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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
- ML17199X994 + (ML17199X994)
- ML17199Y088 + (ML17199Y088)
- 05000249/LER-1988-010-01, :on 880424,main Steam Safety Valve 3-203-4D Opened at Pressure in Excess of Tech Spec 4.6.E Required Setpoint.Caused by Setpoint Drift.Valve Overhauling,Setting & Retesting Prior to Installation Planned + (ML17199Y139)
- ML17199Y180 + (ML17199Y180)
- 05000237/LER-1988-005-06, :on 880426,reactor Bldg Ventilation Sys (RBVS) Tripped,Initiating Standby Gas Treatment a Sys Train.Caused by Spurious Instantaneous Spike on Unit 2 Rbvs.Calibr Check of Unit 2 RBVS Performed Satisfactorily + (ML17199Y223)
- 05000237/LER-1988-006-07, :on 880429,primary Nitrogen Inerting Makeup Sys Line Kinked & Cracked.Caused by Personnel Error & Rigging Procedure Deficiency.Rigging Procedure Improvement Initiated & Addl Rigging Operations Training Planned + (ML17199Y270)
- ML17199Y309 + (ML17199Y309)
- ML17199Y357 + (ML17199Y357)
- ML17199Y400 + (ML17199Y400)
- ML17199Y441 + (ML17199Y441)
- PNO-III-88-046A, updates Augmented Insp Team Investigation of Failure of MSIVs to Close During Test.On 880525,region Determined That Licensee Completed Commitments,Per 880518 Confirmatory Action Ltr.Unit 2 Startup Scheduled on 880526 + (ML17199Y487)
- 05000237/LER-1988-007-06, :on 880504,discovered That CRD Scram Testing Surveillance Interval Exceeded.Caused by Scram Testing Procedure Deficiency.Strip Chart Event Recorder Wired, Utilizing Wire plug-in Jacks + (ML17199Y624)
- ML17199Z054 + (ML17199Z054)
- ML17199Z095 + (ML17199Z095)
- ML17199Z138 + (ML17199Z138)
- ML17199Z183 + (ML17199Z183)
- ML17199Z360 + (ML17199Z360)
- ML17199Z588 + (ML17199Z588)
- 05000237/LER-1988-008-04, :on 880506,reactor Bldg Ventilation Sys Automatically Tripped & Standby Gas Treatment Train Auto Started.Caused by Error in Chemistry Procedure 2000-5. Radiation Source Removed from Monitor + (ML17199Z635)
- 05000249/LER-1988-009-03, :on 880505,Groups II & III Primary Containment Isolation Occurred During Shutdown for Scheduled Refueling Outage.Caused by Mgt Deficiency for Failure to Implement Corrective Actions from Previous Event + (ML17199Z681)
- ML17200A065 + (ML17200A065)
- ML17200A084 + (ML17200A084)
- ML17200A085 + (ML17200A085)
- ML17200A087 + (ML17200A087)
- ML17200A088 + (ML17200A088)
- RAIO-0717-54951, LLC Response to NRC Request for Additional Information No. 41 (Drai No. 884) on the NuScale Design Certification Application + (ML17200A105)
- ML17200A106 + (ML17200A106)
- SBK-L-17117, Inservice Inspection Examination Report + (ML17200A109)
- NL-17-1178, ISFSI - Registration of Spent Fuel Cask Use + (ML17200A111)
- ML17200A113 + (ML17200A113)
- ML17200C780 + (ML17200C780)
- IR 05000400/2017002 + (ML17200C907)
- ML17200C927 + (ML17200C927)
- IR 05000295/2017001 + (ML17200C932)
- ML17200C933 + (ML17200C933)
- RS-17-087, Withdrawal of Inservice Inspection Relief Request I4R-03 Re Examination of the Reactor Pressure Vessel (RPV) Stabilizer Bracket Welds Due to Impracticality + (ML17200C937)
- 05000458/LER-1917-006, Re Potential Loss of Safety Function of Onsite Power Sources Due to Inoperability of Control Building Chiller + (ML17200C938)
- ET 17-0016, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses + (ML17200C939)
- ML17200C940 + (ML17200C940)
- ML17200C942 + (ML17200C942)
- 05000186/LER-1917-005, University of Missouri-Columbia Research Reactor Regarding a Deviation from Technical Specification 3.5.a.3 and Its Associated Note (1) + (ML17200C943)
- RS-17-098, Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) + (ML17200C944)
- L-17-216, Response to NRC Inspection Report 05000440/2017009 and Preliminary White Finding + (ML17200C945)
- RS-17-084, Response to Request for Additional Information for Byron Station and Braidwood Station Post Peening Relief Requests + (ML17200C952)
- L-MT-17-054, Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan. Safeguards Contingency Plan. and Independent Spent Fuel Storage Installation Security Program + (ML17200C955)
- ML17200C957 + (ML17200C957)
- ML17200C967 + (ML17200C967)
- IR 05000237/2017002 + (ML17200D012)
- ML17200D021 + (ML17200D021)
- ML17200D044 + (ML17200D044)
- ML17200D047 + (ML17200D047)