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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20199J8551997-11-24024 November 1997 Special Rept 2-SR-97-001:on 971025,RCS Pressure Transient Resulted in Automatic Actuation of Pressurizer Porv.Caused by Operator Misconception Over Actual Arming Setpoint of LTOP Sys.Alarm Procedures Will Be Revised ML20083R7491995-05-22022 May 1995 Special Rept 1-SR-95-002:on 950505,lightning Strike Damaged Meteorological Instrumentation at Primary & Backup Towers ML20078A3221995-01-12012 January 1995 Special Rept:On 941222,unit 1 Train a EDG Tripped.Caused by Internal Oil Leak of Trip Device Bypassed in Emergency Operating Mode.Trip Device Replaced W/New,Calibr Pressure Switch ML20058C0011993-11-18018 November 1993 Ro:On 931117,unusual Event Declared Due to Loss of All Primary & Backup Meteorological Sys Instruments.Caused by Lightning Strike Damaging back-up Tower Instruments.Local Natl Weather Svc Contacted ML20045G6671993-07-0202 July 1993 RO:930702,unusual Event Declared When RCS Calculated Unidentified Leak Rate Exceeded 1 Gpm.Caused by Leakage from Reactor Coolant Pump Seal Injection Filter Drain Valve. Valves Corrected to Eliminate Leak ML20101L2991992-06-29029 June 1992 Special Rept 1-SR-92-001-00:on 920528,engine Trip Occurred Due to Apparent High Vibration at Engine Rear Vibration Sensor.Caused by Low Lube Oil Pressure.Sensor & Related Components Replaced ML20101D2201992-06-0404 June 1992 Ro:On 920603,control Room Alarms Annunicated Loss of One of Two Compressors in Train a of Control Room HVAC Sys.Caused by Low Oil Pressure in Compressor.Both Trains of Control Room HVAC Sys Restored to Svc & Declared Operable ML20092F0281992-02-13013 February 1992 Special Rept 1-SR-90-002-01:on 900221,RCS Transient Resulted in Automatic Actuation of Porv.Caused by Insufficient Letdown Flow.Repetitive Step of Differing Plant Responses Expected Eliminated ML20062F8251990-11-20020 November 1990 Ro:On 901118,control Room Alarms Annunciated Failure of Inverter Associated W/One of Four 118-volt Ac Safeguards Instrument Buses.Caused by Failed Components within Scr/Diode Assembly ML20058C5131990-10-29029 October 1990 Special Rept SR-1-90-007-00:on 900726,charging Flow Diverted Through Safety Injection Line Due to Personnel Error. Operator Counseled.Procedures Reviewed for Accuracy ML20056A1691990-07-31031 July 1990 Ro:On 900730,ESFAS Occurred Which Resulted in Initiation of Safety Injection Followed by lo-lo Steam Generator Level Reactor Trip Signal.Caused by Potential Problem W/Emergency Lighting.Actions to Prevent Recurrence Will Be Determined ML20056A0821990-07-27027 July 1990 Ro:On 900726,ESF Actuation Signal Occurred Which Resulted in Initiation of Safety Injection.Cause Indeterminate.Plant Restored to Stable Condition ML20043F2961990-06-0808 June 1990 Special Rept SR-1-90-006-00:on 900509,discovered That Tech Spec Temp Limit for Main Steam Penetration Area Exceeded for Greater than 8 H.Caused by Inadequate Operating Procedure for Safeguards Bldg Ventilation Sys.Pipe Supports Insulated TXX-9014, Special Rept 1-SR-90-005-00:on 900404,positive Moderator Temp Coefficient Noted During Low Physics Testing Due to High Boron Concentration in Moderator.Rod Withdrawal Limits Imposed Per Tech Spec 3.1.1.3a,Action a.11990-04-16016 April 1990 Special Rept 1-SR-90-005-00:on 900404,positive Moderator Temp Coefficient Noted During Low Physics Testing Due to High Boron Concentration in Moderator.Rod Withdrawal Limits Imposed Per Tech Spec 3.1.1.3a,Action a.1 ML20012D9531990-03-21021 March 1990 Special Rept 1-SR-90-002:on 900221,RCS Pressure Transient Resulted in Automatic Actuation of Pressurizer Porv.Caused by Failure of Procedure to Consider Variation in Plant Response for Stated Sys.Operating Procedure Will Be Revised ML20012B8541990-03-13013 March 1990 Special Rept:On 900312,ESF Actuation Signal Occurred Which Resulted in Initiation of Train a Safety Injection & RCS Pressure Transient.Caused by Failed Blocking Diode Due to Short.Plant Restored to Stabilized Condition ML20236T9321987-10-27027 October 1987 Special Rept:On 870831,Train a Safety Injection Occurred During Performance of Bimonthly Surveillance of solid-state Protection Sys.Caused by Cognitive Personnel Error.Emergency Procedure 2BEP-0 Entered & Exited When Plant Stabilized ML19309B8571980-03-28028 March 1980 Supplemental Ro:Violation Found Re Piping Min Wall Thickness.Cause Unstated.Engineering Review in Progress. Progress Rept Will Be Submitted by 800418 1997-11-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr 05000445/LER-1999-004-01, :on 990830,some Grated Surfaces Were Noted Outside Design Basis.Caused by Use of Friction Type Grating Fasteners.Mods to Enhance Platforms Are Being Implemented. with1999-10-0606 October 1999
- on 990830,some Grated Surfaces Were Noted Outside Design Basis.Caused by Use of Friction Type Grating Fasteners.Mods to Enhance Platforms Are Being Implemented. with
ML20212L1561999-09-30030 September 1999 Safety Evaluation Supporting Amends 72 & 72 to Licenses NPF-87 & NPF-89,respectively ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 05000445/LER-1999-005, :on 990830,potential Common Cause Failure Identified in Jrak Relief Valves.Caused by Pressure Surges Sys.Pressure Surges Sys Have Been Implemented.With1999-09-29029 September 1999
