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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20216H0781997-09-10010 September 1997 LER 97-S01-00:on 970816,security Sys Degradations Discovered Due to Inclement Weather.All Components Were Returned to Svc & Compensatory Posts Terminated After Completion of Repairs & Testing 05000425/LER-1993-0051993-08-30030 August 1993 LER 93-005-00:on 930809,B Train Chiller Tripped.Caused by High Condenser Pressure Due to Excess of non-condensable Gases in Sys.Solenoid Valve Replaced,Ecw Chiller Purged & Surveillance Test Reperformed successfully.W/930830 Ltr 05000424/LER-1993-0091993-08-23023 August 1993 LER 93-009-00:on 930728,reactor Tripped During Maint Due to Low Pressure Signal.Caused by Cognitive Personnel Error. Personnel Involved Disciplined & Reminded of Importance of Procedural compliance.W/930823 Ltr 05000424/LER-1993-0041993-05-0303 May 1993 LER 93-004-00:on 930410,ESFAS Sequencer Operation Initiated During Testing.Caused by Design Flaw in Circuit Card. Affected Cards in Both Train a & Train B Sequencers modified.W/930503 Ltr 05000425/LER-1990-0081990-07-27027 July 1990 LER 90-008-00:on 900628,indication Received in Control Room That MSIV 2HV-3026A Was Closing.Caused by Failure of O-ring Which Seals Connection of Nonpump Side Manifold Assembly to Boss on Actuator cylinder.O-ring replaced.W/900727 Ltr 05000424/LER-1990-0131990-06-29029 June 1990 LER 90-013-00:on 900601,discovered That Containment Air Lock Leakage Surveillance Exceeded 6-month Test Interval,Per Tech Spec 4.6.1.3.b.Caused by Personnel Error.Plant Surveillance Tracking Program revised.W/900629 Ltr 05000424/LER-1990-0121990-06-28028 June 1990 LER 90-012-00:on 900529,discovered That Sequencer Delay Times Not Taken Into Account During Summation Procedure for Control Room Emergency Filtration Sys.Caused by Inadequate Procedure Review.Procedures changed.W/900628 Ltr 05000424/LER-1990-0111990-05-21021 May 1990 LER 90-011-00:on 900425,reactor Manually Tripped Due to Inadvertent Closure of Main Feed Regulating Valve.Caused by Mispositioning of Local Control Levers.Local Control Levers removed.W/900521 Ltr 1997-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236P6991998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20236Q3051998-06-30030 June 1998 Owner'S Rept for ISI for Sixth Maint/Refueling Outage of Vogtle Electric Generating Plant,Unit 2 ML20249A3911998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Vogtle Electric Generating Plant ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20249A3931998-04-30030 April 1998 Revised MOR for Apr 1998 for Vogtle Electric Generating Plant Unit 1 ML20247F3841998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20154Q9721998-04-20020 April 1998 10CFR50.59(B) Rept of Facility Changes,Tests & Experiments for Vogtle Electric Generating Plant,Units 1 & 2 ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20216D6141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20217Q1301998-03-31031 March 1998 Rev 0 to Vepc Unit 2 Cycle 7,COLR ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20216E2421998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203E4831998-02-11011 February 1998 Rev 1 to Vogtle Electric Generating Plant,Units 1 & 2 Second Ten-Yr Interval Pump Inservice Test Program ML20198T1211998-01-31031 January 1998 Owners Rept for Inservice Inspection for Seventh Maintenance/Refueling Outage ML20202G5441998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20199E5431998-01-31031 January 1998 Rev 3 to WCAP-14720, Vogtle Units 1 & 2 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20198L6471997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20202B7881997-12-0101 December 1997 Rev 8 to ISI-P-006, ISI Program for Gpc Vogtle Electric Generating Plant Unit 1 ML20203H0601997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Vegp,Units 1 & 2 1999-09-30
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August 30, 1993 LCV-0124 Docket No. 50-425 U. S. Nuclear Regulatorj Commissian
- ATTN: Document Control Desk Washington, D. C. 20555 t
Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT LICENSEE EVENT REPORT UNIT OPERATION PER TECHNICAL SPECIFICATION 3.0.3 WHEN BOTH ESF CHILLERS WERE INOPERABLE in accordance with the requirements of 10 CFR 50.73, Georgia Power Company submits the enclosed report related to ar event which occurred on August 9,1993.
Sincerely, C. K. McCoy CKM/NJS
Enclosure:
LER 50-425/1993-005 xc: Georgia Power Com_pany Mr. J. B. Beasley, Jr.
