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gC CEIZRATED D1 BUTION DEMONSTRATIO.'i SYSTEM S
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REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
ACCESSION NBR-8908040189 DOC.DATE: 89/07/27 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH.NAME AUTHOR AFFILIATION SHRXVER,T.D.
Arizona Public Service Co. (formerly Arizona Nuclear Power HAYNES,J.G.
Arizona Public Service Co. (formerly Arizona Nuclear Power RECXP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 89-001-01:on 890103,ESF actuation caused by loss of power to Class 1E 4.6 kv busses.
W/8 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR 3 ENCLL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Standardized plant.
05000529 RECIPIENT ID CODE/NAME PD5 LA CHAN,T INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7
NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSIR/EIB RGN5 FILE 01 EXTERNAL EGGG WILLIAMSE S L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A NOTES COPIES LTTR ENCL 1
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RECIPXENT ID CODE/NAME PD5 PD DAVIS,M.
ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP IRM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB '9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 NRQJ3REP/RPB 10 EG 02 SfD
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1 D-NOIE 'IO ALL "RIDS" RECIPIENIS'LEASE HELP US TO'EDUCE HASTE!
CCNI'ACT 'IHE DOCGMENI'ONTROL DESK, ROCN 'Pl-37 (EXT; 20079)
TO EIaIM2QQPE %3GR NME PBCH DISTRIBUTXQN, LZSTS FOR DOCl2&MIS YOU DCHiT NEEDt FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 45 ENCL 44
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I
Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P 0 BOX 52034
~
PHOENIX, ARIZONA85072-2034 192-00503-JGH/TDS/JEM July 27, 1989 U.
S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C.
20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No.
STN 50-529 (License NPF-51)
Licensee Event.Report 89-001-01 File:
89-020-404 Attached please find Supplement Number 1 to Licensee Event Report (LER) No.
~ 89-001-00 prepared and submitted pursuant to the requirements of 10CFR 50.73.
In accordance with 10CFR 50.73(d),
we are herewith forwarding a copy of this report to the Regional Administrator of,the Region V Office.
If you have any questions, please contact T. D..Shriver, Compliance Manager at (602) 393-2521.
Very truly yours,
//
. i/ii/i"~v' J.
G.
Haynes Vice President'uclear Production JGH/TDS/JEM/kj Attachment cc:
W.
F.
Conway D.
B. Karner E.
E.
Van Brunt, Jr.
J.
B. Martin T. J. Polich M. J.
Davis A. C.
Gehr INPO Records Center (all w/a)
f
NRC Form 345'94L)
I LICENSEE EVENT REPORT ILER)
US. NUCLEAR REOULATOAYCOMMISSION APPROVEO OMS NO. 3(500104 EXPIAESI SI31ISS FACILITYNAME l1)
DOCKET NUMSEA l2)
PA Pal o Verde Unit 2 TITLE (4) 05000529>oF06 ESF Actuation Caused by Loss of Power to Class lE 4. 16 kv Busses EVENT DATE (SI LER NUMSER IS)
REPORT DATE (7l O'THER FACILITIESINVOLVED(SI MONTH OAY 010 3
YEAR 8
9 YEAR 8
9 SEDUENTIAL pose NVMSEII 0 01 MONTH OAY YEAR NVMSER 010 72 78 9
N/A N/A FACILITYNAMES DOCKET NUMSERIS) 0 5
0 0
0 0
5 0
0 0
OPERATINO MODE (~I 1
POWE R LEYEL 1
0 0 e
3 b
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THIS AEPOR'7 IS SUSMITTED PURSUANT TO THE REDUIREMENTS OF 10 CFR gr IChnh one or more or the IPIIo~'npi (11) 73.71(bl 73.71(cl OTHER (Specify In Apttrett INipvrend In Test, HIICForm dddAI NAME Timothy D. Shriver, Compliance Manager TELEPHONE NVMSER AREA CODE 60 239 3-2521, COMPLE'TE ONE LINE FOR EACH COMPONENT FAILURE OESCAISEO IN THIS REPORT (13)
CAUSE
SYSTEM E A COMPONENT X F,MR MANUFAC TUREA W1 20 Y
- jYjgj%ai%4$
COMPONENT MANUFAC.
