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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20044F7611993-05-19019 May 1993 Special Rept:On 930409,discovered That Battery Voltage for Triaxial Seismic Swtiches at Reactor Bldg Mat Elevation 70 ft,0 Inches Read Low at 10.6-volts Dc.Caused by Failure to Communicate LCO During Outage.Battery Replaced ML20029A0051991-01-25025 January 1991 Ro:On 901130,max Reactor Heatup Rate Exceeded Following Control Rod Withdrawal.Caused by Personnel Error.Control Rods Reinserted in Reverse Sequence to Mitigate Heatup Rate & Surveillance Test Procedure Revised ML20028H0341990-09-27027 September 1990 Special Rept:On 900905,discovered Cracked Turbocharger Axial Strut Support on South End of Diesel During Insp.Caused by Fatigue Failure.Diesel Declared Inoperative & Cracked Plate Cut Out & Saved for Further Analysis ML20042F0031990-04-27027 April 1990 Revised Special Rept:On 891121,loose Parts Monitoring Sys Channel 7 Found in Alert Condition by Operations.Initially Reported on 900109.Channel 7 Alarm Setpoint Changed to 3.6 Times Background Signal.Loose Part Condition Did Not Exist ML20012F1491990-03-27027 March 1990 Special Rept:On 900227,Div III Diesel Generator Shut Down. Caused by High Leakage of Fuel Oil in Return Tubing Attached to Strainers 1EGF-STR3C & 1EGF-STR3F Causing Possibility of Fire.Tubing Replaced & Maint Work Order Initiated ML20011F2421990-02-16016 February 1990 Ro:On 891219,lubricating Oil Used at Plant Failed to Meet Viscosity Requirements Specified by Mfg.Lubricant Oil Which Failed to Meet Mfg Viscosity Spec Replaced & Upgrading of Procurement Requirements for Lubricating Oils Underway ML20005G4591990-01-0909 January 1990 Special Rept:On 891121,loose Parts Monitoring Sys Channel 7, Main Steam Line 252 Degrees Azimuth Found in Alert Condition & Declared Inoperable on 891130 in Order to Ensure Valid Alert Signal Could Be Detected from Other Channels ML20005G3101990-01-0808 January 1990 Special Rept:On 891209,invalid Failure of Div I Diesel Generator Occurred.Caused by Tripped Annunciators.Rev to Monthly Operability Procedure & Sys Operating Procedure SOP-0053 Being Implemented ML20005F8561990-01-0808 January 1990 Special Rept:On 891211,invalid Failure of Div II Diesel Generator Occurred During Monthly Surveillance Test Procedure STP-309-0202.Caused by Failed GE Breaker in Exhaust Fan.Breaker Replaced & Generator Returned to Svc ML19351A6581989-12-14014 December 1989 Special Rept:On 891114,trip Occurred on Div I Diesel Generator 1EGS*EG1A.Caused by Defective High Bearing Temp Detector & Water in Plastic Tubing Used to Connect Test Gauge.Shutdown Logic Board & Defective Connector Replaced ML19332B9911989-11-14014 November 1989 Special Rept:On 890620,temp in Diesel Generator Control Room Identified as Above Tech Spec 3/4.7.8 Limit for Greater than 8 H.Similar Event Noted on 890626.Caused by Heat,High Outside Ambient Temps & Insufficient Ventilation ML19332B9381989-11-14014 November 1989 Special Rept:On 891017,invalid Failure of Div 1 Diesel Generator Occurred Due to Trip.Trip Caused by High Vibration Signal from Turbocharger Vibration Switch.Switch Reset Per Maint Work Order R056445 ML19354D4001989-10-27027 October 1989 Informational Rept:On 890928,field Engineer Made Emergency Exit from High Radiation Area Through High Radiation Door AB78-01.Total Exposure Received by Engineer Was 10 Mr.Door Not Required to Be Locked & Therefore Lock on Door Defeated ML19327B1001989-10-16016 October 1989 Special Rept:On 890620 & 26,temp in Diesel Generator 1A & 1B Control Room Found Above Tech Spec Limit of 104 F Greater than 8 H.Caused by Heat Generated Inside Bldg,High Outside Ambient Temp & Insufficient Ventilation 1993-05-19
[Table view] Category:LER)
