Similar Documents at Salem |
|---|
|
LER-1979-029, /03L-0 on 790320:during Channel Functional Test High Voltage Was Found to Be Low.Caused by Breakdown of Diode in High Voltage Power Supply.Diode Was Replaced & Channel Functional Was Completed |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2721979029R03 - NRC Website |
|
text
Report Number:
79-29/03L Report Date:
4/19/79 Occurrence Date:
3/20/79 Facility:
Salem Generating Station Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Inoperable Nuclear Instrumentation Channel N-41 CONDITIONS PRIOR TO OCCURRENCE:
Operational Mode 1 Reactor Power 97%
DESCRIPTION OF OCCURRENCE:
While performing a functional test of power range nuclear instrumen-tation channel N-41, the high voltage was found to be 240 volts less than required.
Technical Specification 3.3.1.1 Action Statement 2 was implemented at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> and channel bistables were placed in the tripped condition.
The channel was repaired and returned to service at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> after the functional test was satisfactorily completed.
The Action Statement was terminated when the channel was returned to service.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
This occurrence was caus~d by the breakdown of a diode in the high voltage power supply.
ANALYSIS OF OCCURRENCE:
Technical Specification 3.3.1.l Action 2 requires that with the nuni-ber of operable channels one less than the total number of channels, startup and/or power operation may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within one hour.
b.
The minimum channels operable requirement is met; however, one additional channel may be bypassed for up to two hours for surveillance testing per Specification 4.3.1.1.
c.
Either thermal power is restricted to < 75% of rated thermal and the power range, neutron flux trip setpoint is reduced to
< 85% of rated thermal power within four hours; or, the quad-rant power tilt ratio is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
79042403~S
~---
LER 79-29/03L The channel bistables were immediately placed in the tripped condition.
The channel was returned to service within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 25 minutes, therefore, Q.P.T.R. monitoring was not required.
CORRECTIVE ACTION
The diode was replaced and the functional test was completed satisfac-torily to verify channel operability.
FAILURE DATA:
Not Applicable Prepared By A. W. Kapple Manager -
SaJem Gnerating Station SORC Meeting No.
27-79
NRC,,!=OR¥~,!i l7!7J)-
U.S. NUCLEAR REGULATURY COMMISSION LICENSEE EVENT REPORT e CONTROL BLOCK: I I.
1 G)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1
6
~
I N IJ I s I G I s I 1 101 o I o I - I o I o I o I o I o I - I o I o 101 4 I 1 I 1 I i I 1 101 I I 0 7
8 9
L.ICENSEE CODE 14 15 L.ICSNSE NUMBER 25 26 L.ICENSE TYPE JO 57 CAT 58
- ~~~~~ L1J©I o l s I 01 o I o 12 I 7 I 2 101 o 13 I 2 lo I 119 IG)I o 14 111 91 7 I 9 IG) 60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I During normal operation, while performing a channel functional test on N.I.
[£llJ I power range channel N-41, the high voltage was found to be low.
T/S 3.3.1.1 Action 2
!)))) I was implemented and the channel bistables were placed in the tripped condition.
The l:2:ill I channel was repaired and the functional satisfactorily completed within three hours
[£:()) ! and 25 minutes at which time the Action Statement was terminated.
Tnis is the second
[§JI]
occurrence of this type.
CE:ID 7
8 9 80 [ill]
7 8
SYSTSM CODE Ir I Al@
9 10
/;":;"\\
L.ER'RO CVENTYEAR
~
REPORT I 7 I 9 I NUMBER 21 22
CAUSE
CAUSE CODE SUBCODE COMPONENT CODE LI]@ Lgj@ II I N!s I TIR I u1@
11 12 13 1a*
SEQUENTIAL.
OCCURRENCE REPORT NO.
CODE I I Io I 2 I 9j I......-1 I o I 3 I 23 24 26 27 28 29 COMP.
SUBCODE u:J@
19 REPORT TYPE UJ JO VALVE SUBCODE l£J@
20 l=l 31 PRIME COMP.
REVISIOl't NC. w 32 COMPONENT TAKEN ° ACTION ON PLANT METHOD HOURS SUBMITTED FORM ~UB.
