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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20205G4071999-03-25025 March 1999 Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325 ML20248M0501998-06-0808 June 1998 Special Rept 98-02:on 980502,Channel 3 of loose-part Detection Sys Was Declared to Be Inoperable.Caused by Failure of Component Inaccessible at Power.Addl Troubleshooting Will Be Performed ML20198S6361998-01-22022 January 1998 Ro:On 980121,determined That Plant Shutdown Would Be Required IAW TS 3.8.1.1,Action D.Caused by 'B' Train EES Charcoal Absorber Being Determined Inoperable.Requested 24 Hour Extension to Allow Restoration of EDG & ESW Train ML20137S6051997-04-10010 April 1997 Special Rept 97-01:on 970227,train a RVLIS Declared Inoperable Due to Failed Circuit Board in Transmitter. Transmitter Will Be Replaced During Next Outage W/Applicable Conditions or No Later than Spring 1998 ML20097D4121996-02-0101 February 1996 Special Rept 96-01:on 960110,invalid Start Failure of DG B Occurred Due to Air Start Distributor Rotor Misalignment. New Shaft & Rotor Installed ULNRC-03108, Special Rept 94-05:on 941111,discovered Unit Vent - High Range Noble Gas Monitor (GTRE0021B) Inoperable for Greater than Seven Days.Caused by Misunderstanding of Channel 216 Failure Characteristics.Monitor Declared Operable on 9411181994-12-0202 December 1994 Special Rept 94-05:on 941111,discovered Unit Vent - High Range Noble Gas Monitor (GTRE0021B) Inoperable for Greater than Seven Days.Caused by Misunderstanding of Channel 216 Failure Characteristics.Monitor Declared Operable on 941118 ULNRC-03066, Special Rept:On 940809,discovered Two Invalid a Failures During Troubleshooting Due to Air Start Solenoid Failures1994-09-0808 September 1994 Special Rept:On 940809,discovered Two Invalid a Failures During Troubleshooting Due to Air Start Solenoid Failures ULNRC-03060, Special Rept 94-03:on 940726,determined Inoperability of One Channel of loose-part Detection Sys.Caused by Intermittent Field Cable Short.Channel Seven on Reactor Head Assembly Remains Inoperable Pending Next Available Outage1994-09-0101 September 1994 Special Rept 94-03:on 940726,determined Inoperability of One Channel of loose-part Detection Sys.Caused by Intermittent Field Cable Short.Channel Seven on Reactor Head Assembly Remains Inoperable Pending Next Available Outage ULNRC-03057, Special Rept 94-02:on 940803,05 & 18,during Tenth Yr Inservice Surveillance Acceptance Criteria of TS 4.6.1.6.1.b.1 Not Met.Observed Tendon Conditions & Voids Do Not Indicate Significant Degradation of post-tensioning Sys1994-08-29029 August 1994 Special Rept 94-02:on 940803,05 & 18,during Tenth Yr Inservice Surveillance Acceptance Criteria of TS 4.6.1.6.1.b.1 Not Met.Observed Tendon Conditions & Voids Do Not Indicate Significant Degradation of post-tensioning Sys ML20072A9341994-08-0505 August 1994 Special Rept:On 940713,valid Failure of DG a Occurred Due to Loose Tachometer Signal Generator Found During Troubleshooting.Tachometer Secured & Verified ULNRC-02925, Special Rept 93-05:on 931020,valid Diesel Generator B Failure Occurred Due to Intermittent Speed Switch Opening Field Flashing Current Limiting Resistor.Surveillance Tests Currently Performed at Least Once Per 31 Days for DG B1993-12-20020 December 1993 Special Rept 93-05:on 931020,valid Diesel Generator B Failure Occurred Due to Intermittent Speed Switch Opening Field Flashing Current Limiting Resistor.Surveillance Tests Currently Performed at Least Once Per 31 Days for DG B ULNRC-02922, Special Rept 93-04:on 931119,channel 7 of loose-part Detection Sys Determined Inoperable for Greater than 30 Days.Charge Converter Replaced.Troubleshooting Revealed Problem W/Sensor Mounting or Associated Sensor Cabling1993-12-20020 December 1993 Special Rept 93-04:on 931119,channel 7 of loose-part Detection Sys Determined Inoperable for Greater than 30 Days.Charge Converter Replaced.Troubleshooting Revealed Problem W/Sensor Mounting or Associated Sensor Cabling ML20095A6951992-04-16016 April 1992 Special