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| | issue date = 10/29/1976 | | | issue date = 10/29/1976 |
| | title = LER 76-062-00 for Dresden, Units 2 and 3 Re Upon Completion of Routine Diesel Generator Surveillance Testing, Control Switch Was Placed in the Stop Position, Generator Output Subsequently Became Erratic, Generator Voltage Began Oscillating. | | | title = LER 76-062-00 for Dresden, Units 2 and 3 Re Upon Completion of Routine Diesel Generator Surveillance Testing, Control Switch Was Placed in the Stop Position, Generator Output Subsequently Became Erratic, Generator Voltage Began Oscillating. |
| | author name = Stephenson B B | | | author name = Stephenson B |
| | author affiliation = Commonwealth Edison Co | | | author affiliation = Commonwealth Edison Co |
| | addressee name = Keppler J G | | | addressee name = Keppler J |
| | addressee affiliation = NRC/RGN-III | | | addressee affiliation = NRC/RGN-III |
| | docket = 05000237, 05000249 | | | docket = 05000237, 05000249 |
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| =Text= | | =Text= |
| {{#Wiki_filter:..... Commonv.rah Edison Dresde.1 Station R.R. # *, Morris, Illinois 60450 Telepho;ie 815/942-2920 BBS Ltr. 1176-757 ., .. October *29, 1976 Mr. James G .. Keppler, Regional Director Directorate of Reg'ulatory Operations -Region III U. S. Nuclear Regulatory Commission 799 :Roosevelt Road Glen Ellyn, Illinois 60137 | | {{#Wiki_filter:.. |
| | Commonv.rah Edison Dresde.1 Nucle~ower Station |
| | ..... R.R. # *, |
| | Morris, Illinois 60450 Telepho;ie 815/942-2920 BBS Ltr. 1176-757 October *29, 1976 Mr. James G.. Keppler, Regional Director Directorate of Reg'ulatory Operations - Region III U. S. Nuclear Regulatory Commission 799 :Roosevelt Road Glen Ellyn, Illinois 60137 |
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| ==REFERENCES:== | | ==REFERENCES:== |
| Docket No. 50-237 No. 50-249 , Enclosed please find Reportable Occurrence report number 50-237/1976-62. This report iS submitted to your off iCe in accordance with the Dresden Nuclear Station Technical Specifications, Section 6.6.B. BBS:jo Enclosure (A . ,-:-, t1 -z2-*-l _, c::r}/1 ; J. / /' . . *-v .._,-..._; /J '.I t.i?t* -!)--B. B. Stephenson fr Station Superintendent Dresden Nuclear Power Station cc: Director of Inspection &.Enforcement Director of Management* information & Program Control | | Docket No. 50-237 Doc~et No. 50-249 Enclosed please find Reportable Occurrence report number 50-237/1976-62. |
| * File/NRC | | This report iS bein~ submitted to your off iCe in accordance with the Dresden Nuclear Po~er Station Technical Specifications, Section 6.6.B. |
| -* ....... --* ';*-------* .. ... .... -*---**--*-.___.._.......__ . **it LICENSEE EVENT REPDF9 I CONrROL Bl:OCK: ..... I __._I (PLf:.ASE PRINT ALL REQUIRED INFORMATION] LICENSEE NAME @E] 7 8 9 14 CATEGORY REPORT TYPE. 1 6 ucrnsr NUMBER 10101-10101019101-10101 15 25 RE PC RT SOURCE DOCKl;T NU.MOER LICENSE TYPE l-4ltlilllfl 26 30 EVENT DATE EVENT TYPE 10131 31 32 REPORT DATE '@E]coNT I I. I lbJ U::J Io I s I o L-Io I 2 I 3 17 J 101q 13lo17ll. I I/ 7 ' B 57 58 59 60 . 61 68 69 74 75 80 EVENT DESCRIPTION @Ifil I UPON CoMP}..E.TtDN OF RoUT1N£ UN1 T ').._h Dr GEN£RA-fop___ SuRycr L.IJCINcf: I* 7 8 9 . . . 