/03L-0:on 780914,gas Turbine Tripped While Output Voltage Being Adjusted.Caused by Faulty Gas Generator Speed Switch 3A in Electronic Controls| ML20147F628 |
| Person / Time |
|---|
| Site: |
Millstone  |
|---|
| Issue date: |
10/12/1978 |
|---|
| From: |
Young R NORTHEAST UTILITIES |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20147F625 |
List: |
|---|
| References |
|---|
| LER-78-021-03L, LER-78-21-3L, NUDOCS 7810200072 |
| Download: ML20147F628 (1) |
|
LER-1978-021, /03L-0:on 780914,gas Turbine Tripped While Output Voltage Being Adjusted.Caused by Faulty Gas Generator Speed Switch 3A in Electronic Controls |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2451978021R03 - NRC Website |
|
text
'
~
~
MUsNEELGVEi.T MWUWV
\\.
dbNTRotOLoCK:
l l
l 1
l Ih (PLEASE PRINT OH TYPE ALL REQUIRED INFORMATION) l @ hl [0 TG } Cf TI Ml N l SI1 l@l 0 l 0 l I O l0 l01010__l In In l@l4 l 1 l.Ll 1 l _1 l@l l
i
}
8 9 LICENSEE COOL I4 16 LICENSt NuusER 22 26 LICENSE TYPE JO 57 car 58 con'1 lOlil
, ', " ' l L'l@l 015 l 01010121415 l@l019 ll - 14 17 la l@l i l n l l l p l 7 I A l@
l "C
}
3 60 6l DOCKE' JUMBER 68 69 EVEf4T DATg 74 75 R E POR T D AT E 80 EyENT DESCnlPTioN AND POOS ABLC (,NSEoVENCES h [O_L2J l On September 14, 1978, at 2 l 00 ho~u rs. thil.e Retforclin.g ro u t i no c urvn i l l a nf n. tha li g l gas turbine tripped.uile the output voltage was__beina adiustad.
The gas turbine 1
[O i.tj l was removed from service and the required surveillances were begun (T.S 4.5.F.M.
- Oi3j [ While testing the Core Spray System, a leaking flange gasket was detected on Core
'll IO Ic i i Spray 'A' System.
(R0-78-21/3L) ll 10 l 7] l 1
I O l s_J l l) d S
DE 10191 1 ElDElg ;S Elg l 8 Ej g l I lIP'P$NE"T l kE C
SB C
SU'E E l U [g j lg "[Zj g l
l 7
8 9
to 11 12 13 18 19 20 SE OVE N TI AL OCCURRENCE REFORT REVISION LE RiRO EVENT YE AH REPORT NO.
CODE TYPE N O.
@,agg L7 18 I l-l 10 12 11I l/l 10 13 I ILl
[-j
, [0_l
, 21 27 23 24 26 27 25 29 30 31 32 TA f AC f
O PL NT
! TH HOURS 22 SE IT FOR1 8.
SU PLI MA F TURER I C lgl4Dl@'l Zl@
lZ l@
l0l0l0l0l l Yl@
lY l@
lN l@
lR111615lq 33.
3 35 30 31 40 di 42 43 44 47
.CAUSE DCSCRIPTION AND CORRECTIVE ACTIONS h [i [ o j [ Investigation revealed that the trip was caused by a faulty aas aenerator soeed I'
li li ] [ switch 3A, in an electronic control.
The electronic control waJ replaced and the I
[ q 7) { gas turbine was tested and declared operable Sept. 16,1978 at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />.
The I
g, l 33 l leaking core spray flange gasket was replaced with a flexitallic.