Rept 92-01:on 920322,emergency Diesel Generator a Failed to Reach Required Voltage & Frequency within 12 S. Caused by Dust Particles Trapped in Voltage Regulator Relay. Relay Replaced & Generator Successfully Started ML20086D6971991-11-20020 November 1991 Special Rept 91-05:on 911021,gasoline Contaminated Soils Discovered During Removal of Undergound Storage Tank.Site Assessment of Excavated Areas Performed to Define Extent of Gasoline Contamination ML20085D8241991-10-0909 October 1991 Special Rept 91-04:on 910927,red Indication Values Received on Wind Direction Instrumentation Computer Screen.On 911004, Discovered That Wind Direction Recorder Inoperable Since 910923.Wind Direction Transmitter Replaced ML20083D2341991-09-19019 September 1991 Special Rept 91-03:on 910820,determined That loose-part Detection Sys Channel Inoperable for More than 30 Days. Caused by Problems W/Sensor Mounting & Associated Sensor Cabling.Corrective Actions to Be Determined ML20082T1151991-09-12012 September 1991 Special Rept:On 910814,valid Diesel Generator Failure Occurred During 1 H Load Test Due to Component Failure. Failed Governor Sent to Vendor for Evaluation ML20082E2471991-07-25025 July 1991 Special Rept 91-01 Re Loose Part Detection Sys Channel Remaining Inoperable for Greater than 30 Days.Cause Under Investigation.Until Further Troubleshooting Completed, Corrective Actions Cannot Be Determined ML20065K1351990-11-0505 November 1990 Revised Special Rept 90-02-01:on 900924,invalid Diesel Generator Failure Occurred Due to Improper Output Breaker Plunger Clearance.Rev Changes Basis for Invalidity of Diesel Generator Failure Per Reg Guide 1.108 ML20062C3821990-10-24024 October 1990 Special Rept 90-02:on 900924,invalid Diesel Generator Failure Occurred Due to Improper Output Breaker Plunger Clearance.Evaluation of Design & Use of Test Link Will Be Performed ML20058N0871990-08-10010 August 1990 Special Rept 90-01:on 900718,invalid Failure of Diesel Generator a Occurred.Caused by Personnel Error Due to Procedural Inadequacy.Procedure Revised to Reflect Loading Requirements When Paralleling Diesel Generator ML20247R0711989-09-14014 September 1989 Special Rept 89-10:on 890810,fifth-yr Inservice Containment Vessel Tendon Surveillance Failure Identified.Caused by Void Existing within Tendon Duct Boundary.Future Tests Will Monitor Containment to Detect Any Potential Degradation ML20246Q1931989-09-0505 September 1989 Special Rept 89-10:on 890810,discovered That Net Refill Vol of Sheathing Filler Grease Exceeded 5% of Net Duct Vol for Tendons.Caused by Initial Filling Method Inducing Air Entrapment Into Filler Matl.Structural Integrity Unaffected ML20247M3311989-07-26026 July 1989 Special Rept 89-09:on 890619,Channel 3 of Loose Part Detection Sys Inoperable.Caused by Problems W/Sensor,Sensor Mounting or Associated Sensor Cabling.Troubleshooting Will Not Be Performed Until Next Outage of Sufficient Duration ML20247M4481989-07-26026 July 1989 Special Rept 89-06:on 890518,ESF Safety Injection Actuation on Train a Received Due to Low Streamline Pressure Signal During Reactor Trip Breaker Trip Actuating Device Operational Test.Plant Restored to Normal Condition ML20247L0081989-07-24024 July 1989 Rev 1 to Special Rept 89-03:on 890330,emergency Diesel Generator a Declared Inoperable.Caused by Cooling Water Leaking from Exhaust Valve Cooling Jumpers Into Rocker Arm Lube Oil Reservoir.Tests Performed Once Per 31 Days ML20247E1791989-07-19019 July 1989 Special Rept 89-07:on 890401,emergency Diesel Generator a Failed to Start as Required During Performance of Surveillance Test Procedure.Caused by Failure of Relay Driver Card.Card Replaced & Proper Operation Verified ML20247E1581989-07-19019 July 1989 Special Rept 89-08:on 890403,emergency Diesel Generator B Failed to Start Due to Operator Failing to Keep Pushbuttons Depressed Long Enough to Generate Start Signal.Procedures Revised to Caution of 1.2 Time Delay ML20245K7171989-05-0101 May 1989 Special Rept 89-03:on 890330,emergency Diesel Generator a Declared Inoperable Due to