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 Start dateSiteTitle
05000333/LER-2008-003FitzPatrick
05000333/LER-2012-005FitzPatrickTransformer Installation Error Causes Loss of Off-Site Power
05000333/LER-2012-008FitzPatrickAutomatic Reactor Shutdown Caused by a Fault in Main Transformer
05000336/LER-1994-003, Application for Amend to License DPR-65,incorporating Addl Requirements Into TS Re non-QA Equipment Utilized to Achieve Feedwater Isolation in Response to MSLB Inside Containment, Per Commitment Made in LER 94-003-00 & Listed I6 May 1994MillstoneApplication for Amend to License DPR-65,incorporating Addl Requirements Into TS Re non-QA Equipment Utilized to Achieve Feedwater Isolation in Response to MSLB Inside Containment, Per Commitment Made in LER 94-003-00 & Listed Insp Repts
05000336/LER-2006-00223 February 2006Docket NumberManual Reactor Trip Due To Trip Of Both Feed Pumps Following A Loss Of Instrument Air
05000336/LER-2008-00322 May 2008Docket NumberFailed Pilot Wire Causes Reactor Trip
05000336/LER-2008-00424 May 2008Millstone Power Station -Reactor Trip Due to a Loss of Normal Power Event
05000336/LER-2008-005Millstone Power Station -Feedwater Heater Level Oscillation and Manual Reactor Trip
05000336/LER-2009-0013 July 2009Docket NumberReactor Trip Due to High Pressurizer Pressure
05000338/FIN-2009007-0231 December 2009 23:59:59North AnnaFailure to Ensure RSST A LTC Controller Settings were Correctly Implemented
05000338/FIN-2010002-0531 March 2010 23:59:59North AnnaFailure to Establish a Procedure for Undervoltage Timers Results in Main Turbine/Reactor Trip
05000338/LER-2003-00411 June 2003Document Number
05000338/LER-2009-00315 November 2009. Inoperable Reserve Station Service Transformer Due to Improper Load Tap Changer Setting
05000338/LER-2009-004Document Numbersequential Revmonth Day ' Year Year Month Day Year North Anna Unit 2 05000339Number No.AUTOMATIC REACTOR TRIP AND ESF ACTUATION DUE TO HUMAN PERFORMANCE ERROR DURING TESTING
05000338/LER-2011-003North Anna Power Station , Units 1 And 2Dual Unit Reactor Trip and ESF ActuatiOns During Seismic Event With a Loss of Offsite Power
05000338/LER-2014-001North Anna1 OF 3
05000338/LER-2016-00123 January 2016
16 March 2016
North Anna1 OF 3
LER 16-001-00 for North Anna, Units 1 and 2, Regarding Emergency Diesel Generators Automatic Start Due to Loss of Power to "C" Reserve Station Service Transformer
05000338/LER-2016-00316 June 2016North Anna1 OF 3
LER 16-003-00 for North Anna, Unit 1, Regarding Engineered Safety Feature Actuation Due to Loss of Power to "A" Reserve Station Service Transformer
05000339/LER-2007-0027 March 2007Document Numbersequentia Revmonth Day Year Year Month Day YearVirginia Electric and Power Company
North Anna Power Station
P. 0. Box 402
Mineral, Virginia 23117
June 29, 2007
U. S. Nuclear Regulatory Commission Serial No.: 07-0280A
Attention: Document Control Desk NAPS: JHL
Washington, D. C. 20555-0001 Docket No.: 50-339
License No.: NPF-7
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the
following Licensee Event Report applicable to North Anna Power Station Unit 2.
Report No. 50-339/2007-002-01
This report has been reviewed by the Station Nuclear Safety and Operating Committee
and will be forwarded to the Management Safety Review Committee for its review.
