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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046B8951993-07-30030 July 1993 LER 93-008-01:on 930518,determined That Control Air Not Analyzed to Function During Seismic Event Due to Lack of Understanding Significance of Control Air Availability for Long Term DG Operation.Ufsar Will Be Updated ML20046B8961993-07-30030 July 1993 LER 93-011-00:on 921219,930209 & 0415,SW Pumps SW-P-41B, SW-P-41B & SW-P-41D Declared Inoperable,Respectively Due High Vibration.Caused by Excessive Abrasive Particles in Ocean Water.Pumps replaced.W/930730 Ltr ML20045G6641993-07-0101 July 1993 LER 93-006-01:on 930401,Train a Svc Water Inoperable Due to Corrosion Product Buildup Between Valve Stem & Packing Follower.Returned SW-V54 to Operable Status & TS 3.7.4 Action D Exited on 930402.W/930701 Ltr ML20045D6791993-06-21021 June 1993 LER 93-002-01:on 930107,determined Potential for Premature Opening of Containment Bldg Spray Sump Isolation Valves. Caused by Failure to Adequately Recognize Potential Sys Interactions.Affected Procedures Revised ML20045C5421993-06-18018 June 1993 LER 93-010-00:on 930522,SG Level Oscillations Occurred in One SG Resulting in SG Being Overfed & Causing high-high SG Water Level.Caused by Personnel Error.Power Reduced to Approx 2.5% & FW to SGs restored.W/930618 Ltr ML20045D3681993-06-18018 June 1993 LER 93-009-00:on 930520,manual Reactor Trip from 100% Power Initiated When MSIV Closed During Quarterly Testing, Resulting in Feedwater & Two Emergency Feedwater Isolations. Caused by Debris in Valves.Valves Replaced ML20045C5341993-06-16016 June 1993 LER 93-008-00:on 930518,identified That Failure of Air Supply to EDG Jacket Cooling Water Temperature Control Valves During Seismic Event Could Cause Overcooling of Edgs. Operability Determination Performed for EDGs.W/930616 Ltr ML20045B5181993-06-11011 June 1993 LER 93-007-00:on 930512,protective Devices Not Analyzed to Function During Environ Excursions Due to Unknown Cause Which Is Under Review.Operability Determination Was performed.W/930611 Ltr ML20024H1621991-05-23023 May 1991 LER 91-004-00:on 910401,steam Generator Indicated That Valve Was Not Opening Properly During Plant Restart.Caused by Differential Pressure Across Dash Plate.Dash Plate Machining Performed on Valves to Prevent Valve disk.W/910523 Ltr ML20044B2281990-07-12012 July 1990 LER 90-014-00:on 900612,discovered That Sample Pump for Steam Generator Blowdown Flash Tank Drain Radiation Monitor Not Running.Caused by Suspended Solids in Steam Generator Blowdown Sys.Solids Cleared from Flow switch.W/900712 Ltr ML20043B6741990-05-23023 May 1990 LER 90-008-01:on 900209,latching Mechanism for Door Entering Containment Encl Bldg Failed,Rendering Air Cleanup Sys Incapable of Producing Negative Pressure.Latching Mechanism Repaired & Mods to Doors/Hardware planned.W/900523 Ltr ML20043B3551990-05-21021 May 1990 LER 90-013-00:on 900419,discovered That Containment Personnel Hatch Unsecured for Approx 28 H.Caused by Installation of Locking Plate Upside Down & Placing Lock Through Only 1 Eyelet.Instructions posted.W/900521 Ltr ML20042F5521990-05-0202 May 1990 LER 90-012-00:on 900402,transmitter Failed to Provide Pressure to Reactor Protection Sys Due to Closed Isolation Valve.Caused by Failure to Identify Valve in Procedures. Valves Manipulated to Correct positions.W/900502 Ltr ML20042E1781990-04-0606 April 1990 LER 90-006-01:on 900206,control Room Ventilation Sys Train a Radiation Monitor Went Into High Alarm Condition.Caused by Mechanical Binding of Check source.Geiger-Muller Tube Replaced & Monitor Returned to svc.W/900406 Ltr ML20042E1741990-04-0505 April 1990 LER 90-011-00:on 900306,actuation