ML18152A711: Difference between revisions
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Emergency Diesel Generator 43 (EDG) {EIIS-DG} | Emergency Diesel Generator 43 (EDG) {EIIS-DG} | ||
automatically started, which is an engineered safety feature actuation. | automatically started, which is an engineered safety feature actuation. | ||
At 0930 hours, the alarms cleared. At 0946 hours, EOG 43 was placed in its cooldown cycle. At 0950 hours, it was returned to the automatic mode. At 0954 hours, the alarm for Bus lJ undervoltage was received and the 43 EOG auto-started again and was manually.loaded onto lJ Bus. 2.0 Safety Consequences and Implications The i3 EOG is designed to supply power to either the Unit 1 (lJ) emergency bus or the Unit 2 (2J) emergency bus. During this event, the *3 EOG was paralleled and loaded tn the lJ emergency bus. During this time, *3 EI)(:, remained capable of supplying power to Unit 2 (2J) emergency bus. Therefore, the health and safety of the public were not affected. | At 0930 hours, the alarms cleared. At 0946 hours, EOG 43 was placed in its cooldown cycle. At 0950 hours, it was returned to the automatic mode. At 0954 hours, the alarm for Bus lJ undervoltage was received and the 43 EOG auto-started again and was manually.loaded onto lJ Bus. 2.0 Safety Consequences and Implications The i3 EOG is designed to supply power to either the Unit 1 (lJ) emergency bus or the Unit 2 (2J) emergency bus. During this event, the *3 EOG was paralleled and loaded tn the lJ emergency bus. During this time, *3 EI)(:, remained capable of supplying power to Unit 2 (2J) emergency bus. Therefore, the health and safety of the public were not affected. | ||
3.0 cause The cause of the auto-start of i3 EOG was a blown DC fuse {EIIS-FU} | |||
The cause of the auto-start of i3 EOG was a blown DC fuse {EIIS-FU} | |||
in the degraded voltage_circuit. | in the degraded voltage_circuit. | ||
Relay {EIIS-59} | Relay {EIIS-59} | ||
| Line 61: | Line 59: | ||
---11/tC ,a,.,,.-,..,, 1171 lfGI 5. 0 Additional Corrective Ac ti.on ( s) The overvoltage relay 59 .ABC~lJl, and the DC control fuse were replaced and the circuit was returned to normal. The *3 EDG was stopped and placed in automatic at 1655 hours. 6.0 Action(s) | ---11/tC ,a,.,,.-,..,, 1171 lfGI 5. 0 Additional Corrective Ac ti.on ( s) The overvoltage relay 59 .ABC~lJl, and the DC control fuse were replaced and the circuit was returned to normal. The *3 EDG was stopped and placed in automatic at 1655 hours. 6.0 Action(s) | ||
Taken to Prevent Recurrence | Taken to Prevent Recurrence | ||
*None required. | *None required. | ||
7.0 Similar Events None. 8.0 Manufacturer/Model Number General Electric/125LV llAlA. - | |||
Events None. 8.0 Manufacturer/Model Number General Electric/125LV llAlA. - | |||
.> .. December 22, 1987 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen: | .> .. December 22, 1987 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen: | ||
e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 316 Surry, Virginie 23883 Serial No.: 87-041 Docket No.: 50-280 50-281 Licensee No.: DPR-32 DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1 and Unit 2. REPORT NUMBER 87-037-00 This report has been reviewed by*the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control. Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323}} | e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 316 Surry, Virginie 23883 Serial No.: 87-041 Docket No.: 50-280 50-281 Licensee No.: DPR-32 DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1 and Unit 2. REPORT NUMBER 87-037-00 This report has been reviewed by*the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control. Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323}} | ||
Revision as of 09:31, 5 May 2019
| ML18152A711 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 12/22/1987 |
| From: | BENSON D L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-041, 87-41, LER-87-037, LER-87-37, NUDOCS 8712310232 | |
| Download: ML18152A711 (4) | |
Text
- ..,.,*,.,,r.
