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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046B4841993-07-30030 July 1993 LER 93-006-00:on 930703,auxiliary Feedwater Signal Inadvertently Actuated Due to Personnel Error.Equipment Reset to Normal Lineup & Fuses Removed for Reinstallation Prior to Reactor startup.W/930730 Ltr ML20045H7611993-07-16016 July 1993 LER 93-007-00:on 930626,CR Alarm Received,Indicating Excessive Temp on Reactor Coolant Pump Motor Stator 1-04 & Manual Trip Initiated.Caused by RTD Failure.Rtd Terminations Disconnected & AOP revised.W/930716 Ltr ML20045A9911993-06-11011 June 1993 LER 93-004-00:on 930514,failure to Satisfy TS Surveillance for Verification of Valve Position Due to Valve Discrepancies Discovered During DBD Review.Valve Cap & Clearance installed.W/930611 Ltr ML20045A4681993-06-0303 June 1993 LER 93-003-00:on 930504,manual Reactor Trip Occurred Following Inadvertent Closure of Fwiv.Caused by Instrumentation Channel Error.Maint Performed on Affected Instrumentation channels.W/930603 Ltr ML20044G4071993-05-26026 May 1993 LER 93-006-00:on 930426,failure to Satisfy TS Surveillance Requirement for Primary Plant ESF Exhaust Filtration Unit Noted.Caused by Poor Labeling,Specification of Wrong Procedure & Discrepancy in Parts list.W/930526 Ltr ML20024H1581991-05-21021 May 1991 LER 91-016-00:on 910418,failure of Check Valve to Prevent Backflow Discovered.Caused by Mfg Error in Machining Process of Valve Body Casting.Valves Reassembled & Scheduled to Receive testing.W/910521 Ltr ML20024G7211991-04-25025 April 1991 LER 91-012-00:on 910326,potential Gas Binding of Centrifugal Charging Pumps Due to Voids in Boric Acid Gravity Feed Line Identified.Caused by Hydrogen Coming Out of Solution in Lower Pressure Ccp Suction header.W/910425 Ltr ML20024G6801991-04-22022 April 1991 LER 91-010-00:on 910322,unit 1 Operated Outside Tech Spec Due to Auxiliary Feedwater Sys Test Line Isolation Valve Not Closed.Root Cause Not Determined.Providing Addl Guidance to Operators & Operators Monitoring valves.W/910422 Ltr ML20029B6421991-03-12012 March 1991 LER 91-004-00:on 910210,potential Transformer Drawer Opened at Bottom of Switchgear Bus 1A3 Auxiliary Cubicle,Causing Load Shed Signal & Reactor Trip.Caused by Personnel Error. Labels Attached to Switchgear bus.W/910312 Ltr ML20028G9551990-09-27027 September 1990 LER 90-026-00:on 900828,surveillance Missed Due to Inadequate Procedural Requirements.Caused by Inadequate Manual Surveillance Scheduling Methods.Station Procedures revised.W/900927 Ltr ML20044A1351990-06-26026 June 1990 LER 90-017-00:on 900527,main Feedwater Flow Control Valve Failed Closed,Resulting in Reduced Feedwater Flow & Decreasing Steam Generator Water Level.Caused by Failure of Solenoid Valve Coil.Solenoid Coil replaced.W/900626 Ltr ML20044A3281990-06-22022 June 1990 LER 90-016-00:on 900521,engineering Determined That Three Atmospheric Relief Valves Declared Inoperable Resulting in Entry Into Tech Spec Limiting Condition for Operation 3.0.3. Pneumatic Controls Drifted Out of calibr.W/900622 Ltr ML20043H1971990-06-19019 June 1990 LER 90-015-00:on 900520,chemistry Sample Special Condition Surveillance Missed.Caused by Procedural Error.Procedures Revised to Provide Appropriate Cautions Re Required Sample. W/900619 Ltr ML20043G1121990-06-13013 June 1990 LER 90-014-00:on 900514,containment Penetration Improperly Isolated While Containment Isolation Valve Made Inoperable for Repairs.Caused by Inadequate Review of Work Order. Supervisor Counseled & Shift Order