of Control Room Emergency Air Cleanup & Filtration Subsystem Occurred.Caused by Failure of Geiger-Muller Tube.Monitor Removed from Svc & Tube replaced.W/900405 Ltr ML20012F5181990-04-0404 April 1990 LER 90-010-00:on 900305,actuation of Control Room Emergency Air Cleanup & Filtration Subsystem Occurred.Caused by Moisture in Detector Housing.Air Intake Monitors Cleaned & Desiccant Placed in housing.W/900404 Ltr ML20012C2461990-03-12012 March 1990 LER 90-008-00:on 900209,latching Mechanism for Door Entering Containment Encl Bldg Failed,Rendering Emergency Air Cleanup Sys Inoperable.Plant Cooldown Initiated,Latching Mechanism Repaired & Door Returned to svc.W/900312 Ltr ML20012C2481990-03-12012 March 1990 LER 90-007-00:on 900208,when Source Check Removed from Control room,RM-6506B Entered High Alarm Condition,Causing ESF Actuation of Emergency Air Cleanup Sys.Caused by Mechanical Binding.Check Source replaced.W/900312 Ltr ML20012B4491990-03-0808 March 1990 LER 90-006-00:on 900206,Train a Radiation Monitor Went Into High Alarm Condition,Resulting in Actuation of Control Room Emergency Air Cleanup & Filtration Subsystem.Caused by Mechanical Binding.Detector Tube remounted.W/900308 Ltr ML20011F4671990-02-22022 February 1990 LER 90-004-00:on 900123,wide-range Gas Monitor Process Flow Rate Value for Vent Radiation Monitor Discovered at Default Instead of Actual Value.Caused by Personnel Error.Process Flow Restored & Technician counseled.W/900222 Ltr ML20006E4591990-02-15015 February 1990 LER 90-003-00:on 900116,wide-range Gas Monitor Low Range Pump Found Inoperable.Caused by Failed Pump Diaphragm Weakened by High Flow Condition.Ruptured Pump Diaphragm Replaced & Pump Returned to Normal operations.W/900215 Ltr ML20006E1731990-02-0808 February 1990 LER 90-002-00:on 900109,discovered That Auxiliary Sample Pump Used to Satisfy Action Requirements of Tech Spec Was Not Operating.Caused by Dislodged Power Fuse.Pump Relocated & Caution Tape Installed to Protect pump.W/900208 Ltr ML20006E1801990-02-0808 February 1990 LER 90-001-00:on 900109,wide Range Gas Monitor Low Range Pump Found to Be Inoperable,Resulting in Noncompliance W/ Tech Specs.Caused by Regulator Isolation Valves Being Left in Open Position.Walkdown of Skids conducted.W/900208 Ltr ML20005E2461989-12-29029 December 1989 LER 89-014-00:on 891129,auxiliary Transformer Supply Breaker to Vital Bus E5 Tripped When Remote Manual Override Relay Energized.Caused by Procedure Inadequacies in Procedure 0S1048.01.Procedure revised.W/891229 Ltr ML20011D4381989-12-19019 December 1989 LER 89-011-01:on 890905,three Unsealed Piping Penetrations in Condensate Storage Tank Encl Identified.Caused by Failure to Transfer Sealing Requirements Into Detail Drawings.Penetrations sealed.W/891219 Ltr ML19332C8511989-11-22022 November 1989 LER 89-013-00:on 891023,discovered That Monitor Used to Satisfy Requirements of Tech Spec 3.3.3.1,Action 27 Had Been Unplugged.Caused by Personnel Error.Individual Counseled & Meeting Held W/Health Physics technicians.W/891122 Ltr ML19325F3301989-11-10010 November 1989 LER 89-012-00:on 891011,one of Two Suction Valves on RHR Train a Pump Closed,Causing Loss of All RHR Cooling Capability.Caused by Procedure Inadequacies.Procedure Revised to Specify Sequence of restoration.W/891110 Ltr ML19325C7891989-10-0505 October 1989 LER 89-011-00:on 890905,determined That Three Piping Penetrations in Condensate Storage Tank Encl Not Sealed.Root Cause Under Investigation.Penetrations Sealed & Tech Specs Surveillance Log revised.W/891005 Ltr 1993-07-30
[Table view] Category:RO)