I 11141 1 I
7 8 9 80 ST S
% POWE R OTHER STATUS ISCOV RY DISCOVERY OESCRIPTION I
l.3J@l Routine Surveillance l
itis 1 LEj @ ll 10 l0 l @l_
NA
~
ACitVITY
'CO TENT RILE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE I 1 I c l L.Z.] @ [Z_J@l
'NA l
l NA I
7 8 9 10 44 45 80 PlRSON'4EL f xFOSunES NUMBER TYPE DESCe<lPTION
.li lil l o l o.l o l@l Z l@l 1:
,ERSONNEL,N,U,',ES OE,CnieriO~@
~ui. eE R NA' l,
[Ll_>LJ.l0]0l_0l@l 0
8 ii
,2
'15 "fSs#,'!JNo '^c" @
~
E Z
NA l
L,LL1] L jg[
8 9
.,0 0
P"'n'ISCni,riON @
NRC USE ONW q
MIiSSYiU@l NA I
LJ_1 I I I I I I I I I I
~ '
- DTIdio**7A 2$3-47;1792X475 Rel@h fL has Jr.
- - g g
{
Attachment to LER 78-21/3L Northeast Nuclear Energy Company Millstone Nuclear Power Station, Unit 1 Provisional License Number DPR-21 Docket Number 50-245 j
IDENTIFICATION OF OCCURRENCE:
The gas turbine generator output breaker inadvertently tripped during surveillance.
CONDITIONS PRIOR TO OCCURRENCE:
j Prior to the occurrence, the unit was operating at a steady state
'l power level of 100 percent.
DESCRIPTION OF OCCURRENCE:
~
On September 14,1978, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, while performing routine surveillance, the gas turbine tripped while the output voltage was being adjusted.
Investigation at the gas turbine local control panel revealed an " exciter trouble / power loss" and a " gas generator overspeed alarm."
The gas turbine generator was removed from service and the required surveillance for Automatic Pressure Relief Subsystem, low pressure cooling and a containment cooling was started in accordance with' Technical Specification 4.5.F.3.
While testing the Core Spray System a leaking flange gasket was detected on the Core Spray "A" System.
APPARENT CAUSE OF OCCURRENCE:
1 An investigation was initiated which revealed that the gas turbine trip was caused by a faulty gas generator speed switch.
Limit j
3A, overspeed was found to have a decreasing trip point as the circuitry temperature increase'd.
All other speed limits including the 3B overspded circuit, functioned properly.
ANALYSIS OF OCCURRENCE:
The gas turbine is 01.1 of two emergency power supplies that are utilized for Engineered Safeguard Systems.
The loss of the gas turbine we..uld mean the loss of the feedwater Coolant Injection System, one loop of the low pressure Coolant Injection System and one loop of the Core Spray System. The entire spectrum of accidents has been analyzed with respect to, the loss of either power supply and has been found acceptable.
At the time of the occurrence, during which the gas turbine was inoperable, the other emergency power supply was operable.
9
%n a
=
L 4
4 4
Attachment to LER'78-21/3L - Page 2
, i CORRECT!VE ACTION:
After the inspection of the electronic control associated with the gas generator speed switch,.it was decided to replace the electronic control containing the. limit 3A switch.
The spare electronic control was installed and, tested satisfactorily.
The
- - gas turbin'e was tested, returned to service, and declared operational at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, September ~16,1978.
The electronic control that was replaced was manufactured by the l
- - Reliance Electric Company, Model No. 927-01-031.
All speed switches will be tested for temperature e.ffect and improved ventilation will be provided.
Additionally, the previously
- - j mentioned core-spray leaking flange gaske* was replaced with a flexitallic gasket.
si 9
e
(
l
\\
i j
I s
e e
w.
