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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045G7421993-06-30030 June 1993 Special Rept:On 930526,Channel 9 (SG A,Channel 2) & Channel 11 (SG C Channel 2) Declared Inoperable When Channels Failed Acceptance Criteria for Background Noise.Work Request Written to Repair Channels During Future Outage ML20044C9631993-05-10010 May 1993 Special Rept:On 930408,vibration & Loose Parts Monitoring Sys Channels 3 & 9 Declared Inoperable While Exhibiting Background Noise Lower than Previous Measurements.Work Requests Written to Repair Channel ML20044C1391993-03-0808 March 1993 Special Rept:On 930203,DG 2B Invalid Failures Occurred Due to Failure of Pneumatic Vibration Switch on Engine.Entire Pneumatic non-emergency Trip Sys in Process of Being Replaced W/Electrical Sys Per Nuclear Station Mod CN-20528 ML20044B8301993-03-0202 March 1993 Special Rept:On 930131,discovered Invalid Failure of DG Due to High Crankcase Pressure Trip.Caused by Failure of Calcon Sensor.Failed Sensor Will Be Replaced During Refueling Outage ML20024H2351991-05-21021 May 1991 Special Rept:On 910422,diesel Generator 2A Failed to Reach Required 441 RPM within 11 Seconds Due to Mispositioned Fuel Oil Strainer.Operators to Be Trained on Incident & Strainers to Be Inspected More Frequently ML20029A3301991-02-12012 February 1991 Special Rept:On 910102,Unit 1 Loose Parts Monitor Channel 11 Declared Inoperable Due to Excessive Noise on Channel Which Was Causing False Alarms.Work Request Written to Repair Channel During Future Outage of Sufficient Length ML20044A5521990-06-20020 June 1990 Special Rept:On 900521 & 0612,invalid Failure of Diesel Generators 2A & 2B Occurred During Monthly Operability Performance Test.First Event Caused by Operator Error.Second Event Caused by Depressing Voltage Control Pushbutton ML20043B1711990-05-17017 May 1990 Special Rept:On 900418,diesel Generator 2B Failure Occurred During Operability Test & Output Breaker Tripped on Reverse Power.Caused by Operator Error.Reverse Power Relays Checked & Found to Be Operating Correctly.Operator Counseled ML20042G8151990-05-0808 May 1990 Special Rept:On 900411,valid Failure of Diesel Generator 2B Occurred.Caused by Fuel Pump 2L Sticking.Helm Joints Will Be Inspected for Freedom of Movement & Clearance & Possibility of Using More Efficient Filters Will Be Evaluated ML20042F4841990-04-30030 April 1990 Special Rept Re Moderator Temp Coefficient More Positive than Limits in Tech Spec 3.1.1.3,Figure 3.1-0.Temp Rod Withdrawal Limits Imposed Until Cycle Burnup Greater than Four EFPD or Boron Concentration Less than 1,363 Ppmb ML19327B6361989-10-25025 October 1989 Special Rept:On 890920,Unit 2 Diesel Generator 2A Declared Inoperable Due to Train a of Nuclear Svc Water Sys Being Taken Out of Svc.Diesel Generator a Tripped.Caused by Drifting of Temp Sensor.Sensor Replaced ML19242D1991979-06-21021 June 1979 Significant Deficiency 79-1:during Installation of Equipment on Section of Main Control Board,Deficient Skip Weld of Wire Duct Detected.Investigation Revealed 60 Improper Welds.All Welds Will Be Repaired by 790629 1993-06-30
[Table view] Category:LER)
MONTHYEARML20045G7421993-06-30030 June 1993 Special Rept:On 930526,Channel 9 (SG A,Channel 2) & Channel 11 (SG C Channel 2) Declared Inoperable When Channels Failed Acceptance Criteria for Background Noise.Work Request Written to Repair Channels During Future Outage ML20044C9631993-05-10010 May 1993 Special Rept:On 930408,vibration & Loose Parts Monitoring Sys Channels 3 & 9 Declared Inoperable While Exhibiting Background Noise Lower than Previous Measurements.Work Requests Written to Repair Channel ML20044C1391993-03-0808 March 1993 Special Rept:On 930203,DG 2B Invalid Failures Occurred Due to Failure of Pneumatic Vibration Switch on Engine.Entire Pneumatic non-emergency Trip Sys in Process of Being Replaced W/Electrical Sys Per Nuclear Station Mod CN-20528 ML20044B8301993-03-0202 March 1993 Special Rept:On 930131,discovered Invalid Failure of DG Due to High Crankcase Pressure Trip.Caused by Failure of Calcon Sensor.Failed Sensor Will Be Replaced During Refueling Outage ML20024H2351991-05-21021 May 1991 Special Rept:On 910422,diesel Generator 2A Failed to Reach Required 441 RPM within 11 Seconds Due to Mispositioned Fuel Oil Strainer.Operators to Be Trained on Incident & Strainers to