MONTHYEARML20046B8951993-07-30030 July 1993 LER 93-008-01:on 930518,determined That Control Air Not Analyzed to Function During Seismic Event Due to Lack of Understanding Significance of Control Air Availability for Long Term DG Operation.Ufsar Will Be Updated ML20046B8961993-07-30030 July 1993 LER 93-011-00:on 921219,930209 & 0415,SW Pumps SW-P-41B, SW-P-41B & SW-P-41D Declared Inoperable,Respectively Due High Vibration.Caused by Excessive Abrasive Particles in Ocean Water.Pumps replaced.W/930730 Ltr ML20045G6641993-07-0101 July 1993 LER 93-006-01:on 930401,Train a Svc Water Inoperable Due to Corrosion Product Buildup Between Valve Stem & Packing Follower.Returned SW-V54 to Operable Status & TS 3.7.4 Action D Exited on 930402.W/930701 Ltr ML20045D6791993-06-21021 June 1993 LER 93-002-01:on 930107,determined Potential for Premature Opening of Containment Bldg Spray Sump Isolation Valves. Caused by Failure to Adequately Recognize Potential Sys Interactions.Affected Procedures Revised ML20045C5421993-06-18018 June 1993 LER 93-010-00:on 930522,SG Level Oscillations Occurred in One SG Resulting in SG Being Overfed & Causing high-high SG Water Level.Caused by Personnel Error.Power Reduced to Approx 2.5% & FW to SGs restored.W/930618 Ltr ML20045D3681993-06-18018 June 1993 LER 93-009-00:on 930520,manual Reactor Trip from 100% Power Initiated When MSIV Closed During Quarterly Testing, Resulting in Feedwater & Two Emergency Feedwater Isolations. Caused by Debris in Valves.Valves Replaced ML20045C5341993-06-16016 June 1993 LER 93-008-00:on 930518,identified That Failure of Air Supply to EDG Jacket Cooling Water Temperature Control Valves During Seismic Event Could Cause Overcooling of Edgs. Operability Determination Performed for EDGs.W/930616 Ltr ML20045B5181993-06-11011 June 1993 LER 93-007-00:on 930512,protective Devices Not Analyzed to Function During Environ Excursions Due to Unknown Cause Which Is Under Review.Operability Determination Was performed.W/930611 Ltr ML20024H1621991-05-23023 May 1991 LER 91-004-00:on 910401,steam Generator Indicated That Valve Was Not Opening Properly During Plant Restart.Caused by Differential Pressure Across Dash Plate.Dash Plate Machining Performed on Valves to Prevent Valve disk.W/910523 Ltr ML20044B2281990-07-12012 July 1990 LER 90-014-00:on 900612,discovered That Sample Pump for Steam Generator Blowdown Flash Tank Drain Radiation Monitor Not Running.Caused by Suspended Solids in Steam Generator Blowdown Sys.Solids Cleared from Flow switch.W/900712 Ltr ML20043B6741990-05-23023 May 1990 LER 90-008-01:on 900209,latching Mechanism for Door Entering Containment Encl Bldg Failed,Rendering Air Cleanup Sys Incapable of Producing Negative Pressure.Latching Mechanism Repaired & Mods to Doors/Hardware planned.W/900523 Ltr ML20043B3551990-05-21021 May 1990 LER 90-013-00:on 900419,discovered That Containment Personnel Hatch Unsecured for Approx 28 H.Caused by Installation of Locking Plate Upside Down & Placing Lock Through Only 1 Eyelet.Instructions posted.W/900521 Ltr ML20042F5521990-05-0202 May 1990 LER 90-012-00:on 900402,transmitter Failed to Provide Pressure to Reactor Protection Sys Due to Closed Isolation Valve.Caused by Failure to Identify Valve in Procedures. Valves Manipulated to Correct positions.W/900502 Ltr ML20042E1781990-04-0606 April 1990 LER 90-006-01:on 900206,control Room Ventilation Sys Train a Radiation Monitor Went Into High Alarm Condition.Caused by Mechanical Binding of Check source.Geiger-Muller Tube Replaced & Monitor Returned to svc.W/900406 Ltr ML20042E1741990-04-0505 April 1990 LER 90-011-00:on 900306,actuation of Control Room Emergency Air Cleanup & Filtration Subsystem Occurred.Caused by Failure of Geiger-Muller Tube.Monitor Removed from Svc & Tube replaced.W/900405 Ltr ML20012F5181990-04-0404 April 1990 LER 90-010-00:on 900305,actuation