Cooling Water Leaking from Exhaust Valve Cooling Water Jumper O-rings on Cylinder 8 Into Rocker Arm Lube Oil Reservoir.Jumpers Replaced ML20245L1891989-04-28028 April 1989 Special Rept 89-02:on 890329,emergency Diesel Generator a Tripped on Overspeed Due to Governor Not Being Set Low Enough.Caused by Procedural Inadequacies.Procedure OT-NE-00001, Standby Diesel Generation Sys to Be Revised ML20235P8921989-02-21021 February 1989 Special Rept 89-01:on 890119,smoke Observed Coming from Diesel Generator Regulator Power Transformer Cabinet.Caused by Open Output Fuses from Exciter Power Potential Transformer.Transformer Meggered ML20150D9781988-07-0808 July 1988 Special Rept 88-02:on 880613,approx 13,000 Gallons of NaOC1, 12.45 Ph Spilled at Cooling Water Chemical Control Sys Bldg. on 880617,second Spill Occurred.Caused by Open Drain Valve. PVC Piping to Be Replaced W/Stronger Piping ML20155C8801988-05-31031 May 1988 Rev 1 to Special Rept 88-01:on 880213,ECCS Actuation Occurred.Caused by Open Main Steam Line Drain Valves & Malfunctioned Main Steam Seal Automatic Pressure Regulator Valve.Eccs Repaired & Plant Restored to Normal ML20154B3901988-05-0909 May 1988 Special Rept 88-01:on 880213,low Steam Line Pressure Signal Received Resulting in Safety Injection.Caused by Personnel Oversight.Msiv Shut ML20236Q3121987-11-16016 November 1987 Special Rept 87-13:on 871106,prior to Fuel Cycle 3,moderator Temp Coefficient Measured to Be Positive 0.372 Pcm/F.Control Rod Withdrawal Limits Established & Control Rods Have Been Maintained within Limits ML20236Q0951987-11-16016 November 1987 Special Rept 87-14:on 871010,free Field Seismic Sensor Made Inoperable.Caused by Voltage Surge in Power Cable to Sensor Due to Lightning Strike.Seismic Monitoring Instrumentation Sys Expected to Be Restored on 871130 ML20236A8931987-10-15015 October 1987 Special Rept 87-11,reporting Number of Tubes Plugged During Third Steam Generator Tube Inservice Insp.Eight Tubes Plugged ML20235W5421987-10-0909 October 1987 Special Rept 87-10:on 870912,three of Six Delivery Valve Cap Screws on Fuel Injection Pump Failed Causing Fuel Oil Leak.Caused by Improper Torquing of Fuel Injector Delivery Valve Flange Capscrews.Flange Removed & Capsrews Replaced ML20235K1821987-09-28028 September 1987 Special Rept 87-09:on 870911,RCS Specific Activity Exceed 1.18 Uci Per G Dose Equivalent I-131.Caused by Release of Radioactive Idodine from Known Fuel Cladding Defects.Fuel Assemblies Will Be Ultrasonically Tested for Defect ML20238C8091987-08-31031 August 1987 Suppl 1 to Special Rept 87-08:on 870706,tendon V18 & Five Addl Tendons Failed to Meet Surveillance Requirement 4.6.1.6.1.e.1.Initially Reported on 870813.Voids in Excess of 5% of Net Duct Vol Did Not Result in Any Degradation ML20237J8661987-08-13013 August 1987 Special Rept 87-08:on 870706,discovered That Net Refill Vol of Sheathing Filler Matl Exceeded 5% Net Duct Vol for Surveillance Tendon V18.Voids Have Not Resulted in Any Degradation of post-tensioning Sys ML20235T5461987-07-13013 July 1987 Special Rept 87-07:on 870601,while Reinserting Scratch Pads for 48 Sensors,Scriber Tip for Sensor 15 Inadvertently Broke.Cause Unknown.Work Request Initiated & Sensor Will Be Replaced ML20235E6131987-07-0606 July 1987 Special Rept 87-06:on 870622,actuation of Seismic Monitoring Instrumentation Occurred.Probably Caused by Equipment Malfunction.Further Investigation Underway to Determine Exact Cause of Malfunction ML20216F8491987-06-22022 June 1987 Special Rept 87-05:on 870608,unusual Event Declared Due to Actuation of Seismic Monitoring Instrumentation.Caused Not Determined.Evaluation Indicated That Industrial Mine Blasts in Area Did Not Cause Actuation ML20209B9921987-04-22022 April 1987 Special Rept 87-02:on 870402,dose Equivalent I-131 of RCS Sampled & Found to Be 1.143 Uci/Gram.Caused by Fuel Cladding Defects.Appropriate Sampling & Analysis Requirements Performed Until RCS Activity Restored within Limits ML20206G1481987-03-0909 March 1987 Special Rept 86-06:on 860303-31,first Eddy Current Inservice