e e POW 28-06-01 NRC Form 386 U.S. NUCLEAR REGULATORY COMMISSION 19,831 APPROVED 0MB NO. 3150-0104 LICENSEE EVENT REPORT (LERI EXPIRES: 8/31/88 FACILITY NAME 11 l I DOCKET NUMBER 121 I PAGE 131 Surry Power Station, Unit 1 and Unit 2 o I s I o I o I o 12 18 1 ol , loF nl~ TITLE 141 Emergency Diesel Generator Auto-Start Due to Failed Relay and Blown Fuse EVENT DATE ISi LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR 1:::::/ SEQUENTIAL kt REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI NUMBER NUMBER 01s1010,0 1 I I 1 I 2 013 8 7 81 7 -o I 3'7 -o I o 1 I 2 212 81 7 o,s,o,o,o, I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: /CMci< ono o, more of rhe follow,ngJ 1111 MOOE 191 N 20.4021b) 20.405(cl
- x 50.7311)12)(;vl 73.711b) -,__ -POWER 20.40511)11Jli)
II0.381cll1 I S0.7311112)1v) 73.711cl LEVEL ,.._ -,__ -110) I 11 o,o 20.405(1)11l(i1)
II0.3S(cll2l l50.73(11(2)(vii) 0TH ER (Specify 1n Absrr*cr ..........
--b*low and in Tur. NRC Form lilllllttllli 20.40511ll1lliiil 50.73(1)(2)(il 60,7311112llviiillAI 366A/ ---20.405111!1lliv) l50.7311112lliil II0.7311) (Z)(viii) 1Bl ---20.405111(1 )Iv) 50.7311ll2lliii) 50.73(1)(211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE David L. Benson, Station Manager 81 o, 4 3 1 5 I 7 1 -13 I 11814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 REPORTABLE
- .::::: :::::::,:.::
- .,.:/}: MANUFAC. REPORTABLE rnr***:***tt:::::::*
- ':':::::::::*:*
MANUFAC-:::::::::::::::::
CAUSE SYSTEM COMPONENT TURER TO NPRDS :.:,:.,.:,:
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CAUSE SYSTEM COMPONENT TURER TO NPRDS :;::::::;:
- ,:::::: :,:,::::::::::
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- /) :{}\ >< l****:*:*:i!ii/::::.,;;*/;;7:):f:)ii:::*
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I I I I I I I :;.:/*:*:':.;
.. ><) I I I I I I .. ** ... * .*. SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR Fxi EXPECTED SUBMISSION h YES (If yo,. compllro EXPECrED SUBMISSION DArEt DATE 1151 I I I NO ABSTRACT (Umir ro 1400 s,,.c*s. i., .. *ppro1tim*r11y fifrHn singl1-spact1 rvp1wrirtt1n lint1s} 1161 On December 3, 1987, at 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br />, with Unit 1 and Unit 2 at 100% power, Bus lJ undervoltage alarm (EIIS-ANN) and Bus lJ overvoltage alarm (EIIS-ANN) were received, Operations personnel observed that the main station battery (EIIS-BTRY) ground lights flickered.
Emergency Diesel Generat*or
- 3 (EDG) (EIIS-DG) automatically started, which is an engineered safety feature actuation.