issued.W/900613 Ltr ML20043F1571990-06-0808 June 1990 LER 90-013-00:on 900509,while Installing Jumpers Across Feedwater Pump Speed Controllers,Pump Coastdown Occurred, Resulting in Loss of Feedwater Flow & Reactor Trip.Caused by Inadequate Procedure Review.Review performed.W/900608 Ltr ML20043E4511990-06-0707 June 1990 LER 90-012-00:on 900508,control Room Personnel Failed to Satisfy Time Limit for Completion of Action Required by Tech Specs Re Plant Radiation Monitoring.Caused by Personnel Error.Individual Counseled & Procedure revised.W/900607 Ltr ML20043F4941990-06-0404 June 1990 LER 90-011-00:on 900504,Pressure Instrument Root Isolation Valve 1SI-8961 Open When Procedure Indicated Valve Should Be Locked Closed.Caused by Lack of Clear Instructions Re Definition of Physical Work. Valve locked.W/900604 Ltr ML20043C0201990-05-29029 May 1990 LER 90-010-00:on 900428 & 29,2-h Surveillance Interval, Including 25% Extension Allowed by Tech Spec 4.0.2,exceeded. Caused by Personnel Error.Procedure Enhancements Initiated & Personnel Involved counseled.W/900529 Ltr ML20043A6691990-05-18018 May 1990 LER 90-009-00:on 900421,reactor Trip Occurred Due to Accidental Bumping of Source Range Reactor Trip Reset/Block Previously Bypassed for Power Operation.Order Issued Suspending Cleaning of Control boards.W/900518 Ltr ML20043A6131990-05-16016 May 1990 LER 90-008-00:on 900416,Train a Diesel Generator Rendered Inoperable Due to Failure to Complete post-work Operability Testing on Starting Air Receiver Check Valve 01. Caused by Inadequate Review.Procedure revised.W/900516 Ltr ML20043A6111990-05-16016 May 1990 LER 90-007-00:on 900416,ESF Actuation Signal Occurred, Resulting in Train a of Control Room Air Conditioning Sys Shifting to Emergency Recirculation Mode.Caused by Personnel Error.Handswitch Added to Radiation monitor.W/900516 Ltr ML20043A4201990-05-14014 May 1990 LER 90-006-00:on 900412,P-6 Permissive Signal Received & Source Range Flux Doubling (Srfd) Actuation Occurred.Caused by Inadvertent Reset of Srfd Block.Integrated Plant Operations Procedures changed.W/900514 Ltr ML20012B6491990-03-0909 March 1990 LER 90-001-00:on 900209,reactor Protection Sys Actuation Occurred Due to Spike on Range Channel.Appropriate Source Range Procedures Revised to Require Insertion of Flux Doubling Signal Block Prior to withdrawal.W/900309 Ltr 1993-07-30
[Table view] Category:RO)
MONTHYEARML20046B4841993-07-30030 July 1993 LER 93-006-00:on 930703,auxiliary Feedwater Signal Inadvertently Actuated Due to Personnel Error.Equipment Reset to Normal Lineup & Fuses Removed for Reinstallation Prior to Reactor startup.W/930730 Ltr ML20045H7611993-07-16016 July 1993 LER 93-007-00:on 930626,CR Alarm Received,Indicating Excessive Temp on Reactor Coolant Pump Motor Stator 1-04 & Manual Trip Initiated.Caused by RTD Failure.Rtd Terminations Disconnected & AOP revised.W/930716 Ltr ML20045A9911993-06-11011 June 1993 LER 93-004-00:on 930514,failure to Satisfy TS Surveillance for Verification of Valve Position Due to Valve Discrepancies Discovered During DBD Review.Valve Cap & Clearance installed.W/930611 Ltr ML20045A4681993-06-0303 June 1993 LER 93-003-00:on 930504,manual Reactor Trip Occurred Following Inadvertent Closure of Fwiv.Caused by Instrumentation Channel Error.Maint Performed on Affected Instrumentation channels.W/930603 Ltr ML20044G4071993-05-26026 May 1993 LER 93-006-00:on 930426,failure to Satisfy TS Surveillance Requirement for Primary Plant ESF Exhaust Filtration Unit Noted.Caused by Poor Labeling,Specification of