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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
[Table view] Category:LER)
[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 05000458/LER-1998-003, :on 980624,design Error Found on Two of Three Sdgs That Could Potentially Degrade Ability of DGs to Perform Safety Function.Caused of Design Error Unknown.Dg Control Logic Modified to Remove Design Error1999-09-0909 September 1999
- on 980624,design Error Found on Two of Three Sdgs That Could Potentially Degrade Ability of DGs to Perform Safety Function.Caused of Design Error Unknown.Dg Control Logic Modified to Remove Design Error
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 ML20195G1621999-06-11011 June 1999 Safety Evaluation Supporting Amend 107 to License NPF-47 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 05000458/LER-1999-008, :on 990418,uplanned Automatic Closure of Div III DG Output Breaker Was Noted Due to Loss of Normal Power to Div III Switchgear During Testing.Caused by Personnel Error.Returned Electrical Lineup to Normal.With1999-05-18018 May 1999
- on 990418,uplanned Automatic Closure of Div III DG Output Breaker Was Noted Due to Loss of Normal Power to Div III Switchgear During Testing.Caused by Personnel Error.Returned Electrical Lineup to Normal.With
ML20206H3141999-05-0505 May 1999 Safety Evaluation Supporting Amend 106 to License NPF-47 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 ML20206D5591999-04-27027 April 1999 Safety Evaluation Supporting Amend 105 to License NPF-47 05000458/LER-1999-004, :on 990325,automatic Actuation of CIV Due to Inadvertent Water Movement Was Noted.Caused by Failure to Coordinate Separate Activities of Different Workers.Dryer Pool Was Returned to Normal Level.With1999-04-26026 April 1999
- on 990325,automatic Actuation of CIV Due to Inadvertent Water Movement Was Noted.Caused by Failure to Coordinate Separate Activities of Different Workers.Dryer Pool Was Returned to Normal Level.With
05000458/LER-1999-003-03, :on 990324,Division I DG Was Declared Inoperable.Caused by Inadequate Assembly of Fuel Pump.Fuel Pump Coupling Was Repaired & DG Was Returned to Svc1999-04-25025 April 1999
- on 990324,Division I DG Was Declared Inoperable.Caused by Inadequate Assembly of Fuel Pump.Fuel Pump Coupling Was Repaired & DG Was Returned to Svc
ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 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 ML20205D3431999-03-26026 March 1999 Safety Evaluation Supporting Amend 104 to License NPF-47 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) 05000458/LER-1999-002-02, :on 990204,discovered That Potentially Rendered safety-related Unit Coolers in Primary Containment Inoperable.Cause Being Investigated.Corrective Action Plan Will Be Submitted in Suppl to Ler.With1999-03-0808 March 1999
- on 990204,discovered That Potentially Rendered safety-related Unit Coolers in Primary Containment Inoperable.Cause Being Investigated.Corrective Action Plan Will Be Submitted in Suppl to Ler.With
ML20207K2221999-03-0303 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-47 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 ML20202C9751999-01-27027 January 1999 Safety Evaluation Supporting Amend 102 to License NPF-47 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 05000458/LER-1998-004-03, :on 980514,noted That Surveillance Test Had Not Been Completed for Primary Containment Leakage Rate Testing Program.Caused by Lack of Proper Emphasis on Procedure Step Re Summation.Revised Pertinent Surveillance Procedures1998-08-11011 August 1998
- on 980514,noted That Surveillance Test Had Not Been Completed for Primary Containment Leakage Rate Testing Program.Caused by Lack of Proper Emphasis on Procedure Step Re Summation.Revised Pertinent Surveillance Procedures
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 05000458/LER-1998-003-02, :on 980624,adequacy of Division 1 & 2 DG Control Air Sys Was Noted.Root Cause Analysis Is Being performed.Multi-disciplinary Team Was Formed to Address Immediate & long-term Corrective Actions1998-07-24024 July 1998
- on 980624,adequacy of Division 1 & 2 DG Control Air Sys Was Noted.Root Cause Analysis Is Being performed.Multi-disciplinary Team Was Formed to Address Immediate & long-term Corrective Actions
05000458/LER-1998-002, :on 980425,failure of Two Trains of Annulus Mixing Was Noted.Caused by Problem W/Instantaneous Trip of Setpoint a & B Supply Breakers.Corrected Trip Settings & Replaced B Breaker1998-07-15015 July 1998
- on 980425,failure of Two Trains of Annulus Mixing Was Noted.Caused by Problem W/Instantaneous Trip of Setpoint a & B Supply Breakers.Corrected Trip Settings & Replaced B Breaker
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 05000458/LER-1998-001, :on 980417,flow Rate Through SGTS Filter Assembly Units Were Found to Be Higher than Design Flow Rate.Caused by Personnel Error.Reviewed & Updated Design & Licensing Basis Documents1998-06-30030 June 1998
- on 980417,flow Rate Through SGTS Filter Assembly Units Were Found to Be Higher than Design Flow Rate.Caused by Personnel Error.Reviewed & Updated Design & Licensing Basis Documents
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 05000458/LER-1998-002-02, :on 980425,each of Two Trains of Annulus Mixing Sys Failed to Start During Testing Due to Different, Apparently Independent Causes.Eoi Personnel Performing Root Cause Analyses.Breaker Replaced1998-05-26026 May 1998
- on 980425,each of Two Trains of Annulus Mixing Sys Failed to Start During Testing Due to Different, Apparently Independent Causes.Eoi Personnel Performing Root Cause Analyses.Breaker Replaced
05000458/LER-1998-001-04, :on 980417,flow Rate Through SBGTS Filter Assembly Units Was Found to Be Higher than Design Flow Rate. Cause Analysis Is Currently Being Performed.Detailed Evaluation of Sys Ability to Perform Was Done1998-05-18018 May 1998
- on 980417,flow Rate Through SBGTS Filter Assembly Units Was Found to Be Higher than Design Flow Rate. Cause Analysis Is Currently Being Performed.Detailed Evaluation of Sys Ability to Perform Was Done
1999-09-09
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' ' .I Gentlemen .- I
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, River Bend Station sUnit 1 .
