2018003-06  + (Reactor Power Transient Caused by the Turbine Bypass Valve Failing Open)
• 05000400/FIN-2013002-05  + (Reactor Power Transient Due to Inadvertent Isolation of the 4B Feedwater Heater)
• GO2-95-277, Reactor Power Uprate Startup Test Rept, for WNP-2  + (Reactor Power Uprate Startup Test Rept, for WNP-2)
• ENS 43627  + (Reactor Pressure Boundary Leakage)
• ENS 48853  + (Reactor Pressure Boundary Leakage)
• 05000286/FIN-2018002-01  + (Reactor Pressure Boundary Leakage Due to Weld Failure in Reactor Vessel Head Penetration #3)
• 05000341/LER-2023-003, Reactor Pressure Boundary Leakage at Socket Weld on Reactor Recirculation Sample Line Caused by Fatigue Failure  + (Reactor Pressure Boundary Leakage at Socket Weld on Reactor Recirculation Sample Line Caused by Fatigue Failure)

• ENS 51861  + (Reactor Pressure Bounday Leakage)

• ML20078D843  + (Reactor Pressure Vessel)
• ML20203C710  + (Reactor Pressure Vessel & Surveillance Program Matls Licensing Info for Surry Units 1 & 2)
• ML20203C727  + (Reactor Pressure Vessel & Surveillance Program Matls Licensing Info for North Anna Units 1 & 2)
• ML052520266  + (Reactor Pressure Vessel (RPV) Removal - NUREG 0612 Compliance)
• NL-11-1081, Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21)  + (Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21))
• ENS 40211  + (Reactor Pressure Vessel Boundry Leakage Found During Inspection)
• 05000400/LER-2018-002, Reactor Pressure Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking  + (Reactor Pressure Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking)
• PMNS20211318, Reactor Pressure Vessel Embrittlement Monitoring and Prediction in Long-Term Operation  + (Reactor Pressure Vessel Embrittlement Monitoring and Prediction in Long-Term Operation)
• ML20127J265  + (Reactor Pressure Vessel End-of-Life Upper Shelf Energy for Nozzle Course Plate Matl)
• ML20055E159  + (Reactor Pressure Vessel Evaluation Rept)
• ML20205P469  + (Reactor Pressure Vessel Failure Probability Following THROUGH-WALL Cracks Due to Pressurized Thermal Shock Events)
• ML111101020  + (Reactor Pressure Vessel Flaw Evaluation)
• ML032731422  + (Reactor Pressure Vessel Flaw Evaluation)
• ML20009D192  + (Reactor Pressure Vessel Flooding Emergency Procedure)
• ML063560114  + (Reactor Pressure Vessel Fluence Evaluation at End of Cycle 15 and 54 EFPY (Non-Proprietary))
• ML101040789  + (Reactor Pressure Vessel Fluence Profiles and Maximum Fluences for Vessel Welds and Plates Extracted from Transware Report Nos. EXL-FLU-001-R-004 and EXL-FLU-001-R-002)
• ML030140545  + (Reactor Pressure Vessel Head (Rvhp) Penetration Concerns at North Anna Power Station, Unit 1)
• L-10-178, Reactor Pressure Vessel Head Commitment Letter  + (Reactor Pressure Vessel Head Commitment Letter)
• 05000454/LER-2012-004, Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Repair Surface Indications  + (Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Repair Surface Indications)
• ML030280586  + (Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60 Day Response for Kewaunee Nuclear Plant, Request for Additional Information)
• NRC 2003-0006, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567)  + (Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567))
• ML030280508  + (Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567))
• ML053070495  + (Reactor Pressure Vessel Head Diagram)
• LIC-03-0163, Reactor Pressure Vessel Head Examination Report  + (Reactor Pressure Vessel Head Examination Report)
• ML063620124  + (Reactor Pressure Vessel Head Inspection)