|
---|
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
[Table view] |
LER-2090-022, |
Event date: |
|
---|
Report date: |
|
---|
4232090022R00 - NRC Website |
|
text
p-3 gg General Offices *$eloon Street, Berkn Connecticut i
l NINNe'sNeUEttIY.YccN7
'T" I8.$sI$tNEv'ic.7Elenny P.O. Box 270 HARTFORD. CONNECTICUT 06414-0270 twrte.ast Near tre gy co naany (10316F6-6000 July 16, 1990 MP-90-700 Re: 10CFR50.73(a)(2)(i)
(-
[' U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Reference:
Facility Operating License No. NPF-49 l<
Docket No. 50-423 Licensee Event Report 90-022-00 Gentlemen:
This letter forwards Licensee Event Report 90-022-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(1), any operation or condition prohibited by the plant's Technical Specification.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: Stephen E. Scace Director, Millstone Station BY:
ff John P. Stetz
- ' Millstone Unit 1 Director SES/PAF:mo
Attachment:
LER 90-022-00 cc: T. T. Martin, Region 1 Administrator W. J. Raymond, Senior Resident Ins 3ector, Millstone Unit Nos.1, 2 and 3 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 9007250027 900716 D PDR ADOCK 05000423 S PDC p h/ Ko8/V E6 22
a C orm no y,g NvCgg Ast F4EQULATORY cosassioN APPHov j oyL}tga bs-Ouas E stimated tusroen po' restonne to compir with this -
mtormation conection reasest: 60 0 hrs Forn ara LICENSEE EVENT REPORT (LER)
- l' @'ts &*aQEO*SrNCLIDi'"'v"E7?a'eiser 84epuistory Comm.ssion. Washmpton. DC 20666 a*c to 1*ie F aperwork koosction Proitet (316D-01De L Office of Management enc Ehuopet. Washmpton. o0 20603 F ACLIT Y NAML l t) DOChil NVMbth 623 6*M Millstone Nuclear Power Station Unit 3 o f s l ol of 014 l 2 l 3 ilOFl 0l 3 init .o Missed Hourly Fire Patrol Due to Procedural Deficiency r vt NT oats r6. tra Nounroeei ArpOnt nitt <r. OTHr A F Accrit, iNvm vro ,e.
Moth DAY YEAR YE As4 MONT H DAY YEAg F ACIUT Y NAML6 olsiofolel l I
~ ~
0 6 1l6 9 0 9 l0 0l2l2 0l 0 0 l7 1l6 9l0 ofsiofolel l l OpgRAtpan THis $1EPORT IS DEING BUDMITTED Pu8 i SUANT TO THE AEculREMENTS ok 10 CFR $- (Check one or more of the followmg)(t11
$Q 403(b) 7Q 4Q2tc) $0. r3la )(2)(ly) 73,71lh)
Po A to 40616H1)(O 60 36(c)d) 60.73(aH2)lv) _
73,71ge) oYo 0l8l0 to ao6I*HiH) _
so.36 cH2) _
60.73 sa)(2Hvii) _
g(m,WFo'm(6tgitg ,
366A) 1 *xt. N g _
20 406teH1)D64 g 60.73(aH2HO 60 73(aH2Hvhi)t A) y ' 20 4D6(aH1)pv) 60 73taH21HO 60 73teH2HviiiHB) I Po antasuiu.vi 6D 73(aH2Hhu 60 73taH2Hz)
LICEN6EE CONT ACT FOR THis it ta M2i NAMg TE trPHONE NUMfil A AHL A cODi Peter A. Freeman, Engineer, X5302 2l0l3 4]4l7l-l1l7l9l1 COMPLETF ONE UNE FOR E ACH COMPONENT F AILUAF r>ESCAiBED IN TH!S AFDOAT tt3i j cAUSE SYSTEM COMPONENT M$MC* E '
g CAUSE SYSTEM COMPONENT MpgC- g i III I I I -
1 II I I I I # '
S
'J I II I I I I
^
l iII I I I SUPALEMENT AL AFPOAT ExprCTED fidi MONT H DAY YEAR L
""1 ves ne vos. compieie Expretto sueuissioN DATr> uo s'NTE 06)%EPN l l l
.. 1-c1,m_ ,o ,.m s ..es , e e . o _ a,e ,i,, n . . s _ . , _ e,,m.s, H.,
On June 18,1990 at approxunosly 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, with the plant at 80Q power (Mode 1), the Shift Supervisor (SS) discovered that an hourly firewatch patrol had not been estabhshed in Battery no. 4 inverter Room, located in the West Switchgear area of the Control Building. An hourly firewatch patrol was required after the fire detection zone panel for the affected area had been declared inoperable.
