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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20198Q4391997-11-0303 November 1997 LER 97-S001-00:on 971003,vital Area Barrier Gratings in Main Steam Valve Bldg Floor Not Secured.Caused by Inadequate Verification/Validation Process for Ensuring Vital Area Boundary Integrity.Security Instructions Will Be Revised ML20217F2321997-09-29029 September 1997 LER 970934-01:on 970918,RHR Pump Suction Relief Valve Setpoint Not IAW TS Was Determined.Caused by Insufficient Configuration Control.Declared B Train RHR Valve Inoperable, Recalibrated to Correct Setpoint & Declared Operable 05000336/LER-1997-003, Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revised1997-04-15015 April 1997 Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revised 05000336/LER-1993-0191993-09-10010 September 1993 LER 93-019-00:on 930812,reactor Trip Occurred Due to Low SG Level.Conducted Shift Briefing of Event to Operating Shift While Assuming Watch.Briefing Included Listed Requirements for Subsequent Specific start-up.W/930910 Ltr 05000423/LER-1993-0121993-09-0303 September 1993 LER 93-012-00:on 930805,piece of Plywood Discovered in Train a of Sws.Caused by Inadequate Work Control During 1991 Outage to Repair Sws.Plywood Removed & Increased Attention Being Paid to Matl Exclusion in Critical sys.W/930903 Ltr 05000336/LER-1993-0181993-09-0303 September 1993 LER 93-018-00:on 930805,letdown Manual Isolation Valve 2-CH-442 Developed Leak Which Exceeded TS Limits.Root Cause Has Not Been Determined.Valve Replaced & All Code Required Post Intallation Tests Successfully completed.W/930903 Ltr 05000336/LER-1993-0081993-09-0202 September 1993 LER 93-008-01:on 930505,declared Charging Pumps Inoperable Due to Low Control Power Voltage.Established Administrative Controls & Installed Interposing Relay within C Charging Pump Control circuit.W/930902 Ltr 05000423/LER-1993-0041993-08-31031 August 1993 LER 93-004-01:on 930331,RT Occurred Due to electro-hydraulic Control Power Supply Failure.Replaced Faulty Power Supply. W/930831 Ltr 05000423/LER-1993-0111993-08-30030 August 1993 LER 93-011-00:on 930731,MSSV Lift Setpoint Drift Occurred Due to Unknown Cause.Reduced Setpoint for Power Range Neutron Flux High Trip to 10%.W/930830 Ltr 05000336/LER-1993-0161993-08-27027 August 1993 LER 93-016-00:on 930729,reportability Determination Made Re Analysis for Boron Dilution Event.Caused by Inadequate Review of Results of Boron Dilution in Relation to Plant Operating Conditions.Boron Results revised.W/930827 Ltr 05000336/LER-1993-0141993-08-13013 August 1993 LER 93-014-00:on 930714,discovered Surveillances Procedures Had Not Been Performed within Specified Time Intervals Due to Insufficent Planning.Missed Surveillances Immediately performed.W/930813 Ltr 05000423/LER-1990-0261990-07-25025 July 1990 LER 90-026-00:on 900625,Train B Containment Hydrogen Monitor Failed Calibr Surveillance.Caused by Inadequate Engineering Interface Between Facilities Design Organization.Caution Tags Placed on Main Control Board indicators.W/900725 Ltr 05000423/LER-1990-0251990-07-20020 July 1990 LER 90-025-00:on 900616,hourly Vice Fire Watch Maintained During Condition That Required Continuous Fire Watch Be Established.Caused by Personnel Error.Continuous Fire Watch Established & Personnel Involved counseled.W/900720 Ltr 05000336/LER-1990-0101990-07-20020 July 1990 LER 90-010-00:on 900621,door Identified in Configuration Not Consistent W/Bechtel Design Drawings During High Energy Line Review.Caused by Lack of Knowledge of Requirements.Double