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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

• ML20262K473  + (W/D Sequence Loading & Load Shedding Panels DR105 & 106 Train a)
• 05000336/LER-1981-018-21, W/Plant in Hot Standby, Mechanical Snubber Not Previously on IE Bulletin 81-01 Evaluation List Discovered.Caused by Failure of List to Include Mechanical Snubbers on Small Diameter Pipe or Parts  + (W/Plant in Hot Standby, Mechanical Snubber Not Previously on IE Bulletin 81-01 Evaluation List Discovered.Caused by Failure of List to Include Mechanical Snubbers on Small Diameter Pipe or Parts)
• 05000395/LER-1983-008-03, W/Plant in Mode 1,main Control Board Indication for Steam Generator B Steam Pressure Decreased Approx 100 Psig.Caused by Plugged Transmitter Sensing Line.Sensing Line Back Flushed  + (W/Plant in Mode 1,main Control Board Indication for Steam Generator B Steam Pressure Decreased Approx 100 Psig.Caused by Plugged Transmitter Sensing Line.Sensing Line Back Flushed)
• 05000317/LER-1980-011-03, W/Rcs at 130 Degrees & 250 Psia,Shutdown Cooling Suction Header Relief Lifted & Failed to Reset.Caused by Personnel Error.Valve Reset  + (W/Rcs at 130 Degrees & 250 Psia,Shutdown Cooling Suction Header Relief Lifted & Failed to Reset.Caused by Personnel Error.Valve Reset)
• 05000267/LER-1983-022-03, W/Reactor Operating at Approx 13% Power,One Class I Hydraulic Shock Suppressor Found Inoperable.Faulty Rod Seal Allowed Gradual Loss of Operating Fluid from Reservoir.Snubber Replaced  + (W/Reactor Operating at Approx 13% Power,One Class I Hydraulic Shock Suppressor Found Inoperable.Faulty Rod Seal Allowed Gradual Loss of Operating Fluid from Reservoir.Snubber Replaced)
• 05000366/LER-1980-106-03, W/Reactor in Cold Shutdown,Insp of Drywell Insulation Revealed Crystalline Deposits Around Seams on Sacrificial Shield.Cause Unknown. Investigation Inconclusive  + (W/Reactor in Cold Shutdown,Insp of Drywell Insulation Revealed Crystalline Deposits Around Seams on Sacrificial Shield.Cause Unknown. Investigation Inconclusive)
• ML19276E494  + (W/Regard to Questionnaire & Examination of License SNM-1130, There Have Been No Individual Radiation Exposures Beyond Limits,Source Is Stored in Secure Condition & Is Used About Once a Month)
• 05000280/LER-1981-007-03, W/Unit 1 Defueled & 2 at 100% Power,Power for Several Radiation Monitors Lost.Caused by Shorting of Test Lead to Ground Causing Supply Fuse to Blow.Fuse Replaced.Monitors Returned to Svc  + (W/Unit 1 Defueled & 2 at 100% Power,Power for Several Radiation Monitors Lost.Caused by Shorting of Test Lead to Ground Causing Supply Fuse to Blow.Fuse Replaced.Monitors Returned to Svc)
• 05000280/LER-1980-028-03, W/Unit at 100% Power, Reduction in Svc Water Pressure to Charging Pump Experienced.Caused by Missing Valve Disk for 2-SW-113.Check Valve Replaced  + (W/Unit at 100% Power, Reduction in Svc Water Pressure to Charging Pump Experienced.Caused by Missing Valve Disk for 2-SW-113.Check Valve Replaced)
• 05000321/LER-1981-110-03, W/Unit in Hot Standby, Mainstack Monitor Found Inoperative.Caused by Corrosion of Carbon Vanes on Pump B.Vanes Cleaned & Reinstalled in Pump  + (W/Unit in Hot Standby, Mainstack Monitor Found Inoperative.Caused by Corrosion of Carbon Vanes on Pump B.Vanes Cleaned & Reinstalled in Pump)
• 05000362/LER-1983-064-03, W/Unit in Mode 2,ex-core Logarithmic Power Safety Channel C Declared Inoperable & on 830918,channel B Declared Inoperable.Caused by Failed Cable Connectors.Connectors Replaced  + (W/Unit in Mode 2,ex-core Logarithmic Power Safety Channel C Declared Inoperable & on 830918,channel B Declared Inoperable.Caused by Failed Cable Connectors.Connectors Replaced)
• 05000251/LER-1983-010-03, W/Unit in Shutdown,Steam Generator 4A Steam Supply Valve MOV-4-1403 to Auxiliary Feedwater Pump B Failed to Open in Response to Auto Start Signal.Caused by Carbon Buildup  + (W/Unit in Shutdown,Steam Generator 4A Steam Supply Valve MOV-4-1403 to Auxiliary Feedwater Pump B Failed to Open in Response to Auto Start Signal.Caused by Carbon Buildup)
• ML18141A642  + (W05/07/2018 E-mail Westinghouse Transfer of Control Application/Review - Schedule)
• ML23069A276  + (W11 RIC 2023 Opening & Closing Slides)
• ML23061A067  + (W11 RIC 2023 Presentation by George Wilson Re Part 53 Rulemaking)
• ML23061A083  + (W11 RIC 2023 Presentation by Rob Taylor Re Perspectives on Risk-Informed Licensing of Advanced Reactors)
• ML23069A275  + (W11 RIC 2023 Presentation_Adam Stein)
• ML23061A064  + (W11 RIC 2023 Presentation_Jennifer Uhle)
• ML22140A239  + (W11-transcript)
• ML22140A240  + (W12-transcript)
• ML22140A238  + (W12-transcript)
• ML22140A241  + (W13-transcript)
• ML23207A114  + (W14 Million Person Study Boice RIC 2023)
• ML22003A169  + (W14 Reactor Decommissioning and Low-level Waste, RIC 2022, Forms and Presentations)
• ML22140A242  + (W14-transcript)

