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#REDIRECT [[05000280/LER-1987-037, :on 871203,emergency Diesel Generator 3 Automatically Started.Caused by Blown Fuse & Failed Relay. Undervoltage Relay 59 ABC-1J1 & Dc Control Fuse Replaced.W/]]
| number = ML18152A711
| issue date = 12/22/1987
| title = LER 87-037-00:on 871203,emergency Diesel Generator 3 Automatically Started.Caused by Blown Fuse & Failed Relay. Undervoltage Relay 59 ABC-1J1 & Dc Control Fuse Replaced.W/ 871222 Ltr
| author name = Benson D
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =
| addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
| docket = 05000280
| license number =
| contact person =
| document report number = 87-041, 87-41, LER-87-037, LER-87-37, NUDOCS 8712310232
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 4
}}
 
=Text=
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NRC Form 386 19,831 e                                                                                                          e                                                    POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION 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 NUMBER    kt    REVISION NUMBER MONTH                      DAY                    YEAR              FACILITY NAMES                                DOCKET NUMBERISI 01s1010,0 1                                  I          I 1    I2      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                                                        &sect;:  /CMci< ono o, more of rhe follow,ngJ 1111 POWER MOOE 191 I 11 N
20.4021b) 20.40511)11Jli)                      --                20.405(cl II0.381cll1 I
:x  50.7311)12)(;vl S0.7311112)1v)                                --    73.711b) 73.711cl LEVEL 110)                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 15      I  7 1-13                I      11814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC-        REPORTABLE              :*.::::: :::::::,:.:: ::::::::: :.,.:/}:                                                            MANUFAC.          REPORTABLE CAUSE      SYSTEM        COMPONENT TURER          TO NPRDS                        :.:,:.,.:,: *:-:;::: :;:::,:,:::::: CAUSE      SYSTEM        COMPONENT TURER                        rnr***:***tt:::::::*            :::::::::::::::::
:;::::::;: :,:::::: :,:,::::::::::                                                                            TO NPRDS      :::::::::::::::::::::::::::::: ::::::,:::;:::,:,:
:/) :{}\ ><
I          I    I    I              I  I    I                                      \)}              << I                            I            I    I    I                  I    I    I l****:*:*:i!ii/::::.,;;*/;;7:):f:)ii:::*
:;.:/*:*:':.; . ><)
I          I I I                      I I      I                                                                                        I            I I        I                  I    I    I                                                  ..  ** ... * .*.
t*****;*i*:::***1*;***1:1:.**;;::*;1:***1****.*i****
SUPPLEMENTAL REPORT EXPECTED 1141                                                                                                                                  MONTH              DAY                  YEAR EXPECTED Fxi SUBMISSION h          YES (If yo,. compllro EXPECrED SUBMISSION DArEt                                                                        NO DATE 1151 I                  I                      I ABSTRACT (Umir          ro 1400 s,,.c*s. i., .. *ppro1tim*r11y fifrHn singl1-spact1 rvp1wrirtt1n lint1s} 1161 On December 3, 1987, at 0928 hours, 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 hours, the alarms cleared. At 0946 hours, EDG #3 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 #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 hours 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 hours. 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 hours.
8712310232 871222 PIIR AIIOCK 05000280                                                                                                                                                                                          -_j s                                              DCII
                                                                                                                                                                                                                                        ~
NRC Form 386
!fl f!j I
 
a
----------......;~----------....Z~---~---.                                e                                . . . .---~~=~
U.I INCLIAII IIIOULATOIIY COIIM. . 10,W LICENSEE EVENT REPORT ILERI TEXT CONTINUATION                              All'PIIIOYIO Otill OfO JI IO..OIC>*
IJINII. 1/Jlla
**en.in -  111 DOCKI T INIIIIII 111          LIii ._.._Ill Ill                        ,ao1    111 Surry Power Station, Units l & 2 o 11 1o 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 hours, 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 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} 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 hours 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 hours.
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.
 
POW 28-06-01
    ~,
IIIIC , _ _ _ .
e                                        e            U.I. liUCLUII IIIQULATOIIY COMMIDION LICENSEE EVENT REPORT (LERI TEXT CONTINUATION                        A"IIOVID OMI 110. ltllO..()I~
IXl'IIIH: 1/llta PACILITY IIAMI 111                                    DOCKIT liUMIIII IJI                                            PAOI Ill Surry Power Station, Units 1 & 2 I
TIJCT ,,, _ _ ,,.....,... ---11/tC  ,a,.,,.-,..,, 1171 0  16 IO IO IO 12 I 81 0 8 17 - 0 13  7 -      0  p      O 13 OF O      I3
: 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
                                        *None required.
7.0      Similar Events None.
8.0        Manufacturer/Model Number General Electric/125LV llAlA.
NIIICPOIIM-lfGI
 
e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 316 Surry, Virginie 23883 December 22, 1987 U.S. Nuclear Regulatory Commission                    Serial No.:            87-041 Document Control Desk                                Docket No.:            50-280 016 Phillips Building                                                        50-281 Washington, D.C. 20555                                Licensee No.:          DPR-32 DPR-37 Gentlemen:
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}}

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