Door reinforced.W/900720 Ltr 05000423/LER-1990-0241990-07-20020 July 1990 LER 90-024-00:on 900620,control Bldg Isolations Occurred Due to Radiation Monitor Detector Degradation.Other Equipment Not Affected.Degradation Caused Radiation Levels to Exceed High Alarm Setpoint.Detector replaced.W/900720 Ltr 05000336/LER-1990-0081990-07-18018 July 1990 LER 90-008-00:on 900620,determined That Grab Sample of Unit Stack Gas Not Taken.Caused by Lack of Communication Between Personnel.Grab Sample Obtained & analyzed.W/900718 Ltr 05000336/LER-1987-0091990-07-18018 July 1990 LER 87-009-02:on 870902,unit Experienced Automatic Reactor Trip Due to Low Steam Generator Level.Caused by Valve Stem Slightly Loose from Valve Plug.Damaged Stem/Plug Assembly replaced.W/900718 Ltr 05000423/LER-1990-0211990-07-16016 July 1990 LER 90-021-00:on 900607,integrated Leak Rate Test Supply & Exhaust Valve 3HVU*V5 Discovered Unlocked & Opened.Caused by Failure to Use Applicable Procedure for Nonroutine Evolution.Valve Closed & locked.W/900716 Ltr 05000336/LER-1990-0091990-07-16016 July 1990 LER 90-009-00:on 900617,inadvertent Partial Actuation of Train B of Enclosure Bldg Filtration Sys Occurred.Root Cause Not Determined.No Corrective Actions Recommended Until Further Testing & Troubleshooting performed.W/900716 Ltr 05000423/LER-1990-0221990-07-16016 July 1990 LER 90-022-00:on 900618,discovered That Hourly Fire Watch Patrol Had Not Been Established in Battery 4 Inverter Room. Caused by Procedural Deficiency.Hourly Fire Watch Established.Procedures revised.W/900716 Ltr 05000423/LER-1990-0191990-07-0303 July 1990 LER 90-019-00:on 900606,automatic Reactor Trip from Negative Flux Rate Signal Occurred Due to Dropped Control Rod.Caused by Broken Connection in Stationary Coil Power Cable for Rod. Special EOP Performed & Connector replaced.W/900703 Ltr 05000000/LER-1986-022, Partially Deleted LER 86-022-02:on 861018,potential Undetected Access Into Vital Area Discovered.Caused by Use of Incorrect Procedure.Card Reader Replaced & Tested to Ensure Proper Operation1987-02-20020 February 1987 Partially Deleted LER 86-022-02:on 861018,potential Undetected Access Into Vital Area Discovered.Caused by Use of Incorrect Procedure.Card Reader Replaced & Tested to Ensure Proper Operation 05000000/LER-1986-030, Partially Deleted LER 86-030-00:on 861211,unauthorized Opening Into Protected Area Discovered.Caused by Area Not Properly Identified as Area for Security Concern.Signs Posted1986-12-16016 December 1986 Partially Deleted LER 86-030-00:on 861211,unauthorized Opening Into Protected Area Discovered.Caused by Area Not Properly Identified as Area for Security Concern.Signs Posted 05000000/LER-1986-026, Partially Deleted LER 86-026-00:on 861124,vital Area Door Discovered W/O Alarm Capability.Caused by Personnel Error. Secutiry Officer in Question Terminated & Function of Administrative Sergeant Reviewed1986-12-0101 December 1986 Partially Deleted LER 86-026-00:on 861124,vital Area Door Discovered W/O Alarm Capability.Caused by Personnel Error. Secutiry Officer in Question Terminated & Function of Administrative Sergeant Reviewed 05000000/LER-1986-023, Partially Deleted LER 86-023-01:on 861023,unauthorized Access Into Vital Area Door Discovered.Caused by Card Reader Malfunction.Malfunctioning Card Reader Replaced.Cause Still Under Investigation1986-11-21021 November 1986 Partially Deleted LER 86-023-01:on 861023,unauthorized Access Into Vital Area Door Discovered.Caused by Card Reader Malfunction.Malfunctioning Card Reader Replaced.Cause Still Under Investigation 