ENS 39586 | 3 February 2003 05:00:00 | Philadelphia Va Medical Center | Possible Medical Event at Philadelphia Veterans Administration Medical Center | 10 CFR 35.3045(a)(3) | | Brachytherapy |
ENS 40008 | 22 July 2003 14:48:00 | Monticello | Helb Door Not Latched as Required Due to Personnel Error | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | | Unanalyzed Condition |
ENS 40091 | 20 August 2003 15:45:00 | Kewaunee | Unauthorized Access | 10 CFR 73.71(b)(1), Safeguards Event | | |
ENS 40107 | 27 August 2003 13:24:00 | Hope Creek | Control Room Access Door Latch Was Determiend to Be Not Fully Engaging. | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | | |
ENS 40124 | 2 September 2003 01:45:00 | Portsmouth Gaseous Diffusion Plant | Manual Actuation of Safety Equipment for Autoclave Containment | Other Unspec Reqmnt | | |
ENS 40134 | 5 September 2003 13:33:00 | Susquehanna | High Pressure Coolant Injection (Hpci) Declared Inoperable. | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Reactor Core Isolation Cooling | |
ENS 40146 | 10 September 2003 22:46:00 | Monticello | Unanalyzed Condition Due to a Potential Break in Fire Protection Water System | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | | Safe Shutdown Unanalyzed Condition Fire Protection Program |
ENS 40161 | 16 September 2003 04:30:00 | Davis Besse | Reactor Coolant System Pressure Increase Caused a Valid Signal | 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Reactor Coolant System Emergency Core Cooling System | |
ENS 40216 | 2 October 2003 22:15:00 | Arkansas Nuclear | Rcs Boundary Leakage Due to Small Crack on Drain Line Welded Cap | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Reactor Coolant System | Boric Acid |
ENS 40272 | 23 October 2003 20:40:00 | Susquehanna | Nonemergency Notification Due to Failure to Maintain Control Structure Habitability Envelope | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | HVAC | |
ENS 40305 | 10 November 2003 04:15:00 | Sequoyah | Sequoyah Unit 2 Auxiliary Feedwater Actuation During Outage | 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Feedwater Main Steam Isolation Valve Auxiliary Feedwater Main Condenser | |
ENS 40314 | 10 November 2003 22:40:00 | Summer | Fitness for Duty Program Condition | 10 CFR 26.73, Applicability | | Fitness for Duty |
ENS 40326 | 17 November 2003 17:10:00 | Perry | Division 1 and 2 Diesel Generators and All Eccs Systems Were Declared Inoperable | 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Service water | |
ENS 40359 | 28 November 2003 03:55:00 | Catawba | Component Cooling System Surge Tank Supports May Fail During a Seismic Event | 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | | Unanalyzed Condition |
ENS 40373 | 3 December 2003 18:30:00 | Callaway | Emergency Procedure Deficiency Causes Unanalyzed Condition | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | Control Room Emergency Ventilation | Unanalyzed Condition |
ENS 40378 | 6 December 2003 04:49:00 | Hope Creek | a Level 3 Low Reactor Water Level Was Reached During a Reactor Water Level Transient | 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Reactor Protection System Reactor Water Cleanup | |
ENS 40476 | 25 January 2004 17:10:00 | LaSalle | Inoperable Refueling Interlock | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Control Rod | Safe Shutdown |
ENS 40481 | 26 January 2004 20:30:00 | Monticello | Recirculation Fan Alteration Affects Accident Mitigation | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Emergency Diesel Generator | |
ENS 40505 | 3 February 2004 23:25:00 | Seabrook | Safeguards Report | 10 CFR 73.71(b)(1), Safeguards Event | | |
ENS 40519 | 13 February 2004 11:25:00 | Waterford | 24 Hour Notification Per Licensee Condition 2.F | Other Unspec Reqmnt | | |
ENS 40544 | 19 February 2004 20:00:00 | Soil Testing And Engineering, Inc. | Agreement State Report | Agreement State | | Stolen |
ENS 40576 | 8 March 2004 16:30:00 | Peach Bottom | Hpci System Inoperable Due to Failure of Torus Suction Valve to Fully Open | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Primary containment | |
ENS 40578 | 8 March 2004 05:00:00 | Va Boston Healthcare System | Loss of Licensed Material | 10 CFR 20.2201(a)(1)(i) | | |
ENS 40596 | 17 March 2004 20:57:00 | Wolf Creek | Switchgear Rooms Flooding Analysis Concerns | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | | |
ENS 40606 | 23 March 2004 18:15:00 | Us Army | the Us Army Reported a Missing Beam Splitter for a M1A1 Tank. | 10 CFR 20.2201(a)(1)(ii) | | |
ENS 40636 | 3 April 2004 08:00:00 | Brunswick | High Pressure Coolant Injection System Inoperable | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Reactor Core Isolation Cooling Core Spray Automatic Depressurization System Low Pressure Coolant Injection | Time of Discovery |
