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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20080G4721995-01-18018 January 1995 Ro:On 941223,invalid Failure Experienced on 2A DG During Normal Start of Engine to Support Transformer Maint Activities.Speed Module Which Initiates Various Control & Support Features as Function of Engine Speed Replaced ML20078L8961994-11-21021 November 1994 Ro:On 941101,DG 2A Invalid Failure Occurred.Problem Isolated to Failed 125 Volt Dc Relay on Instantaneous pre-position Circuit Board.Subj Circuit Board Will Be Replaced W/New Design During Next Unit 2 Refueling Outage ML20114C1141992-08-19019 August 1992 Special Rept:On 920407,fuel Injection Pump in Right Cylinder 7 Seized,Preventing Injection of Fuel Into Associated Cylinder.Caused by Particulate Contamination.On 920320,noise Emanated from Right Cylinder 4 ML20086F9791991-11-22022 November 1991 Special Rept:On 910920,22,27,1001 & 02,invalid Failures of Diesel Generators 1A & 1B Occurred.Redundant Diesel Generator Operable During Each Event.Diesel Generator 1B Placed on Weekly Testing Frequency ML20079P5851991-10-0909 October 1991 Ro:On 910904,09 & 16,seismic Monitoring Instrumentation (Tape Decks 1 & 2 & Sensor 5) Inoperable for More than 30 Days.Playback Tape Deck & Sensor Repaired & Restored to Operable Status ML20058A3681990-10-0101 October 1990 Deviation Investigation Rept 90-026-00:on 900815,EDG 2A Cylinder 10L Dislocated Pushrod Due to Collapsed Hydraulic Lifter ML20055G3461990-06-27027 June 1990 Ro:On 900412,engine Tripped Due to Spurious High Jacket Water Temp Trip Valve Actuation During Partial Surviellance to Verify Operability of Diesel Generator 2A.Nuclear Work Request Initiated to Repair or Replace Trip Valve ML20247C5601989-05-18018 May 1989 Special Rept:On 890224,during Local Leak Rate Surveillance Test,Overall Max Pathway Containment Leakage Failed to Meet Acceptance Criteria & Containment Isolation Valves Exhibited Excessive Leakage.Caused by Improper Valve Stroking ML20246P9061989-03-20020 March 1989 Ro:On 890214,nonvalid Test & Failure Experienced on 2B Diesel Generator.Caused by Nuclear Station Operator Inexperience & Procedural Discrepancy.Nuclear Station Operator Counseled & Procedure Change Initiated ML20236E1821989-03-10010 March 1989 Ro:On 890305,moderator Temp Coefficient Determined to Be More Positive than Allowed by Tech Spec 3.1.1.3.a & Limiting Condition for Operation Entered.Control Rods Maintained within New Withdrawal Limits Until Core Burnup Reached ML20195G5811988-06-13013 June 1988 Deviation Investigation Rept 88-076-00:on 880516,diesel Genrator 1B Uncontrollably Loaded During Monthly Operability Surveillance.Caused by 3IMX Relay Failure.Load Reduced W/ Governor Control Switch & Subj Relay Replaced ML20238D9711987-12-21021 December 1987 Ro:On 870925,during Monthly Operability Surveillance of Diesel Generator 1A,fuel Oil Leak Occurred at Connection of Fuel Pump W/Fuel Pump Discharge Line.Caused by Cracked Fitting at Cylinder Pump Discharge.Pump & Line Replaced ML20237C9051987-12-0303 December 1987 Ro:On 871105,diesel Generator 2A Inoperable for 22 H.Caused by Dirty Voltage Range & Adjustment Potentiometer (Pot) in Voltage Regulator.Pot Cleaned & Exercised Through Full Range ML20236F8351987-10-27027 October 1987 Ro:On 870814,governor Hunting Observed Following Diesel Generator Startup.Caused by Intermittent Operation of 4EX3 Relay.Diesel Generator 1B Will Remain on Monthly Testing Schedule Per Tech Spec 4.8.1.1.2 ML20236T9321987-10-27027 October 1987 Special Rept:On 870831,Train a Safety Injection Occurred During Performance of Bimonthly Surveillance of solid-state Protection Sys.Caused by Cognitive Personnel Error.Emergency Procedure 2BEP-0 Entered & Exited When Plant Stabilized ML20236Q1301987-10-19019 October 1987 Ro:On 870812,reactor Tripped Following Safety Injection & Main Steam Line Isolation During Power Ascension.Caused by Fully Open Governor Valve.Necessary Equipment auto-started/ Actuated Per Design ML20236E5011987-06-25025 June 1987 Ro:On 870318 & 0417,diesel Generator 1A Failed to Reach Rated Speed,Voltage & Frequency within Required Time Set by Tech Specs.Caused by Inadequate Prime in Fuel Oil Supply Line & Ruptured Diaphragm,Respectively ML20236B8871987-06-18018 June 1987 Ro:On 870428,valid Test & Failure on Diesel Generator 2B Occurred.Caused by Method Used for Determining Start Time. Diesel Generator Monthly Operability Surveillance Procedures Revised ML20207T2771987-03-0606 March 1987 Ro:On 870210,diesel Generator 1A Experienced Valid Test Failure.Caused