05000000/LER-1986-024, Partially Deleted LER 86-024-00:on 861113,attempted Introduction of Unauthorized Weapon Into Protected Area Discovered.Caused by Personnel Attempt to Enter Plant W/ Concealed Gun.Personnel Denied Facility Access1986-11-18018 November 1986 Partially Deleted LER 86-024-00:on 861113,attempted Introduction of Unauthorized Weapon Into Protected Area Discovered.Caused by Personnel Attempt to Enter Plant W/ Concealed Gun.Personnel Denied Facility Access 05000000/LER-1986-007, Partially Deleted LER 86-007-01:on 860218,loss of Alarm Surveillance Occurred.Caused by Water Leaking Into Cable Due to Heavy Rain.Cable Dried,Leak Repaired & Design Corrected1986-10-0606 October 1986 Partially Deleted LER 86-007-01:on 860218,loss of Alarm Surveillance Occurred.Caused by Water Leaking Into Cable Due to Heavy Rain.Cable Dried,Leak Repaired & Design Corrected 05000000/LER-1986-021, Partially Deleted LER 86-021-00:on 860911,vital Area Doors Failed to Alarm When Tested During Surveillance.Caused by Failure to Report Door Transactions to Host Computer.Central Procesing Unit Board Replaced1986-09-15015 September 1986 Partially Deleted LER 86-021-00:on 860911,vital Area Doors Failed to Alarm When Tested During Surveillance.Caused by Failure to Report Door Transactions to Host Computer.Central Procesing Unit Board Replaced 05000000/LER-1986-020, Partially Deleted LER 86-020-00:on 860812,security Sys Experienced Loss of Power.Caused Withheld.Numerous Failures Experienced Until Machine a Designated as Prime.Procedures to Reboot Computers Revised1986-08-15015 August 1986 Partially Deleted LER 86-020-00:on 860812,security Sys Experienced Loss of Power.Caused Withheld.Numerous Failures Experienced Until Machine a Designated as Prime.Procedures to Reboot Computers Revised 05000000/LER-1986-004, Partially Deleted LER 86-004-01:on 860204,loss of Dynamic Reporting of Alarm Surveillance Occurred.Cause Withheld. Computer Svcs Personnel Will Continue to Monitor Sys for Indicators of Cause1986-06-11011 June 1986 Partially Deleted LER 86-004-01:on 860204,loss of Dynamic Reporting of Alarm Surveillance Occurred.Cause Withheld. Computer Svcs Personnel Will Continue to Monitor Sys for Indicators of Cause 05000000/LER-1986-016, Partially Deleted LER 86-016-00:on 860501,vital Area Door Discovered W/O Alarm Capabilities.Caused by Access Control Security Officer Asleep at Post.Determination to Suspend or Discontinue Employment Being Made1986-05-0606 May 1986 Partially Deleted LER 86-016-00:on 860501,vital Area Door Discovered W/O Alarm Capabilities.Caused by Access Control Security Officer Asleep at Post.Determination to Suspend or Discontinue Employment Being Made 05000000/LER-1986-015, Partially Deleted LER 86-015-00:on 860428,stationary Side of Door Failed to Alarm When Tested.Cause Withheld.Alarm Repaired1986-05-0202 May 1986 Partially Deleted LER 86-015-00:on 860428,stationary Side of Door Failed to Alarm When Tested.Cause Withheld.Alarm Repaired 05000000/LER-1986-014, Partially Deleted LER 86-014-00:on 860421,bomb Threat Received by Security Officer in Security Assembly Room. Cause Not Applicable.Actions Taken to Minimize Station Threat & Investigation Underway1986-04-25025 April 1986 Partially Deleted LER 86-014-00:on 860421,bomb Threat Received by Security Officer in Security Assembly Room. Cause Not Applicable.Actions Taken to Minimize Station Threat & Investigation Underway 05000000/LER-1986-013, Partially Deleted LER 86-013-00:on 860414,vital Area Door W/O Alarm Capability Discovered.Caused by Personnel Error. Personnel Removed from Shift & Vital