Be Inspected More Frequently ML20029A3301991-02-12012 February 1991 Special Rept:On 910102,Unit 1 Loose Parts Monitor Channel 11 Declared Inoperable Due to Excessive Noise on Channel Which Was Causing False Alarms.Work Request Written to Repair Channel During Future Outage of Sufficient Length ML20044A5521990-06-20020 June 1990 Special Rept:On 900521 & 0612,invalid Failure of Diesel Generators 2A & 2B Occurred During Monthly Operability Performance Test.First Event Caused by Operator Error.Second Event Caused by Depressing Voltage Control Pushbutton ML20043B1711990-05-17017 May 1990 Special Rept:On 900418,diesel Generator 2B Failure Occurred During Operability Test & Output Breaker Tripped on Reverse Power.Caused by Operator Error.Reverse Power Relays Checked & Found to Be Operating Correctly.Operator Counseled ML20042G8151990-05-0808 May 1990 Special Rept:On 900411,valid Failure of Diesel Generator 2B Occurred.Caused by Fuel Pump 2L Sticking.Helm Joints Will Be Inspected for Freedom of Movement & Clearance & Possibility of Using More Efficient Filters Will Be Evaluated ML20042F4841990-04-30030 April 1990 Special Rept Re Moderator Temp Coefficient More Positive than Limits in Tech Spec 3.1.1.3,Figure 3.1-0.Temp Rod Withdrawal Limits Imposed Until Cycle Burnup Greater than Four EFPD or Boron Concentration Less than 1,363 Ppmb ML19327B6361989-10-25025 October 1989 Special Rept:On 890920,Unit 2 Diesel Generator 2A Declared Inoperable Due to Train a of Nuclear Svc Water Sys Being Taken Out of Svc.Diesel Generator a Tripped.Caused by Drifting of Temp Sensor.Sensor Replaced ML19242D1991979-06-21021 June 1979 Significant Deficiency 79-1:during Installation of Equipment on Section of Main Control Board,Deficient Skip Weld of Wire Duct Detected.Investigation Revealed 60 Improper Welds.All Welds Will Be Repaired by 790629 1993-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal 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 ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9561999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20203A2581999-02-0505 February 1999 Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE ML20204C9161999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Catawba Nuclear Station,Units 1 & 2 ML20199K8711999-01-13013 January 1999 Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9 ML20199E3071998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Catawba Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20205E9441998-12-31031 December 1998 1998 10CFR50.59 Rept for Catawba Nuclear Station,Units 1 & 2, Containing Brief Description of Changes,Tests & Experiments,Including Summary of Ses.With ML20206P2081998-12-31031 December 1998 Special Rept:On 981218,inoperability of Meteorological Monitoring Instrumentation Channels,Was Observed.Caused by Data Logger Overloading Circuit.Replaced & Repaired Temp Signal Processor ML20203A4101998-12-22022 December 1998 Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr ML20203A4041998-12-22022 December 1998 Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr ML20198B1341998-12-14014 December 1998 Revised Special Rept:On 980505,discovered That Certain Fire Barriers Appeared to Be Degraded.Caused by Removal of Firestop Damming Boards.Hourly Fire Watches Established in Affected Areas ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20199E3221998-11-30030 November 1998 Revised MOR for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20198E3151998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20196D4041998-11-19019 November 1998 Rev 1 to Special Rept:On 980618,determined That Method Used to Calibrate Wind Speed Instrumentation Loops of Meteorological Monitoring Instrumentation Sys Does Not Meet TS Definition for Channel Calibration.Procedure Revised ML20195E5521998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20198E3261998-10-31031 October 1998 Revised Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20154M7661998-10-12012 October 1998 LER 98-S01-00:on 980913,terminated Vendor Employee Entered Protected Area.Caused by Computer Interface Malfunction. Security Retained Vendor Employee Badge to Prevent Further Access & Computer Malfunction Was Repaired.With 1999-09-07
[Table view] |
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> Duke Ibutt Company . - (803) 831 3 000
- . ~ ':Catwrt>a Nuclear Station .