ACTION. FUTURE EFFECT SHUTOOWN
~
ATTACHMENT NPR04 StIPP.LlER MANUFACTURER l!!..J@
43 44 47 l!!J@W@ UJ@
L£J@
I o Io I o I I l!J@ t2:U
36 37 40 41 42 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l P I 31 2 13 I 2s l This occurrence was caused by the breakdown of a diode in the high voltage power cr:IIJ I supply.
The diode was replaced and the channel functional was completed satisfactorily o::IIJ I to verify channel operability.
ITEJ 1
a 9 FACILITY
/3Q\\
STATUS
~POWER OTHER STATUS \\:::;:J ITTIJ ~
I 0 I 91 7 !@I~
---'N_.../...-A~ _
a 9
to 12 11 ACTIVITY CONTENT
~
REL.EASED OF REL.EASE AMOUNT OF ACTIVITY DJI] w@) WI N/A 7
8 9
10 1 t PERSONNEL EXPOSURES
~
NUMBER
~TYPE
DESCRIPTION
DJJ] I ol o I olW N/A 1
a 9 11 12 1-3-----------------------------------------------------------------.....,...------a~o 7
ao METHOO OF DISCOVERY DESCRIPTlON OISCOVERY
~@I Functional Test 44 45 46 80 L.OCATION OF RSL.EASC: @
NL'.A 44 45 so PERSONNEL. INJURIES t:;;'\\
NUMBER DESCRIPTION~
[2TIJ I 0 I 0 I 0 I@
N A a s 11
~12-------------=<-=--------------------------------------------------------------a-'o LOSS OF OR DAMAGE TO FACIL.ITY ~
TYP'i:
DESCRIPTION
'l:::::J ITE w@
N A 8
9 10 so PUBLICITY
(.";;\\
SE ISSUED~ DESCRIPTION~
NRC U ONLY ITI2:] Lz.Jei N/A I I I I I I I I I I l I J 1
a 9
- 1... o ________________..__..,... ________________________________
~ss 69
- o NAMEOFPREPAR~R---------A
.-:::::w::::::.==K=a~p~p~l __ e __ """"'.:=...'.~
PH aN e: _..(..... 6...
o::9~) =3..... 6 s
... -=1
.... 0
..... 0
..... 0-.......s-...a=l::E!!l::::....:::x-O:cM* t,
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000272/LER-1979-001-03, /03L-0 on 790102:during Normal Operation,The No 12 Containment Fan Coil Unit Shifted to Slow Speed,But No Indication of Svc Water Flow Was Noted.Caused by Burned Out Coil in Solenoid SV-624,supplying Control Air for 12SW223 | /03L-0 on 790102:during Normal Operation,The No 12 Containment Fan Coil Unit Shifted to Slow Speed,But No Indication of Svc Water Flow Was Noted.Caused by Burned Out Coil in Solenoid SV-624,supplying Control Air for 12SW223 | | | 05000272/LER-1979-001, Supplemental LER 79-001/03X-1:on 790102,during Normal Operations,Containment Fan Coil 12 Shifted to Slow Speed. Operator Noticed No Indication of Svc Waterflow.Caused by Burned Out Coil in Solenoid Valve SV-624.Coil Replaced | Supplemental LER 79-001/03X-1:on 790102,during Normal Operations,Containment Fan Coil 12 Shifted to Slow Speed. Operator Noticed No Indication of Svc Waterflow.Caused by Burned Out Coil in Solenoid Valve SV-624.Coil Replaced | | | 05000272/LER-1979-002-03, /03L-0 on 790103:excessive Leak Rate in W1 100 Air Lock Noted.Doors Were Reworked & Airlock Returned to Operation.Seals Failed Due to Split at Vulcanized Seam. Door Seals Were Replaced | /03L-0 on 790103:excessive Leak Rate in W1 100 Air Lock Noted.Doors Were Reworked & Airlock Returned to Operation.Seals Failed Due to Split at Vulcanized Seam. Door Seals Were Replaced | | | 05000272/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000272/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000272/LER-1979-003-03, /03L-0 on 790103:containment Pressure Exceeded Tech Spec Max.Caused by Isolation of Pressure/Vacuum Relief System for Rework of 1CV6 | /03L-0 on 790103:containment Pressure Exceeded Tech Spec Max.Caused by Isolation of Pressure/Vacuum Relief System for Rework of 1CV6 | | | 05000272/LER-1979-004, Forwards Updated LER 79-004/03X-1 | Forwards Updated LER 79-004/03X-1 | | | 05000272/LER-1979-004-03, /03L-0 on 790103:Loop 4 Channel IV Was 100 Psi Too High.Caused by Steam Pressure Transmitter Being Frozen by an Outside Air