Area Checked for Unauthorized Personnel W/None Being Found1986-04-18018 April 1986 Partially Deleted LER 86-013-00:on 860414,vital Area Door W/O Alarm Capability Discovered.Caused by Personnel Error. Personnel Removed from Shift & Vital Area Checked for Unauthorized Personnel W/None Being Found 05000000/LER-1986-012, Partially Deleted LER 86-012-00:on 860412,breach Discovered in Protected Area Barrier.Caused by Personnel Error. Personnel Counseled1986-04-17017 April 1986 Partially Deleted LER 86-012-00:on 860412,breach Discovered in Protected Area Barrier.Caused by Personnel Error. Personnel Counseled 05000000/LER-1986-011, Partially Deleted LER 86-011-00:on 860410,vital Area Intrusion Alarm Failure Occurred.Cause of Event Deleted. Alarm & Door Tested Satisfactorily1986-04-15015 April 1986 Partially Deleted LER 86-011-00:on 860410,vital Area Intrusion Alarm Failure Occurred.Cause of Event Deleted. Alarm & Door Tested Satisfactorily 05000000/LER-1986-003, Partially Deleted LER 86-003-00:on 860125,loss of Dynamic Reporting of Vital Area Door Activity Occurred.Caused by Equipment Malfunction.Corrective Action Withheld1986-01-29029 January 1986 Partially Deleted LER 86-003-00:on 860125,loss of Dynamic Reporting of Vital Area Door Activity Occurred.Caused by Equipment Malfunction.Corrective Action Withheld 05000000/LER-1986-002, Partially Deleted LER 86-002-00:on 860117,loss of Alarm Surveillance on Doors Occurred.Caused by Erroneously Listing Officer as Being Posted on Door 398.Processing of Rev to Physical Security Plan Initiated1986-01-23023 January 1986 Partially Deleted LER 86-002-00:on 860117,loss of Alarm Surveillance on Doors Occurred.Caused by Erroneously Listing Officer as Being Posted on Door 398.Processing of Rev to Physical Security Plan Initiated 05000000/LER-1986-001, Partially Deleted LER 86-001-00:on 860105,loss of Dynamic Reporting of Vital Door Activity Occurred.Cause & Corrective Action Completely Deleted1986-01-10010 January 1986 Partially Deleted LER 86-001-00:on 860105,loss of Dynamic Reporting of Vital Door Activity Occurred.Cause & Corrective Action Completely Deleted 05000336/LER-1983-012, Updated LER 83-012/03X-1:on 830322 & 26,charging Pump C Shut Down Due to Lost Oil Pressure.Caused by Failed Integral Oil Pump Drive Coupling.Coupling Repaired1984-03-12012 March 1984 Updated LER 83-012/03X-1:on 830322 & 26,charging Pump C Shut Down Due to Lost Oil Pressure.Caused by Failed Integral Oil Pump Drive Coupling.Coupling Repaired 05000336/LER-1983-020, Updated LER 83-020/01X-1:on 830613,2,557 Degraded Tubes Discovered on Steam Generator Tubing.Cause Undetermined. Tubes W/Flaws Less than + or - 40% Through Wall or Eddy Current Probe Restrications repaired.W/840213 Ltr1984-02-13013 February 1984 Updated LER 83-020/01X-1:on 830613,2,557 Degraded Tubes Discovered on Steam Generator Tubing.Cause Undetermined. Tubes W/Flaws Less than + or - 40% Through Wall or Eddy Current Probe Restrications repaired.W/840213 Ltr 05000336/LER-1983-007, Updated LER 83-007/01T-1:on 830318,nonconservative Safety Analysis Assumption Discovered in Steam Generator Tube Rupture Analysis.Radiological Consequences of Reanalysis Being Analyzed1983-12-0909 December 1983 Updated LER 83-007/01T-1:on 830318,nonconservative Safety Analysis Assumption Discovered in Steam Generator Tube Rupture Analysis.Radiological Consequences of Reanalysis Being Analyzed ML20064F8591978-11-28028 November 1978 /03L-0 on 781115:spent Fuel Pool(Sfp)Ventilation Particulate & Gaseous Setpoints Exceeded Tech Specs Setpoints of Table 3.3-6,items 2.c & 2.d.Caused by