PO Bas 256; Clawr, S C 29710 :
^ DUKEPOWER May 8, 1990-Document. Control' Desk U S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Catawba Nuclear Station Docket'No. 50-414 Special. Report - Unit 2.
PIR-2-C90-0130;rIIR-C90-039 Gentlemen:
pursuant.to' Technical Specifications 6.9.2 and 4.8.1.1.3 please find attached a. 1 Special Report'concerning-Unit 2' Diesel Generator 2B Valid Failure on April 11,l .]
1990. j l
Very truly yours, _
' I Tony B. Owen 6'on}7n A Station Manager keb\ REPORT.SP-xc: Mr. S. D. Ebneter 'American Nuclear Insurers Regional Administrator, Region II :c/o Dottie Sherman, ANI Library.
- p. U. S. Nuclear Regulator Commission The Exchange,: Suite.245.
101 Marietta Street, NW, Suite 2900. '270 Farmington Avenue- -;
Atlanta, GA 30323 lFarmington,. CT :.06032' -d
'I i
M & M Nuclear Consultants Mr. K. Jabbour-1221 Avenues of-the Americas- -U..S. Nuclear' Regulatory Commission New York,-NY 10020' Office of. Nuclear Reactor Regulation Washington,: D. C.
- 20555--
INPO Records Centor~ r Suite 1500 . .
Mr. W. T. Orders q 1100LCircle 75 Parkway NRC Resident Inspector Atlanta, GA 30339 Catawba Nuclear Station-l i
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'SPECIAL REPORT CATAWBA NUCLEAR STATION.
DIESEL GENERATOR 2B VALID FAILURE DURING-MONTHLY OPERABILITY TESTING OF ENGINE PROBLEM INVESTIGATION REPORT SERIAL No. 2-C90-0130 INCIDENT INVESTIGATION REPORT C90-039-2 A valid failure (start # 573) of Diesel Generator (D/G)128 occurred'on-April 11,.1990 at'0159 hours0.00184 days <br />0.0442 hours <br />2.628968e-4 weeks <br />6.04995e-5 months <br />. The failure occurred in the start attempt for the normal. monthly. operability performance test' , _ .
(PT/2/A/4350/02B).-D/G 2B was on-a monthly operability. test schedule.
at the time of this valid failure. There has been 1 valid failure in-the past 20 valid starts and 3 valid failures in the past'100 valid starts for D/G 2B.. l Following the initial 1 failure, Instrument, Electrical, and Mechanical 4 craft along with Engineering personnel looked to determine'theicause ]
of.the D/G not starting. Thoro-were no obvious' problems.' indicated or observed that1would'have prevented a. successful start' After review of-the findings and further' discussion with1the operators, the decision to restart the D/G to troubleshoot was made. Personnel'were placed at: .
strategic locations to observe panel,. controls, and engine functions.- 1 The D/G was auto started..The D/G started. It started in-the normal time of 6.2 seconds. No abnormal' indications were seen or reported ~ i D
during the start and run. In the same manner, observed start #2 was
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conducted'as a key start, with the same satisfactory ~results.
After the two successful normal' starts, the following were inspected;
-Fuel filters Fuel strainers Fuel rack _ linkages from governor to the fuel pungs for alignment j All fuel rack linkages for free movement j s
2L fuel pump was found sticking. The heim joint was removedLand the l injection pump was verified to have smooth and non-sticking movement.
l The.'2L heim joint was original. equipment. It had been in servicef some i ten years and had seen more than 670 hours0.00775 days <br />0.186 hours <br />0.00111 weeks <br />2.54935e-4 months <br /> of service. A new heim . )
joint, from spares, was. adjusted to the. replaced joint length and 1 installed. The pump and'new heim joint. assembly was-then rechbcked to verify movement to be smooth and non-sticking.