- on 990830,potential Common Cause Failure Identified in Jrak Relief Valves.Caused by Pressure Surges Sys.Pressure Surges Sys Have Been Implemented.With
ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20212G8171999-09-22022 September 1999 Safety Evaluation Supporting Amends 71 & 71 to Licenses NPF-87 & NPF-89,respectively ML20212G8431999-09-22022 September 1999 Safety Evaluation Supporting Amends 70 & 70 to Licenses NPF-87 & NPF-89,respectively ML20216F9381999-09-21021 September 1999 Safety Evaluation Supporting Amends 69 & 69 to Licenses NPF-87 & NPF-89,respectively ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr ML20211K0321999-08-31031 August 1999 Safety Evaluation Supporting Amends 68 & 68 to Licenses NPF-87 & NPF-89,respectively ML20211J9521999-08-30030 August 1999 Safety Evaluation Supporting Amends 67 & 67 to Licenses NPF-87 & NPF-89,respectively ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210N1701999-08-0303 August 1999 Safety Evaluation Supporting Amends 66 & 66 to Licenses NPF-87 & NPF-89,respectively ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20196J0741999-06-28028 June 1999 Safety Evaluation Supporting Amends 65 & 65 to Licenses NPF-87 & NPF-89,respectively 05000446/LER-1999-004, :on 990522,train a EDG Start,Occurred.Caused by Lockout Relay Actuation.Developed Troubleshooting Plan to Help Identify Cause of Problem.With1999-06-18018 June 1999
- on 990522,train a EDG Start,Occurred.Caused by Lockout Relay Actuation.Developed Troubleshooting Plan to Help Identify Cause of Problem.With
05000445/LER-1999-003-01, :on 990519,discovered Battery Surveillances Were Not Performed with Proper Periodicity as Required by Ts.Caused by Misinterpretation of Sr.Resistance Readings Taken,Noed Requested & LAR Requested.With1999-06-10010 June 1999
- on 990519,discovered Battery Surveillances Were Not Performed with Proper Periodicity as Required by Ts.Caused by Misinterpretation of Sr.Resistance Readings Taken,Noed Requested & LAR Requested.With
05000445/LER-1999-002-01, :on 990518,missed TS Surveillance for SG Gross Activity Composite Sampling Was Noted.Caused by Cognizant Personnel Being Distracted from Normal Duties.Sg Sample Was Taken IAW TS Appropriate TS Requirement.With1999-06-10010 June 1999
- on 990518,missed TS Surveillance for SG Gross Activity Composite Sampling Was Noted.Caused by Cognizant Personnel Being Distracted from Normal Duties.Sg Sample Was Taken IAW TS Appropriate TS Requirement.With
05000445/LER-1999-001-01, :on 990510,discovered That Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures.Caused by Less than Adequate Procedures.Revised Circuit Testing Procedures1999-06-0808 June 1999
- on 990510,discovered That Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures.Caused by Less than Adequate Procedures.Revised Circuit Testing Procedures
ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station 05000446/LER-1999-003, :on 990421,discovered That CR HVAC Train a Was Outside TS AOT Limits Due to Blown Fuse.Caused by Incorrect Landing of Wires That Provide Relay Control Power for CR Ventilation Circuitry.Fuse Was Replaced.With1999-05-20020 May 1999
- on 990421,discovered That CR HVAC Train a Was Outside TS AOT Limits Due to Blown Fuse.Caused by Incorrect Landing of Wires That Provide Relay Control Power for CR Ventilation Circuitry.Fuse Was Replaced.With
ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected 05000445/LER-1998-007, :on 981112,RHR Sys Loop Suction Valves Were Not Disabled by Removing Thermal Overload Relays from Respective Breakers.Caused by Failure to Follow Procedures.Removed Thermal Overload Relays.With1999-04-0707 April 1999
- on 981112,RHR Sys Loop Suction Valves Were Not Disabled by Removing Thermal Overload Relays from Respective Breakers.Caused by Failure to Follow Procedures.Removed Thermal Overload Relays.With
ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20207M3611999-03-0808 March 1999 Safety Evaluation of TR ER-80P, Improving Thermal Power Accuracy & Plant Safety While Increasing Operating Power Level Using LEFM Sys. Rept Acceptable.Staff Finds FW Flow Measurement Using LEFM Can Provide Thermal Power ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 05000446/LER-1999-002, :on 990103,main Turbine Generator Control Valves Suddenly & Unexpectedly Closed While at 100 Percent Rated Power.Cause of Event Could Not Be Determined.Ehc Sys Has Been Connected to Minidas.With1999-01-20020 January 1999
- on 990103,main Turbine Generator Control Valves Suddenly & Unexpectedly Closed While at 100 Percent Rated Power.Cause of Event Could Not Be Determined.Ehc Sys Has Been Connected to Minidas.With
05000446/LER-1999-001, :on 981226,identified That TS Surveillance for Containment Integrity Verification Was Not Performed.Caused by Personnel Error.Required Surveillance Was Performed & Applicable Procedures Were Revised.With1999-01-19019 January 1999
- on 981226,identified That TS Surveillance for Containment Integrity Verification Was Not Performed.Caused by Personnel Error.Required Surveillance Was Performed & Applicable Procedures Were Revised.With
ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 1999-09-30
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Text
_g. 3 s
hmS Log # TXX-92278 File # 10013 10125 Ref. # 10CFR50.72(a)(i)
TUELECTRIC William J. Cah!!!, Jr.