Monitor Recalibr W/O Taking Into Account Tech Spec Limit ML20064F1651978-11-21021 November 1978 /03L-0 on 781025:during Oper,Surveillance Test on Channel a Reactor Protec Sys Core Protec Calculator Reveated Sys Ground Traced to Signal for Pressurizer Pressure W/In Containment Boundary.Source Not Known at This Time ML20064E6611978-11-16016 November 1978 /03L-0 on 781024:plant Computer Malfunction Caused CEA Pulse Counting Position to Be in Oper.Cause of Computer Failure Could Not Be Traced ML20064E1501978-11-0606 November 1978 /03L-0 on 781007:daily Tech Spec 4.3.1.1.1.,Table 4.3-1,items 2.a & 2.b,Nuc Pwr Surveillance & Delta-T Pwr Channel Calibr Not Performed Due to Personnel Error. Supervisors Told to Perform Req Surveillance ML20064D6131978-11-0303 November 1978 /03L-0 on 781025:Analysis of Instru Installations Revealed That Two Transmitters Assoc W/Channel a Steam Generator Low Water Lever Were non-seismically Mounted. Channel a SG Was Bypassed.Seismic Brackets Will Be Used ML20064D6011978-11-0101 November 1978 /03L-0 on 781004:during Surveillance Testing, Setpoint for Reactor Protec Sys Reactor Coolant Low Flow Trip on Channel B Was Out of Spec.Setpoint Was Readjusted. Rev Will Req Low Flow Trip Unit Setpoint Be Reset ML20064B8171978-10-0202 October 1978 /03L-0 on 780906:Loss of Methyl Iodide Removal Efficiency for a Ebfs Train. Cause Unknown 1997-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
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J NZRTHEAST UTILITIES *=' o"* " ' S * " S" "' S """ " " * " * " .
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w$s EaYsI:nTettNee$rYC Sm*n P.O. BOX 270
( ' y ' Ene'esI$tIeNervIcel*N.rany HARTFORD. CONNECTICUT 06141-D270 N:rineast Nstw Energy Company (203)E 55-5000 August 13, 1993 i MP-93-642 Re: 10CFR50.73(a)(2)(i)
U.S. Nuclear Regulatory Commission -
Document Control Desk Washington, D.C. 20555 ,
Reference:
Facility Operating License No. DPR-65 Docket No. 50-336 Licensee Event Report 93-014-00 Gentlemen: .
This letter forwards Licensee Event Report 93-0014-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i). Specifically. Technical Specification surveillances were not performed within the required interval. :
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY ,
FOR: Stephen E. Scace l Vice President - Millstone Station !
[ -
BY: Harr( y ? .y .. s Millstone nit x
1 Di ect[ .
SES/JLC:cic ,
Attachment:
LER 93-014-00 cc: T. T. Martin, Region 1 Administrator P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1, 2 and 3 G. S. Vissing NRC Project Manager, Millstone Unit No. 2 I
S00.7.3 9308160109 930813 9 PDR ADOCK 05000336
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A NRO bm 366 U. S NUCLE AR REGULATORY COMM:S Sf 0N APPROVED OMS NO. 315D-01Da (6-89) E APIRE S : 4(30'92
- Estm.a'ed burcea re' resoonse to ecmpty ein inrs in'ormation conection roovest: 50 0 h*s Forwarc comments rega'em; D#oen estmate to fne Reco'es LICENSEE EVENT REPORT (LER) ane Renens Management e anch (p-E30L U S Nuc!e ar Regmatory Corn %ssion. Wasmrpor' DC 20EE5. anc to the Ps:e work Rec. action Proxt (3150-C1D41 CMce et Vanape"wnt ant' 6 sCpet WashingiCm Dc 205 3 DOC M T NJMB E R (2 ) 84 y F ActuTY NAME (1)
Millstone Nuclear Power Stauon Una 2 oj si of ol ela l3 ls 1lod0l3 i
TITLE (4)
Technical Specihcanon Surveillance Not Performed Within Required Time Interval i EVEtc DATE (5) ( F A NuMPE; sm l RE POAT DATE (71 OTwE A F AOt ? TIE S NVOL VE D iP i F AO'UTY f=AME S uONw oAv vtAR vEAR LT ;
