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 Start dateSiteTitleTopic
05000266/LER-2008-00116 January 2008Point BeachPoint Beach Nuclear Plant Unit 1Temporary Modification
05000266/LER-2008-00316 July 2008Point BeachAppendix R Fire Scenario Resulting In Safe Shutdown Required Capability Not MaintainedSafe Shutdown
Unanalyzed Condition
05000266/LER-2011-00127 November 2011Point BeachLoss of Offsite Power to Unit 1 Safeguards Buses
05000266/LER-2012-0036 June 2011Point Beach2B-04 Safeguards 480V Bus De-Energized
05000266/LER-2013-0016 February 2013Point BeachLoss of Offsite Power to Unit 1 Safeguards Buses
05000266/LER-2016-0021 April 2016
31 May 2016
Point BeachOperation or Condition Prohibited by Technical Specifications
LER 16-002-00 for Point Beach, Unit 1, Regarding Operation or Condition Prohibited by Technical Specifications
Safe Shutdown
Offsite Circuit
05000269/FIN-2014007-0430 June 2014 23:59:59OconeeDegraded Voltage Relay Scheme
05000269/LER-2014-00128 March 2014OconeeUnanalyzed condition associated with the 13.8kV emergency power cables located in the underground trench.Safe Shutdown
Unanalyzed Condition
05000275/FIN-2014007-0130 September 2014 23:59:59Diablo CanyonFailure to Document Degraded Emergency Diesel Generator Fuel Injector Nozzles in the Corrective Action Program
05000275/LER-2007-00112 May 2007Emergency Diesel Generator Auto-start on Loss of Offsite 230kV Startup Power
05000277/FIN-2014004-0130 September 2014 23:59:59Peach BottomCorrective Actions Not Timely for EOC of Appendix R Broken WiresFire Protection Program
05000282/FIN-2014004-0230 September 2014 23:59:59Prairie IslandFailure to have Adequate Procedures to Address Low Bus Voltage ConditionsSignificance Determination Process
05000293/LER-2001-006Reactor Vessel Water Level
05000293/LER-2003-002Reactor Vessel Water Level
05000293/LER-2003-0031 June 2003
05000293/LER-2003-0056 September 2003
05000293/LER-2008-006PilgrimAutomatic Scram Resulting From Switchyard Breaker Fault During Winter Storm 05000Safe Shutdown
Reactor Vessel Water Level
05000321/LER-2010-0043 June 2010HatchEmergency Diesel Generator lA Excess Fuel Oil Return Tubing FailureMission time
Anticipated operational occurrence
05000323/LER-2005-00219 November 2005Unplanned Emergency Diesel Generator Auto-start During Testing Due to Personnel Error in Relay Testing
05000325/LER-2004-00315 August 2004Docket Number08 15 2004 2004 -- 003 - 00 10 13 2004 05000Operation Prohibited by Technical Specifications due to Inoperable Emergency Diesel GeneratorSafe Shutdown
Past operability
05000325/LER-2016-0024 March 2016BrunswickEmergency Diesel Generator 3 Inoperable Due to Failure to Auto-StartSafe Shutdown
Time to boil
Commercial Grade Dedication
Enforcement Discretion
Probabilistic Risk Assessment
FLEX
Offsite Circuit
05000325/LER-2017-00217 April 2017BrunswickForeign Material in Switch Results in Unplanned Automatic Start of Emergency Diesel GeneratorsForeign Material Exclusion
05000331/FIN-2014003-0530 June 2014 23:59:59Duane ArnoldLicensee-Identified ViolationSignificance Determination Process
05000333/FIN-2008005-0331 December 2008 23:59:59FitzPatrickLicensee-Identified Violation
05000333/FIN-2009004-0230 September 2009 23:59:59FitzPatrickLicensee-Identified Violation
05000333/LER-2003-001Jamas A, Fitzpatrick Nuclear Power Plant 05000333 1 Of 7Automatic Reactor Shutdown Due to Grid Instability Associated With the August 14, 2003 Transmission Grid Blackout and related Plant MODE Change with the A EDG Subs stem InoperableReactor Vessel Water Level
Qualified Offsite Circuit
Offsite Circuit
05000333/LER-2005-006Iodinelasperable 115 kV Line in Excess of Technical Specification Allowed Out of Service TimeProbabilistic Risk Assessment
Reserve Station Service Transformer
Offsite Circuit
05000333/LER-2016-00123 January 2016
23 March 2016
FitzPatrickSystem Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer
LER 16-001-00 for James A. FitzPatrick Regarding System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer
Ultimate heat sink
Residual transfer
Frazil ice
Downpower
05000334/LER-2007-00227 November 2007Docket NumberUndetected Loss of 138 kV 'A' Phase to System Station Service Transformer Leads to Condition Prohibited by Plant Technical SpecificationTime of Discovery
Temporary Modification
Qualified Offsite Circuit
Offsite Circuit
05000335/FIN-2013004-0230 September 2013 23:59:59Saint LuciePartial Loss of Offsite Power due to Non-segregated Bus FailureSignificance Determination Process
05000335/LER-1982-037, Forwards LER 82-037/03L-013 September 1982Saint LucieForwards LER 82-037/03L-0
05000335/LER-2003-0020 5 0 0 03 3 5 Page 1 of 3
05000335/LER-2004-00425 September 2004Dual Unit Loss Of Offsite Power During Hurricance JeanneSafe Shutdown
