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 Start dateSiteTitle
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 Inoperable
05000333/LER-2004-001Docket NumberInadvertent Actuation of ECCS and EDGs While in Refueling Mode
05000333/LER-2005-005Docket NumberAutomatic Reactor Scram on Low Reactor Vessel Water Level During Reactor Feed Pump Control Reset
05000333/LER-2013-00617 December 2013FitzPatrick1 OF 6
05000335/LER-2016-0012 June 2016
29 July 2016
Saint LucieInadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical Specifications
LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical....
05000341/FIN-2011009-0330 June 2011 23:59:59FermiInadequate Procedures to Control the Plant from the Dedicated Shutdown Panel
05000341/FIN-2015004-0131 December 2015 23:59:59FermiFailure to Satisfy Technical Specification Requirements During an Unplanned Operation with the Potential to Drain the Reactor Vessel
05000341/LER-1988-004, Special Rept:On 880110,ECCS Actuation Occurred.Operator Manually Tripped Sys.Details of Event Discussed in LER 88-00411 April 1988FermiSpecial Rept:On 880110,ECCS Actuation Occurred.Operator Manually Tripped Sys.Details of Event Discussed in LER 88-004
05000341/LER-2006-00329 July 2006Docket Number07 29 2006 2006 - 003 - 00 09 21 2006 05000Automatic Reactor Shutdown Due To Loss of Division 1 Power
05000341/LER-2007-00215 November 2007Docket Number11 15 2007 2007 -0002 -000 01 14 2008 05000Automatic Initiation of Alternate Rod Insertion and Manual Reactor Scram Due to Perturbations in the Reference Leg Backfill System
05000341/LER-2010-0026 June 2010Docket Number6 6 2010 2010 - 002 -000 08 03 2010 05000Automatic Reactor Scram and Loss of Offsite Power Due to Severe Weather
05000341/LER-2012-0067 November 2012Manual Reactor Scram Due to Hydrogen Leakage Into the Stator Water Cooling System
05000341/LER-2013-00122 January 2013FermiLoss of Secondary Containment Function
05000341/LER-2017-00219 January 2017
16 March 2017
FermiHigh Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to be Inoperable
LER 17-002-00 for Fermi 2 Regarding High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to be Inoperable
05000352/FIN-2015001-0331 March 2015 23:59:59LimerickOperability of High Pressure Coolant Injection and Entries into Operational Conditions at Low Reactor Pressures with High Reactor Water Level Trip Actuated
05000352/LER-2011-002Docket Number, AUtomatic Actuation Of The ReactOi Protection System Due To A Main Turbine Trip
05000353/LER-1995-004, Forwards LER 95-004 Re Engineered Safety Sys Actuation Due to Momentary Spurious Low Rv Water Level Isolation Signal16 March 1995LimerickForwards LER 95-004 Re Engineered Safety Sys Actuation Due to Momentary Spurious Low Rv Water Level Isolation Signal
05000354/FIN-2015002-0430 June 2015 23:59:59Hope CreekOperations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment
05000354/FIN-2017001-0331 March 2017 23:59:59Hope CreekOperations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment
05000354/LER-2004-01010 October 2004Manual Reactor Scram Due to Moisture Separator Dump Line Failure
05000354/LER-2005-0037 June 2005Reactor Coolant System Leak from Check Valve Position Indicator
05000366/LER-2001-00226 October 2001Edwin I. Hatch Nuclear Plant - Unit 2Reactor Recirculation Pump Flow Rate Changes Cause Reactor Scram on APRM High Flux
05000366/LER-2001-00325 December 2001Edwin I. Hatch Nuclear Plant - Unit 2Sudden Closure of Main Steam Line Isolation Valve Causes Pressure Increase and Reactor Scram on APRM High Flux
05000366/LER-2004-00225 September 2004Edwin I. Hatch Nuclear Plant - Unit 2Unplanned Group 2 PCIS Isolation From a Water Level Transient Following Manual Reactor Scram
05000366/LER-2005-00323 May 2005Docket Number(S)Manual Reactor Scram Inserted in Response to Reactor Water Chemistry Event Caused by a Condenser Tube Leak
05000366/LER-2007-008Edwin I. Hatch Nuclear Plant - Unit 2Reactor Scram On Low Reactor Water Level Due to Partial Loss Of Condensate S stem
05000374/LER-2001-003Docket NumberReactor Scram Due to Undervoltage Protective Circuit Actuation on Division 1 ESF Bus
05000387/FIN-2008004-0230 September 2008 23:59:59SusquehannaHPCI and RCIC Made Inoperable Due to Operator Actions During Shutdown
05000387/FIN-2010004-0430 September 2010 23:59:59SusquehannaFailure to Accurately Model the Simulator for RPV Level Control Using the Integrated Control System
05000387/FIN-2013003-0430 June 2013 23:59:59SusquehannaImplementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1
05000387/LER-1983-013, Forwards LER 83-013/03L-011 February 1983SusquehannaForwards LER 83-013/03L-0
05000387/LER-1983-092, Forwards Transient Analysis & Damage Repts for Startup Transformer T-10 Failure on 830624 (Ref LER 83-092/03L-0), Fulfilling Util 830630 Commitment2 November 1983SusquehannaForwards Transient Analysis & Damage Repts for Startup Transformer T-10 Failure on 830624 (Ref LER 83-092/03L-0), Fulfilling Util 830630 Commitment
05000387/LER-2015-00629 September 2015
30 March 2016
SusquehannaLoss of Safety Function due to Inoperability of Both Trains of the Standby Gas Treatment System and a Loss of Safety Function of the Control Room Emergency Outside Air Supply System due to Air Flow Controller found in Manual
LER 15-006-01 for Susquehanna, Unit 1, Regarding Loss of Safety Function due to Inoperability of Both Trains of the Standby Gas Treatment System and a Loss of Safety Function of the Control Room Emergency Outside Air Supply System due to Air Flow...