of Control Room Emergency Air Cleanup & Filtration Subsystem Occurred.Caused by Moisture in Detector Housing.Air Intake Monitors Cleaned & Desiccant Placed in housing.W/900404 Ltr ML20012C2461990-03-12012 March 1990 LER 90-008-00:on 900209,latching Mechanism for Door Entering Containment Encl Bldg Failed,Rendering Emergency Air Cleanup Sys Inoperable.Plant Cooldown Initiated,Latching Mechanism Repaired & Door Returned to svc.W/900312 Ltr ML20012C2481990-03-12012 March 1990 LER 90-007-00:on 900208,when Source Check Removed from Control room,RM-6506B Entered High Alarm Condition,Causing ESF Actuation of Emergency Air Cleanup Sys.Caused by Mechanical Binding.Check Source replaced.W/900312 Ltr ML20012B4491990-03-0808 March 1990 LER 90-006-00:on 900206,Train a Radiation Monitor Went Into High Alarm Condition,Resulting in Actuation of Control Room Emergency Air Cleanup & Filtration Subsystem.Caused by Mechanical Binding.Detector Tube remounted.W/900308 Ltr ML20011F4671990-02-22022 February 1990 LER 90-004-00:on 900123,wide-range Gas Monitor Process Flow Rate Value for Vent Radiation Monitor Discovered at Default Instead of Actual Value.Caused by Personnel Error.Process Flow Restored & Technician counseled.W/900222 Ltr ML20006E4591990-02-15015 February 1990 LER 90-003-00:on 900116,wide-range Gas Monitor Low Range Pump Found Inoperable.Caused by Failed Pump Diaphragm Weakened by High Flow Condition.Ruptured Pump Diaphragm Replaced & Pump Returned to Normal operations.W/900215 Ltr ML20006E1731990-02-0808 February 1990 LER 90-002-00:on 900109,discovered That Auxiliary Sample Pump Used to Satisfy Action Requirements of Tech Spec Was Not Operating.Caused by Dislodged Power Fuse.Pump Relocated & Caution Tape Installed to Protect pump.W/900208 Ltr ML20006E1801990-02-0808 February 1990 LER 90-001-00:on 900109,wide Range Gas Monitor Low Range Pump Found to Be Inoperable,Resulting in Noncompliance W/ Tech Specs.Caused by Regulator Isolation Valves Being Left in Open Position.Walkdown of Skids conducted.W/900208 Ltr ML20005E2461989-12-29029 December 1989 LER 89-014-00:on 891129,auxiliary Transformer Supply Breaker to Vital Bus E5 Tripped When Remote Manual Override Relay Energized.Caused by Procedure Inadequacies in Procedure 0S1048.01.Procedure revised.W/891229 Ltr ML20011D4381989-12-19019 December 1989 LER 89-011-01:on 890905,three Unsealed Piping Penetrations in Condensate Storage Tank Encl Identified.Caused by Failure to Transfer Sealing Requirements Into Detail Drawings.Penetrations sealed.W/891219 Ltr ML19332C8511989-11-22022 November 1989 LER 89-013-00:on 891023,discovered That Monitor Used to Satisfy Requirements of Tech Spec 3.3.3.1,Action 27 Had Been Unplugged.Caused by Personnel Error.Individual Counseled & Meeting Held W/Health Physics technicians.W/891122 Ltr ML19325F3301989-11-10010 November 1989 LER 89-012-00:on 891011,one of Two Suction Valves on RHR Train a Pump Closed,Causing Loss of All RHR Cooling Capability.Caused by Procedure Inadequacies.Procedure Revised to Specify Sequence of restoration.W/891110 Ltr ML19325C7891989-10-0505 October 1989 LER 89-011-00:on 890905,determined That Three Piping Penetrations in Condensate Storage Tank Encl Not Sealed.Root Cause Under Investigation.Penetrations Sealed & Tech Specs Surveillance Log revised.W/891005 Ltr 1993-07-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2841999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Seabrook Station. with ML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212B8671999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Seabrook Station. with ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210R9781999-08-0606 August 1999 ISI Exam Rept of Seabrook