80 f @faLJTEST1NG:, TH£ CONTROL.. S0v1TcH 'P).._P,CC:::D IN TH:G".STOP'' pos1T10N. . f 7 B 9 80 lo14 I THC 6-ENERAToR OUT PU/ SVBSE. QUE:NTLY ERR.41/C.. THE G-EIVE"RATOR-I 7 8 9 . . . 80 lol51 !VOLTAGE BE.Gr-,f'J osc1 L/..:..AT/NG-, AND THE AC AND De CURRENT f'l'lCTE Rs I 7 .* 8 g* . . 80 [Q]B] I WC.NT OF"F.;.SCAL£. TH£ DIESEi-G-ENE.RAToR. WAS 1wir1£DfAT£J,,Y I 7 8 9 PR:ME (St:E' .'\ITAOISD Si-IEE.T) . 80 SYSTEM CAUSE COMPONENT COMPONENT , COOE CODE COMPONENT CCJOE SUPPUEn MANUFACTURER VIOLATION @01£1£1 l[J 1£1.NIGlllNIEI lAJ IWI01lll71 w 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION lolel .f-:n-4£ 1>1£$EJ_ Gi=.NERATOR.. Mf!J...FUNcn oN RESUt..IED [Rom A SHORTED SEJ....ENIVM 7. 8 9 . . . . . 80 lolsl !"i?f:CTIFIER. IN 1H£ GENER.ATOR. 1-1£&.D CIRCUIT, THE SHORT WflS. | | . ; ,-:-, t1 -z2- |
| * 1 7 0* g . . so :, | | . (A.*-v*-l~_,?.._,-..._;c::r}/1 |
| * 1 *,* 7* 8 9 FACILITY . . . . ... ... **. *... . . (S£it STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EID l-Gl*9 I NA U3J J\11-l I 7 B 9 10 . 12 13 44 45 4-6-----------:------'80 FORM OF . ACTIVITY | | /J '.I J. / |
| | ~ :.{~** t.i?t* |
| | /' |
| | -!)-- |
| | L-i('~ B. B. Stephenson fr Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc: Director of Inspection &.Enforcement Director of Management* information & Program Control |
| | * File/NRC |
| | |
| | -* ....... --* ';*-------* .. ... ~.... -*---**--*- .___.._.......__ |
| | LICENSEE EVENT REPDF9 CONrROL Bl:OCK: ..... |
| | . **itI __._I__.____..l.__..*l~_,I I (PLf:.ASE PRINT ALL REQUIRED INFORMATION] |
| | 1 6 LICENSEE LICENSE EVENT NAME ucrnsr NUMBER TYPE TYPE |
| | @E] IIILIDIRISl~I 10101-10101019101-10101 l-4ltlilllfl 10131 7 8 9 14 15 25 26 30 31 32 REPORT RE PC RT CATEGORY TYPE. SOURCE DOCKl;T NU.MOER EVENT DATE REPORT DATE |
| | '@E]coNT I I. I lbJ U::J Io I s I o L- Io I2 I 3 17J 101q 13lo17ll. I I/ IOl;Ll~l?l&.1 7 ' B 57 58 59 60 . 61 68 69 74 75 80 EVENT DESCRIPTION |
| | @Ifil I UPON CoMP}..E.TtDN OF RoUT1N£ UN1 T ').._h Dr ~S£k GEN£RA-fop___ SuRycr L.IJCINcf: I* |
| | 7 8 9 . . . 80 f |
| | @faLJTEST1NG:, TH£ CONTROL.. S0v1TcH WA~ 'P).._P,CC:::D IN TH:G".STOP'' pos1T10N. .f 7 B 9 80 lo148 9I THC 6-ENERAToR 7 . . . |
| | OUT PU/ SVBSE. QUE:NTLY B~Cfim£ ERR.41/C.. THE G-EIVE"RATOR-80 I |
| | lol51 !VOLTAGE .BE.Gr-,f'J 7 .* 8 g* . |
| | osc1 L/..:..AT/NG-, AND THE AC AND De CURRENT f'l'lCTE Rs 80 I |
| | [Q]B] I WC.NT OF"F.;.SCAL£. TH£ uN1T-~ DIESEi- G-ENE.RAToR. WAS 1wir1£DfAT£J,,Y vc=~1F1E_D I 7 8 9 PR:ME (St:E' .'\ITAOISD Si-IEE.T) . 80 SYSTEM CAUSE COMPONENT COMPONENT , |
| | COOE CODE COMPONENT CCJOE SUPPUEn MANUFACTURER VIOLATION 7 |
| | @01£1£1 l[J 8 9 10 11 12 1£1.NIGlllNIEI 17 lAJ 43 44 IWI01lll71 47 w 48 CAUSE DESCRIPTION lolel .f-:n-4£ 1>1£$EJ_ Gi=.NERATOR.. Mf!J...FUNcn oN RESUt..IED [Rom A SHORTED SEJ....ENIVM |
| | : 7. 8 9 . . . . . 80 lolsl !"i?f:CTIFIER. IN 1H£ GENER.ATOR. 1-1£&.D CIRCUIT, THE SHORT WflS. APPM~.ENT/.._y* |
| | * 1 7 0* g . . so |
| | *'<1;:~'.'.'il!@l'.:'~rc:110~E'.i{:1.:ttv:,>A~/~RAV0Ae'(~Bt1+£nUP'D'F:'pT:RT' :at:fwttAl:fHt:"pb~*,cs:8r-:¥//e***'Rtic:-hF-i'tE:R :, |
| | * 1 |
| | *,* 7* 8 9 FACILITY . . . . ... ~ET:l~D ~;* . . . **. *... . . (S£it f.JTAUlGi5"<;1~£'t:_'/)80 STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EID 7 B 9 |
| | ~J l-Gl*9 10 . |
| | I~ 12I 13 NA 44 U3J 45 J\11-l 4-6-----------:------'80 I |
| | FORM OF . |
| | ACTIVITY |