At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, the alarms cleared. At 0946 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.59953e-4 months <br />, EDG #3 was placed in its cooldown cycle, At 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, it was returned to the automatic mode. At 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br />, the alarm for Bus lJ undervoltage was received, and the #3 EDG auto-started again and was manually loaded onto lJ Bus. The cause of the auto-start of 113 EDG was a blown DC fuse (EIIS-FU) in the degraded voltage circuit. Relay (EIIS-59) 59 ABC-lJl, the overvoltage relay surge capacitor, failed and shorted to the relay case. This caused the positive DC fuse in the degraded voltage circuit to blow. The first auto-start of #3 EDG at 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br /> was due to the arcing of the surge capacitor with the relay case. When the surge capacitor failed and flashed to ground, DC power was lost, causing the undervoltage signal and the auto-start of the diesel at 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br />. The undervoltage relay 59 ABC-lJl and the DC control fuse were replaced, and the circuit was returned to normal, The #3 EDG was stopped and placed in automatic at 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />. 8712310232 871222 PIIR AIIOCK 05000280 -_j s DCII NRC Form 386 !fl f!j I a e ----------......;~----------....Z~---~---
........ ---~~=~ U.I INCLIAII IIIOULATOIIY COIIM .. 10,W LICENSEE EVENT REPORT ILERI TEXT CONTINUATION
- en.in -111 DOCKI T INIIIIII 111 LIii ._.._Ill Ill All'PIIIOYIO Otill OfO JI IO..OIC>*
IJINII. 1/Jlla ,ao1 111 Surry Power Station, Units l & 2 o 11 1 o Io Io 12 I SI o a 17 -o 13 I 7 -01 o o 12 oF o I 3 TIXT,, _ -* _... --.. IIIIIC ,,.,_ _.'al 1171 1.0 Description of the Event On December 3, 1987, at 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br />, with Units 1 and Unit 2 at 100\ power, Bus lJ undervoltage alarm {EIIS-ANN}
and Bus lJ overvoltage alarm {EIIS-ANN}
were received.
Operations personnel observed that the main station battery {EIIS-BTRY}
ground *lights flickered.
Emergency Diesel Generator 43 (EDG) {EIIS-DG}
automatically started, which is an engineered safety feature actuation.
At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, the alarms cleared. At 0946 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.59953e-4 months <br />, EOG 43 was placed in its cooldown cycle. At 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, it was returned to the automatic mode. At 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br />, the alarm for Bus lJ undervoltage was received and the 43 EOG auto-started again and was manually.loaded onto lJ Bus. 2.0 Safety Consequences and Implications The i3 EOG is designed to supply power to either the Unit 1 (lJ) emergency bus or the Unit 2 (2J) emergency bus. During this event, the *3 EOG was paralleled and loaded tn the lJ emergency bus. During this time, *3 EI)(:, remained capable of supplying power to Unit 2 (2J) emergency bus. Therefore, the health and safety of the public were not affected.
3.0 cause The cause of the auto-start of i3 EOG was a blown DC fuse {EIIS-FU}
in the degraded voltage_circuit.
Relay {EIIS-59}
59 ABC-lJl, the overvoltage relay surge capacitor, failed and shorted to the relay case. This caused the positive DC fuse in the degraded voltage circuit to blow. The first auto-start of 13 EDG at 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br /> was due to the arcing of the surge capacitor with the relay case. When the surge capacitor failed and flashed to ground, DC power was lost, causing the undervoltage signal and the auto-start of the diesel at 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br />. 4.0 Immediate Corrective Action The inunediate corrective actions included paralleling EOG 13 with lJ emergency bus's normal supply and loading the diesel onto the bus.
.. IIIIC ,___. ~, PACILITY IIAMI 111 e e LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKIT liUMIIII IJI '*'.:,*. POW 28-06-01 U.I. liUCLUII IIIQULATOIIY COMMIDION A"IIOVID OMI 110. ltllO..()I~
IXl'IIIH:
1/llta PAOI Ill Surry Power Station, Units 1 & 2 0 16 IO IO IO 12 I 81 0 8 17 -0 13 I 7 -0 p O 13 OF O I 3 TIJCT ,,, __ ,,.....,...
---11/tC ,a,.,,.-,..,, 1171 lfGI 5. 0 Additional Corrective Ac ti.on ( s) The overvoltage relay 59 .ABC~lJl, and the DC control fuse were replaced and the circuit was returned to normal. The *3 EDG was stopped and placed in automatic at 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />. 6.0 Action(s)
Taken to Prevent Recurrence
- None required.
7.0 Similar Events None. 8.0 Manufacturer/Model Number General Electric/125LV llAlA. -
.> .. December 22, 1987 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen:
e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 316 Surry, Virginie 23883 Serial No.: 87-041 Docket No.: 50-280 50-281 Licensee No.: DPR-32 DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1 and Unit 2. REPORT NUMBER 87-037-00 This report has been reviewed by*the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control. Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323