TURER EPOATASLE TO NPRDS i(s((rgb)@iAG@oY~
SUPPLEMENTAL AEPOAT EXPECTED (14)
MONTH DAY YEAR YES IIIyn, comprere fXPfCyfDSVSMISSIDH DAyfl X
No EXPECTED SVSMISSION DATE (15)
ASSTRACT ILimrt to 1400 rpetn. Ie., epprorimenly Mreen IInpre reeve rypelvrrtren irnnI (14)
At 1940 MST on January 3,
- 1989, Palo Verde Unit 2 was in Mode 1
(POWER OPERATION) at approximately 100 percent power when a total loss of offsite power to the class lE 4. 16 kv busses 2E-PBA-S03 and 2E-PBB-S04 occurred.
The loss of power (LOP) to busses 2E-PBA-S03 and 2E-PBB-S04 generated an Engineered Safety Features (ESF) signal which automatically started both "A" and HBR Diesel Generators.
The diesel generators started satisfactorily and assumed the loads on the 4. 16 kv class 1E busses.
At approximately 1959 MST on January 3,
1989 a Notification of. Unusual Event (NUE) was declared due to the loss of both offsite power sources to the in-plant class lE busses.
The NUE was terminated at approximately 1648 MST on January 4,
1989 after offsite power was restored to one of the class lE 4. 16 kv busses.
The loss of power (LOP) was caused by a reduced impulse withstand voltage rating due to rain saturation of contamination on the ESF transformer
- bushings, and a possible ground potential rise attributed to lightning in the area.
This allowed a fault to initialize at the ESF transformer bushings.
The contamination is a build up of mineral deposits from misting of the cooling towers.
Two bushings on each transformer failed due to the fault and were replaced.
NAC Corm 344
4l
NRC Fe/es 344A 1943 I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION U.S. NUCLEAR REOULATORY COMIAISSION APPROVEO OMS NO 3150W104 EXPIRE9: 5/31/SS FACILITYNAME III OOCRET NUMSER (31 LER NUMSER ISI 5t Q V5 NTIAL NVMetm mtV/5/ON NVM441 PACE ISI Palo Verde Unit 2 TEXT ////sso/4 emcee ie tete/eme(
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DESCRIPTION
OF WHAT OCCURRED:
A.
Initial Conditions:
o so oo5 2989 00 l 01.02 oFO 6
B.
At 1940 HST on January 3,
- 1989, Palo Verde Unit 2 was in Hode 1
(POWER OPERATION) at approximately 100 percent power.
Reportable Event Description (Including Dates and Approximate Times of Major Occurrences):
Event Classification:
An event or condition that resulted in an automatic actuation of an Engineered Safety Feature (ESF)(JE).
At approximately 1940 HST on January 3,
- 1989, Palo Verde Unit 2 was in Hode 1
(POWER OPERATION) when a complete loss of offsite power to the 4. 16 kv class 1E busses (BU)(EB) 2E-PBA-S03 and 2E-PBB-S04 occurred.
The loss of power (LOP) was caused by a reduced impulse withstand voltage rating due to rain saturation of contamination on the ESF transformer
- bushings, and a possible ground potential rise attributed to lightning in the area.
This allowed a fault to initialize at the ESF transformer bushings.
The contamination is a
build up of mineral deposits from misting of the cooling towers.
ESF Service Transformer Normal Supply Breakers (BKR)(EA) 2E-NAN-S03A and 2E-NAN-S04A tripped on Instantaneous Overcurrent and Phase Differential which caused a
LOP to the class 1E busses 2E-PBA-S03 and 2E-PBB-S04.
Due to the LOP on class 1E busses 2E-PBA-S03 and 2E-PBB-S04 an ESF LOP signal was generated which load shed the busses and automatically started the RA" and RBR Emergency Diesel Generators (DG)(EK).
The DG's started and assumed the loads on 2f-PBA-S03 and 2E-PBB-S04 as designed.
Technical Specification (T.S.) Limiting Condition for Operation (LCO) 3.8. 1. 1 ACTIONs "aR and "dU were entered at 1940 HST on January 3,
1989.