05000388/FIN-2014008-0130 September 2014 23:59:59SusquehannaInadequately Maintained Procedures for Plant Shutdown to Hot Standby led to Reactor Water Level and Power Transients
05000388/LER-2012-002SusquehannaUnit 2 Manual Scram Due to Loss of the Integrated Control System
05000395/LER-2012-00117 January 2012Docket NumberVice President, Nuclear Operations
803.345.4342
August 3, 2012SCE~r .so
A SCANA COMPANY
Document Control Desk
U. S. Nuclear Regulatory Commission
Washington, DC 20555
Dear Sir / Madam:
Subject:VVIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1
DOCKET NO. 50-395
OPERATING LICENSE NO. NPF-12
LICENSEE EVENT REPORT (LER 2012-001-01)
CORE EXIT THERMOCOUPLES & REACTOR WATER LEVEL INDICATION
SYSTEM INOPERABLE DUE TO AN INADEQUATE MAINTENANCE
PROCEDURE
Attached is Licensee Event Report (LER) No. 2012-001-01 for the Virgil C. Summer Nuclear
Station Unit 1. This revised report describes a condition where Core Exit Thermocouples and
Reactor Water Level Indication System would not be operable for accident monitoring. This
report is submitted in accordance with 10 CFR 50.73(a)(2)(i)(B).
This letter and attached LER contain no new commitments and no revisions to existing
commitments.
Should you have any questions, please call Bruce Thompson at (803) 931-5042.
Very truly yours,
Dal
Thomas D. Gatlin
TS/TDG/jw
Attachment
c: K. B. Marsh P. Ledbetter
S. A. Byrne J. C. Mellette
J. B. Archie EPIX Coordinator
N. S. Carps K. M. Sutton
J. H. Hamilton INPO Records Center
R. J. White Marsh USA, Inc.
W. M. Cherry R. J. Schwartz
V. M. McCree NSRC
R. E. Martin RTS (CR-11-01807)
NRC Resident Inspector FileV(818.07)
M. N. Browne PRSF (RC-12-0116)
V fALVirgil C. Summer Station • Post Office Box 88 .Jenkinsville, SC • 29065 • F (803) 345-5209
1
NRC FORM 366
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
(10-2010) Estimated burden per response to comply with this mandatory collection
request: 80 hours.0Reported lessons learned are incorporated into the
licensing process and fed back to industry. Send comments regarding burden
estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, or by Internet e-mail to
infocollects.resource@nrc.gov, and to the Desk Officer, Office of Information
and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management andLICENSEE EVENT REPORT (LER) Budget, Washington, DC 20503. If a means used to impose an information(See reverse for required number of 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 to, thedigits/characters for each block) information collection.
1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE
Virgil C. Summer Nuclear Station Unit 1 05000 395 1 OF 5
4. TITLE
Core Exit Thermocouples & Reactor Water Level Indication System Inoperable due to Inadequate Maintenance Procedure
05000397/FIN-2012005-0531 December 2012 23:59:59ColumbiaFailure to Follow Shutdown Cooling Isolation Logic Bypass Procedures Results in Loss of Safety Function
05000397/FIN-2015003-0630 September 2015 23:59:59ColumbiaImplementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 2
05000397/LER-2006-00131 October 2006Reactor Trip due to Digital Electro-Hydraulic Control System Card Failure
05000397/LER-2009-0018 February 2009Reactor Scram due to Turbine Control System,Trip Header Depressurization
05000397/LER-2009-0057 November 2009Manual Reactor Scram due to Main Turbine DEH Control System Fluid Leak
05000410/FIN-2015001-0231 March 2015 23:59:59Nine Mile PointFailure to Perform an Adequate Review of Planned Work Activities Results in a Manual Reactor Scram
05000410/FIN-2018003-0230 September 2018 23:59:59Nine Mile PointMinor Violation
05000410/LER-2001-00224 May 2001
05000410/LER-2001-0062 December 2001
05000410/LER-2002-00216 March 2002
05000410/LER-2003-00124 July 2003
05000410/LER-2003-002
05000410/LER-2013-0042 December 2013Nine Mile PointManual Reactor Protection System Actuation due to Loss of Reactor Recirculation Flow
05000410/LER-2015-00218 February 2015Nine Mile PointManual Reactor Scram Due to Unexpected Reactor Water Level Change