Damper Directing Cold Air Onto the Sensing Lines | /03L-0 on 790103:Loop 4 Channel IV Was 100 Psi Too High.Caused by Steam Pressure Transmitter Being Frozen by an Outside Air Damper Directing Cold Air Onto the Sensing Lines | | | 05000272/LER-1979-005-03, /03L-0 on 790104:during Normal Operations,Position Indication for Rod 2D5 Began Oscillating.Rod Position within 12 Steps of Bank D.Caused Traced to Rod Indication Coil Stack on Reactor.Repairs Planned for Next Reactor Outage | /03L-0 on 790104:during Normal Operations,Position Indication for Rod 2D5 Began Oscillating.Rod Position within 12 Steps of Bank D.Caused Traced to Rod Indication Coil Stack on Reactor.Repairs Planned for Next Reactor Outage | | | 05000272/LER-1979-005, Supplemental LER 79-05L/03X-1:on 790104,during Normal Operation,Individual Rod Position Indication for Rod 2D5 Began Oscillating.Cause Could Not Be Identified.Connectors Checked & RPI Coil Stack Replaced | Supplemental LER 79-05L/03X-1:on 790104,during Normal Operation,Individual Rod Position Indication for Rod 2D5 Began Oscillating.Cause Could Not Be Identified.Connectors Checked & RPI Coil Stack Replaced | | | 05000272/LER-1979-006-03, /03L-0 on 790102:inservice Insp Data Packages Not Being Reviewed.Cause Was Lack of Administrative Control to Correlate Responsibilities of Two Station Depts.Dept Review Procedures Have Been Rewritten | /03L-0 on 790102:inservice Insp Data Packages Not Being Reviewed.Cause Was Lack of Administrative Control to Correlate Responsibilities of Two Station Depts.Dept Review Procedures Have Been Rewritten | | | 05000272/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000272/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000272/LER-1979-007-03, /03L-0 on 790126:while Performing Channel Check of Pressurizer Level,Channel II Found 5% Lower than Others. Caused by Instrument Drift Resulting in Zero Shift in Transmitter Output | /03L-0 on 790126:while Performing Channel Check of Pressurizer Level,Channel II Found 5% Lower than Others. Caused by Instrument Drift Resulting in Zero Shift in Transmitter Output | | | 05000272/LER-1979-008-03, /03L-0 on 790111:during Normal Operation While Refilling Boric Acid Storage Tanks,Operator Added Improper Batch of Acid to Tanks & Pumped Concentrates Tank to Storage Tanks.Caused by Personnel Error | /03L-0 on 790111:during Normal Operation While Refilling Boric Acid Storage Tanks,Operator Added Improper Batch of Acid to Tanks & Pumped Concentrates Tank to Storage Tanks.Caused by Personnel Error | | | 05000272/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000272/LER-1979-009-03, /03L-0 on 790112:No 13 Auxiliary Bldg Exhaust Fan Removed from Svc to Replace Motor.Caused by Worn Keyway in Drive Motor Shaft | /03L-0 on 790112:No 13 Auxiliary Bldg Exhaust Fan Removed from Svc to Replace Motor.Caused by Worn Keyway in Drive Motor Shaft | | | 05000272/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000272/LER-1979-011, Forwards LER 79-011/01X-2 | Forwards LER 79-011/01X-2 | | | 05000272/LER-1979-011-01, /01X-2 on 790116:RMS Channel Which Had Alarmed & Cleared Had Been Reset at Control Console But Not at RMS Panel.Caused by Procedure Inadequacy.Procedure Changed Initiated to Clarify Functions | /01X-2 on 790116:RMS Channel Which Had Alarmed & Cleared Had Been Reset at Control Console But Not at RMS Panel.Caused by Procedure Inadequacy.Procedure Changed Initiated to Clarify Functions | | | 05000272/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000272/LER-1979-012-03, /03L-0 on 790115:No 11 Steam Generator Steam Flow Channel II Failed Low.No Cause Found.Operator Took Manual Control & re-established Steam Generator Level.Channel Indication Normalized within 10 Minutes | /03L-0 on 790115:No 11 Steam Generator Steam Flow Channel II Failed Low.No Cause Found.Operator Took Manual Control & re-established Steam Generator Level.Channel Indication Normalized within 10 Minutes | | | 05000272/LER-1979-013-04, /04L on 790102:non-radioactive Waste Effluent Total Suspended Solids Exceeded Tech Specs.Caused by Abnormally High Number of Demineralized Regenerations Supporting Initial Flushes for Startup Preparation | /04L on 790102:non-radioactive Waste Effluent Total Suspended Solids Exceeded Tech Specs.Caused by Abnormally High Number of Demineralized Regenerations Supporting Initial Flushes for Startup Preparation | | | 05000272/LER-1979-013, Supplemental LER 79-013/04X-1:on 790102,during Preparation of Annual Nonradioactive Environ Operating Rept,Average 1978 Suspended Solids Concentrate in Discharge Exceeded Limit. Caused by Abnormally High Demineralizer Regenerat | Supplemental LER 79-013/04X-1:on 790102,during Preparation of Annual Nonradioactive Environ Operating Rept,Average 1978 Suspended Solids Concentrate in Discharge Exceeded Limit. Caused by Abnormally High Demineralizer Regenerations | | | 05000272/LER-1979-014-03, /03L-0 on 790220:during Normal Operation,Radiation Monitoring Sys Channel 1R 12B Alarms Found Not Operating. Channel Later Returned to Svc & Operated Properly.Caused by Unknown Factor | /03L-0 on 790220:during Normal Operation,Radiation Monitoring Sys Channel 1R 12B Alarms Found Not Operating. Channel Later Returned to Svc & Operated Properly.Caused by Unknown Factor | | | 05000272/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000272/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000272/LER-1979-015-03, /03L-0 on 790212:during Normal Operation,Noted Required Surveillance to Be Performed Every 78-h Had Not Been Done on 790210 When Scheduled.Caused by Personnel Error.Entry Made in Log Instructing Supervisor | /03L-0 on 790212:during Normal Operation,Noted Required Surveillance to Be Performed Every 78-h Had Not Been Done on 790210 When Scheduled.Caused by Personnel Error.Entry Made in Log Instructing Supervisor | | | 05000272/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000272/LER-1979-016-03, /03L-0 on 790220:control Operator Observed Zero Svc Water Flow Through Unit.Caused by Burned Out Coil in Solenoid Valve.Coil Replaced | /03L-0 on 790220:control Operator Observed Zero Svc Water Flow Through Unit.Caused by Burned Out Coil in Solenoid Valve.Coil Replaced | | | 05000272/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000272/LER-1979-017-03, /03L-0 on 790219:gross Activity Surveillance of Coolant Sys & Steam Generators Was Not Performed.Caused by Personnel Error in Not Returning Gas Bottles to Storage.New Bottle Storage Pad Will Be Built | /03L-0 on 790219:gross Activity Surveillance of Coolant Sys & Steam Generators Was Not Performed.Caused by Personnel Error in Not Returning Gas Bottles to Storage.New Bottle Storage Pad Will Be Built | | | 05000272/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000272/LER-1979-018-03, /03L-0 on 790223:auxiliary Feedwater Pump Breaker Cubicle Was Hot.Caused by Burned Out Closing Spring Charging Motor.Motor & Breaker Replaced | /03L-0 on 790223:auxiliary Feedwater Pump Breaker Cubicle Was Hot.Caused by Burned Out Closing Spring Charging Motor.Motor & Breaker Replaced | | | 05000272/LER-1979-020-03, /03L-0 on 790225:pressurizer Level Channel II Was Declared Inoperable.Caused by non-linearity of Strain Gauge in Level Sensor Transmitter.Strain Gauge Replaced Along W/ Zero & Span