The loss of both offsite power sources to the in-plant class 1E busses led to the declaration of a Notification of Unusual Event (NUE) at approximately 1959 HST on January 3,
1989 in accordance with approved Emergency Plan Implementing Procedures.
At approximately 2010 HST on January 3,
1989 the appropriate state and local agencies were notified via the Notification and Alert Network (NAN).
The Nuclear Regulatory Commission (NRC) Operations Center was notified at approximately 2034 HST on January 3,
1989 via the Emergency Notification System (ENS).
The NUE was reported in Special Report 2-89-001 on January 9,
1989.
Following the LOP load shed the Control Room Operators (utility, licensed) identified that the supply breaker for non-class 1E 480
'smg
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NRC Perrrr SSSA'445 I
LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REOULATORY COMMISSION APPROVEO OMS NO. 5150WIO(
EXPIRES: 8/ll/88 PACILI'TYNAME (11 OOCKET NUMSER tll LER NUMSER (Sl PACE (SI Palo.Verde Unit 2 TEXT /// rrrrrre ance ir t54r/15/E rrPP aANiaWNRC-foerr 8/E/ASI ((TI o
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YEAR;~
8 9
SEQVENTIAL NVM ER 0 0 1
AEVl5KIN MVMPEA
- 01. 03 OF 0 6
volt Motor Control Center (HCC)(EC)(NHN-H72) was open due to a lockout relay (86)(EA) trip.
Protective Relaying and Control (PR&C) personnel (uti,lity, non-licensed) inspected the breaker and found no tripped flags and no indication of a problem in the breaker.
The Shift Supervisor (utility, licensed) directed the operator to reset the 86 lockout and close the breaker.
The breaker closed as designed, and no additional problems were experienced with the breaker.
Troubleshooting and rework of the ESF transformers was conducted in accordance with approved work control documents.
It was identified that two bushings on each. transformer were damaged and the bushings were replaced.
The ESF transformers were not damaged.
After satisfactory completion of appropriate retests, ESF transformer 2E-NBN-X04 was energized from offsite power at approximately 1438 HST on January 4,
1989.
At approximately 1646 HST on January 4,
1989, transformer 2E-NBN-X04 was paralleled with RB" diesel generator and offsite power was restored to class IE bus 2E-PBB-S04.
At approximately 1648 HST on January 4,
1989 the NUE was terminated due,to offsite power being restored to one class IE 4. 16 kv bus.
LCO 3.8. 1. 1 ACTION RdR was then exited.
At approximately 1808 HST on January 4,
1989, transformer 2E-NBN-X03 was energized from offsite power.
At approximately 1925 HST on January 4,
1989, transformer 2E-NBN-X03 was paralleled with RA" diesel generator and offsite power was restored to class 1E bus 2E-PBA-S03.
LCO 3.8. 1. 1 ACTION RaR was then exited.
C.
The response of the Operations staff to the LOP and their subsequent recovery actions were both appropriate and timely.
There were no operator errors that contributed to the event.
Status of structures,
- systems, or components that were inoperable at the start of the event that contributed to the event:
D.
Not applicable
- - no structures,
- systems, or components were inoperable at the start of the event that contributed to the event.
Cause of each component or system failure, if known:
r The cause of the failure of the bushings was due to a reduced impulse withstand voltage rating due to rain saturation of contamination of the ESF transformer
- bushings, and a possible ground potential rise attributed to lightning in the area.
This allowed a fault to initialize at the ESF transformer bushings.
The contamination is a build up of mineral deposits from misting of the cooling towers.
'rAC / 0AM 554A IS Slr
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NRC FPNII 388A (843 I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION U.S. NUCLEAR REOULATORY COMMISSION APPROVED OM8 NO 3ISOWI04 EXPIRES.'/31/88 FACILITYNAME (II OOCXET NUMSER (3l LER NUMSER (SI PACE (SI Palo Verde Unit. 2 TEXTO'IN44 44444 (4 /4444448 444 ~ //48Ar/K/ICAr/II3(E(A'4/ (17l o
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E.
Failure mode, mechanism, and effect of each failed component, if known:
The failed bushings created a line to ground fault and caused the transformer supply breakers to trip open creating the LOP to the class lE 4.16 kv busses.
G.