MONTHYEARML20044F7611993-05-19019 May 1993 Special Rept:On 930409,discovered That Battery Voltage for Triaxial Seismic Swtiches at Reactor Bldg Mat Elevation 70 ft,0 Inches Read Low at 10.6-volts Dc.Caused by Failure to Communicate LCO During Outage.Battery Replaced ML20029A0051991-01-25025 January 1991 Ro:On 901130,max Reactor Heatup Rate Exceeded Following Control Rod Withdrawal.Caused by Personnel Error.Control Rods Reinserted in Reverse Sequence to Mitigate Heatup Rate & Surveillance Test Procedure Revised ML20028H0341990-09-27027 September 1990 Special Rept:On 900905,discovered Cracked Turbocharger Axial Strut Support on South End of Diesel During Insp.Caused by Fatigue Failure.Diesel Declared Inoperative & Cracked Plate Cut Out & Saved for Further Analysis ML20042F0031990-04-27027 April 1990 Revised Special Rept:On 891121,loose Parts Monitoring Sys Channel 7 Found in Alert Condition by Operations.Initially Reported on 900109.Channel 7 Alarm Setpoint Changed to 3.6 Times Background Signal.Loose Part Condition Did Not Exist ML20012F1491990-03-27027 March 1990 Special Rept:On 900227,Div III Diesel Generator Shut Down. Caused by High Leakage of Fuel Oil in Return Tubing Attached to Strainers 1EGF-STR3C & 1EGF-STR3F Causing Possibility of Fire.Tubing Replaced & Maint Work Order Initiated ML20011F2421990-02-16016 February 1990 Ro:On 891219,lubricating Oil Used at Plant Failed to Meet Viscosity Requirements Specified by Mfg.Lubricant Oil Which Failed to Meet Mfg Viscosity Spec Replaced & Upgrading of Procurement Requirements for Lubricating Oils Underway ML20005G4591990-01-0909 January 1990 Special Rept:On 891121,loose Parts Monitoring Sys Channel 7, Main Steam Line 252 Degrees Azimuth Found in Alert Condition & Declared Inoperable on 891130 in Order to Ensure Valid Alert Signal Could Be Detected from Other Channels ML20005G3101990-01-0808 January 1990 Special Rept:On 891209,invalid Failure of Div I Diesel Generator Occurred.Caused by Tripped Annunciators.Rev to Monthly Operability Procedure & Sys Operating Procedure SOP-0053 Being Implemented ML20005F8561990-01-0808 January 1990 Special Rept:On 891211,invalid Failure of Div II Diesel Generator Occurred During Monthly Surveillance Test Procedure STP-309-0202.Caused by Failed GE Breaker in Exhaust Fan.Breaker Replaced & Generator Returned to Svc ML19351A6581989-12-14014 December 1989 Special Rept:On 891114,trip Occurred on Div I Diesel Generator 1EGS*EG1A.Caused by Defective High Bearing Temp Detector & Water in Plastic Tubing Used to Connect Test Gauge.Shutdown Logic Board & Defective Connector Replaced ML19332B9911989-11-14014 November 1989 Special Rept:On 890620,temp in Diesel Generator Control Room Identified as Above Tech Spec 3/4.7.8 Limit for Greater than 8 H.Similar Event Noted on 890626.Caused by Heat,High Outside Ambient Temps & Insufficient Ventilation ML19332B9381989-11-14014 November 1989 Special Rept:On 891017,invalid Failure of Div 1 Diesel Generator Occurred Due to Trip.Trip Caused by High Vibration Signal from Turbocharger Vibration Switch.Switch Reset Per Maint Work Order R056445 ML19354D4001989-10-27027 October 1989 Informational Rept:On 890928,field Engineer Made Emergency Exit from High Radiation Area Through High Radiation Door AB78-01.Total Exposure Received by Engineer Was 10 Mr.Door Not Required to Be Locked & Therefore Lock on Door Defeated ML19327B1001989-10-16016 October 1989 Special Rept:On 890620 & 26,temp in Diesel Generator 1A & 1B Control Room Found Above Tech Spec Limit of 104 F Greater than 8 H.Caused by Heat Generated Inside Bldg,High Outside Ambient Temp & Insufficient Ventilation 1993-05-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARRBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) ML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 RBG-44337, Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 11997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 1 ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 RBG-44295, Monthly Operating Rept for Oct 1997 for River Bend Station Unit 11997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for River Bend Station Unit 1 RBG-44243, LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee1997-10-13013 October 1997 LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee 1999-09-09
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p GULF STATA S UTILITIE'S COMPANY R%1R FlhD ST AYlON PObt 08 FICE BOX ??ti Sf IfiANCISVitLE LOL!$iANA 70776 P
AHL A CODf 4td 6J6 tOb4 346 %$1 September 27, 1990 RBG- 33664 File Nos. G9.5, G9.25.1.4 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Enclosed is Gulf States Utilities Company's Special Report concerning a valid failure of the Division I diesel generator at River Bend Station. This report is submitted pursuant to River Bend Station Technical Specifications 4.8.1.1.3 and 6.9.2.