Mr. M. Sheibani NORMS U. S. Nucitar Reculatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Ilood, Licensing Project Manager, NRR Mr. B. R. Bonser, Senior Resident Inspector, Vogtle 9309070362 930830 I PDR ADOCK 05000425 0* / i S PDR M I j
f macFORJ3e4 U.S.NJCLEAR REGULATORY COMWh&4GN APPROVED OMB NO.3154 0104 a (689) EXPtRES 4rMB2 l
ESTNATED BURDEN PER RESPONSE TO COMPLY WITH THIS LICENSEE EVENT REPORT (LER) "Tu S EC"57su'RDDeSTETS*TwE" S"*
r ND ': PORTS MANAGEMENT BRANCH (P433). U$ NUCLEAR NEGULA : ftv COMMISSION, WASHINGTON. DC 20555. AND TO THE PAPt.RWORK REDUCTION PROJECT (31500104). OFFICE OF ,
MANAGEMENT AND BUDGET. WASHINGTON DC20503
- ACIUTV hAME (1) DOCAET NUMBER (2) F AM N Vogtle Electric Generating Plant - Unit 2 0l5l0l0l0l4l2l5 1 OF 3 !
TITLE $4)
UNIT OPERATION PER TECHNICAL SPECIFICATION 3.0.3 WHEN BOTH ESF CHII I FRS WERE INOPERABLE EVENT DATE (5) EER NUMBER (6) REPORT DATE (7) OTHER FACluTIES INVOLVED (0) f MONTH DAY YEAR YEAR &E j k MONT*e DAY YEAR F ACluTY NAMES DOCKET NUMBER (S) i liiliII_ ;
018 O l9 9 3 9 13 01015 010 Ol8 3 10 9l3 l l l l l l l OPERAT M TMtS REPORT t$ GubWTTED FUR &UANT TO THE REQU6REMENT& OF to CFR ?:(Checa en. or more of she doiMweig)(11) enODE p) 204325)
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%.m w75. m w rm.m m 7x.m(s) w 7m.x m LaCENSEE CONT ACT FOR THL& LER (12) hAME TELEWtONE NUMBER Mehdi Sheibani, Nuclear Safety and Compliance
^ * ' ' ' '
I 71016 81216 l- 13121019 '
COMPLETE ONE UNE FOR EACM COMPONENT FA8 LURE DESCRnBED IN TH48 REPORT (13) ,
CAUSE f$YSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS g$
pm y CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS y;f,; Mh)g ;. l Nd.J j$$ yd x X K lM P lS lV l A l6 l1 l0 N , yd & l l l l l l l M~ %gg%ggg '
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&UPPLEMENTAL REPORT EAPLCTED(14) l l l l l l l EAPECTED MONTH.
$@h DAY YEAR SuawsSoN
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On August 9,1993, personnel were conducting a monthly surveillance test per Procedure 14400-2,
" Control Room Emergency Filtration Actuation Logic Test." In accordance with the procedure, the "A" train essential chilled water (ECW) system chiller actuation handswitch had been taken to the "Stop" position to prevent the chiller from staning when an actuation signal was initived to test the "B" train chiller response. The "B" train chiller was started at 2045 EDT, but momec ster it tripped. Personnel exited the pocedure and the "A" train chiller was returned to standby status at 2101 EDT. The 16-minute period when neither ECW chiller was available for automatic actuation I and senice represented unit operation per Technical Specification (TS) 3.0.3 since the ECW chillers perform an engineered safety feature fimetion, and there is no other TS action requirement which addresses unit operation with both chillers out of service.
The cause of the "B" train chiller trip was high condenser pressure due to an excess of non-i condensable gases in the system. A clogged purge solenoid valve prevented a control room ,
l annunciator from alerting personnel that purging of the excess noncondensable gases from the I system was needed. The solenoid valve was replaced, the ECW chiller was purged, and the surveillance was reperfonned successfully.
hRC Forni3 6(649)
I NRC MA J anA U.S. NUCLEAR $4GULATORY COMil&&#ON AVr*RCorED OMB NO 31aOC104 (6 89) EXPIRES 4r304I2 EST24ATED BURDEN PER RZSPONSE TO COMPLY WITH THIS 2"elR$EE,,CTION " ' ^" l UCENSEE EVENT REPORT (LER) no BURDE E le THE DS TEXT CONTINUATION Lyg^gNT SRANCH,P w $Q )
R ROJECT (315401 OFFICE OF 1*,^[ERW F ACUT Y hAteE (1) DOCKE) NUMBER (2) LER NUMBER (8) PAGE (3) re^a y 5eouga,m- i ag$y; Vogtle Electric Generating Plant - Unit 2 1 TEXT (# mars apace a segwett, am maWeonet AIRC Ferne .M6A s)(17) 0 l5 l0 l010 l41215 9l3 -
0 l0 l5 0l0 l2 oF l3 ;
A. REQUIREMENT FOR REPORT 1
i This report is required per 10 CFR 50.73 (a)(2)(i) because the unit operated in a condition :
prohibited by the Technical Specifications (TS) when more than one engineered safety feature l (ESF) chiller of the essential chilled water (ECW) system was inoperable, requiring entry into TS i 3.0.3.