For failures of components with multiple functions, list of systems or secondary functions that were also affected:
Not applicable
- - the failed bushings do not have multiple functions.
For failure that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the train was returned to service:
Not applicable
- - no safety system trains were rendered inoperable due to this event.
Method of discovery of each component or system failure or procedural error:
The failed bushings were identified during troubleshooting/rework of the ESF transformers.
I.
Cause of Event
The cause of the event, has been determined to be a reduced impulse withstand voltage rating due to rain saturation of contamination on the ESF transformer bushings, and a possible ground potential rise attributed to lightning in the area.
This allowed a fault to initialize at the ESF transformer bushings.
The contamination is a
build up of mineral deposits from misting of the cooling towers.
J.
Safety System
Response
The following safety systems actuated in response to the LOP.
These responses are in. accordance with system design.
Diesel Generators A and B
Control Room Essential Ventilation A and B
All essential battery chargers and voltage regulators re-energized.
4.
Auxiliary Feedwater Pump B
5.
Essential Cooling Water Pumps A and B
6.
Essential Spray Pond Pumps A and B
7.
Essential Chillers A and B
8.
Battery Room Essential Exhaust Fans A and B
9.
Condensate Transfer Pumps A and B
- 10. Diesel Generator Essential Ventilation Units A and B
4AC II/AM)44A l9 43 I
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NRC Form 39SA (9431 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROI/EO OMS NO, 3(50&104 EXPIRES: 8/31/88 FACILITYNAME (11 DOCKET NUMSER LTI LER NUMSER (8(
xiii SEGI/ENTIAL NUMSSR
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Palo Verde Unit 2 TEXT /// more soooe is IssFsowE oso aANiona/ HRC %%derr 3/F(A'/ (17) o so o o 52 98 9
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Failed Component Information:
The failed bushings are manufactured by Westinghouse.
and are style
¹234C115G05.
II.
ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
Throughout the event, the plant remained stable at approximately 100 percent power.
Diesel Generators A and B started and assumed all safety related loads as required.
The event did not result in any challenges to fission product barriers or result in any releases of radioacti.ve materials.
Therefore, there was no threat to the health and safety of the public.
III.
CORRECTIVE ACTIONS
A-.
Immediate:
B.
Two failed bushings on each transformer were replaced.
The transformers were inspected/tested and found not to be damaged before re-energizing them.
Action to Prevent Recurrence:
Several
corrective actions
have been or will be implemented, in all three (3)
PVNGS units, to prevent recurrence.
They include:
Installation of a drip loop on each conductor leading to the 15 kv bushings of each ESF transformer has been completed in all three PVNGS units.
The bushings on each ESF transformer in all three PVNGS units were cleaned.
Creepage extenders have been installed on the ESF transformer high side bushings in Unit 2.
In Units 1
and 3 creepage extenders have been installed on one ESF transformer and will be installed on the other ESF transformers during the present outages.
A program will be implemented for routine washing of all
- bushings, insulators and other porcelain devices subject to cooling tower drift.
This program is expected to be implemented by August 31, 1989.
IV.
PREVIOUS SIMILAR EVENTS
There have not been any previous similar events reported.
Other events reporting a
LOP to class
- 4. 16 kv busses involved various causes (i.e.,
rrlc Ir/r\\M sooA l9 93>
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NRC PoIIS 888A
/843 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION U.S. NUCLEAR REOULATORY COMMISSION APPROVEO OMS NO 3150WI04 EXPIRESI 8/SI/88 PACILI'TYNAME III OOCKET NVMSER ISI
'YEAR LER NUMSER (8) 58OUENTIAL NUM Ell II8VIS IQN NUMOSII PACE ISI Palo Verde Unit 2 TEXt ///mP/8 saece /8 /Pou/PNE IMP mAISSPN////IC'hem DRESS/ IITI o
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personnel
- error, equipment malfunction).
No previous LOP event was caused by a reduced impulse withstand voltage rating due to rain saturation of contamination on the ESF transformer bushings.
Therefore, no previous actions
.to prevent recurrence could have prevented this event.