Insp Performed on Steam Generators a & D to Meet Tech Spec 3/4.4.5 Surveillance Requirements.Number of Tubes Containing Imperfections Encl ML20212E2681987-02-27027 February 1987 Special Rept 87-01:on 870130,dose Equivalent I-131 of RCS Found to Be 1.53 Uci/G.Caused by Fuel Cladding Defects. Appropriate Sampling & Analysis Performed Until Activity Restored within Limits ML20215N8651986-10-31031 October 1986 Special Rept 86-08:from 860922,loose-part Detection Sys Inoperable.Caused by Ground Condition in Channel 5 Hard Wire/Soft Wire Junction Box.Hand Hole Cover & Junction Box Will Be Repaired During Next Outage ML20214X4051986-09-23023 September 1986 Special Rept 86-07:on 860825,RCS Sampled & Found to Exceed Tech Spec 3.4.8 Limitation.Caused by Defects in Cladding of Fuel.Appropriate Sampling & Analysis Requirements Performed Until RCS Specific Activity Restored within Limits ML20212N5721986-08-15015 August 1986 Special Rept 86-05:on 860808,loose Part Detection Sys Channel 5 Inoperable in Excess of Tech Spec 3.3.3.8 30-day Limit.Caused by Ground Condition Due to Steam Generator Sludge Lance Hand Hole Cover Leak.Cover Resealed 1999-03-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E2691999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20212A3361999-09-14014 September 1999 1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20212A0201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210Q8331999-08-0505 August 1999 Rev 4 to Callaway Cycle 10 Colr ML20210T9481999-08-0303 August 1999 Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for Ue Callaway Plant,Unit 1 ML20216D8791999-07-31031 July 1999 Rev 3 to Callaway Cycle 10 Colr ML20210T4451999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20209H0881999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With ML20195H4831999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With ML20206R7111999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp ML20205S5791999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Callaway Plant Unit 1.With ML20207A7401999-03-30030 March 1999 Draft, Evaluation of Risk of Induced Steam Generator Tube Rupture, for Callaway Plant ML20205G4071999-03-25025 March 1999 Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325 ML20204B6741999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Callaway Plant,Unit 1.With ML20199E7011998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Callaway Plant.With ULNRC-03990, 1998 Annual Rept for Ameren Corp/Union Electric Co. with1998-12-31031 December 1998 1998 Annual Rept for Ameren Corp/Union Electric Co. with ML20198D9811998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Callaway Plant,Unit 1.With ML20195C8341998-11-10010 November 1998 Rev 20 to Operating QA Manual ML20195C8181998-11-0909 November 1998 Rev 19 marked-up Changes to Operating QA Manual ML20195D6931998-10-31031 October 1998 Non-proprietary Rev 3 to Electrosleeving Qualification for PWR Recirculating SG Tube Repair ML20195D3581998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Callaway Plant,Unit 1.With ML20154L4931998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Callaway Plant Unit 1.With ML20151Y5151998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Callaway Plant,Unit 1.With ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20237B8421998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Callaway Plant,Unit 1 ML20155H7381998-06-30030 June 1998 10CFR50.59 Summary Rept for Jan-June 1998. with ML20236Q9991998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Callaway Plant,Unit 1 ML20249C5851998-06-30030 June 1998 Rev 1 to Callaway Cycle 10,COLR ML20248M0501998-06-0808 June 1998 Special Rept 98-02:on 980502,Channel 3 of loose-part Detection Sys Was Declared to Be Inoperable.Caused by Failure of Component Inaccessible at Power.Addl Troubleshooting Will Be Performed ML20249A7681998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Callaway Plant,Unit 1 ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247G0811998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Callaway