4 6
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000336/LER-1978-014, Forwards LER 78-014/03L-0 | Forwards LER 78-014/03L-0 | | | 05000336/LER-1978-014-03, /03L-0 on 780617:while Performing Monthly Control Element Assembly Surveillance Testing,Assembly 2 Dropped to Zero Steps from 178 Steps.No Component Failures Causing Control Element Assembly to Drop | /03L-0 on 780617:while Performing Monthly Control Element Assembly Surveillance Testing,Assembly 2 Dropped to Zero Steps from 178 Steps.No Component Failures Causing Control Element Assembly to Drop | | | 05000245/LER-1978-018-03, /03L-0 on 780905:during Surveillance on Vessel Level Instru,It Was Found That 1 of the 4 Reactor low-low Water Level Switches Was Nonfunctional,Due to Mech Hangup Caused by Dry Lubrication | /03L-0 on 780905:during Surveillance on Vessel Level Instru,It Was Found That 1 of the 4 Reactor low-low Water Level Switches Was Nonfunctional,Due to Mech Hangup Caused by Dry Lubrication | | | 05000245/LER-1978-018, Forwards LER 78-018/03L-0 | Forwards LER 78-018/03L-0 | | | 05000336/LER-1978-019-03, /03X-2 on 780803:while Operating 13U Diesel for Surveillance,Leaking Injector Pump Observed.Caused by Elemental Lead Inclusions,Resulting in Stress Risers at Surface of Valve Cages | /03X-2 on 780803:while Operating 13U Diesel for Surveillance,Leaking Injector Pump Observed.Caused by Elemental Lead Inclusions,Resulting in Stress Risers at Surface of Valve Cages | | | 05000336/LER-1978-019, Forwards LER 78-019/03X-2 | Forwards LER 78-019/03X-2 | | | 05000245/LER-1978-021-03, /03L-0:on 780914,gas Turbine Tripped While Output Voltage Being Adjusted.Caused by Faulty Gas Generator Speed Switch 3A in Electronic Controls | /03L-0:on 780914,gas Turbine Tripped While Output Voltage Being Adjusted.Caused by Faulty Gas Generator Speed Switch 3A in Electronic Controls | | | 05000336/LER-1978-021-03, /03L-0:on 780827,during Steady State Operation, Plant Computer Experienced Malfunction W/Spare Annunciator Point & Was Taken Out of Svc.Caused by Improper Installation of Spare Photodarlington Optical Isolator ILCA2-55 | /03L-0:on 780827,during Steady State Operation, Plant Computer Experienced Malfunction W/Spare Annunciator Point & Was Taken Out of Svc.Caused by Improper Installation of Spare Photodarlington Optical Isolator ILCA2-55 | | | 05000245/LER-1978-021, Forwards LER 78-021/03L-0 | Forwards LER 78-021/03L-0 | | | 05000336/LER-1978-022-03, /03L-0 on 780906:Loss of Methyl Iodide Removal Efficiency for a Ebfs Train. Cause Unknown | /03L-0 on 780906:Loss of Methyl Iodide Removal Efficiency for a Ebfs Train. Cause Unknown | | | 05000336/LER-1978-022, Forwards LER 78-022/03l-0 | Forwards LER 78-022/03l-0 | | | 05000336/LER-1978-023-03, /03L-0 on 780912:during Routine steady-state Operation,Spent Fuel Storage Ventilation Gaseous Radiation Monitor Failed Low.Caused by Shorted Local Alarm Horn Which Blew Power Supply Fuse.Horn Disconnected & Fuse Replaced | /03L-0 on 780912:during Routine steady-state Operation,Spent Fuel Storage Ventilation Gaseous Radiation Monitor Failed Low.Caused by Shorted Local Alarm Horn Which Blew Power Supply Fuse.Horn Disconnected & Fuse Replaced | | | 05000336/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | | 05000245/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | | 05000336/LER-1978-024-03, /03L-0 on 781004:during