NIIC I OEM N4A I98)<
11.
|
|---|
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| | | Reporting criterion |
|---|
| 05000529/LER-1989-001, :on 890103,total Loss of Offsite Power to Class 1E 4.16 Kv Busses 2E-PBA-S03 & 2E-PBB-S04 Occurred.Caused by Reduced Impulse Withstand Voltage Rating Due to Rain.Failed Bushings on Each Transformer Replaced |
- on 890103,total Loss of Offsite Power to Class 1E 4.16 Kv Busses 2E-PBA-S03 & 2E-PBB-S04 Occurred.Caused by Reduced Impulse Withstand Voltage Rating Due to Rain.Failed Bushings on Each Transformer Replaced
| | | 05000530/LER-1989-001, :on 890303,electrical Grid Disturbance Resulted in Main Generator Output Breakers Opening,Resulting in Reactor Power Cutback & Steam Bypass Control Sys Actuation. Caused by Malfunction in Subj Control Sys |
- on 890303,electrical Grid Disturbance Resulted in Main Generator Output Breakers Opening,Resulting in Reactor Power Cutback & Steam Bypass Control Sys Actuation. Caused by Malfunction in Subj Control Sys
| | | 05000530/LER-1989-001-02, :on 890303,electrical Grid Disturbance Resulted in Main Generator Output Breakers Opening.Caused by Malfunction in Steam Bypass Control Sys.Operations Personnel Stabilized Plant |
- on 890303,electrical Grid Disturbance Resulted in Main Generator Output Breakers Opening.Caused by Malfunction in Steam Bypass Control Sys.Operations Personnel Stabilized Plant
| 10 CFR 50.73(e)(2) | | 05000530/LER-1989-001-01, :on 890303,electrical Grid Disturbance Resulted in Opening Main Generator Output Breakers,Low Pressure Reactor Trip & Turbine Trip.Caused by Steam Bypass Control Sys Malfunction.Plant Stabilized |
- on 890303,electrical Grid Disturbance Resulted in Opening Main Generator Output Breakers,Low Pressure Reactor Trip & Turbine Trip.Caused by Steam Bypass Control Sys Malfunction.Plant Stabilized
| | | 05000530/LER-1989-002, :on 890203,discovered That Detector Bypass Valve Installed Backwards in Plant Vent Sys Low Range Radioactive Gaseous Effluent Monitor.Cause Not Determined. Valve Properly Installed & Monitors Inspected |
- on 890203,discovered That Detector Bypass Valve Installed Backwards in Plant Vent Sys Low Range Radioactive Gaseous Effluent Monitor.Cause Not Determined. Valve Properly Installed & Monitors Inspected
| | | 05000529/LER-1989-002-02, :on 890610,main Steam Safety Valve Setpoints Discovered Out of Tolerance.Caused by Setpoint Drift.Valves Readjusted.Testing Will Continue on Refueling Schedule Until Satisfactory Performance Observed |
- on 890610,main Steam Safety Valve Setpoints Discovered Out of Tolerance.Caused by Setpoint Drift.Valves Readjusted.Testing Will Continue on Refueling Schedule Until Satisfactory Performance Observed
| 10 CFR 50.73(e)(2) | | 05000530/LER-1989-003, :on 890218,control Room Essential Filtration Actuation Signal on Train B Actuated.Caused by Spurious Trip from Control Room Ventilation Intake Radiation Monitor RU-30 & Detector.Detector Replaced |
- on 890218,control Room Essential Filtration Actuation Signal on Train B Actuated.Caused by Spurious Trip from Control Room Ventilation Intake Radiation Monitor RU-30 & Detector.Detector Replaced
| | | 05000529/LER-1989-003-01, :on 890216,feedwater Control Sys (FWCS) Malfunction Resulted in Reactor Trip Due to Low Level in Steam Generator 1.Caused by Malfunction of Steam Generator Valve.Pneumatic Relays in FWCS Replaced |
- on 890216,feedwater Control Sys (FWCS) Malfunction Resulted in Reactor Trip Due to Low Level in Steam Generator 1.Caused by Malfunction of Steam Generator Valve.Pneumatic Relays in FWCS Replaced
| 10 CFR 50.73(e)(2) | | 05000528/LER-1989-003-01, :on 890217,preplanned Alternate Sampling Sys for Fuel Bldg Discovered Inoperable.Caused by Temporary & Permanent Electrical Loads in Excess of Circuit Capacity. Circuit Breaker Supplying Power Opened |