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0l7 1l4 9' 3 9 l3 0l1l4 0l 0 0l8 1l3 9l3 ojsjololol l l OPER ATING THis REDOAT IS BEING SUBM'TTED PURSUANT TO THE REOUIEEMEN'S OF 10 CFR $ (ctwcw one or tw:ye of tne fo40wm;;m11 20 402:t) 2D a02tc) 50. 73 t a)(2)(w) 73 71(b) popgE g 20 405ta):1 H.) 50 36'c)(1) 50.73(aH2H ) 73 71 rc) i hE P 1l0l0 20 aoStair1>o. 3: 3E ,:3 ct) se 73 ;a3 ;23,,,,3 OT eER isnea,y e At stra " betw aa:' en 50 73[all2HvmllAl Tm NRc Fom 36E A) 20 eD5;atti) Dos y 50.73 t a t C) D e i
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UcLNSE E CONTACT FOn Tets LE R (12) ,
TE.f P"ONE NUVEE D NAME AREA CODE John L Criscione, Semor Encineer, ext. 4M 4 2l0l3 4l4l7l-l1l7l9l1 COVDLETE ONE UNE rDA E ACH couPONEN FAiURE DE SCRBE0 IN TwS REPOAT c13, ;
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I i i I ! I I i 11 I I I I SJDW EVENT As REDO T E *PECTED fla )
MONN DAV VEAR E X PE C TE D Sche ss ON VE5 et ves comroe'e EXCECTED SUEM SSON DATE ) NO l l l AESTRACT L.mt la taDO spaces < e . as:.itee.a e y f t eeri sm; e-s:: ate iv: t*wr:ttee hoes) (16)
On July 14,1993, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, wnh the plant m Mode 1.100% power level, it was d:scovered that surveillance procedures SP 2$05C-1, " Post incident Recirculauon System Operability TestJ and SP 2610F-1, .
"PORY Block Vahe Operabihty Test," had not been performed within the spcified time mterval m accordance I with Technical Specihcanon 4.0.2. SP 2605C-1 senbes the Facihty 1 post mcident recirculation f an can be started by the operator from the Comrol Room and that it operates for at least 15 minutes. SP 2610F-1 venfies that the block vahe can operate throuch one complete tyde of full travel and valve posinon indicanon Is
' available m the Contro! Room. These quarterly surveinance procedures are reqmred to be conducted every 3 t months, not to exceed a maumum of 115 days ((92 days + 25c) c = 115 days). SF 2605C-1 and SP 2610F-1 i I had been previously performed on March 1,1993. Upon d:scovery of the missed surveillances, they were ,
immeiately performed 9
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- "*"C "*'*' 5' 6' LICENSEE EVENT REPORT (LER) comments regaromg o'*o"e, u estimate"" ' '?
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NeCorSS TEXT CONTINUATION a,o neoorts Manage,ent Bra,=n ir-r,aa, u s %:iear RepJeto v Commsstom Wasmngrom Dc 20555 and tc t*e Pane worn Recutt.on P*o,e=t 13:50-01D41. omte of Manapement anc buopet W arr9ngton Dc cc6c3 FAcW Y NAME 11, DOCKET NJ4E4 ic; Ln:e rf unts o PAGE23i VEAR ""a caust N
man Millstone Nuclear Power Station Unn 2 0l 5l 0l 0l 0l3 l3 l6 9l3 0l1l4 0l0 0l 2 OF Oj3 TEXT W mo*e srace >s *ec mec use a=0.t ona' NAc Fo- 3t6A s, (171
- 1. De cnpimn of Event :
On July 14.1003 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, wnh the plant in Mode 1.1009 power level it was discovered that suneillance procedures SP 2t30SC-1. " Post incident Recirculanon System Operabihty Test, and SP 2610F-1. PORY Block Vahe Operabiht) Test." had not been performed wnhm the specified ume interval m accordance wnh Technical Specification 4.0.2. SP 260SC-1 verifies the Facihty 1 post incident rearculation fan can be staned by the operator from the Control Room, and that it operates for at least 15 minutes, SP 2ts10F-1 senfies that the block valve can operate through one complete cycle of full travel and vahe posinon mdicanon is available m the Comrol Room. These quanerly surveillance procedures are required to be conducted esen 3 months. not to exceed a maximum of 115 days ((92 da3 s + 259) = 115 day s). SP 260SC-1 and SP 2610F-1 had been previously performed on March 1.