Docket No. 50-458
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~ t L Enclosed ' is Gulf ' States Utilities Company's ~Special Report. -l A ,
concerning diesel generator control room temperature in excess of .{
x>,w: 1 the limits lof' Technical Specification 3.7.8 forl greater.than !
. _ .1 Jeightr, hours. This supplemental- report is being submitted I
R>f : pursuant to River Bend Technical; Specification 3.7.8. i
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, Sincerely, ,
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m- J. E. Booker ;
T- Manager-River Bend Oversight i L' -
River Bend Nuclear Group
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C l,- B/.FP/ HM/ ch 8 cer. U.:S.-Nuclear Regulatory Commission ,
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tArlington, TX 76011
,f i i j W NRC~ Resident Inspector 5' n ' ' Post Office Box 1051 ,
! o St..Francisville. LA 70775 v
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gDR ADOCX 05000458 PNU
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I SPECIAL REPORT f
REPORTED CONDITION As identified in CSU's Special Report dated 7/19/89 (RBG-31263), at !
approximately 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> on 6/20/89, temperature in the diesel generator IB control room was identified as above the Technical Specification (3/4.7.8) limit of 104'F for greater than eight hours. The diesel generator IB control room ' temperature returned within the Technical Specification limit on l 6/21/89. At approximately 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on 6/26/89, temperature in the diesel '
generator IA and IB control rooms were again identified as above the 104'F for greater than eight '
Technical Specification (3/4.7.8) limit of hours. The temperature excursions were noted during the performance of STP-000-0001, " Daily Operating Logs". This supplemental report provides the
- record peak temperature in the diesel generator control rooms for 9/15/89 through 10/13/89. Due to milder outside ambient temperatures, the diesel generator control room temperatures were at or below the Technical Specification limit during much of the reporting period. Supplemental reports will continue until the temperatures are continuously within the Technical Specification limit.
INVESTIGATION The following table shows the peak temperature recorded daily during the performance of STP-000-0001 from 9/15/89 through 10/13/89. .;
DATE DGIA CONTROL ROOM TEMP ('F) DCIB CONTROL ROOM TEMP (*F) 9/15/89 107 108 9/16/89 108 107 9/17/89 105 107 9/18/89 104 106 9/19/89 104 107 9/20/89 104 106 9/21/89 104 107 9/22/89 100 108 9/23/89 102 108 9/24/89 99 102 9/25/89 100 102 9/26/89 99 100 9/27/89 100 103 9/28/89 100 102 <
9/29/89 100 103 9/30/89 99 102 10/01/89 98 101 10/02/89 100 103 1C/03/89 102 105 10/04/89 102 105 10/05/89 102 105 10/06/89 104 106 10/07/89 104 107 Page 1 of 2
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DATE DCI A CONTROL ROOM TEMP (*F) DGlB CONTROL ROOM TEMP ('F) y,.s-10/08/89 105 107 g' 10/09/89' .102 105 E 10/10/89 100' 99 f' , ' *
'10/11/89 100 102
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10/12/89- 101 103 e 10/13/89 101 103 L
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' ANALYSIS AND CORRECTIVE ACTION I
The. apparent' cause of the . elevated temperatures is a combination of heat c generated inside the building by the stsadby df.esel generator " Keep Warm" e system, high outside ambient temper, cures, and insufficient ventilation in
- 1 the diesel engine room due to undersizing of the engine room's normal exhaust fans. A modification request has been prepared to increase the capacity of-the engine room normal exhaust fan.
The elevated temperatures has no effect on the operability of safety-related equipment located in the diesel generator control room. The diesel generator-control room is a mild environment as defined in 10CFR50.49(c)(iii), and as
, such, is excluded from the final rule on environmental qualifications.
Safety-related equipment located within the diesel generator control rooms which has been identified to be susceptible to'sicnificant thermal aging mechanisms (e.g., Agastat relays) are periodica11, replaced under an
- y. equipment qualification preventive maintenance task to ensure operability of the equipment. Temperaturea in the diesel generator control room continue to exceed the limits of Technical Specification 3.7.8 on a periodic basis. A supplemental report will be provided each 30 days to provide the recorded temperatures until the diesel generator control room temperatures are continuously within the Technical Specification limit.
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