Wrong Procedure & Discrepancy in Parts list.W/930526 Ltr ML20024H1581991-05-21021 May 1991 LER 91-016-00:on 910418,failure of Check Valve to Prevent Backflow Discovered.Caused by Mfg Error in Machining Process of Valve Body Casting.Valves Reassembled & Scheduled to Receive testing.W/910521 Ltr ML20024G7211991-04-25025 April 1991 LER 91-012-00:on 910326,potential Gas Binding of Centrifugal Charging Pumps Due to Voids in Boric Acid Gravity Feed Line Identified.Caused by Hydrogen Coming Out of Solution in Lower Pressure Ccp Suction header.W/910425 Ltr ML20024G6801991-04-22022 April 1991 LER 91-010-00:on 910322,unit 1 Operated Outside Tech Spec Due to Auxiliary Feedwater Sys Test Line Isolation Valve Not Closed.Root Cause Not Determined.Providing Addl Guidance to Operators & Operators Monitoring valves.W/910422 Ltr ML20029B6421991-03-12012 March 1991 LER 91-004-00:on 910210,potential Transformer Drawer Opened at Bottom of Switchgear Bus 1A3 Auxiliary Cubicle,Causing Load Shed Signal & Reactor Trip.Caused by Personnel Error. Labels Attached to Switchgear bus.W/910312 Ltr ML20028G9551990-09-27027 September 1990 LER 90-026-00:on 900828,surveillance Missed Due to Inadequate Procedural Requirements.Caused by Inadequate Manual Surveillance Scheduling Methods.Station Procedures revised.W/900927 Ltr ML20044A1351990-06-26026 June 1990 LER 90-017-00:on 900527,main Feedwater Flow Control Valve Failed Closed,Resulting in Reduced Feedwater Flow & Decreasing Steam Generator Water Level.Caused by Failure of Solenoid Valve Coil.Solenoid Coil replaced.W/900626 Ltr ML20044A3281990-06-22022 June 1990 LER 90-016-00:on 900521,engineering Determined That Three Atmospheric Relief Valves Declared Inoperable Resulting in Entry Into Tech Spec Limiting Condition for Operation 3.0.3. Pneumatic Controls Drifted Out of calibr.W/900622 Ltr ML20043H1971990-06-19019 June 1990 LER 90-015-00:on 900520,chemistry Sample Special Condition Surveillance Missed.Caused by Procedural Error.Procedures Revised to Provide Appropriate Cautions Re Required Sample. W/900619 Ltr ML20043G1121990-06-13013 June 1990 LER 90-014-00:on 900514,containment Penetration Improperly Isolated While Containment Isolation Valve Made Inoperable for Repairs.Caused by Inadequate Review of Work Order. Supervisor Counseled & Shift Order issued.W/900613 Ltr ML20043F1571990-06-0808 June 1990 LER 90-013-00:on 900509,while Installing Jumpers Across Feedwater Pump Speed Controllers,Pump Coastdown Occurred, Resulting in Loss of Feedwater Flow & Reactor Trip.Caused by Inadequate Procedure Review.Review performed.W/900608 Ltr ML20043E4511990-06-0707 June 1990 LER 90-012-00:on 900508,control Room Personnel Failed to Satisfy Time Limit for Completion of Action Required by Tech Specs Re Plant Radiation Monitoring.Caused by Personnel Error.Individual Counseled & Procedure revised.W/900607 Ltr ML20043F4941990-06-0404 June 1990 LER 90-011-00:on 900504,Pressure Instrument Root Isolation Valve 1SI-8961 Open When Procedure Indicated Valve Should Be Locked Closed.Caused by Lack of Clear Instructions Re Definition of Physical Work. Valve locked.W/900604 Ltr ML20043C0201990-05-29029 May 1990 LER 90-010-00:on 900428 & 29,2-h Surveillance Interval, Including 25% Extension Allowed by Tech Spec 4.0.2,exceeded. Caused by Personnel Error.Procedure Enhancements Initiated & Personnel Involved counseled.W/900529 Ltr ML20043A6691990-05-18018 May 1990 LER 90-009-00:on 900421,reactor Trip Occurred Due to Accidental Bumping of Source Range Reactor Trip Reset/Block Previously Bypassed for Power