Plant Unit 1 ML20217R2031998-04-27027 April 1998 Cycle 10 Colr ML20216H0651998-04-15015 April 1998 SER Approving Licensee Proposed Alternative to Use Code Case N-508-1 for Rotation of Serviced Snubbers & Prvs for Purpose of Testing in Lieu of ASME B&PV Code,Section Xi,Article IWA-7000 Requirements ML20216K0531998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Callaway Plant,Unit 1 ML20217F3181998-03-24024 March 1998 SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program ML20216G3551998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Callaway Plant, Unit 1 ML20203M0101998-02-25025 February 1998 Rev 11 to Callaway Cycle 9 Colr ML20203A7951998-02-0909 February 1998 Rev 10 to Callaway Cycle 9 Colr ML20202D4821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Callaway Plant ML20198S6361998-01-22022 January 1998 Ro:On 980121,determined That Plant Shutdown Would Be Required IAW TS 3.8.1.1,Action D.Caused by 'B' Train EES Charcoal Absorber Being Determined Inoperable.Requested 24 Hour Extension to Allow Restoration of EDG & ESW Train ULNRC-03775, 1997 Annual Rept for Union Electric1997-12-31031 December 1997 1997 Annual Rept for Union Electric ML20198Q0631997-12-31031 December 1997 Rev 9 to Callaway Cycle 9 Colr ML20198J6791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Callaway Plant,Unit 1 1999-09-30
[Table view] |
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- Etscraic 7 February 21, 1989 L <
' Callaway Plant -
U. S. Nuclear Regulatory Cctamission .
'j Document Control Desk '
{! Washington, DC ~ .20555 i
t ULNRC-1917 i
Gentlemen:
DOCKET NUMBER 50 -83 CALLAWAY PLANT tv.T 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 89-01 INVALID FAILURE OF DIESEL GENERATOR
'B' DURING TROUBLESHOOTING WHEN 'A' PHASE EXCITER POWER TRANSFORMER HEATED DUE TO BLOWN FUSES l The enclosed Special Report is submitted pursuant to ,
l Technical Specification 4.8.1.1.3 concerning the invalid failure of i Diesel Generator 'B' due to the heating of 'A' phase power potential transformer during troubleshooting. This was due to blown fuses on 'B' and 'C' phases of the transformer.
[
. D. Blosser 8903020410999hhjgg Manager, Callaway Plant
{DR ADOCK 05o PDC. 'b oO TPS/MKD:jih Enclosure cc: Distribution attached I
/ if MaHog Aattmsu P.O. Box 62Q Fution, MO 65251 [l j
cc distribution for ULNRC 1917 Mr. A. Bert Davis Mr. Thomas Alexion (2 copies)
Regional Administrator Office of Nuclear Peactor Regulation U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Region III Mail Stop 13-E-21 799 Roosevelt Road Washington, D.C. 20555 Glen Ellyn, IL 60137 American Nuclear Insurers Mr. O. Maynard c/o Dottie Sherman, Library Wolf Creek Nuclear Operating Corp.
The Exchange Suite 245 P. O. Box 411 270 Farmington Avenue Burlington, KS 66839 Farmington, CT 06032 Mr. Merlin Williams Manager, Electric Department Supt. of Regulatory Quality &
Missouri Public Service Commission Administrative Services P. O. Box 360 Wolf Creek Nuclear Operating Corp.
Jefferson City, MO 65102 P. O. Box 411 j
Burlington, KS 66839 Institute of Nuclear Power Operations Mr. R. W. DeFayette Suite 1500 Chief, Project Section 3A 1100 Circle 75 Parkway U.S. Nuclear Regulatory Commission Atlanta, GA 30339 Region III 799 Roosevelt Road NRC Resident Inspector Glen Ellyn, IL 60137 D. F. Schnell (400)
G. L. Randolph R. P. Wendling (470)
J. V. Laux A. C. Passwater/D. E. Shafer/D. J. Walker (470)
G. A. Hughes Z170.05 (QA Record)
Z403R (Z170.09 Commercial Record)
M. S. Evans M. E. Taylor H. Wuertenbnecher, Jr. (100)
S. L. Auston (470)(NSRB)
S. J. Bellers/D. R. Oelrichs E210.01 Z40ULNRC A160.761 N. Date (Sandra Auston) (470)
J SPECIAL REPORT 89-01 INVALID FAILURE OF DIESEL GENERATOR 'B' DURING TROUBLESHOOTING-WHEN 'A' PHASE EXC, ITER POWER TRANSFORMER HEATED DUE TO BLOWN' FUSES On 1/19/89, Emergency diesel generator (D/G) 'B' was secured during troubleshooting when smoke was observed coming from the D/G regulator power transformer cabinet. This was an invalid failure which is reported per Technical Specification (T/S) 4.8.1.1.3.