by Failure of Check Valve to Supply Day Tank in Event That Check Valve Fails to Seat.Addl Soft Seat Check Valve Installed Between Engine & Supply Day Tank ML20212K9321987-02-27027 February 1987 Special Rept;On 870215,wide-range Noble Gas Monitor Taken Out of Svc for Mod to Demonstrate Capability to Test for Radioiodine,Per TMI Action Plan Item II.F.1.Mod Scheduled for Completion by mid-Mar 1987 ML20198S1011986-05-29029 May 1986 Special Rept:On 860505,diesel Generator 2A Declared Incapable Due to Contaminated Fuel & Broken Rocker Arms on Seven Left Cylinder.Caused by Bent Retaining Rings & Insufficient Generator Crosshead Procedure.Parts Replaced ML20195D1001986-05-19019 May 1986 Ro:On 860430,Unit 2 Diesel Generator 1B Required 12.5 to Reach Rated Conditions.Caused by Inadequate Prime in Fuel Oil Supply Line.Union Lightened ML20203F6021986-03-20020 March 1986 Special Rept:On 860223 & 0313,diesel Generator 1B Experienced Two Nonvalid Tests & Failures Due to Isochronous Relay Failure.Caused by Intermittent Continuity Between Contacts in Isochronous Relay While in Test Mode ML20203K9371986-03-11011 March 1986 Special Rept:On 860212 & 17,Cooper Bessemer Diesel Generator 2A Failures Occurred Due to Rocker Arm Failure.Caused by Liner Misalignment W/Subsequent Head Alignment.Heads Realigned or Replaced ML20135F8431985-09-0303 September 1985 Ro:On 850813,30- & 250-ft Wind Direction Recorders & 30-ft Air Temp Recorder in Main Control Room Reported Inoperable. Caused by Damaged Fuses in Communication Line Between Meteorological Tower & Control Room.Fuses Replaced ML20127J2541985-06-13013 June 1985 Ro:On 850527,control Room Indication of 30-ft Wind Speed Lost.Caused by Problems W/Communication Links Between Tower Instrumentation & Control Room Readouts.Work in Progress to Restore Operability ML20126M8411985-06-0303 June 1985 Correction to 850523 Special Rept:Second & Third Sentences of Second Paragraph Should Read ...On One of Sys Five Sensor Signal Cables.This Signal Cable Is for Free Field Sensor ML20127E1111985-05-23023 May 1985 Special Rept:On 850419,seismic Instrumentation Sys Began Alarming Continuously.Troubleshooting Indicated 120 Mv Peak to Peak 60 Cycle Signal on Sys Fire Sensor Signal Cables. Problem Under Investigation ML20107D5151985-02-0808 February 1985 Updated Special Rept Re Diesel Generator Failures. Reevaluation Reduced Failures of Diesel Generator 1A to One Common Failure,Decreasing Total to Two Failures Out of 58 Valid Tests ML20106A1761985-01-12012 January 1985 Special Rept:On 841228,suction Relief Valve 1RH8708A & on 841230,RHR Sys Lifted on High Pressure Transient During Restoration of Loop Following Performance of Surveillance Procedure Bvs 0.5-2.SI.3 ML20076K7771983-07-0808 July 1983 Ro:On 830630,during Insp of Spent Fuel Rack,Five Propane Gas Cylinders Found in Spent Fuel Pool Area.Caused by Personnel Error.Cylinders Will Be Stored Outside Fuel Handling Bldg.Signs Re Combustible Matl Will Be Posted 1995-01-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20207H7731998-11-30030 November 1998 Rev 0 to WCAP-15125, Evaluation of Pressurized Thermal Shock for Byron,Unit 1 ML20207H8011998-11-30030 November 1998 Rev 0 to WCAP-15124, Byron Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20198D1501998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195F8321998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a1998-10-0909 October 1998 Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154L5501998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20197C9051998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20151Z9651998-08-31031 August 1998 Revised MOR for Aug 1998 for Byron Nuclear Power Station. Rept Now Includes Page 9 Which Was Omitted from Previously Issued Rept ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B3361998-08-14014 August 1998 B2R07 ISI Summary Rept,Spring 1998 Outage, 961005-980518 ML20237B4841998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2 1999-09-30
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PAD DL(.$g,:a, e Mr. A. Bert Davis Regional Administrator Region 3 U.S. Regulatory Commission 799 Roosevelt Road Glenn Ellyn, Illinois 60137
Dear Sir:
This report is submitted in accordance with Byron Station Unit 2 Operating License NPF-60 Appendix A, Technical Specification 4.8.1.1.3, reporting of j Diesel Generator Failures. i I
This report addresses two nonvalid tests and failures experienced on the 2A diesel generator. The criteria to determine valid tests and failures is in accordance with Section C.2.e of Regulatory Guide 1.108.