Surveillance Testing, Setpoint for Reactor Protec Sys Reactor Coolant Low Flow Trip on Channel B Was Out of Spec.Setpoint Was Readjusted. Rev Will Req Low Flow Trip Unit Setpoint Be Reset | /03L-0 on 781004:during Surveillance Testing, Setpoint for Reactor Protec Sys Reactor Coolant Low Flow Trip on Channel B Was Out of Spec.Setpoint Was Readjusted. Rev Will Req Low Flow Trip Unit Setpoint Be Reset | | | 05000336/LER-1978-024, Forwards LER 78-024/03L-0 | Forwards LER 78-024/03L-0 | | | 05000336/LER-1978-025-03, /03L-0 on 781007:daily Tech Spec 4.3.1.1.1.,Table 4.3-1,items 2.a & 2.b,Nuc Pwr Surveillance & Delta-T Pwr Channel Calibr Not Performed Due to Personnel Error. Supervisors Told to Perform Req Surveillance | /03L-0 on 781007:daily Tech Spec 4.3.1.1.1.,Table 4.3-1,items 2.a & 2.b,Nuc Pwr Surveillance & Delta-T Pwr Channel Calibr Not Performed Due to Personnel Error. Supervisors Told to Perform Req Surveillance | | | 05000336/LER-1978-025, Forwards LER 78-025/03L-0 | Forwards LER 78-025/03L-0 | | | 05000336/LER-1978-026, Forwards LER 78-026/03L-0 | Forwards LER 78-026/03L-0 | | | 05000336/LER-1978-026-03, /03L-0 on 781025:Analysis of Instru Installations Revealed That Two Transmitters Assoc W/Channel a Steam Generator Low Water Lever Were non-seismically Mounted. Channel a SG Was Bypassed.Seismic Brackets Will Be Used | /03L-0 on 781025:Analysis of Instru Installations Revealed That Two Transmitters Assoc W/Channel a Steam Generator Low Water Lever Were non-seismically Mounted. Channel a SG Was Bypassed.Seismic Brackets Will Be Used | | | 05000336/LER-1978-027-03, /03L-0 on 781024:plant Computer Malfunction Caused CEA Pulse Counting Position to Be in Oper.Cause of Computer Failure Could Not Be Traced | /03L-0 on 781024:plant Computer Malfunction Caused CEA Pulse Counting Position to Be in Oper.Cause of Computer Failure Could Not Be Traced | | | 05000336/LER-1978-027, Forwards LER 78-27/03L-0 | Forwards LER 78-27/03L-0 | | | 05000336/LER-1978-028-03, /03L-0 on 781115:spent Fuel Pool(Sfp)Ventilation Particulate & Gaseous Setpoints Exceeded Tech Specs Setpoints of Table 3.3-6,items 2.c & 2.d.Caused by Monitor Recalibr W/O Taking Into Account Tech Spec Limit | /03L-0 on 781115:spent Fuel Pool(Sfp)Ventilation Particulate & Gaseous Setpoints Exceeded Tech Specs Setpoints of Table 3.3-6,items 2.c & 2.d.Caused by Monitor Recalibr W/O Taking Into Account Tech Spec Limit | | | 05000336/LER-1978-028, Forwards LER 78-028/03L-0 | Forwards LER 78-028/03L-0 | | | 05000336/LER-1978-029-03, /03L-0 on 781025:during Oper,Surveillance Test on Channel a Reactor Protec Sys Core Protec Calculator Reveated Sys Ground Traced to Signal for Pressurizer Pressure W/In Containment Boundary.Source Not Known at This Time | /03L-0 on 781025:during Oper,Surveillance Test on Channel a Reactor Protec Sys Core Protec Calculator Reveated Sys Ground Traced to Signal for Pressurizer Pressure W/In Containment Boundary.Source Not Known at This Time | | | 05000336/LER-1978-029, Forwards LER 78-029/03L-0 | Forwards LER 78-029/03L-0 | | | 05000336/LER-1978-030, Forwards LER 78-030/03L-0 | Forwards LER 78-030/03L-0 | | | 05000245/LER-1978-030-03, /03L-0 on 781215:suppression Chamber Oxygen Concentration Was Too High Due to a Slow Nitrogen Purge Rate.Personnel Were Reminded to Monitor Parameters | /03L-0 on 781215:suppression Chamber Oxygen Concentration Was Too High