Group Vke Preskkno V. S. Nuclear Regulatory Commiss_ ion Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF REPORT FOLLOWING A NOTIFICATION OF UNUSUAL EVENT (NUREG-0654)
Gentlemen:
As specified in the CPSES Emergency Plan, TV Electric hereby transmits the enclosed report which summarizes the incident which occurred on June 3, 1992.
As stated-in the corrective action, an evaluation is in process and a Licensee Event Report (LER) will be submitted in-accordance with 10CFR50.73 by July _6,'1992.
Sincerely, k'
3h, William J. Cahill, Jr.
By:
Yi Roger D. Walker Manager of Regulatory Affairs 08/ds Enclosure c - (ir. R. D. Martin, Region IV Resident Inspectors, CPSES (2)
Mr. Robert Lansford, Division of Emergency Management Mr. B.-E. Holian, NRR Mr. T. A.' Bergman, NRR 1C0Cd2
$8 9206120063 920604 i[
ADOCK 0500 5
{DR P.o. Box 1002 Glen Rose.Texa. 7&M3-1002
/,f.
Enclosuria TXX-92278' Pag'e 1 of 1' TU Electric Comanche Peak Steam Electric Station, Unit 1 Docket No. 50-445 Notification of Unusual Event As a Result of Initiating a Plant Shutdown Required by Technical Specifications Recort Requirement This report is being submitted as recommended by NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness-in Support of Nuclear. Power - Plants" and in accordance with Comanche Peak Steam Electric Station (CPSES) Emergency Plan Procedures.
The CPSES Emergency Pian procedures require that a written summary be submitted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the closecut of the Notification of Unusual Event (NOUE).
Event Description On June 3,
1992, at approximately 0123 CDT, CPSES Unit I was in Mode 1,
Power Operation,.with the reactor at approximately 100 percent of rated thermal power.
Control Room alarms annunciated the loss of one of two compressors associated ~with
, Train A of the Control Room Heating Ventilation and Air Conditioning (HVAC) System.
After unsuccessfully attempting to restart the compressor, the train was declared inoperable.
Train B.of the Control Room HVAC System had been removed from service and declared inoperable. previously for performance of a modification to reduce vibration.
The' loss of both trains of Control Room HVAC resulted in the requirement to initiate a plant shutdown in accordance with CPSES Unit 1 Technical Specification 3.0,3.
-At approxinately 0223 CDT, a plant shutdown was initiated, and at 0250 the Emergency Plan was activated with the Notification of Unusual Event.
The Nuclear Regulatory Commission and the appropriate offsite agencies were notified in accordance with the applicable regulatory and procedural requirements.
By-0823 CDT, Train A of,the Control Room HVAC System had been restored to service and--the - NOUE ? was -terminated.
Reactor power had been reduced to approximately 8 percent. = Initial review of the event indicates that all Technical Specification action requirements were satisfied, and all systems functioned as designed.
'Immediate cause The -immediate cause of the Control Room HVAC air conditivning unit trip has been attributed to compressor low oil pressure.
' Corrective Actions
~Immediate' actions were taken to troubleshoot the cause of the air conditioning unit trip and to place the plant in a condition allowed by the CPSES Unit 1 Technical Specifications.
As a result of subsequent actions, both trains of the Control Room HVAC System were restored to service and declared operable. Additional actions will be determined based on the results of the findings of the plant incident investigation of this event.
The details of the event, including root cause determination and recommendations for corrective actions, will be included in the Licensee Event - Report to be submitted to the Maclear Regulatory Commission pursuant to 10CFR50.73.
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