Station, for RFO 6,period 3 ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20210R6001999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Seabrook Station, Unit 1.With ML20210H1151999-06-30030 June 1999 Naesc Semi-Annual Fitness-for-Duty Rept for 990101-0630 ML20209H1371999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Seabrook Station, Unit 1.With ML20195G5391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Seabrook Station, Unit 1.With ML20195C0491999-05-25025 May 1999 Offshore Intake Seal Deterrent Barrier Design ML20206E4761999-04-30030 April 1999 LER 99-S01-00:on 990408,contractor Employee Was Granted Temporary Unescorted Access to Seabrook Station Protected Area.Caused by Failure of Contractor Employee to Provide Accurate Info.Individual Access Revoked.With ML20206N1751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Seabrook Station, Unit 1.With ML20196L2081999-04-19019 April 1999 Rev 01-07-00 to RE-21, Cycle 7 Colr ML20205K5441999-03-31031 March 1999 Decommissioning Update ML20205L8141999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Seabrook Station. with ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20207F4941999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Seabrook Station. with ML20199E6731998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Seabrook Station, Unit 1.With ML20198P1831998-12-31031 December 1998 LER 98-S01-00:on 981214,incomplete pre-employment Screening Records Was Noted.Caused by Failure of Contractor Employee to Provide Accurate Info.Subject Contractor Employees Employment Was Terminated.With ML20202E8241998-12-31031 December 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980701-981231 ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20198B8661998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Seabrook Station, Unit 1.With ML20195D0311998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Seabrook Station, Unit 1.With ML20154H5291998-10-0808 October 1998 Special Rept:On 980928,meteorological Monitoring Instrumentation Channel Inoperable for Period Greater than 7 Days.Caused by Vendor to Follow Std Industry Practice for Calibr of Instrumentation.Instruments Installed ML20154M8421998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Seabrook Generating Station,Unit 1.With ML20151V5951998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Seabrook Station, Unit 1.With ML20237B4501998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Seabrook Station ML20236R1781998-06-30030 June 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980101-0630 ML20236M3591998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Seabrook Station, Unit 1 ML20237A4871998-06-0303 June 1998 North Atlantic Seabrook Station 1998 Exercise on 980603 ML20248M2951998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Seabrook Station, Unit 1 ML20247G2641998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Seabrook Station ML20247H3171998-04-27027 April 1998 Rev 1 to Seabrook Station SGs B & C Isi,May/June 1997 ML20216F8891998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Seabrook Station 05000443/LER-1998-002, Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted1998-03-20020 March 1998 Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted ML20216H9211998-03-13013 March 1998 Fitness for Duty Program Performance Data Personnel Subject to 10CFR26 ML20248L2811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Seabrook Station, Unit 1 ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20202G3701998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Seabrook Station ML20198G0271997-12-31031 December 1997 Commonwealth Energy Sys 1997 Annual Rept ML20248L7711997-12-31031 December 