| * CONTENT RELEASED | | * CONTENT RELEASED |
| * OF RELEASE AMOUNT OF ACTIVITY E.EI lZJ l.Zl IL--_ ___;._Ni..,;,_1-1 __ ___. LOCATION OF RELEASE Nil 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER. . TYPE DESCRiPTION jdlOIOI 7 9,9 11 lKJ NA 12 . 13 80 ., . PERSONNEL -INJURIES NUMBER DESCRIPTION | | * OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE E.EI lZJ l.Zl IL--_ ___;._Ni..,;,_1-1_ ____. |
| * EEllOIOIDI 7 . B 9 11 12 80 OFFSITE CONSEQUENCES }v/1 , .. 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE . DESCRIPTION lZ.J NA 7 a g _______ PUBLICITY Em /\/11 7 B 9 80 ADDITIONAL FACTORS E@ 7 B 9 M 80 | | 44 Nil 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER. . TYPE DESCRiPTION |
| ,)J EVENT DESCRIPTION (Continued) to be operable, as were the Unit-2 LPCI, core spray, and CCSW systems.. Since* the Vnit-3 diesel generator was out of service at the time, all fuel movements were suspended on Unit-3, which was in a refueling_outage, The diesel generator was manually shut down, This is not a repetitive occurrence, CA.USE DESPCRIPTION (Continued) The rectifier failure evidently resulted in damage to, a* unit. in the circuit. Both were replaced, and the Unit 2/3'' tliesei genera'tor successfully tested and returned to service. Modification requests. have been initiated. t.o replace the rect_ifiers on all three diesel generators with physically large'!-unfrs that have higher voltage ratings. Installation of these higher capacity units will a §atisfactdry long-terin corrective action. | | ~ jdlOIOI lKJ NA 7 9,9 11 12 . 13 80 PERSONNEL -INJURIES NUMBER DESCRIPTION |
| * The rectifiers are model 300U80 selenium components manufactured by International Rectifier. | | * EEllOIOIDI ,___-~N_A~*~~~~~~~~~~~~~~~~~~~.,.--~ |
| }} | | 7 . B 9 11 12 80 OFFSITE CONSEQUENCES |
| | ~ }v/1 , .. |
| | 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE . DESCRIPTION 7~J a glZ.J 1~0_,_;..;_ NA_______ -'-------~-------------"-'-----'----------;:'::'.00 PUBLICITY 7 |
| | Em B 9 |
| | /\/11 80 ADDITIONAL FACTORS E@ M 7 B 9 80 |
| | |
| | ,)J EVENT DESCRIPTION (Continued) to be operable, as were the Unit-2 LPCI, core spray, and CCSW systems.. Since* |
| | the Vnit-3 diesel generator was out of service at the time, all fuel movements were suspended on Unit-3, which was in a refueling_outage, The diesel generator was manually shut down, This is not a repetitive occurrence, (50~237/1976-62} |
| | CA.USE DESPCRIPTION (Continued) |
| | The rectifier failure evidently resulted in damage to, a* s~milar unit. in the circuit. Both were replaced, and the Unit 2/3'' tliesei genera'tor ~a~ successfully tested and returned to service. |
| | Modification requests. have been initiated. t.o replace the rect_ifiers on all three diesel generators with physically large'!- unfrs that have higher voltage ratings. Installation of these higher capacity units will provid~ a §atisfactdry long-terin corrective action. |
| | * The rectifiers are model 300U80 selenium components manufactured by International Rectifier.}} |
LER 76-062-00 for Dresden, Units 2 and 3 Re Upon Completion of Routine Diesel Generator Surveillance Testing, Control Switch Was Placed in the Stop Position, Generator Output Subsequently Became Erratic, Generator Voltage Began Oscillating.| ML17252B482 |
| Person / Time |
