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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
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March 31,1986 Mr. James G. Keppler
. Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn IL 60137 ULNRC-1280
Dear Mr. Keppler:
DOCKET NUMBER 50-483 ,
CALLAWAY PLANT UNIT 1 '
FACILITYOPERATINGLICENSENPF-30}-
SPECIAL REPORT 86-01 ,
DIESEL GENERATOR FAILURE DURING AN INVALID TEST The enclosed Special Report is submitted pursuant to Technical Specification 4.8.1.1.3 and 6.9.2 concerning a diesel generator failure during an invalid test.
l k wt G. L. Randolph I
Manager, Callaway Plant e #' -
hl713 d-DEY/TPS/;WK/drs Enclosure cc Distribution attached I
8604000243 060331 1 PDR ADOCK 05000403 S PDR g2W l
i Mading Address:PO. Box 620 FultortMO65251 l
l } 0,].
cc distribution for ULNRC-1280 Mr. Paul O'Connor Manager, Electric Department Office of Nuclear Reactor Regulation Missouri Public Service Commission U.S. Nuclear Regulatory Commission P. O. Box 360 Mail Stop P-316 Jefferson City, MO 65102 7920 Norfolk Avenue Bethesda, MD 20014 Mr. O. Maynard Kansas Gas and Electric Company P. O. Box 208 American Nuclear Insurers Wichita, KS 62701 c/o Dottie Sherman, Library The Exchange Suite 245 Mr. Nicholas A. Petrick 270 Farmington Avenue Executive Director, SNUPPS Farmington, CT 06032 5 Choke Cherry Road Rockville, MD 20850 Mr. J. H. Smith Bechtel Power Corporation Records Center SNUPPS Project Institute of Nuclear Power Operations 15740 Shady Grove Road Suite 1500 Gaithersburg, MD 20877-1454 1100 Circle 75 Parkway Atlanta, CA 30339 NRC Resident Inspector D. F. Schnell (400)
R. J. Schukai (470)
S. E. Miltenberger J. F. McLaughlin J. E. Davis (240LER)
(Z40LER) (w/c)
D. W. Capone /R. P. Wendling (470)
F. D. Field (470)
A. P. Neuhalfen A. C. Passwater/D. E. Shafer/D. J. Walker (470)
G. A. Hughes 240.03 (QA Record)
J. M. Price D. E. Young M. E. Taylor H. Wuertenbaecher, Jr. (100)
S. L. Auston (470)(NSRB)
J. D. Schnack
. GLR Chrono 3456-0021.6 3456-0260 Z40ULNRC G56.37 N. Date (Sandra Auston) (470)
w .'
SPECIAL REPORT 86-01 DIESEL GENERATOR FAILURE DURING AN INVALID TEST Surveillance Procedure ISP-SA-2413A, Diesel Generator and Sequencer Testing (Train A), was in progress on 3/6/86 to satisfy various 18 month Technical Specification (T/S) surveillance requirements. The plant had entered Mode 5, Cold Shutdown, on 3/4/86. During performance of the
"'A' Train Blackout Without SIS (Safety Injection Signal)" portion of ISP-SA-2413A, the 'A' emergency diesel generator (D/G) was intentionally secured without loading to at least 50% of continuous rating. The D/G was secured to investigate a failure of the load sequencer to properly sequence the required emergency loads onto the 4.16 kV safety-related bus (NB01) energized by 'A' D/G.
Since the successful D/G start was terminated intentionally without loading to at least 50% of continuous rating, it is not considered a valid test or failure in accordance with Regulatory Position C.2.e(4) of Regulatory Guide 1.108, Revision 1. August 1977. The D/G testing frequency established by T/S Table 4.8-1 is therefore not affected by this incident and this Special Report is being submitted as required for all D/G failures, valid or nonvalid, per T/S 4.8.1.1.3. It is noted that the D/G could have been manually loaded and a valid test completed had the operators not intentionally secured the D/G for troubleshooting of the load sequencer.
Starts of the D/G's have been tracked since the completion of Preoperational Testing on 5/11/84. The starting history of the D/G's as of the date of this report is summarized as follows:
Number of Number of Number of Failures During Failures During i- D/G Valid Tests Valid Tests Invalid Tests A 31 1* Si B 27 0 15
- Reference Special Report 84-02.
- Reference Special Reports 85-01, 85-02, 85-07, and 86-01.
5 Reference Special Report 85-05. ;
The following is a summary of the events applicable to this incident.
- The "'A' Train Blackout Without S1S" portion of ISP-SA-2413A began at approximately 2018 on 3/6/86.
- Loads shed off bus NB01 as required when the test signal (blackout without SIS) was initiated.
'A' D/G successfully started and attained the required voltage and frequency.
L
s o' SPECIAL REPORT 86-01 Page 2
'A' D/G output breaker closed.
- Only 'A' Centrifugal Charging Pump and 'A' Component Cooling Water Pump sequenced onto bus NB01 and were powered by the 'A' D/G.
- Testing activities were halted and troubleshooting initiated.
- Troubleshooting of the 'A' D/G output breaker identified that the plunger bolt (which actuates certain stationary contacts when the breaker closes) was out of adjustment.
Consequently, the stationary contacts did not initiate a signal to the load sequencer that the breaker was closed.
The condition also prevented synchronizing of the D/G with offsite power by not allowing a synchronizing check relay to pick up.
- Temporary adjustments were made such that the synchronizing check relay picked up. The D/G was paralleled with offsite power and the loads were transferred off the D/G. The D/G output breaker was opened, and the D/G secured and declared inoperable at approximately 2350 on 3/6/86.
The plunger bolt was found to be out of adjustnent by approximately 3/32 of an inch. It was adjusted within tolerance per Electrical Preventive Maintenance Procedure MPE-ZZ-QS005, Cleaning, Inspection, and Lubrication of 13.8 kV and 4.16 kV Breakers, at 0210 on 3/7/86.
- The "'A' Train Blackout Without SIS" portion of ISP-SA-2413A was again commenced at approximately 2040 on 3/7/86 and completed satisfactorily.
'A' D/G was declared operable at 2222 on 3/7/86.
! Verification of proper adjustment of the plunger bolt for 'A' D/G output breaker was last performed on 5/20/85 during an 18 month preventive maintenance inspection. The cause of the plunger bolt being out of adjustment is unknown. This type of problem has not been a frequently experienced occurrence associated with the D/G output breakers; however, due to the significance of the plunger bolt / stationary contacts function, a preventive maintenance inspection for proper adjustment of the plunger bolt will be evaluated for increased periodicity for 'A' and 'B' D/G output breakers.
This incident occurred while the plant was in Mode 5. In this mode, T/S 3.8.1.2 requires only one diesel generator to be operable.
'B' D/G was operable while 'A' D/G was out of service for testing and
.a .
SPECIAL REPORT 86-01 Page 3 inoperable due to the output breaker plunger bolt. Performance of ISP-SA-2413B, Diesel Generator and Sequencer Testing (Train B), began following completion of ISP-SA-2413A. On 3/10/86 the load sequencer for for 'B' train functioned satisfactorily when the breaker closed during the "'B' Train Blackout Without SIS" portion of ISP-SA-2413B.
Surveillance tests are currently performed at least once per 31 days for each D/C. This is in conformance with tha schedule of Regulatory Position C.2.d of Regulatory Guide 1.108. Revision 1 August 1977, and Technical Specification Table 4.8-1 which require the test interval.to be not more than 31 days if the number of failures in the last 100 valid tests is one or zero.
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