05000335/LER-2012-00110 February 2012Unit 1 Inadvertent Start of EDG upon Unexpected Under Voltage Condition
05000336/FIN-2015007-0330 June 2015 23:59:59MillstoneInadequate Evaluation of Circuit Breaker Interrupting CapabilitySignificance Determination Process
05000336/FIN-2016008-0130 September 2016 23:59:59MillstoneUnapproved OMA in Lieu of Meeting III.G.2 Fire Protection Requirements for Fire Area R-14, Lower 4kV Switchgear Room and Cable VaultSafe Shutdown
Operator Manual Action
Significance Determination Process
Exemption Request
Fire Protection Program
05000341/FIN-2012007-0331 March 2012 23:59:59FermiFailure to Identify EDG\\\'s Neutral Grounding Resistor Exceeded its Design ValuesCondition Adverse to Quality
05000352/LER-2013-002LimerickCondition That Could Have Prevented Fulfillment of the Offsite Power Safety FunctionTime of Discovery
Offsite Circuit
05000354/FIN-2009007-0431 December 2009 23:59:59Hope CreekDegraded Voltage Protection Scheme Design
05000354/LER-2001-0018 May 2001Docket Number
05000362/LER-2002-00127 February 2002Docket NumberSignificance Determination Process
05000366/LER-2001-0018 March 2001Half scram
Temporary Modification
05000366/LER-2004-00118 February 2004Edwin I. Hatch Nuclear Plant - Unit 21 OF 5
05000366/LER-2016-00113 April 2016
8 June 2016
Hatch2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability
LER 16-001-00 for E.I. Hatch, Unit 2, Regarding 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability
Time of Discovery
Mission time
Design basis earthquake
05000368/LER-2017-00226 April 2017
26 June 2017
Arkansas Nuclear
Arkansas Nuclear One – Unit 2
Automatic Start of an Emergency Diesel Generator Due to the Momentary Loss of Offsite Power due to Severe Weather
LER 17-002-00 for Arkansas Nuclear One, Unit 2, Regarding Automatic Start of an Emergency Diesel Generator Due to the Momentary Loss of Offsite Power due to Severe Weather
Safe Shutdown
High winds
Mission time
05000369/FIN-2018010-0131 March 2018 23:59:59Mcguire
McGuire
Failure to Update Offsite Circuit Operability Limit for Single Busline AlignmentOffsite Circuit
05000373/LER-2005-0012 February 2005Single Failure Vulnerability of Division 1 and 2 Protective Relay Circuitry Due to Latent Design DeficiencySafe Shutdown
Unanalyzed Condition
Temporary Modification
05000373/LER-2013-00613 August 2013Inadvertent Automatic Start of the 1A Diesel Generator Cooling Water Pump Due to Improper Adjustment of Mechanically Operated Contact Switch
05000374/LER-2003-001Nuclear wwwexeloncorp corn Exelon Generation Company, LLC LaSalle County Station
2601 North 21"Road
Marseilles, IL 61341-9757
March 11, 2003
10 CFR 50.73
United States Nuclear Regulatory Commission
Attention: Document Control Desk
Washington, D.C. 20555
LaSalle County Station, Unit 2
Facility Operating License No. NPF-18
NRC Docket No. 50-374
Subject: L Licensee Event Report
In accordance with 10 CFR 50.73(a)(2)(iv), Exelon Generation Company,
(EGC), LLC, is submitting Licensee Event Report Number 03-001-00,
Docket No. 050-374.
Should you have any questions concerning this letter, please contact
Mr. Glen Kaegi, Regulatory Assurance Manager, at (815) 415-2800.
Respectfully,
,i(-e-d-oe-A-- g tz/kia-/e-ta
Susan R. Landahl
Plant Manager
LaSalle County Station
Attachments
L Licensee Event Report
cc: L Regional Administrator - NRC Region III
NRC Senior Resident Inspector - LaSalle County Station
NRC FORM 366 U.S. NUCLEAR REGULATORY
(7-2001) - COMMISSION
- -
LICENSEE EVENT REPORT (LER)
(See reverse for required number of
digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004
Estimated burden per response to comply with this mandatory
information collection request: 50 hrs. Reported lessons learned are
incorporated into the licensing process and fed back to industry. Send
comments regarding burden estimate to the Records Management Branch
(T-6 E6), U. S. Nuclear Regulatory Commission, Washington, DC
20555-0001, and by Internet e mail to bis I enrc.gov, and to the Desk
Officer, Office of Information and Regulatory Affairs, NOEB-10202
(3150-0104), Office of Management and Budget, Washington, DC
20503 If a means used to impose information collection does not display
a currently valid OMB control number, the NRC may not conduct or
sponsor, and a person is not required to respond o, the information
collection
I. FACILITY NAME LaSalle County Station, Unit 2 I DOCKET NUMBER
05000374
I PAGE
1 of 3
4.TITLE
Manual Scram Due to Lowering Reactor Water Level as a Result of a Trip of the 2B
Condensate/Condensate Booster Pump .
05000382/FIN-2014008-0230 June 2014 23:59:59WaterfordFailure to Identify and Correct Condition Adversely Affecting Flooding Mitigation DesignCondition Adverse to Quality