• ML22140A243  + (W15-transcript)

• ML22140A244  + (W16-transcript)
• ML21081A321  + (W17 - Evans - Illinois Emergency Management Agency Center)
• ML21081A320  + (W17 - Ford - National Incident Management System (Nims) Emergency Operations Center Toolkit)
• ML21081A322  + (W17 - Johnson - Emergency Operations Centers - Evaluation and Response to Nuclear-Related Accidents)
• ML21081A323  + (W17 - Lilliendahl - U.S. Nuclear Regulatory Commission Incident Response Program)
• ML22140A245  + (W17-transcript)
• ML22140A246  + (W18-transcript)
• ML13046A107  + (W19-1579-004, Rev 0, Final Status Survey Plan for the Leslie C. Wilbur Nuclear Reactor Facility at the Worcester Polytechnic Institute)
• ML22140A247  + (W19-transcript)
• ML21078A097  + (W20 - Laura Kozak - Slide Deck 4)
• ML22140A248  + (W20-transcript)
• ML19077A321  + (W23 - Austgen - Nuclear Energy Institute Perspective - Streamlining NRC Environmental Reviews)
• CNRO-2003-00057, W3 CEDM Nozzle Freespan Lengths  + (W3 CEDM Nozzle Freespan Lengths)
• ML081200338  + (W3-2008-03 - Draft - Outlines)
• ML19161A109  + (WAAP-11397 HELB CUF Limit on AP1000 and New Reactors)
• ML24194A027  + (WAAP-13009, Revision 0, Evinci Microreactor Westinghouse TRISO Fuel Design Methodology Topical Report NRC Pre-submittal Meeting)
• ML25105A144  + (WAAP-13236 RIC 2025 - Industrializing Nuclear Artificial Intelligence)
• ML20054F485  + (WAPD-40 Cask SAR for Packaging)
• ML19281A067  + (WARD-D-0169, Clinch River Breeder Reactor Plant,Response of Plant to Postulated Loss of One Heat Transport Loop W/ Failure of Both Reactor Shutdown Sys. Addresses Anticipated Event Causing Most Severe Loss of Heat Removal)
• ML22083A065  + (WAT-2022-02 Draft Outline Comments)
• ML22080A228  + (WAT-2022-02 Final Op Test)
• ML22080A229  + (WAT-2022-02 Final Written Exam)
• W3F1-2022-0019, WAT-2022-02 Post Exam Analysis  + (WAT-2022-02 Post Exam Analysis)
• ML22108A266  + (WAT-2022-02 Public Forms)
• ML030350127  + (WAT-RETAKE EXAM-07/2002- Comment Resolution)