On June 16,1990 at approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, the fire detection zone panel for Battery no. 4 inverter Room was declared inoperable upon determining a Technical Specification surveillance could not be completed within its required due date because of manpower expenditures involving the intake Structure. Firewatch patrols were established for all areas that were being monitored by the subject fire protection zone panel with the exception of Battery no. 4 Inverter Room.
The root cause of the event was procedural deficiency. Specific guidance for establishing a firewatch patrol within the Battery no. 4 inverter Room when the subject fire detection zone panel was declared inoperable was not provided.
Immediate corrective action was to establish an hourly firewatch patrol in Battery no. 4 inverter Room. As action to prevent recurrence, the applicable procedures will be revised to include the subject inverter Room with its associated Battery Room. This revision will be implemented by July 16, 1990.
gAgForm 366.
g -m3m u o uscua neowonv co-ssoN -ogogp+
e.. mai.e wo., n ...-.. io e,no,-nn in,.
UCENSEE EVENT REPORT (LER) %**g",g *l @ g 'L5 y l',j,,,',",y,'f,,, t TEXT CONTINUATION ano n.oets uanao.m.ni eranen in-saco. v.s Nuew t i a r n o o 3 bc W Off o Manap.m.n1 and Ewopet Wasnington DC 20503 F AChJTY NAME 0) DOCKET NJMBER m t F A Ni#@F A sp PAGE (31 vgAR % N Millstone Nuclear Power Station Unit 3 0l f,l 0l 0l 0l4 l2 l3 9l0 0l0l2 0l0 0l 2 OF 0l3 ['
Text m more space is r.Quir.0. use goddeonal NRc Form 3%A O OD
- l. Deerir9 inn of Event On June 18,1990 at approximatel) 2l00 hours, with the plant at 809 power (Mode 1), the Shift ,
Supervisor (SS) discovered that an hourly firewatch patrol had not been estabhshed in Battery no. 4 ,
inverter Room, located in the West Switchgear area of the Control Building, after its associated fire !
detection zone panel had been declared moperable. The event duration was approximately 2 days. 1 On June 16,1990 at approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, the fire detection zone panel for Battery no. 4 inverter Room was declared inoperable when it was determmed that a Technical Specihcation surveillance could not be completed within the required interval period because of manpower constreints. The surveillance could not be completed within its required interval because repetitive outages requiring contmual manning t of the intake Structure had occupied all available personnel. An hourly hrewatch patrol was established l for areas monitored by the subject hre detection tone panel including Battery no. 4 invener Room. This action was taken to ensure compliance with Technical Specification 3.3.3.7.b (Fire Detection Instrumentation). .
At approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, on June 18, 1990, during performance of the shiftly firewatch patrol tour, the SS discovered that while an hourly brewatch patrol had been established for surroundmg areas, except for Battery no. 4 invener Room. An hourly firewatch patrol was immediately estabbshed for Battery no. 4 invener Room. On July 16; 1990 surveillance testing for the fire detection zone panel which monitors Battery no. 4 inverter Room was successfully completed with no deficiencies noted.