Sincerely,
D. G. Stoddard, Site Vice President
North Anna Power Station
Enclosure
Commitments contained in this letter: None
cc: United States Nuclear Regulatory Commission
Region II
Sam Nunn Atlanta Federal Center
61 Forsyth Street, SW, Suite 23T85
Atlanta, Georgia 30303-8931
Mr. J. T. Reece
NRC Senior Resident Inspector
North Anna Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIOP APPROVED BY OMB NO. 3150-0104 EXPIRES: 6/30/2007
(6-2004) Estimated burden per response to comply with this mandatory collection
request: 50 hours. Reported lessons learned are incorporated into the licensing
processcaorgsfedar3dacMovinpvsatr4SgnedIvccoem rriEsieranntselreMinR5b2irdeortitrzactreator
Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail toLICENSEE EVENT REPORT (LER) infocollects@nrc.gov, and to the Desk Officer, Office of Information and
Ri ule a i ngrf8n Ni I 15m 0a 6s im se megg atto flfai SOBiggi2 (f3a 0-e0n 6) iseOcr ofpoManaargeznt and
to imposeSee reverse for required number of collection does not display a currently valid OMB control number, the NRC may
digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the
information collection.
1. FACILITY NAME 2.'DOCKET NUMBER 3. PAGE
NORTH ANNA POWER STATION , UNIT 2 05000 339 1 OF 4
4. TITLE
Automatic Start of 2H EDG on Loss of "B" Reserve Station Service Transformer Due To Cable Fault
05000339/LER-2009-00128 April 2009Document Numbersequential Revmonth Day Year Year Month Day Year

Virginia Electric and Power Company
North Anna Power Station
P. 0. Box 402
Mineral, Virginia 23117
June 22, 2009
U. S. Nuclear Regulatory Commission
Attention: Document Control Desk
One White Flint North
11555 Rockville Pike
Rockville, MD 20852-2378
Serial No.: 09-288
NAPS:M MPW
Docket No.: 50-339
License No.: NPF-7
Dear Sirs:
Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the
following Licensee Event Report applicable to North Anna Power Station Unit 2.
Report No. 50-339/2009-001-00
This report has been reviewed by the Facility Safety Review Committee and will be
forwarded to the Management Safety Review Committee for its review.
Sincerely,
Daniel G. Stoddard, P.E.
Site Vice President
North Anna Power Station
Enclosure
Commitments contained in this letter: None
cc: United States Nuclear Regulatory Commission
Region II
Sam Nunn Atlanta Federal Center
61 Forsyth Street, SW, Suite 23T85
Atlanta, Georgia 30303-8931
NRC Senior Resident Inspector
North Anna Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISS101. APPROVED BY OMB NO. 3150-0104
D
EXPIRES: 8/31/2010 (9-2007)

Estimated burden per response to comply with this mandatory collection
request: 80 hours.DReported lessons learned are incorporated into the licensing
e 4corsand NWiacy rocesangfe bactststn. Sdcom nentevceranNN-erginburdentigatto- p52)ur icrg
Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail toLICENSEE EVENT REPORT (LER) infocollects@nrc.gov, andDDto the Desk Officer,DOffice of InformationDand
Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and
Budget, Washington, DC 20503.DIf 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
digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the
information collection.
1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE
NORTH ANNA POWER STATION , UNIT 2 05000 339 1 OF 4
4. TITLE
Automatic Start of 2H EDG Due To Loss of "B" Reserve Station Service Transformer

05000339/LER-2010-002North Anna
05000339/LER-2011-00128 September 2011North AnnaInoperable Emergency Diesel Generator Due to Coolant Leak
05000423/FIN-2014005-0231 December 2014 23:59:59MillstoneFailure to Manage Risk of RSST Testing
05000423/LER-2007-00225 April 2007Docket NumberLoss of Offsite Power Caused by Transmission System Operator While Defueled
05000458/LER-2015-0027 March 2015River BendEmergency Diesel Generator Start Circuit Actuation Due to Loss of Power from Reserve Station Service No. 2