Operation.Order Issued Suspending Cleaning of Control boards.W/900518 Ltr ML20043A6131990-05-16016 May 1990 LER 90-008-00:on 900416,Train a Diesel Generator Rendered Inoperable Due to Failure to Complete post-work Operability Testing on Starting Air Receiver Check Valve 01. Caused by Inadequate Review.Procedure revised.W/900516 Ltr ML20043A6111990-05-16016 May 1990 LER 90-007-00:on 900416,ESF Actuation Signal Occurred, Resulting in Train a of Control Room Air Conditioning Sys Shifting to Emergency Recirculation Mode.Caused by Personnel Error.Handswitch Added to Radiation monitor.W/900516 Ltr ML20043A4201990-05-14014 May 1990 LER 90-006-00:on 900412,P-6 Permissive Signal Received & Source Range Flux Doubling (Srfd) Actuation Occurred.Caused by Inadvertent Reset of Srfd Block.Integrated Plant Operations Procedures changed.W/900514 Ltr ML20012B6491990-03-0909 March 1990 LER 90-001-00:on 900209,reactor Protection Sys Actuation Occurred Due to Spike on Range Channel.Appropriate Source Range Procedures Revised to Require Insertion of Flux Doubling Signal Block Prior to withdrawal.W/900309 Ltr 1993-07-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 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) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With 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 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 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 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 ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively 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 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 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 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, 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 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
[Table view] |
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Z C Log i TXX-91143 71/ELEC7RlC File # 10200 Ref. # 50.73
% !!!iarn J. Cahlit. Jr. 50.73(a)(2)(i)
I:sn utnt h e htmknl April 22, 1991 U. S. Nuclear Regulatory Comission Attnt Document Control Desk Washington, D. C. 20555 SUBJECTS CONANCHEPEAKSTEAMELECTRICSTATION(CPSES)
DOCKET NO. 50-445 CONDITION PROHIBITED BY THE PLANT'S TECHNICAL SPECIFICATIONS LICENSEE EVENT REPORT 91-010 00 Gentlemen:
Enclosed is Licensee Event Report 91-010-00 for Comanche Peak Steam Electric Station Unit 1. " Unit 1 Operated Outside Technical Specifications Due to Auxiliary Feedwater System Test Line Isolation Valve not Fully closed."
Sincerely, W. J. Cahill Jr.
Bys ..f<l6 /A// !
W'. G. 6~uldemond_ /
Manager, Site Licensing JAA/bm c - Mr. R. D. Martin, Region IV Resident Inspcctors CPSES (3) 400 North Olise Street Lil 81 Dallas,1exai 75201 9104240049 910422 PDR ADOCK 05000445 / l 6 PDR
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On March 22,1991, an Auxiliary Operator discovered the Train B Motor Driven Auxiliary
' Feedwater Pump Recirculation Test Line Isolation Valve one_ quarter turn open. _The valve was last operated on March 13,1991, during an Auxiliary Feedwater operability test With the valve one quarter turn open, auxiliary feedwater flow is 8 gallons per minute less than assumed in the safety analysis; therefore, Train B Auxiliary Feedwater was inoperable from March 13 until the valve was closed on March 22. This exceeded the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Technical Specification Action Statement for one auxiliary feedwater pump or associated flow path inoperable.
