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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
- ML20086S620 + (Systems Interaction Evaluation Procedure for Application to Indian POINT-3)
- Information Notice 1985-85, Systems Interaction Event Resulting in Reactor System Safety Relief Valve Opening Following a Fire-Protection Deluge System Malfunction + (Systems Interaction Event Resulting in Reactor System Safety Relief Valve Opening Following a Fire-Protection Deluge System Malfunction)
- ML20098D995 + (Systems Interaction Results from the Digraph Matrix Analysis of a Nuclear Power Plants High Pressure Safety Injection System)
- ML20098E026 + (Systems Interaction Results from the Digraph Matrix Analysis of a Nuclear Power Plants High Pressure Safety Injection System)
- ML14225A615 + (Systems JPM B)
- ML14225A621 + (Systems JPM C Mod)
- ML14225A623 + (Systems JPM D Mod)
- ML14225A624 + (Systems JPM E Mod)
- ML14225A625 + (Systems JPM F Mod)
- ML14225A631 + (Systems JPM G)
- ML14225A649 + (Systems JPM H)
- ML14225A659 + (Systems JPM I Mod)
- ML14225A663 + (Systems JPM J)
- ML14225A671 + (Systems JPM K)
- ML14225A608 + (Systems JPM a)
- ML18017B760 + (T Avg - Delta T Control Loop Temperature Process Control Block Diagram. Sheet 19)
- ML18017B761 + (T Avg - Delta T Control,Rod Insertion Limit Process Control Block Diagram. Sheet 20)
- ML18017B743 + (T Avg - Delta T Protection System Process Control Block Diagram. Sheet 2)
- ML18017B762 + (T Avg - Delta T Rod Speed & Reduced T Avg Load Follow Process Control Block Diagram. Sheet 21)
- ML20266F651 + (T Bolt Assembly 1/2-13X2.50,Spring Loaded. No Rev Date)
- ML20266E229 + (T Bolt Assembly 1/2-13x2.50,Spring Loaded)
- 05000280/LER-2077-021-01, T Flooding of Valve Pit Containing Emergency Service Water Valves + (T Flooding of Valve Pit Containing Emergency Service Water Valves)
- ML25058A126 + (T Gurdziel Comment Posting Response)
- 05000316/LER-2078-022-01, T Re Higher Calculated Peak Clad Temperature + (T Re Higher Calculated Peak Clad Temperature)
- 05000316/LER-2078-001-01, T Re Two Independent ESF Ventilation System Exhaust Air Filter Trains + (T Re Two Independent ESF Ventilation System Exhaust Air Filter Trains)
- 05000280/LER-2078-012-01, T for Surry Unit 2 Failure to Meet Containment Integrity + (T for Surry Unit 2 Failure to Meet Containment Integrity)
- 05000280/LER-2078-006-01, T for Surry Unit 2 Review of Fire Protection Yard Piping Revealed That Two Pipe Extensions May Not Have Been Seismically Qualified + (T for Surry Unit 2 Review of Fire Protection Yard Piping Revealed That Two Pipe Extensions May Not Have Been Seismically Qualified)
- ML24205A116 + (T&E ISG Regulatory Analysis - Qualitative)
- ML24297A357 + (T&E Implementation Guidance Public Meeting - Meeting Summary)
- ML24297A347 + (T&E Implementation Guidance Public Meeting - Meeting Transcripts)
- ML24284A258 + (T&E Implementation Guidance Public Meeting Presentation)
- ML18130A786 + (T&E Limited Outreach Response)
- 05000280/LER-2077-016-03, T, LER 1977-016-03L Re Excessive Boron Concentration, LER 1977-017-03L, and LER 1977-018-03L + (T, LER 1977-016-03L Re Excessive Boron Concentration, LER 1977-017-03L, and LER 1977-018-03L)
- 05000237/LER-1978-004-01, T-0 for Dresden, Unit 2 Re Improper 125V DC Cable Separation + (T-0 for Dresden, Unit 2 Re Improper 125V DC Cable Separation)
- 05000289/LER-1978-016-01, T-0:on 780503,B&W Identified That for Cycle 4, Peak RCS Pressure Following Accident Exceeds Max Allowable Pressure by 4.4 Psig.Caused by Assuming Larger Instrument Error Associated W/Pressure Sensor.Tech Spec to Be Changed + (T-0:on 780503,B&W Identified That for Cycle 4, Peak RCS Pressure Following Accident Exceeds Max Allowable Pressure by 4.4 Psig.Caused by Assuming Larger Instrument Error Associated W/Pressure Sensor.Tech Spec to Be Changed)
- 05000255/LER-1979-042-01, T-0:on 791012,during Testing of Pressurizer Code Safety Valves,Lift Setting for Two Valves Were 2,897 & 2,462 Psia,Violating Tech Specs.Caused by Mispositioning of Alignment Pin.Future Testing Will Be Done W/Steam + (T-0:on 791012,during Testing of Pressurizer Code Safety Valves,Lift Setting for Two Valves Were 2,897 & 2,462 Psia,Violating Tech Specs.Caused by Mispositioning of Alignment Pin.Future Testing Will Be Done W/Steam)
- 05000255/LER-1982-033-03, T-82B (B Safety Injection Tank) Level Reached Tech Spec Limit of 198 Inches.Caused by Minor Leakage Past Loop Check Valve & Tank Check Valve or Fill & Drain Valve.Valves Will Be Inspected at Next Outage + (T-82B (B Safety Injection Tank) Level Reached Tech Spec Limit of 198 Inches.Caused by Minor Leakage Past Loop Check Valve & Tank Check Valve or Fill & Drain Valve.Valves Will Be Inspected at Next Outage)
- ML12293A302 + (T. Alexander Ltr. Approval of Partial Final Site Survey Plan for University of Michigan Ford Nuclear Reactor)
- ML030380597 + (T. Alexion Memo Re T. Saporito Ltr 2.206 Arizona Public Service Company/Palo Verde Nuclear Generating Stations, Unit 1,2, and 3)
- ML16195A398 + (T. Bassett Letter Safety Concerns at Pilgrim)
- ML12276A199 + (T. Carter Email to S. Roberts Path Forward for Orau/Orise IV Work at University of Michigan Ford Nuclear Reactor)
- ML092720221 + (T. Carter Ltr from Wpi 9/21/09 Transportation Plan)
- ML072960585 + (T. Gatlin Ltr Quality Assurance Program Approval for Radioactive Material Packages No. 0479, Revision 7)
- ML16239A101 + (T. Gurdziel Email Subj: Resolution of Mechanical Problems at the FitzPatrick Plant)
- ML18206A134 + (T. Herrera E-Mail Regarding Avets Information for General Licensed Device)
- ML110270028 + (T. J. Neider Letter Transnuclear In. - NRC Investigation Report No. 4-2010-071 - Non-Cited Violation, Certificate of Compliance No. 72-1029)
- ML021000305 + (T. Koshy Acting Section for PDII-2 Effective 04/08/02 for 3 Months for R.Correia)
- ML15148A564 + (T. Reilly Ltr Zion Nuclear Power Station License Termination Plan Public Comment Period)
- ML052590233 + (T. S. for License Amendment, Temporary Extension of the Nuclear Services Seawater System Train Completion Time)
- IA-19-027, T. Saunders - Presentations for Confirmatory Order (IA-19-027) + (T. Saunders - Presentations for Confirmatory Order (IA-19-027))
- ML071930085 + (T. Seckerson Letter to R. Conte Dtd 05/18/07 Licensing of Indian Point)