05000458/LER-2015-002, Operations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments18 February 2015River BendOperations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments
A05437, Responds to 851212 Request for Addl Info to Confirm That Adverse Impact of Completing Degraded Grid Protection Mods Outweighs Intended Improvements.Description of Probabilistic Assessment Results & Design Analysis Encl13 January 1986MillstoneResponds to 851212 Request for Addl Info to Confirm That Adverse Impact of Completing Degraded Grid Protection Mods Outweighs Intended Improvements.Description of Probabilistic Assessment Results & Design Analysis Encl
A07899, Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof25 April 1989MillstoneProvides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof
B10909, Forwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 83110127 September 1983MillstoneForwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 831101
B11026, Forwards Responses to 840106 Request for Addl Info Re Probabilistic Safety Study.Info Suppls Util 831109 & 840110 Responses.Min Safety Injection Flow Sufficient to Maintain Vessel Mixture Level Core6 February 1984MillstoneForwards Responses to 840106 Request for Addl Info Re Probabilistic Safety Study.Info Suppls Util 831109 & 840110 Responses.Min Safety Injection Flow Sufficient to Maintain Vessel Mixture Level Core
B11111, Forwards Response to Draft SER Open Items19 April 1984MillstoneForwards Response to Draft SER Open Items
B11138, Forwards Revised Responses to Draft Instrumentation & Control Sys Branch SER Open Items 1,6 & 21,per NRC 840313 Meeting.Responses to Draft SER Open Items 3,7 & 19 Also Encl.Responses Will Be Incorporated in Future FSAR Amend4 May 1984MillstoneForwards Revised Responses to Draft Instrumentation & Control Sys Branch SER Open Items 1,6 & 21,per NRC 840313 Meeting.Responses to Draft SER Open Items 3,7 & 19 Also Encl.Responses Will Be Incorporated in Future FSAR Amend
B11185, Forwards Current Status of Procedures & Sys Review Branch Draft SER Open Items & Revised Responses for Open Items PSRB-13,15 & 1815 May 1984MillstoneForwards Current Status of Procedures & Sys Review Branch Draft SER Open Items & Revised Responses for Open Items PSRB-13,15 & 18
B11335, Forwards Procedures Re Degraded Grid Voltage,Including Change 2,Rev 4 to OP2347B, Normal Station Svc Transformer 15G-2S & Change 2,Rev 5 to OP 2347A, Reserve Station Svc Transformer 15G-22S4 December 1984MillstoneForwards Procedures Re Degraded Grid Voltage,Including Change 2,Rev 4 to OP2347B, Normal Station Svc Transformer 15G-2S & Change 2,Rev 5 to OP 2347A, Reserve Station Svc Transformer 15G-22S
B11497, Forwards Revs to FSAR Sections 8.2 & 8.3 Re Offsite Power Sys & Emergency Switchgear Bus Protection,Respectively, Closing SER (NUREG-1031),Confirmatory Items 44,45,46 & 50 Per J Knox Request1 April 1985MillstoneForwards Revs to FSAR Sections 8.2 & 8.3 Re Offsite Power Sys & Emergency Switchgear Bus Protection,Respectively, Closing SER (NUREG-1031),Confirmatory Items 44,45,46 & 50 Per J Knox Request
B11633, Forwards Summaries of Projects Evaluated for Public Safety Impacts & Proprietary Millstone Nuclear Power Station Unit 1 Integrated Safety Assessment Program Public Safety Impact Model. Proprietary Rept Withheld (Ref 10CFR2.790)7 August 1985MillstoneForwards Summaries of Projects Evaluated for Public Safety Impacts & Proprietary Millstone Nuclear Power Station Unit 1 Integrated Safety Assessment Program Public Safety Impact Model. Proprietary Rept Withheld (Ref 10CFR2.790)
B11747, Forwards Review of Integrated Safety Assessment Program Topic 1.25, Degraded Grid Voltage Procedures, Resulting from Review of SEP Topics VIII-1.A & VII-3 Per 850517 Commitment9 October 1985MillstoneForwards Review of Integrated Safety Assessment Program Topic 1.25, Degraded Grid Voltage Procedures, Resulting from Review of SEP Topics VIII-1.A & VII-3 Per 850517 Commitment