1993. Upon disemery of the missed surveillances they were immediately performed.
In May 1993, an minauve was established to schedule all Techmcal Specif canon suneillances by computer. The imual result was the mcorporation of weekly and monthly survel!!ances onto the computer schedule. to be followed by quanerly and yearly suneillances. Howeser, by the time quarterly and later s .rveillances were issued and scheduled. these two particular surveillances had already passed their 250 margm for performance and were thereby missed as the on-shift Operations personnel were nm noufied of the schedule revNon.
On July 14. 1093 uhen the Operations Technician was reviewmp surveillances requ red m June, n was discosered the two suneillances had not been performed. The Shift Supenisor was notified on Juh-1J. 1003 and the suneillance immed:ateh performed.
r 11 Came af Event The cause of thn incidem was program failure. miufhcient planning. The computer generated
, sunei!!ance schedule was not validated nor schedule omasions promulgated by the miegrated team and Operauons Staff to ensure all sunei!!ances were scheduled. When the d:scovery was made that the imual !
comptner generated schedule did not mcorporate quarterly surveillances, compensatory action was not
- taken m a umely fashion to ensure these quanerly suneillances were completed wnhm the allowable 1
inten al A contributory cause was personnel error, work organization. and planning. The review of completed survei!!ances with respect to required frequency uas not done at the appropnate periodicity.
111. Anahm of Evem Per Techrocal Spenficanon 4.0 2, each sune1 Hance requirement shall be performed withm the specified time mienal wnh a maximum allouable extension not to exceed 259 of the surveillance ume mterval.
This esent n being reponed pursuant to the requirements of 10CFR50.73(a)(2)O), meident category 30 day Licensee Esern Report.
At no time was the safety of the plant at nsk due to survet!!ances were not performed wnhin the requ red mierval because the last quarterly surveillantes were sainfactority performed on March 1.1993 for SP 2605C-1 and SP 2610F-1. On Jah 14,1993. when the encovery was made these surveillances had not been performed withm the a!!awase ume mienal for the next cuarter, they were immediately -
perf ormed satisf acionly . This resulted in surveillance performance 20 days outside the allowable mierval f or the quaner, ,
Between the performance of the last quarterly suneillances and July 14.1993 performance. no :
mamtenance or modifications were made to the applicable equipment to affect operabilnv. Therefore. it I is unEkely the equipment would hate failed to satisfy the safety related funcuorn '
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NRC For'r: SMA US MJOLEAR REGJLATC>RY COMrAS$CN APPROVED OMB NC 315c-c %4 .
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- d LICENSEE EVENT REPORT (LER) cor,a.,"*$ re"paro no"d.,aen estir 2:. to 1%. s"ecouis .i TEXT CONTINUATION anc Recom Managewt eranen a-sm u s Nuew Repwato y Comm s:A W a smn;; ton DC 20555 and to t e Paperwom Maxtion Profect (340-0504; O* bee c1 Manapeme"t anc bud,)e' W MN*tC%rn Dc 20603 F AOLIT Y NAME (1, OccAET NUMBER 421 i FC tJt MFif L M1 H C$E i91 vEAR N Nd "et .NEsDe 94MUt Milistone Nuclear Power Station l' "" -
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,E n ~ mue sw=,,s e w en uw aw.vw Nm surm mA s; on lY. Correctn e Action l'pon dscmery of the rmued suneillances, both were perinrmed immedtately, Suneillances due in May and June were also checked to determme if similar problems eusted. ,
To prevent recurrence, the folloump acuonc were implememed:
- 1. The Operations Technician has vahdated the computer generated surveillance schedule through July 1u94 to ensure ALL sunediances are 1sted.
- 2. An Operauons tracking system utilizmg a hst of all surveillances for a particular period is being modihed to melude independent status checks on sunedlences by the on shift Supervismg Control Operator (SCO), the Operations Assistant, and the Operanons Techmcian.
3 Other apphcable Una 2 departments reviewed this event and determmed adequate measures are in place to pres ent recurrence of this problem. Imtiauves and programs are in place to ensure proper scheduhng and verificanon of compleuon of suneillances.