f B. UNIT STATUS AT TIME OF EVENT i
At the time of this event, Unit 2 was operating in Mode 1 (power operation) at 99 percent of ;
rated thermal power. Other than that described herein, there was no inoperable equipment which {
contributed to the occurrence of this event. ;
t C. DESCRIPTION OF EVENT ;
On August 9,1993, personnel were conducting a surveillance test per Procedure 14400-2,
" Control Room Emergency Filtration Actuation Logic Test." In accordance with the procedure, :
the "A" train ECW chiller actuation handswitch had been taken to the "Stop" position to prevent !
the chiller from starting when an actuation signal was initiated to test the "B" train chiller response. The "B" train chiller was staned at 2045 EDT, but moments later it tripped. ,
Personnel exited the procedure and the "A" train chiller was returned to standby status at 2101 ;
i EDT. The 16-minute period when neither ECW chiller was available for automatic actuation and service represented unit operation per TS 3.0.3 since the ECW chillers perform an engineered .
safety feature function, and there is no other TS action requirement which addresses unit .
operation with both chillers out of service. l D. CAUSE OF EVENT i
The cause of the "B" train chiller trip was high condenser pressure due to an excess of non- !
condensable gases in the system. A clogged purge solenoid valve prevented a control room ,
annunciator from alening personnel that purging of the excess noncondensable gases from the ,
system was needed.
E. ANALYSIS OF EVENT The time during which no ECW chiller was available for automatic actuation represented a minimal at-risk period. Furthermore, the "A" train was available for service via manual actuation.
Based on these considerations, there was no adverse effect on plant safety or on the health and safety of the public as a result of this event.
t 4
NRC FORJ 3MA U.S.NUCLEAd #4GULATORY COM45$40N APPROVED OMB NO.3150 4104 Sep) EXPIRES C30S2 ESTIMATED BURDEN PER RESPON6E TO COMPLY WffH THIS
- LICENSEE EVENT REPORT (LER) MNYr RE" E Bu"RO TEd $'w' RTE +
TEXT CONTINUATION g
^ 4EPORTS y muMANA NT BR w
THE PAPERWORK REDUCTION PROJECT (31504104). OFFICE OF MANAGEMENT AND BUDGET, WASHsNGTON. DC 20503.
F ACALITV NAME (1) DOCKET NUMBER (2) LLR NUMBER (E) PAGE p)
YEAR ; EE ENTaAL *: R &
Vogtle Electric Generating Plant - Unit 2 TLX1 (# aw.ro speco e rogured, une mesural MfC Ftrm J66A a)(17) 0 l5 l0 l0 l0 l4 l2 l5 9 l3 0l0l5 -
0l0 l3 oF l3
- 1. The solenoid valve was replaced, the ECW chiller was purged, and the surveillance test was reperformed successfully.
- 2. A TS char.ge is being considered which would provide for the necessary test configuration ['
and preclude the need to enter TS 3.0.3 should a failure occur in the train being tested.
O. ADDITIONAL INFORMATION l F
I
- 1. Failed Components
'l Purge Solenoid Valve manufactured by Automatic Switch Company Part No. 2146251 5
1
- 2. Previous Similar Events -
None
- 3. Energy Industry Identification System Code Chilled Water System - KM t
l t
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05000424/LER-1993-004 | LER 93-004-00:on 930410,ESFAS Sequencer Operation Initiated During Testing.Caused by Design Flaw in Circuit Card. Affected Cards in Both Train a & Train B Sequencers modified.W/930503 Ltr | | 05000425/LER-1993-005 | LER 93-005-00:on 930809,B Train Chiller Tripped.Caused by High Condenser Pressure Due to Excess of non-condensable Gases in Sys.Solenoid Valve Replaced,Ecw Chiller Purged & Surveillance Test Reperformed successfully.W/930830 Ltr | | 05000424/LER-1993-009 | LER 93-009-00:on 930728,reactor Tripped During Maint Due to Low Pressure Signal.Caused by Cognitive Personnel Error. Personnel Involved Disciplined & Reminded of Importance of Procedural compliance.W/930823 Ltr | |
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