B11930, Discusses Effects of Hurricane Gloria,Including Preparations for Storm & Loss of Offsite Power Events at Millstone Units 1 & 2 on 850927.Advance Notification Associated W/Severe Weather Events Permits Advance Precautionary Actions31 December 1985Millstone
Haddam Neck
05000000
Discusses Effects of Hurricane Gloria,Including Preparations for Storm & Loss of Offsite Power Events at Millstone Units 1 & 2 on 850927.Advance Notification Associated W/Severe Weather Events Permits Advance Precautionary Actions
B12280, Forwards Pages 3-6,3-15,3-18 & 3-25 Omitted from Section 3 & Isap Topics 1.02,1.16.1,2.06 & 2.07 Omitted from App C of 860731 Isap Final Rept1 October 1986MillstoneForwards Pages 3-6,3-15,3-18 & 3-25 Omitted from Section 3 & Isap Topics 1.02,1.16.1,2.06 & 2.07 Omitted from App C of 860731 Isap Final Rept
B12995, Forwards Revised Isap Rept,Including Update on Isap Topic Reviews,Evaluation of New Topics,Integrated Implementation Schedule,List of Existing Topics & long-term Plan for Resolution of Topic 1.06,per 870804 Comments on NUREG-11849 November 1988MillstoneForwards Revised Isap Rept,Including Update on Isap Topic Reviews,Evaluation of New Topics,Integrated Implementation Schedule,List of Existing Topics & long-term Plan for Resolution of Topic 1.06,per 870804 Comments on NUREG-1184
B13099, Forwards Rev 2 to Probabilistic Safety Study Update.Advises That Study Update Will Be Integral Part of Util Response to Generic Ltr 88-20.W/three Oversize Figures Encl10 February 1989MillstoneForwards Rev 2 to Probabilistic Safety Study Update.Advises That Study Update Will Be Integral Part of Util Response to Generic Ltr 88-20.W/three Oversize Figures Encl
B13175, Forwards Update Re Implementation Status of Improvement Actions Discussed in Util 880527 Response to SALP Board 880329 Recommendations & Addl Info Pertinent to SALP Repts 50-245/86-99 & 50-336/86-9915 June 1989MillstoneForwards Update Re Implementation Status of Improvement Actions Discussed in Util 880527 Response to SALP Board 880329 Recommendations & Addl Info Pertinent to SALP Repts 50-245/86-99 & 50-336/86-99
B13180, Responds to NRC Station Blackout Rule Re Plant Capability for Maintaining Core Cooling & Containment Integrity17 April 1989MillstoneResponds to NRC Station Blackout Rule Re Plant Capability for Maintaining Core Cooling & Containment Integrity
B14267, Application for Amend to License DPR-65,revising TS Table 3.3-3, ESFAS Instrumentation, Item 6.b, Refueling Water Storage Tank-Low, as Result of Sump Recirculation Actuation Signal Logic Design Mods Being Implemented28 October 1992MillstoneApplication for Amend to License DPR-65,revising TS Table 3.3-3, ESFAS Instrumentation, Item 6.b, Refueling Water Storage Tank-Low, as Result of Sump Recirculation Actuation Signal Logic Design Mods Being Implemented
B15380, Application for Amend to License DPR-65,extending AOT When One Offsite Circuit Inoperable from Current 72 H to Seven Days6 October 1995MillstoneApplication for Amend to License DPR-65,extending AOT When One Offsite Circuit Inoperable from Current 72 H to Seven Days
B15403, Forwards Addl Info Re 951006 Proposed Rev to Ts,Extending cycle-specific Ac Sources AOT & Revised Ts,As Identified by NRC in 951012 Telcon23 October 1995MillstoneForwards Addl Info Re 951006 Proposed Rev to Ts,Extending cycle-specific Ac Sources AOT & Revised Ts,As Identified by NRC in 951012 Telcon
B15776, Forwards Response to RAI Re 24-month Fuel cycle-electrical Power Systems Surveillance Extensions23 July 1996MillstoneForwards Response to RAI Re 24-month Fuel cycle-electrical Power Systems Surveillance Extensions
B15910, Forwards Response to RAI Re Alternate AC Power Source Requirements18 October 1996MillstoneForwards Response to RAI Re Alternate AC Power Source Requirements
ENS 428887 October 2006 22:01:00SurryManual Scram Due to Unusual Noise in Turbine Building
ENS 432177 March 2007 08:05:00North AnnaEmergency Diesel Generator Autostart on Loss of "B" Reserve Station Service Transformer