|---|
| Site: |
Dresden  |
|---|
| Issue date: |
10/29/1976 |
|---|
| From: |
Stephenson B
Commonwealth Edison Co |
|---|
| To: |
James Keppler
NRC/RGN-III |
|---|
| References |
|---|
| BBS LTR 76-757 LER 76-062-00 |
| Download: ML17252B482 (3) |
|
|
|---|
Category:Letter
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2024-02-02
[Table view]
Category:Licensee Event Report (LER)
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05000249/LER-2015-0012016-01-22022 January 2016
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LER 89-029-05, Dresden Unit 2, Elevated HPCI Discharge Piping Temperature Due to Reactor Feedwater System Back Leakage
ML17252B5391981-06-10010 June 1981
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ML17252B5411981-06-0808 June 1981
LER 81-030/01T-0 for Dresden, Unit 2 Re Operator Noticed the HPCI Steam Line Was Cold and Filled with Water. the HPCI System Was Declared Inoperable
ML17252B5401981-06-0505 June 1981
LER 81-024/03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue
ML17252B5271981-06-0303 June 1981
LER 81-023/03L-0 for Dresden, Unit 2 Re While Running HPCI Pump Test, the Operator Observed Torus Wide Range Level Instrument Reading 0 Inches and Narrow Range Level Instrument Reading, About - 2 Inches and Oscillating
ML17252B5281981-04-14014 April 1981
LER 81-015/03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1
ML17252B5291981-03-23023 March 1981
LER 81-011-03L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered Safe
ML17252B5301981-02-20020 February 1981
LER 81-080/031-0 for Dresden, Unit 2 Re Abnormal Degradation of Systems Other than Those Specified in Item B.1.e Above Designed to Contain Radioactive Material Resulting from the Fission Process
ML17252B5321981-02-17017 February 1981
LER 81-070/03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip
ML17252B5331981-02-0202 February 1981
LER 81-020/03L-0 for Dresden, Unit 2 Re During Refueling Outage LPCI Test Spray Valve Failed to Shut Electrically, One Set of Thermal Contacts Would Not Reset
ML17252B5341981-01-23023 January 1981
LER 80-049/03L-0 for Dresden, Unit 2 Re at Completion of Secondary Containment Leak Rate Test the Reactor Building Ventilation Isolation Valve 2A-5742 Would Not Open
ML17252B5351981-01-23023 January 1981
LER 80-050/03L-0 for Dresden, Unit 2 Re the 1501-62D Pressure Switch Actuated at 44.2 Inches of Water Increasing, Tech. Spec. Limit Is Less than or Equal to 41.6 Inches of Water Increasing
ML17252B5371980-12-30030 December 1980
LER 80-046-00 for Dresden 2 Regarding a Failure to Receive CRD Volume During a Reactor Scram
ML17252B5361980-12-29029 December 1980
LER 80-046/03L-0 for Dresden, Unit 2 Re Conditions Leading to on Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation
ML17252B5381980-12-0303 December 1980
LER 80-043/03L-0 for Dresden, Unit 2 Re Surveillance Testing of the Condenser Low Vacuum Switches, Pressure Switch 2-503D Was Found to Have a Trip Point of 22.85 Inches Hg
ML17252B5421980-11-12012 November 1980
LER 80-042/03L-0 for Dresden, Units 2 and 3 Re That Technical Staff Personnel Revealed That the Ultrasonic Testing of the Scram Discharge Volume Was Not Performed During the 1500-2300 Shift
ML17252B5431980-11-12012 November 1980
LER 80-041/03L-0 for Dresden, Unit 2 Re Reactor Building Vent and Refueling Floor Rad Monitor Surveillance (DCP 2007-12) Was Performed