^l A one-hour load rua, required by T/S 4.8.1.1.2.a.5, had been
- successfully completed at 0516 CST. With the D/G still loaded, .
j troubleshooting was undertaken to correct an apparent problem with the '
voltage regulator null meter. A licensed operator attempted to null the meter by raising the manual (base) voltage adjuster while. the automatic (voltage) adjuster was in control. Because the exciter power potential transformer (PPT) 'C' phase fuse had previously, unknowingly blown, the meter would not null and the base adjuster affected the generator output.. The '
effect was seen as an increase in field current and an increase in lagging Kilovolt Amperes Reactive (KVAR's). The generator load reached 6.2 megawatt (MW) at a 0.7 power factor (PF) which corresponds to 8857KVA lagging (this is below the generator 30 minute rating of 9300 KVA). During the' time the operator was troubleshooting the null meter, it is suspected that the exciter PPT 'B' phase fuse failed.
- After. discussion between the utility system engineer and the licensed shift supervisor, it was decided to continue troubleshooting with the D/G ,
unloaded. When unloading was halted at 800 KW to stabilize the PF betweer 0.89 and 0.92, smoke was observed coming from the D/G local regulator pot transformer cabinet. The D/G was immediately secured at approximately 0600.
1 Upon investigation, plant personnel discovered the output fuses from the exciter PPT 'C' and 'B' phases were open. The resulting load on PPT 'A' phase, with increased harmonic heating, had caused the PPT to reach l approximately 150*C. This heating caused.a section of clear plastic insulation on the lead to the primary coil of the 'A' phase PPT to melt.
Smoke came from this melted plastic insulation which was installed by the manufacturer to space lead wires.
A visual exmination of the PPT showed a small amount of discoloration on-the top of the 'A' phase primary winding. An engineering evaluation has determined that the 'A' phase coil was not damaged. The 'B' and 'C' phase coils showed no damage.
f' The PPT was meggered. All readings were acceptable. A transformer l turns ratio test indicated no turn to turn insulation damage. The 'C' and
'B' phase PPT fuses were replaced. D/G 'B' was re-started. PPT secondary currents'and temperature were monitored. The manual voltage adjuster was exercised up and down and the null meter responded as expected. A one-hour load test of the D/G was successfully completed. i L
._~_a_---a_-___ .--w--,_----u._ _ _ _ = . _ _ _
.. =
The 'C' phase PPT fuse is suspected to have blown prior to 1/19/89. An engineering evaluation has affirmed the operability of the D/G with one fuse blown. A review of records shows that the second fuse did not blow until this troubleshooting. The cause of the fuse failures is unknown. A preventive maintenance work request will be evaluated to check the fuses on a routine periodic frequency. The operability of D/G 'A' was also evaluated; its PPT phase fuses were found to be operating normally.
Prior to this event, the D/G had been declared inoperable at 0245 on 1/18/89 to permit preventive maintenance. The D/G 'B' was declared operable at 1831 on 1/20/89. The D/G was unavailable for two days and 15.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
T/S 3.8.1.1 action statements were satisfied. Since this failure occurred during troubleshooting and not during a valid test, the surveillance test interval of T/S Table 4.8-1 is not affected. This position is consistent with Regulatory Guide 1.108C.2.e(7).
The starting history of the 'B' D/G as of this report date is summarized as follows:
No. of Failures No. of Failures No. of Valid Tests During Valid Tests During Invalid Tests 69 0 2#
- Reference Special Report 85-05 Surveillance tests are currently performed at least once per 31 days for the 'B' D/G. This is in conformance with the schedule of T/S Table 4.8-1 which requires a test interval of not more than 31 days if the number of failures in the last 20 valid tests is one or less or the number of failures in the last 100 valid tests is four or less.
l ._. _____ _ __