Potentiometers.Transmitter Recalibrated | /03L-0 on 790225:pressurizer Level Channel II Was Declared Inoperable.Caused by non-linearity of Strain Gauge in Level Sensor Transmitter.Strain Gauge Replaced Along W/ Zero & Span Potentiometers.Transmitter Recalibrated | | | 05000272/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000272/LER-1979-021-03, /03L-0 on 790302:overhead Annuciators in Control Room Alarmed,Indicating Power Range Nuclear Instrumentation Channel Failure.Caused by Failure of N41 Channel High Voltage Power Supply.Failed Power Supply Replaced | /03L-0 on 790302:overhead Annuciators in Control Room Alarmed,Indicating Power Range Nuclear Instrumentation Channel Failure.Caused by Failure of N41 Channel High Voltage Power Supply.Failed Power Supply Replaced | | | 05000272/LER-1979-022-03, /03L-0 on 790221:during Normal Operations,While Conducting Routine Insp,Nrc Inspector Found Missed Tech Spec Surveillance Reading.Caused by Personnel Error.Surveillance Posted on Plant Status Board | /03L-0 on 790221:during Normal Operations,While Conducting Routine Insp,Nrc Inspector Found Missed Tech Spec Surveillance Reading.Caused by Personnel Error.Surveillance Posted on Plant Status Board | | | 05000272/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000272/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000272/LER-1979-024-03, /03L-0 on 790313:air Particulate Monitor Was Declared Inoperable.Caused by Failing Motor Bearings Which Led Filter Paper Drive to Slow & Activate Failed Filter Alarm.Motor Was Cleaned & Bearing Replaced | /03L-0 on 790313:air Particulate Monitor Was Declared Inoperable.Caused by Failing Motor Bearings Which Led Filter Paper Drive to Slow & Activate Failed Filter Alarm.Motor Was Cleaned & Bearing Replaced | | | 05000272/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000272/LER-1979-025-03, /03L-0 on 790315:during Normal Operation on 790302,retest Not Performed After 790302 Maint on Chilled Water Pump 11.Caused by Personnel Error.Procedure Reviewed & Rewritten | /03L-0 on 790315:during Normal Operation on 790302,retest Not Performed After 790302 Maint on Chilled Water Pump 11.Caused by Personnel Error.Procedure Reviewed & Rewritten | | | 05000272/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000272/LER-1979-026-03, /03L-0 on 790318:No 13 Reactor Coolant Loop Protection Channel III Inoperable.Caused by Faulty Channel Summator Module.Summator Was Replaced | /03L-0 on 790318:No 13 Reactor Coolant Loop Protection Channel III Inoperable.Caused by Faulty Channel Summator Module.Summator Was Replaced | | | 05000272/LER-1979-027-01, /01X-1 on 790325:while Providing Backup Protection to Hope Creek,Facility Fresh Water Tanks Were Below Tech Spec Required Levels.Caused by Poor Communications Between Facilities.Water Level Restored | /01X-1 on 790325:while Providing Backup Protection to Hope Creek,Facility Fresh Water Tanks Were Below Tech Spec Required Levels.Caused by Poor Communications Between Facilities.Water Level Restored | | | 05000272/LER-1979-027, Forwards LER 79-027/01X-1 | Forwards LER 79-027/01X-1 | | | 05000272/LER-1979-028, Has Been Voided | Has Been Voided | | | 05000272/LER-1979-029-03, /03L-0 on 790320:during Channel Functional Test High Voltage Was Found to Be Low.Caused by Breakdown of Diode in High Voltage Power Supply.Diode Was Replaced & Channel Functional Was Completed | /03L-0 on 790320:during Channel Functional Test High Voltage Was Found to Be Low.Caused by Breakdown of Diode in High Voltage Power Supply.Diode Was Replaced & Channel Functional Was Completed | | | 05000272/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | |
|