1997 Western Massachusetts Electric 1997 Annual Rept. Supporting Info,Encl ML20198G1021997-12-31031 December 1997 Baycorp Holdings 1997 Annual Rept ML20198N7021997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Seabrook Station, Unit 1 ML20198G0351997-12-31031 December 1997 Eastern Edison Co 1997 Annual Rept ML20198G0681997-12-31031 December 1997 Taunton Municipal Lighting Plant 1997 Annual Rept ML20248L7671997-12-31031 December 1997 North Atlantic 1997 Annual Rept ML20198F9511997-12-31031 December 1997 United Illuminating Co 1997 Annual Rept ML20236M9561997-12-31031 December 1997 Amended Public Service of New Hampshire 1997 Annual Rept 1999-09-30
[Table view] |
Text
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= Nsw H, ampshire Ted C. Feigenbaum '
1- - Senior Vice President and -
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NYN-90112 i
May 21, 1990-United States-Nuclear Regulatory Commission Washington, DC 20555 Attentions Document Control Desk
Reference:
-(a)
Facility Operating License NPF-86 Docket No. 50-443
Subject:
Licensee Event Report (LER) No.90-013 00: Noncompliance.with Technical' Specifications - Unsecured High Radiation Area s
Gentlemen Enclosed please find Licensee Event Report (LER) No. 90-013-00 for Seabrook Station. This submittal documents an event which occurred on April 19, 1990, and;.is being reported pursuant to 10CFR50.73(a)(2)(i).
Should you require further information regarding this matter, please contact Mr. Richard R.-Belanger at (603) 474-9521, extension 4048.
Very truly yours,
[g G Ted C. Feigenbaum-
Enclosures:
NRC Forms 366, 366A 5 ,
y 9005290177 900521 PDR n
ADOCK 03000443 S PDC 3
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New Hampshire Yonkee Division of Public Service Company of New Hampshire ,
P.O. Box 300
- Telephone (603) 474 9521 i
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- United States Nuclear, Regulatory Comission. ,
May 21,'1990
= Attention: ' Document Control Desk: Page two- q i
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. cci Mr. Thomes.T. Martin !
C1 . Regional' Administrator .
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United States Nuclear Regulatory Comission D Region-I l M(/
475 Allendale' Road i.' King'of Prussia,'PA 19406
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- 1 Mr. Noel Dudley NRC Senior Resident Inspector
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A7 PROVED OMS N131000104 y' 3. LICENSEE EVENT REPORT (LER) milt *1'*'o f ACILITY NAME tu DOCKET NUM9tR (2) PAGE (3, Seabrook Station- o 15 l 0 lo l 0141413 1!OFl013 r TITLE 14l Noncompliance'with Technical Specification - Unsecured High Radiation Area
. EVENT DATE tli LER NUMetR (6) REPORT DATE (7i OTHER F ACILITit$ INVOLVED 14)
MONTH DAY YEAf; YEAR -
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NAME TELEPHONE NUMBER -
Richard R. Belanger, Lead Engineer - Compliance, Extension 4048 ^ " ' ' ' '
61013 41 714 1-19 15 1211 COMPLETE ONE LINT FOR E ACH COMPONENT F AILURE DISchistD IN THIS REPORT (13)
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l l l-i- a:TRACTe m er.,m o u u. . ,.., ,,,,,, .-,. . orv - ,re.. u..iiisi On April 19, 1990, at 5:18 p.m. EDT, it was discovered that the containment
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personnel hatch was unsecured and had been unsecured for approximately twenty-eight _ -;
hours. This occurred contrary to Seabrook Station Technical Specification 6.11.2. I 1
i The' lock was removed on April 18, 1990, to allow operation of the-personnel airlock. At 1:30 p.m. of that day the locking plate and lock were replaced on the controls for the hatch. A second individual verified that the lock was secure.
