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 Issue dateTitle
05000331/FIN-2017004-01Failure to Maintain Reactor Water Level within Procedurally Required Level Band Results in Reactor Recirculation Pump Runback
ENS 43271Manual Reactor Scram Due to Lowering Reactor Vessel Water Level
ENS 53676Automatic Reactor Trip Due to Feedwater Regulating Valve Failing Closed
IR 05000331/199301013 September 1993Insp Rept 50-331/93-10 on 930708-0823.No Violations Noted. Major Areas Inspected:Followup of Events,Operational Safety, Maint,Surveillance,Regional Requests,Mgt Meetings & Rept Reviews
IR 05000331/19930153 November 1993Insp Rept 50-331/93-15 on 930824-1014.Violations Noted. Major Areas Inspected:Followup of Events,Operational Safety, Maintenance,Surveillance,Regional Request & Temporary Instruction
IR 05000331/19970062 September 1997Insp Rept 50-331/97-06 on 970324-0701.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Assessment of Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems
IR 05000331/200300315 April 2003IR 05000331-03-003, on 12/29/2002-03/31/2003, Ies Utilities, Inc.; Duane Arnold Energy Center; Flood Protection Measures, Operability Evaluations, Refueling and Outage Activities, Surveillance Testing, Event Follow-up, and Other Activities
IR 05000331/20040069 March 2004IR 05000331-04-006(DRS), 01/26/2004 - 02/13/2004; Duane Arnold Energy Center; Safety System Design and Performance Capability
IR 05000331/20090035 August 2009IR 05000331-09-003, on 04/01/09 - 06/30/09, Duane Arnold Energy Center, Equipment Alignment and Follow-Up of Events and Notices of Enforcement Discretion
IR 05000331/20140054 February 2015IR 05000331/2014005; 10/01/2014 - 12/31/2014; Duane Arnold Energy Center; Inservice Inspection Activities; Operability Determinations and Functionality Assessments; Surveillance Testing; Radiological Hazard Assessment and Exposure Controls;
IR 05000331/201700422 January 2018NRC Integrated Inspection Report 05000331/2017004; 07200032/2017001; and Emergency Preparedness Annual Inspection Report 05000331/2017501
IR 05000331/201901311 December 2019Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000331/2019013
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
L-2019-105, License Amendment Request (TSCR-183): Application to Revise Operating License and Technical Specifications for Permanently Defueled Condition20 June 2019License Amendment Request (TSCR-183): Application to Revise Operating License and Technical Specifications for Permanently Defueled Condition
ML01310042910 October 2001Transmittal of Emergency Plan Implementing Procedures EPIP Index Rev 122, EPIP 2.5 Rev 13, EPIP 2.6 Rev 7, EPIP 2.7 Rev 5, EPIP 3.1 Rev 10, EPIP 3.2 Rev 11, EPIP 3.3 Rev 16, EPIP 4.2 Rev 5, EPIP 4.3 Rev 9, EPIP 4.5 Rev 5, EPIP 5.2 Rev 8 for
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0328303551 October 2003Transmittal of Entire EAL Basis Document (Table of Contents Rev)
ML0328902508 October 20031 to EPIP 1.1, Revision 28 to EPIP 1.2, Revision 5 to EPIP 1.4, and Revision 5 to EPIP 1.5
ML04042042430 January 2004Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process
ML05124033231 January 2005Attachments - Initial Submittal of the Jpms for Duane Arnold Initial Exam - Jan/Feb 2005
ML05125031231 January 2005Final As-Administered Jpms for the Duane Arnold Initial Examination - Jan/Feb 2005
ML05227007318 April 2005Event Notification Report for April 18, 2005
ML05305030916 December 2010Current Facility Operating License DPR-49, Tech Specs, Revised 03/17/2018
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML0806704197 March 2008CDBI Findings
ML10035115721 September 2009DAEC 2009 Initial Exam Proposed Written-RO
ML10293052416 December 2010Issuance of Renewed Facility Operating License No. DPR-49 for Duane Arnold Energy
ML11241080424 November 1980LER 80-055/01T-0:on 801110,main Steam Relief Valve Stuck Open Resulting in Rx Scram.Caused by Wiring Error During 1980 Design Change Work & Inadequate post-installation Testing.Error Corrected & Test Procedure Revised
ML12121A68730 April 2012Regional Library TRM Rev. 21
ML13051A2661 March 2013Reliefs from the Requirements of the ASME Boiler and Pressure Vessel Code for the Fourth 10-Year Inservice Inspection Interval
ML13308A83916 April 20132013 DAEC Initial License Examination Administered Written Exam with Answers and References
ML13308A92616 April 20132013 DAEC Initial License Examination Proposed Written Exam with Answers
ML16153A09118 August 2016Issuance of Amendment to Revise the Value of Reactor Steam Dome Pressure
ML16211A51412 September 2016Issuance of Amendment to Revise Technical Specifications 2.1.1.2, Safety Limit Minimum Critical Power Ratio
ML17115A19724 April 20175/1/17, Meeting Slide for Pre-application Teleconference with NextEra Energy Duane Arnold, LLC Regarding a License Amendment Request for Duane Arnold Energy Center to Adopt TSTF-542
ML17157B68022 May 2017Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
ML17199A11818 July 2017NRR E-mail Capture - LIC-109 Acceptance - DAEC LAR (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control MF9829