ML17252B1841980-10-31031 October 1980
LER 80-40/01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open
ML17252B5441980-10-29029 October 1980
LER 80-039/03X-1 for Dresden, Unit 2 Re HPCI Inboard Steam Supply Valve Opened and Had a Dual Light Indication
ML17252B5451980-10-23023 October 1980
LER 79-017-01X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety
ML17252B5461980-10-0808 October 1980
LER 80-016/01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line
ML17252B5471980-10-0707 October 1980
LER 80-036/03L-0 for Dresden, Unit 2 Re Discovery That the Six Month Functional Test Required by Tech. Spec. 4.12.A.1 of the Cardox System Heat Detectors Was Not Performed within the Allowable Surveillance Interval
ML17252B5481980-10-0101 October 1980
LER 80-033/03L-0 for Dresden, Unit 2 Re the Frequency of Water Addition to the Torus Increased. Leak Rate Tests Indicated a Leak in the 2B LPCI Heat Exchanger
ML17252B1861980-08-22022 August 1980
LER 80-032/03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block
ML17252B5501980-08-19019 August 1980
LER 80-027/03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator
ML17252B5161980-08-14014 August 1980
LER 80-024/03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d
ML17252B1881980-08-0404 August 1980
LER 80-030/03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds
ML17252B1911980-06-13013 June 1980
LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches
ML17252B1901980-06-13013 June 1980
LER 80-023/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches
ML17252B1921980-06-10010 June 1980
LER 80-025/03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1
ML17252B5521980-06-0505 June 1980
LER 80-017/03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close
ML17252B1931980-06-0303 June 1980
LER 80-002/03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close
ML17252B5531980-05-27027 May 1980
LER 80-015/03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance
ML17252B1941980-05-27027 May 1980
LER 80-022/03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125
ML17252B1951980-05-0808 May 1980
LER 80-021/01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operability
ML17252B1961980-04-29029 April 1980
LER 80-017/03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start
2020-05-14
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Text
..
Commonv.rah Edison Dresde.1 Nucle~ower Station
..... R.R. # *,
Morris, Illinois 60450 Telepho;ie 815/942-2920 BBS Ltr. 1176-757 October *29, 1976 Mr. James G.. Keppler, Regional Director Directorate of Reg'ulatory Operations - Region III U. S. Nuclear Regulatory Commission 799 :Roosevelt Road Glen Ellyn, Illinois 60137
REFERENCES:
Docket No. 50-237 Doc~et No. 50-249 Enclosed please find Reportable Occurrence report number 50-237/1976-62.
This report iS bein~ submitted to your off iCe in accordance with the Dresden Nuclear Po~er Station Technical Specifications, Section 6.6.B.
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L-i('~ B. B. Stephenson fr Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc: Director of Inspection &.Enforcement Director of Management* information & Program Control
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LICENSEE EVENT REPDF9 CONrROL Bl:OCK: .....