1 The force required to move the' complete fuel. rack:was checked and,was d found to be consistent with previous-tests of thisland the other unit :{
2 engine. Then as an~added measure, the fuel rail-bearings were. . l lubricated even though they were scheduled for the-following month.
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.J After completing the above maintenance activities, personnel were strategically placed and the D/G started uneventfully. Following, the operability test wasTsatisfactorily performed and the D/G declared operable.
1 Cencurrently with the above inspection activities, MES contacted WW j Gallman, General Office, to inform and request assistance in -4 researching for other failures-involving sticking fuel racks d attributable to heim joints. Conversations-_with a. Senior. Design .
I Engineer of Energy Services Group, Cooper-Industries informs us that )
no failures have been reported concerning binding heim joints as the-
.l source of failure. This was borne out in conversations with two -l neighboring utilities, in-that;they had not, nor had they heard of a similar failure mechanism. !
Physically, a bound heim joint will prevent'the fuel racks;from. !
opening, effecting the start, however it will not prevent the D/G'from "
i shutting down. All heim joints are checked for free movement each outage. All joints were satisfactory at the last inspection. i Detailed inspection of the bound ball and retainer showed that the ball retainer had a pinch mark. The pinch mark was approximately-one quarter inch long and caused a-slight protrusion of metal, about an eighth inch long by one sixty-fourth inch wide...The. pinched area
]j probably caused some slight closure of the normal ball to housing l clearance at the pinch site. The pinch by itself was not aLproblem.
j The failure was caused by a particle (or particles) of grit that had gotten into the joint and in time worked around and collected at the l reduced clearance area to ultimately cause binding and prevent the. :j fuel racks from opening.
l 4
To verify that no-other problem had caused the failure to-start, the I diesel generator was allowed .to sit for_ a week, then with personnel l strategically placed, satisfactority tested again.
This valid failure is considered an isolated incident--in that; ]
- No other failures were caused by this' mechanism-l
- All information'and evidence evalua'ted indicates less.than .
sterile housekeeping conditions coupled with an insignificantly (by itself) damaged heim joint housing and-time to concentrate 3 the dust caused the' failure of 2B diesel generator to~ start.
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.Near future activities to. prevent this condition from again causing a failure are: q
- 1. In the upcoming outage, 2EOC3, tho'heim joints will receive 4 an inspection for freedom of movement and clearance. ;
- 2. The ventilation system will be evaluated to determine if :
more efficient filters can be used to reduce dust introduction'into the diesel generator rooms and not j adversely impact current ventilation design considerations.
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Finally,~although-existingidocuments used to: classify Diesel ~ Generator testing
- Adentify.this as a valid 1 failure,-new draft: guidance indicates thatteventsiof 9- s *
> this sort in .theLfuture.may: not classify this ~ as a f valid failure. As:this 4
. guidance ~ is formalized ' Duke may ask that It be reclassified :as 'an" invalid :
~
failure' consistent with'the guidelines-and technical bases of:
1.'- NSAC-198'(The Reliabilit'y of, Emergency Diesel Generators!at;U.S.
-Nuclear' Power plants); .
- 2. INPO-(Institute of-Nuclear power ~ Operations),'and _
- 3. .NUMARC (Nuclear. Management.and Resources Council), and specifically,' i
- 4. .NUMARC 87-00-(Guidelines and. Technical Bases.for NUMARC Initiatives' AddressingLStation Blackoutfat Light Water Reactors) Revision 1, ,j Dated April-6,'1990, AppendixL-D',Eand page 4; EXCEPTIONS;J i
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" Unsuccessful attempts'to start or load-run should~not 7
be counted as .
valid demands-ornfailures when they can be-definitelyTattributedito 4
, .any.of the following..
-l "o. component malfunctions'or operating errors.that,did.not^ h' prevent the emergency generator frem being' restarted and brought to load :within a few minutes (i.e. , without .
J
, -corrective maintenance or significant problem' diagnosis)"1
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