On November 5, 1987 at 0956 the 2A diesel generator (DG) was started per the Monthly Operability Surveillance, 2BOS 8.1.1.2.a-l. Approximately twenty l minutes into the full load run the engine operator noticed several large kilo voltage-ampere reactive (KVAR) swings. The 2A DG was unloaded, shutdown and Limiting Condition for Operation Action Requirement (LCOAR) 2BOS 8..l.1-la was entered for one diesel generator inoperable. Following several conversations j with the voltage regulator specialists at the Commonwealth Edison Tech Center, !
and the Load Dispatcher, it was decided to restart the 2A DG for a maintenance run. The Tech Center Personnel theorized that the KVAR swings may have been induced by an unstable grid. At 1356 the 2A DG was started and synchronized to the grid. The 2A DG was operated with no abnormalities for seventy four minutes. Based on the successful maintenance run, the 2A DG was restarted, at 1556, per the Monthly Operability Surveillance. Fifty six minutes into the ;
full load run the engine operator noticed another large KVAR swing. At 1710 l the engine was shutdown. Tech Center personnel were contacted and brought to '
the site to assist in the investigation. Following two troubleshooting runs !
the root cause was determie d, and corrective action was taken. At 0305 on l November 6, 1987 the 2A DG was restarted per the Monthly Operability Surveillance. At 0541 the Surveillance was successfully completed. 140AR 2BOS 8.1.1-la was exited at 0830 on November 6, 1987. .
l The root cause for these two events was a dirty voltage range and adjustment potentiometer (POT) in the voltage regulator. The source of the dirt is most likely an accumulation from construction activities in the general area. The effect of the dirty POT was an erratic voltage control signal from the voltage regulator to the diesel generator exciter. With the DG synchronized to the grid (Test Mode), this condition created the large KVAR swings. The faulty POT Q2220249g71203 I o g ADOCK 05000455 "a DEC10 m g p w
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would have had minimal effect on the 2A DG in the emergency mode. Minor voltage swings may have occurred, however, due to the total possible range adjustment on the POT, no voltage swings could have occurred outside the L- Technical Specification limits of + or - 420 volts. Per Section C.2.a.2 of Regulatory Guide 1.108 these two failures are considered nonvalid tests and i failures.
l l The faulty POT was cleaned with contact cleaner and exercised through its full range. Another POT with a similar function was also cleaned and exercised.
These corrective actions will also be performed on the 1A, 1B, and 2B DG's.
AIRS 454-512-87-0287, and 455-512-87-0288 will track the completion of this work for Unit One and Unit Two respectively. 1 I
The 2A diesel generator was inoperable for twenty.two hours during this event. The testing frequency for the 2A DG will remain on a monthly bacis ac nonvalid failures do not affect the testing frequency. The 2A DG has completed forty two consecutive valid tests without a valid failure.
b$t.L R. E. Querio Station Manager l Byron Nuclear. Power Station' .
REQ /MMR/JC/bf (0179z) cc: P. Brochman, NRC Senior Resident Inspector U.S. NRC Document Control Desk, Washington, D.C.
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