-The root cause for why the valve was not fully closed could not be determined. Possibilities include the Operator falling to fully close the valve when restoring from the test, the valve being disturbed after it was closed on March 13, or vibration causing the valve to slightly back off its seat. Corrective actions include providing additional guidance to Operators on ensuring these type of valves are closed, having Operators monitor these type of valves during the next pump runs, and having Engineering take vibration readings on the valve.
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. Encio.sure to TXX 91143 hua ,ong yd u 6. evdat An htuJL A10HY umWibbevN Appio g a3 p 181%IAft D DJ4DE N PE R RE SHONSE 10 COMPLY WITH TH15 PF04:dATION LICENSEE EVENT REPORT (LER) MC"U,'g *,'; yy *,"* ', g,'"3 gg',33, TEXT CONTINUATlON Sg*gf 73,"o ,"f*g,","Z'gflg,"l,'Oc*'g%
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- 1. DESCRIPTION OF THE REPORTABLE EVENT A. REPORTABLE EVENT CLASSIFICATION Any operation or condition prohibited by the plant's Technical Specifications.
B. PLANT OPERATING CONDITIONS PRIOR TO THE EVENT On March 22,1991, Comanche Peak Steam Electric Station Unit 1 was in Mode 5, Cold Shutdown, with reactor coolant temperature at 135 degrees Farenheit and pressure at 325 pounds per square inch gage. Steam Generator 04 (Ells:(SG)(SB))
was being filled with the Train B Motor Driven Auxiliary Feedwater Pump (MDAFW)
(Ells:(P)(BA)).
C. STATUS OF STRUCTURES, SYSTEMS, OR COMPONENTS THAT WERE INOPERABLE AT THE START OF THE EVENT AND THAT CONTRIBUTED TO THE EVENT There were no inoperable structures, systems or components that contributed to the event.
D. NARRATIVE
SUMMARY
OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES At 0145, March 22,1991, while filling Steam Generator 04, the Auxiliary Operator (AO)(utility, non licensed) heard an unusual noise in the vicinity of the Train 8 MDAFW Pump. Investigation determined that 1 AF-0055, Train B MDAFW Pump Recirculation Test Line Isolation Valve (Ells:(ISV)(BA)), was one quarter turn open.
The valve was closed and the noise stopped.
1 AF 0055 was last opened during an Auxiliary Feedwater operability test on March 13,1991. The valve was opened, closed and independently verified closed at the conclusion of the test. There have been no work clearances or tests performed
. between March 13,1991, and March 22,1991, that would require 1 AF 0055 to be operated.
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35 81CE OF WANAQtWLNT AND DJDGEt WARHINoinst to 30!Ko eecsay Name 0 Jun.i Nene (b L4 R N n Fap M COMANCHE PEAK - UNIT 1 0l51010l0l414l5 9l1
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The valvo is operated by a floor stand with a 24 inch diameter handwheel. There are three drive shafts connecting four gear boxes from the hand wheel to the valve. The handwheel is required to be tumed counterclockwise to close the valve and this is clearly labeled. Also, due to the diameter of the handwheel and the gear reduction, the use of a leverage device is not permitted. The valve was opened and closed for this evaluation by the AO (utility, non licensed) that operated the valve during the March 13 test. The valve stroked without the need of a second person or leverage device. The closing feel was
- spongy" due to the extensive linkage, but there did not appear to be any binding or extraordinary effort required to close the valve.
An engineering evaluation determined that with 1 AF 0055 one quarter turn open, flow from Train B MDAFW Pump would be 8 gallons per minute less than assumed in the safety analysis; therefore, Train B Auxiliary Feedwater was inoperable from March 13 to March 22, when 1 AF 0055 was closed. CPSES Unit 1 Technical Specifications require three independent steam generator auxiliary feedwater pumps and associated flow paths be operable during modes 1,2, or 3. Unit 1 was in modes 1,2, or 3 from March 13 to March 20; therefore, the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Action Statement for one auxillary feedwater pump or associated flow path inoperable was exceeded.