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1 6 LICENSEE LICENSE EVENT NAME ucrnsr NUMBER TYPE TYPE
@E] IIILIDIRISl~I 10101-10101019101-10101 l-4ltlilllfl 10131 7 8 9 14 15 25 26 30 31 32 REPORT RE PC RT CATEGORY TYPE. SOURCE DOCKl;T NU.MOER EVENT DATE REPORT DATE
'@E]coNT I I. I lbJ U::J Io I s I o L- Io I2 I 3 17J 101q 13lo17ll. I I/ IOl;Ll~l?l&.1 7 ' B 57 58 59 60 . 61 68 69 74 75 80 EVENT DESCRIPTION
@Ifil I UPON CoMP}..E.TtDN OF RoUT1N£ UN1 T ').._h Dr ~S£k GEN£RA-fop___ SuRycr L.IJCINcf: I*
7 8 9 . . . 80 f
@faLJTEST1NG:, TH£ CONTROL.. S0v1TcH WA~ 'P).._P,CC:::D IN TH:G".STOP pos1T10N. .f 7 B 9 80 lo148 9I THC 6-ENERAToR 7 . . .
OUT PU/ SVBSE. QUE:NTLY B~Cfim£ ERR.41/C.. THE G-EIVE"RATOR-80 I
lol51 !VOLTAGE .BE.Gr-,f'J 7 .* 8 g* .
osc1 L/..:..AT/NG-, AND THE AC AND De CURRENT f'l'lCTE Rs 80 I
[Q]B] I WC.NT OF"F.;.SCAL£. TH£ uN1T-~ DIESEi- G-ENE.RAToR. WAS 1wir1£DfAT£J,,Y vc=~1F1E_D I 7 8 9 PR:ME (St:E' .'\ITAOISD Si-IEE.T) . 80 SYSTEM CAUSE COMPONENT COMPONENT ,
COOE CODE COMPONENT CCJOE SUPPUEn MANUFACTURER VIOLATION 7
@01£1£1 l[J 8 9 10 11 12 1£1.NIGlllNIEI 17 lAJ 43 44 IWI01lll71 47 w 48 CAUSE DESCRIPTION lolel .f-:n-4£ 1>1£$EJ_ Gi=.NERATOR.. Mf!J...FUNcn oN RESUt..IED [Rom A SHORTED SEJ....ENIVM
- 7. 8 9 . . . . . 80 lolsl !"i?f:CTIFIER. IN 1H£ GENER.ATOR. 1-1£&.D CIRCUIT, THE SHORT WflS. APPM~.ENT/.._y*
- '<1;:~'.'.'il!@l'.:'~rc:110~E'.i{:1.:ttv:,>A~/~RAV0Ae'(~Bt1+£nUP'D'F:'pT:RT' :at:fwttAl:fHt:"pb~*,cs:8r-:¥//e***'Rtic:-hF-i'tE:R :,
- ,* 7* 8 9 FACILITY . . . . ... ~ET:l~D ~;* . . . **. *... . . (S£it f.JTAUlGi5"<;1~£'t:_'/)80 STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EID 7 B 9
~J l-Gl*9 10 .
I~ 12I 13 NA 44 U3J 45 J\11-l 4-6-----------:------'80 I
FORM OF .
ACTIVITY
- OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE E.EI lZJ l.Zl IL--_ ___;._Ni..,;,_1-1_ ____.
44 Nil 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER. . TYPE DESCRiPTION
~ jdlOIOI lKJ NA 7 9,9 11 12 . 13 80 PERSONNEL -INJURIES NUMBER DESCRIPTION
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7 . B 9 11 12 80 OFFSITE CONSEQUENCES
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7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE . DESCRIPTION 7~J a glZ.J 1~0_,_;..;_ NA_______ -'-------~-------------"-'-----'----------;:'::'.00 PUBLICITY 7
Em B 9
/\/11 80 ADDITIONAL FACTORS E@ M 7 B 9 80
,)J EVENT DESCRIPTION (Continued) to be operable, as were the Unit-2 LPCI, core spray, and CCSW systems.. Since*
the Vnit-3 diesel generator was out of service at the time, all fuel movements were suspended on Unit-3, which was in a refueling_outage, The diesel generator was manually shut down, This is not a repetitive occurrence, (50~237/1976-62}
CA.USE DESPCRIPTION (Continued)
The rectifier failure evidently resulted in damage to, a* s~milar unit. in the circuit. Both were replaced, and the Unit 2/3 tliesei genera'tor ~a~ successfully tested and returned to service.
Modification requests. have been initiated. t.o replace the rect_ifiers on all three diesel generators with physically large'!- unfrs that have higher voltage ratings. Installation of these higher capacity units will provid~ a §atisfactdry long-terin corrective action.