Due to a Slow Nitrogen Purge Rate.Personnel Were Reminded to Monitor Parameters | | | 05000245/LER-1978-030, Forwards LER 78-030/03L-0 | Forwards LER 78-030/03L-0 | | | 05000336/LER-1978-030-03, /03L-0:on 781106 CEA 63 in Regulating Group 3 Reed Switch Position Indicator Channel Inoperable.Caused by Intermittent Open in the Reed Switch Assembly Power Supply Lead Which Produced Erratic Indication | /03L-0:on 781106 CEA 63 in Regulating Group 3 Reed Switch Position Indicator Channel Inoperable.Caused by Intermittent Open in the Reed Switch Assembly Power Supply Lead Which Produced Erratic Indication | | | 05000245/LER-1978-031-03, /03L-0 on 781218:during Nuclear Review Board Audit a Surveillance Requirement (Reduced High Flux Prior to Startup) Was Found Unaccomplished Since Its Introduction. Caused by Procedural Error | /03L-0 on 781218:during Nuclear Review Board Audit a Surveillance Requirement (Reduced High Flux Prior to Startup) Was Found Unaccomplished Since Its Introduction. Caused by Procedural Error | | | 05000245/LER-1978-031, Forwards LER 78-031/03L-0 | Forwards LER 78-031/03L-0 | | | 05000336/LER-1978-031, Forwards LER 78-031/03L-0 | Forwards LER 78-031/03L-0 | | | 05000336/LER-1978-031-03, /03L-0:on 781107 C Reactor Bldg Closed Cooling Water Temp Was Found Low Due to Failed Svc Water Temp Control Valve Shear Pin Connecting Actuator to Valve. Caused by Sheared Tension Pin | /03L-0:on 781107 C Reactor Bldg Closed Cooling Water Temp Was Found Low Due to Failed Svc Water Temp Control Valve Shear Pin Connecting Actuator to Valve. Caused by Sheared Tension Pin | | | 05000245/LER-1978-032-03, /03L-0 on 781227:diesel Fire Pump Fuel Oil Sample Surveillance Inadvertently Overlooked During Routine Survey of Completed Surveillances.Not on Surveillance Schedule. Subsequently Added to Schedule | /03L-0 on 781227:diesel Fire Pump Fuel Oil Sample Surveillance Inadvertently Overlooked During Routine Survey of Completed Surveillances.Not on Surveillance Schedule. Subsequently Added to Schedule | | | 05000245/LER-1978-032, Forwards LER 78-032/03L-0 | Forwards LER 78-032/03L-0 | | | 05000336/LER-1978-032, Forwards LER 78-032/03L-0 | Forwards LER 78-032/03L-0 | | | 05000336/LER-1978-032-03, /03L-0 on 781130:Channel B Reactor Protect Sys Core Protection Calculator Positive 18 Volt Logic Power Supply Failed.Caused by Normal Aging of a Capacitor in the Auxiliary Rectifier Circuit | /03L-0 on 781130:Channel B Reactor Protect Sys Core Protection Calculator Positive 18 Volt Logic Power Supply Failed.Caused by Normal Aging of a Capacitor in the Auxiliary Rectifier Circuit | | | 05000336/LER-1978-033-03, /03L-0 on 781205:while Operating 12U Diesel for Surveillance,Low Cooling Water Flow Alarm Received.Caused by Shells in the Heat Exhanger | /03L-0 on 781205:while Operating 12U Diesel for Surveillance,Low Cooling Water Flow Alarm Received.Caused by Shells in the Heat Exhanger | | | 05000336/LER-1978-033, Forwards LER 78-033/03L-0 | Forwards LER 78-033/03L-0 | | | 05000336/LER-1978-034, Forwards LER 78-034/03L-0 | Forwards LER 78-034/03L-0 | | | 05000336/LER-1978-034-03, /03L-0 on 781227:during Surveillance,Svc Water Isolation Valve 2-SW-3.2A Failed to Close.Caused by Actuating Air Flow Being Blocked | /03L-0 on 781227:during Surveillance,Svc Water Isolation Valve 2-SW-3.2A Failed to Close.Caused by Actuating Air Flow Being Blocked | |
|