II, cause nf Event The root cause of the event was procedural deficiency. Two procedures were utilized by the SS dering the event. A procedure entitled " Removing Fire Detection Equipment from Service," specihes associated coverage areas for individual fire detection zone panels but did not differentiate between the Battery Room and the Invener Room which are located adjacent to each other in the West Switchgear area of i the Control Building. Technical Specification 3.3.3,7 does not hst the subject Inverter Room as a separate hre zone while the Fire Protection Evaluation Report documents the Inverter Room as an independent zone. The applicable procedures were modeled from the Fire Control Panel data base >
which mimics the Technical Specification. The t.econd procedure utihzed by the SS, Fire Detection '
Protection and Control." specifies all associated areas for each fire detection zone panel, but does differentiate between the Battery Room and the Invener Room. Tab:es associated with the procedure :
pictorially indicate the general location of hre detectors for each fire detection zone panel but does not meludc e hst of affected areas,
- i. -
r L 111. Annhsis of Event This event is reponable pursuant to 10CFR 50.73 (a)(2)(i), as an event or condition prohibited by plant Technical Specifications. Technical Specihcation 3.3.3.7.b requires an hourly firewatch patre! be established within one hour if more than one-half of the early warning fire detection instruments are deemed inoperable in any fire zone listed in table 3.3-11 (Fire Detection Instrumentation). ,
Fire suppression for the affected area consists of the unit hre brigade. The fire brigade is required to respond when mdication of hre is received at the Control Room. Fire detection was deemed inoperable because administrative requirements could not be fulfilled, nat because of Mechanical / Electrical failure. t On July 16, 1990 the applicable fire detectors were satisfactorily tested and deemed operable. Fire detection for the affected area was fully capable of performing its design function throughout the event. ,
Therefore, the event posed no signincant safety consequences, germ 3a
hRc f orm 366A U.s NJcLE A4 REQJLAToRY CoMMJSStoN APPROVED OMD NO. 3110-0104
, (6-69P E xpiAE $ e /30Jp2 Estimatec tiaroen per response to comply with this LICENSEE EVENT REPORT (LER) 'agm,*Jg,,*g*y'*"
n '*g*5hg,9,"',*g ,,',*',*,*,',',,,
TEXT CONTINUATION .no no.> ort Man p.mont er.nen (D-63oi. u s Nacier Aepuistory Commissen. Washington De 20666. ena to the Parerwork Steasetion Protect (316>01041, othee of Management and buoppt W ashington De P0603 F ACILITY NAME o) Docket NUMBER (2) t F A NUMPFm #p l FAGE (3i vEAn *Lassmat q qiEs-Millstone Nuclear Power Station Unit 3 ~ ~
0l 6l 0l 0l 0l4 l2 l3 9l0 0l 2l2 0l0 0l 3 OF 0l3 Ttxt m more op e. is seawee. ese nooitionai Nnc Form 366rel on
]V. Entrectwe Actinn immediate corrective action was to establish n hourly firewatch patrol in Battery no. 4 inverter Room located in the West Switchgear Room area of the Control Building. As action to prevent recurrence, the applicable procedures will be revised to include the subject inverter Room with its associated Battery Room. This revision will be instituted by July 18.1990.
V. Additionni informntion LERs86-027 and 90-016 discuss two previous events which have the sa".ie underlying concerns.
LER 66-027 (Mislocated Firewatch Due to Personnel Error) discusses an event in which a cornmunications error between shift personnel resuhed in a firewatch being improperly stationed. The corrective action for this event was to further clarify the physical location of fire detection zones. This revision did not provide for sub-divisions in any fire zone area. Therefore, the corrective actions of LER 88-027 would not have prevented the events of LER 90-022 from occurring.
LER 90-018 (Improperly Established Firewatch Due to Miscommunications) discusses an event in which a communications error between shift personnel resulted in an hourly firewatch patrol location being established by firewatch personnel in lieu of a non-licensed operator (PEO) as requested by the Shift Supervisor. The corrective action for this event was to modify the applicable procedure to verify proper firewatch patrol tocation within one hour of establishment. This corrective action would not have prevented the event of LER 90-022 from occurring, since the corrective action assumes that the areas identified for firewatches are accurately determined by shift management. Implementation of procedure changes to clearly identify these sub-divisions in conjunction with the corrective actions discuned in LERs88-027 and 90-022 should preclude similar events.
EllR Cndes Evstems i
Control Building - NA Fire Detection System - IC Comnonents Fire Detector - DET !
1 l
1 i l
- IC"M*"" ***
,
|
---|
|
|
| | Reporting criterion |
---|
05000336/LER-1990-008 | 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-1990-009 | 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 | | 05000336/LER-1990-010 | 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-1990-019 | 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 | | 05000423/LER-1990-021 | 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 | | 05000423/LER-1990-022 | 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-1990-024 | 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 | | 05000423/LER-1990-025 | 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 | | 05000423/LER-1990-026 | 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 | |
|