ENS 40639 | 3 April 2004 15:50:00 | Salem | Valid Actuation of Auxiliary Feedwater System During Maintenance | 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Steam Generator Reactor Protection System Auxiliary Feedwater Shutdown Cooling Residual Heat Removal Decay Heat Removal | Ultimate heat sink |
ENS 40642 | 5 April 2004 05:30:00 | Susquehanna | Loss of Safety Function for Emergency Diesel Generators During Surveillance Testing | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | Emergency Diesel Generator | |
ENS 40646 | 5 April 2004 15:40:00 | Susquehanna | Loss of Safety Function for Emergency Diesel Generators During Surveillance Testing | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | Emergency Diesel Generator | |
ENS 40647 | 5 April 2004 23:16:00 | Hatch | Brief Loss of Noaa Weather Radio Capability | 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness | | |
ENS 40649 | 6 April 2004 04:10:00 | Hatch | Momentary Loss of Noaa Weather Radio System | 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness | | |
ENS 40665 | 11 April 2004 04:23:00 | Salem | Plant Had a Valid Esf Signal to Start 1C Emergency Diesel Generator | 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Emergency Diesel Generator Decay Heat Removal | |
ENS 40703 | 24 April 2004 15:50:00 | Dresden | Isolation Condenser Declared Inoperable | 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | High Pressure Coolant Injection | Time of Discovery |
ENS 40706 | 26 April 2004 13:30:00 | McGuire | Non-Licensed Employee Tested Positive for Controlled Substance | 10 CFR 26.73, Applicability | | |
ENS 40714 | 29 April 2004 02:30:00 | Brunswick | Hpci System Inoperable Following Planned Maintenance | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection | Time of Discovery Mission time Overspeed trip |
ENS 40770 | 22 May 2004 01:46:00 | Surry | Unanalyzed Condition Due to Auxiliary Feedwater Not Being in Compliance with Justification for Continued Operation (Jco). | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | Auxiliary Feedwater | Unanalyzed Condition |
ENS 40788 | 3 June 2004 16:45:00 | Limerick | Part 21 Notification of Failure of Spring Charging Function in Circuit Breaker | 10 CFR 21.21 | | |
ENS 40821 | 16 June 2004 18:00:00 | Perry | 24 Hour Notification of Plant Exceeding Its Power Limit | Other Unspec Reqmnt | Feedwater | Time of Discovery |
ENS 40824 | 17 June 2004 09:21:00 | Hatch | High Pressure Coolant Injection (Hpci) Declared Inoperable | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Coolant Injection Reactor Core Isolation Cooling Emergency Core Cooling System | |
ENS 40840 | 24 June 2004 19:00:00 | Nuclear Fuel Services Inc. | - * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
| 10 CFR 20.1906(d)(1) | | |
ENS 40842 | 25 June 2004 14:50:00 | Seabrook | Plant Exceeded Lco Action Statement Limits | Other Unspec Reqmnt | | Grab sample |
ENS 40882 | 20 July 2004 07:44:00 | Perry | Alert Declared Due to High Offgas Effluent Alarm Pegged High and Unable to Confirm within 15 Minutes | 10 CFR 50.72(a)(1)(i), Emergency Class Declaration | | |
ENS 40904 | 29 July 2004 01:00:00 | Salem | Unidentified Reactor Coolant System (Rcs) Leak | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | Reactor Coolant System Primary containment | Unidentified leakage |
ENS 40925 | 5 August 2004 03:24:00 | Indian Point | Low Refueling Water Storage Tank Level | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | | Time of Discovery |
ENS 40952 | 14 August 2004 15:25:00 | Grand Gulf | Grand Gulf Standby Service Water "C" and High Pressure Core Spray Declared Inoperable | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | Service water High Pressure Core Spray | |
ENS 40983 | 24 August 2004 14:17:00 | Clinton | High Pressure Core Spray (Hpcs) Declared Inoperable | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | High Pressure Core Spray | Time of Discovery Reactor Vessel Water Level |
ENS 41018 | 4 September 2004 05:56:00 | Saint Lucie | Manual Reactor Trip Due to Steam Generator Level Oscillations | 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation | Steam Generator Feedwater Steam Bypass Control System | Downpower |
ENS 41024 | 8 September 2004 05:00:00 | Crystal River | Potential Reactor Coolant System Pressure Boundary Leak Located | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Reactor Coolant System | Pressure Boundary Leakage Pressure boundary leak Unidentified leak |
ENS 41027 | 8 September 2004 18:45:00 | Crystal River | Emergency Feedwater System Actuation | 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Feedwater | |
ENS 41032 | 1 September 2004 04:00:00 | Princeton University | Two Tritium Exit Signs Missing | 10 CFR 20.2201(a)(1)(i) | | Tritium Exit Sign Exit Sign |