- 4. The draft revision to Operations Department Instruction. 2-OPS-4.03, "Flowpath for Technical Specihcanon Required Sunedlances" was tersed to address changes to the process brought about by the Integrated Team irunatise to schedule Techrucal Specificanon suneillances using the P2 schedule. The ODI also includes a requirement for the Operanons Assistant to serify complenon of scheduled Techmcal Specificanon sunedlances at regular intervals. ;
V Adinonal Inf ormation T here were no faded components associated with this esent.
Similar Esenb: !_ERN 93-001,02-001, 91-006,41-007 90-020, M-007, M-005 5
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05000423/LER-1993-004 | LER 93-004-01:on 930331,RT Occurred Due to electro-hydraulic Control Power Supply Failure.Replaced Faulty Power Supply. W/930831 Ltr | | 05000245/LER-1993-006, Forwards Updated LER 93-006-01 Which Was Previously Submitted W/O Rev Bars | Forwards Updated LER 93-006-01 Which Was Previously Submitted W/O Rev Bars | | 05000336/LER-1993-007, Incorporates NRC Comments Discussed During 940324 Telcon Into 931217 Application for Amend to License DPR-65,revising TS 3.8.1.1,as Result of LER 93-007-00,dtd 930428 & Util 930726 Response to NOV from Insp Rept 50-336/93-81 | Incorporates NRC Comments Discussed During 940324 Telcon Into 931217 Application for Amend to License DPR-65,revising TS 3.8.1.1,as Result of LER 93-007-00,dtd 930428 & Util 930726 Response to NOV from Insp Rept 50-336/93-81 | | 05000336/LER-1993-008 | LER 93-008-01:on 930505,declared Charging Pumps Inoperable Due to Low Control Power Voltage.Established Administrative Controls & Installed Interposing Relay within C Charging Pump Control circuit.W/930902 Ltr | | 05000423/LER-1993-011 | LER 93-011-00:on 930731,MSSV Lift Setpoint Drift Occurred Due to Unknown Cause.Reduced Setpoint for Power Range Neutron Flux High Trip to 10%.W/930830 Ltr | | 05000245/LER-1993-011, Responds to NRC 981002 Request to Counsel That NNECO Waive Any Assertion of Statue of Limitations for 60-90 Days with Respect to NRC Ability to Initiate Civil Penalty Action Based on Apparent Violation of 10CFR50.59 Re LER 93-0 | Responds to NRC 981002 Request to Counsel That NNECO Waive Any Assertion of Statue of Limitations for 60-90 Days with Respect to NRC Ability to Initiate Civil Penalty Action Based on Apparent Violation of 10CFR50.59 Re LER 93-011-00 | | 05000423/LER-1993-012 | LER 93-012-00:on 930805,piece of Plywood Discovered in Train a of Sws.Caused by Inadequate Work Control During 1991 Outage to Repair Sws.Plywood Removed & Increased Attention Being Paid to Matl Exclusion in Critical sys.W/930903 Ltr | | 05000336/LER-1993-014 | LER 93-014-00:on 930714,discovered Surveillances Procedures Had Not Been Performed within Specified Time Intervals Due to Insufficent Planning.Missed Surveillances Immediately performed.W/930813 Ltr | | 05000336/LER-1993-016 | LER 93-016-00:on 930729,reportability Determination Made Re Analysis for Boron Dilution Event.Caused by Inadequate Review of Results of Boron Dilution in Relation to Plant Operating Conditions.Boron Results revised.W/930827 Ltr | | 05000336/LER-1993-018 | LER 93-018-00:on 930805,letdown Manual Isolation Valve 2-CH-442 Developed Leak Which Exceeded TS Limits.Root Cause Has Not Been Determined.Valve Replaced & All Code Required Post Intallation Tests Successfully completed.W/930903 Ltr | | 05000336/LER-1993-019 | LER 93-019-00:on 930812,reactor Trip Occurred Due to Low SG Level.Conducted Shift Briefing of Event to Operating Shift While Assuming Watch.Briefing Included Listed Requirements for Subsequent Specific start-up.W/930910 Ltr | | 05000336/LER-1993-023, Forwards LER 93-023-02,documenting Event Occurred at Unit 2 on 930622.Commitments Made within Ltr Listed | Forwards LER 93-023-02,documenting Event Occurred at Unit 2 on 930622.Commitments Made within Ltr Listed | |
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