E. THE METHOD OF DISCOVERY OF EACH COMPONENT OR SYSTEM FAILURE OR PROCEDURAL ERROR The AO heard an unusual noise in the vicinity of the Train B MDAFW Pump.
Investigation determined that 1 AF 0055 was one quarter turn open.
II. COMPONENT OR SYSTEM FAILURES A. . FAILURE MODE, MECHANISM, AND EFFECT OF EACH FAILED COMPONENT No failed components contributed to this event.
B. CAUSE OF EACH COMPONENT OR SYSTEM FAILURE No failed components contributed to this event.
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D. FAILED COMPONENT INFORMATION No failed components contributed to this event.
111. ANALYSIS OF THE EVENT A. SAFETY SYSTEM RESPONSES THAT OCCURRED There were no safety system actuations associated with this event.
B. DURATION OF SAFETY SYSTEM TR AIN INOPERADILITY Train B MDAFW Pump was inoperable from March 13 through March 22.
C. SAFETY CONSEQUENCES AND IMPLICATIONS OF THE EVENT The Auxiliary Feedwater System (Ells:(BA))is designed to provide a supply of high-pressure feedwater to the secondary side of the steam generators for reactor coolant heat removal following a loss of normal foodwater. After a loss of the main feedwater system (Ells:(SJ)), either the two motor driven auxiliary feedwater pumps together, the turbine driven pump alone, or any combination are capable of providing sufficient flow to the steam generators to allow the plant to be taken to a safe shutdown condition.
The Train A MDAFW Pump and the Turbine Driven Auxiliary Foodwater Pump (TDAFW) (Ells:(P)(BA)) were operable during the time that the Train B MDAFW Pump was inoperable; therefore, the Auxiliary Feedwater System could perform its intended safety function. At no time did a condition exist that required the operation of the Auxiliary Feedwater System to mitigate the event. At no time during this period did an actual condition exist that threatened the health or safety of the public.
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IV. CAUSE OF THE EVENT 1
( ROOT CAUSE 1
l The investigation could not determine how the valve became one quarter turn open; however, three possibilities are:
- 1. The AO and independent verifier failed to fully close the valve when restoring from the test on March 13,1991.
- 2. The valve was disturbed after it was closed on March 13,1991.
- 3. Vibration caused the valve to slightly back off its seat.
V. CORRECTIVE ACTIONS
- CORRECTIVE ACTIONS TO PREVENT RECURRENCE
. ROOT CAUSE (POTENTIAL)
- 1. The AO and the independent verifier (utility, non licensed) failed to fully close the valve when restoring from the test on March 13,1991.
CORRECTIVE ACTION A Lesson's Learned memo has been issued to Shift Operations personnel describing the problem as well as additionalinstruction to ensure that the auxiliary feedwater pump recirculation test line isolation valves are closed.
- 2. The valve was disturbed after it was closed on March 13,1991.
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- 3. Vibration caused the valve to back slightly off its seat.
CORRECTIVE ACTION Auxiliary Operators will check 1 AF 0055 the next two times the Train B MDAFW Pump is run with 1 AF 0055 closed to determine the possibility of a vibration problem. This check will also include 1 AF 0042, Train A MDAFW Pump Recirculation Test Line Isolation Valve and 1 AF 0069, TDAFW Pump Recirculation Test Line isolation Valve.
A Lesson's Learned memo has been issued to alert Shift Operations personnel of the possibility of auxiliary feedwater pump recirculation test line isolation valves vibrating open. It also alerts Operators of ways the test valves can be monitored to be closed and to be aware of the sounds in the auxiliary feedwater pump rooms.
Engineering will take vibration readings on 1 AF 0055 during the next Train B MDAFW Pump run test. If vibration is determined to cause valve movement, then additional corrective actions will be taken to secure the valves.
VI. PREVIOUS SIMILAR EVENTS There have been no previous similar events reported pursuant to 10CFR50.73.
Vll. ADDITIONAL INFORMATION The times listed in the report are approximate and Central Standard Time.
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