Sincerely, fu W.Manager-Oversight H. Odell River Bend Nuclear Group LA /PDG/RGW/DNL/DCH/G H/pg Enclosure cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 :
NRC Senior Resident inspector Post Office Box 1051 St. Francisville, LA 70775 h
O w' h 'Z .Y y ems ,ee 2, noocx, 030004se a
PDC
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. REP'0[tTED CONDITION At 0800 on 09/05/90 with the reactor operating at 65% power (Operational ;
Condition 1), while performing a routine visual inspection on Division I r diesel, the system engineer discovered a cracked turbocharger axial strut -
support plate on the south end of the diesel. Note that the Division I j diesel generator was manufactured by Transamerica Delaval. Inc., model DSR !
- 48. The crack was 4" long and began at the outermost edge of the vertical ;
fillet weld joining the plate to the exhaust manifold support and proceeded I diagonally towards a notch in the plate. This cracked member never resulted in the Division I diesel being unable to fulfill its design ;
purposes. However, this is classified as a valid failure in accordance ;
with Regulatory Guide (R.G.) 1.108, position C.2.e.8. This Special Report t is submitted pursuant to Technical Specifications 4.8.1.1.3 and 6.9.2. [
INVESTIGATION l
The support plate is 3/4" thick, carbon steel and is welded to an adjoining n haust manifold support on one side and welded to the turbocharger support !
pedestal on the adjacent side. The strut is connected to the plate by two 1 bolts, mating a welded strut end piece with the support plate. '
The diesel was declared inoperative at 0800 on 09/05/90 and the cracked I plate was. cut out and saved for- further analysis. Several observed conditions seem to point to a fatigue failure due to vibration and stress. i They are: (1) poor fitup of the strut end piece to the plate causing a :
stress loading of the plate in the upward direction and (2) review of t vibration data shows Division I diesel turbocharger vibration levels are consistently higher than the Division II diesel turbocharger levels. The ;
Division I diesel generator turbocharger vibration levels also showed an '
' increasing trend in the axial direction in the month prior to the discovery of the. crack.
GSU continues to evaluate this failure. When the failure evaluation'is ,
concluded, a revision will be made to this Special Report and submitted to t the NRC by March 1, 1991.
CORRECTIVE ACTION i The; cracked support plate was removed and a redesigned support plate was fabricated and installed. This new su) port plate is 3/4" A516-GR70 carbon '
steel .with the notch removed, whici resulted in a four-fold increase in section~ modulus. The fitup between the strut end piece and the plate was corrected and the strut end piece was bolted to the plate. The horizontal fillet weld size was increased to 1/2" to provide greater strength.
Vibration tests performed following the repair indicated that the vibration levels in the axial direction have decreased to' normal levels.
The support plate on the Division II diesel was visually inspected for any ;
signs of failure. None were found. It was noted, additionally, that the strut end piece and the support plate did not have the poor fitup exhibited by the Division I diesel. The Division I diesel was declared operable at 1700 on 09/05/90.
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L.: L'ength of Time Diesel Generator was Out-of-Service: 15' hours 1
', Current Surveillance Interval: ,
. Division 1. Monthly i Division 11 ' Monthly i Division III Monthly. I t
Test Intervals Conforms to Technical Specification:' l Yes l
. I Failures for Division I: ,
i 1 Valid. failure (s)inthelast 20 Valid Tests ~
1 Valid failure (s) in the.last 100 Valid Tests 1
. i Failures for Division II: i 1
0 Valid failure (s) in the last 20 Valid Tests 4 Valid failure (s) in the last 100 Valid Tests !
Failures for Division III:
EValidfailure(s)inthelast-20ValidTests 2 Valid failure (s) in the last 100 Valid Tests. i Number of' Valid Failures in previous'100 Valid Tests of all Diesel [
Generators at River Bend Station: .;
I 3 .
9 d
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