The controls are locked by sliding a plate in front of the box that encases the q hatch controls. The box and plate each have an eyelet in one corner. With the two 4 eyelets aligned, the plate is secured by placing a lock through both eyelets. ;
On this occasion the plate was installed upside down. When the locking plate was '
in front of the controls, the lock was placed through only one eyelet. The individual who verified that the lock was secure did not recognize that the lock was placed only through one eyelet.
The root cause of this event was personnel error involving a lack of attention to detail.
There were no adverse safety consequences as a result of this event.
The event and its consequences were discussed with all Health Physics operations technicians. Instructions for locking the hatch will be posted at the personnel hatch location.
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0l0 Ol2 OF 0l3 On. April 19, 1990, at 5:18 p.m. EDT, it was' discovered lthat the containment t
' personnel hatch was unsecured and had been unsecured for approximately twenty-eight' f hours. .This occurred contrary to Seabrook Station Technical Specification 6.11.2, which' requires High Radiation Areas, which are areas accessible to personnel with' ,
radiation levels greater than 1000mR/hr at 18 inches-from the radiation pource, be +
locked to prevent unauthorized entry. t
Background
On. April 18, 1990, at 12:40 p.m. the containment personnel hatch controls were' unlocked to allow operation of the personnel airlock for a containment entry. At '
1:30 p.m. of_that day the locking plate and lock were placed on the hatch _ controls.
A second individual then verified that the lock was secure.
The containment hatch controls are secured by sliding a square plate, with an eyelet in one corner, in front of the box encasing the hatch controls. This box ,
also has an eyelet in one corner. With the two eyelets aligned, the plate'is secured by placing a' lock through both eyelets, rendering the controle inaccessible.
However, on this occasion the plate was placed in~the sliding track upside down.
When the-locking plate was in front of the controls, the eyelets did not match and the lock was placed through only one eyelet. The individual who verified the plate was secure had not recognized the lock was.only through one eyelet and the plate could be moved and the hatch controls exposed without removing the lock.
Root Caus2 The root cause of this event has been determined to be personnel error involving a lack of attention to detail. The individual verified that the lock was in place, ;
but did not attempt to move the plate and therefore did not realize that the
-containment personnel hatch controls were not secured.
Safety consecuences Although the controls to the containment personnel hatch were unsecured, all inner doors were still-locked and controlled separately. Therefore, controlled access to containment was maintained. The reactor cavity was the only potentially accessible area within containment with elevated dose rates. A total dose rate of 1670 mR/hr was determined to exist at 18 inches from the neutron shield.
For the twenty-eight hour period that the containment personnel hatch was unsecured, the breaker that operates the hatch controls was tagged out. There were no hatch entries recorded by the security system and no personnel entered the containment building during the time the hatch was unsecured. There were no adverse safety consequences as a result of this event.
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- . ' . d' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION uProvgo onie No siso-eio4 -
EXPimtt; 8/31/m 8 AttLITY esAME 11) Docnti Nues0ER (21 LER NVh0SER ($1 PAQt (3) viaA 8E yu'h* b E7w*aN ;
Seabrook Station oF 0 5 010 l o l 414 3 910 -
Ol 113 -
010 013 Ol3 TENT W asers apses e assisust ans eslistener Nnc w miij gin Corrective Actions To prevent recurrence.of this type of event, a meeting was conducted with all Health Physics operations technicians to discuss the event and its consequences. A
. memo was also issued to the technicians to reinforce the discussion. Furthermore, Li those technicians unfamiliar with the operation and locking of the hatch went to l the personnel airlock and were instructed on the proper locking of the hatch.
i The technician involved was counselled on the event and the need for increased attention to detail. 3 In addition, a sign with instructions for proper operation of the personnel hatch locking mechanism will be located at the site of the controls.
Plant Conditions At the time of this event, the plant was in MODE 1, Power Operation, at approximately 9 percent power, with Reactor Coolant System (AB) temperature at 562*F and-pressure at 2235 psig.
I This was the first event of this type at Seabrook Station.
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e U S GPO1986-0 624 636/466 4I