- on 890217,preplanned Alternate Sampling Sys for Fuel Bldg Discovered Inoperable.Caused by Temporary & Permanent Electrical Loads in Excess of Circuit Capacity. Circuit Breaker Supplying Power Opened
| | | 05000530/LER-1989-004, :on 890104,exhaust Rocker Arm for Cylinder 8L Failed,Resulting in Emergency Diesel Generator Trip.Caused by Crack in Rocker Arm.On 890107,ESF Actuation Occurred.Also Reported Per Part 21.Rocker Arm Redesigned |
- on 890104,exhaust Rocker Arm for Cylinder 8L Failed,Resulting in Emergency Diesel Generator Trip.Caused by Crack in Rocker Arm.On 890107,ESF Actuation Occurred.Also Reported Per Part 21.Rocker Arm Redesigned
| 10 CFR 21 10 CFR 21.21(b)(2) 21(b)(3) | | 05000528/LER-1989-004-01, :on 890305,reactor Trip Occurred on Dnbr.Caused by Control Element Assembly Calculator Failure.Processor Board Replaced |
- on 890305,reactor Trip Occurred on Dnbr.Caused by Control Element Assembly Calculator Failure.Processor Board Replaced
| 10 CFR 50.73(e)(2) | | 05000529/LER-1989-005-02, :on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Design Mod Issued to Supply Dedicated Power to Loads |
- on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Design Mod Issued to Supply Dedicated Power to Loads
| | | 05000530/LER-1989-005-02, :on 890628,discovered That Sample Flow Rate for Plant Vent Low Range Radioactive Effluent Monitor Below Alarm Setpoint.Caused by Loose Set Coupling Screw. Pre-planned Alternate Sampling Program Begun |
- on 890628,discovered That Sample Flow Rate for Plant Vent Low Range Radioactive Effluent Monitor Below Alarm Setpoint.Caused by Loose Set Coupling Screw. Pre-planned Alternate Sampling Program Begun
| | | 05000528/LER-1989-005, :on 890412,determined That Deficiencies Identified by Control Components,Inc of Atmospheric Dump Valves Constituted Reportable Part 21 Condition.Caused by Improperly Seated Piston Ring.Valve Replaced |
- on 890412,determined That Deficiencies Identified by Control Components,Inc of Atmospheric Dump Valves Constituted Reportable Part 21 Condition.Caused by Improperly Seated Piston Ring.Valve Replaced
| 10 CFR 21.21(b)(2) 10 CFR 50.73(e)(2)(v) | | 05000529/LER-1989-005, :on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Power Restored to Alternate Sampling Sys |
- on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Power Restored to Alternate Sampling Sys
| | | 05000530/LER-1989-005-01, :on 890628,sample Flow Rate for Vent low-range Radioactive Effluent Monitor Below Low Flow Alarm Setpoint, Rendering Monitor Inoperable.Caused by Loose Set Screw on Coupling.Set Screw on Sample Pump Tightened |
- on 890628,sample Flow Rate for Vent low-range Radioactive Effluent Monitor Below Low Flow Alarm Setpoint, Rendering Monitor Inoperable.Caused by Loose Set Screw on Coupling.Set Screw on Sample Pump Tightened
| | | 05000528/LER-1989-006-02, :on 890731,loss of Power to Panel 1E-PNB-D26 Caused Power to Remote Indicating & Control Unit & Train B Actuation Signal.Cause for Power Loss Being Investigated. Power Restored to Distribution Panel |
- on 890731,loss of Power to Panel 1E-PNB-D26 Caused Power to Remote Indicating & Control Unit & Train B Actuation Signal.Cause for Power Loss Being Investigated. Power Restored to Distribution Panel
| | | 05000530/LER-1989-006-01, :on 890606,operations Personnel Discovered That Two Required Dayshift,Shiftly Surveillances Not Performed within Required Interval.Caused by Personnel Error. Personnel Counseled |
- on 890606,operations Personnel Discovered That Two Required Dayshift,Shiftly Surveillances Not Performed within Required Interval.Caused by Personnel Error. Personnel Counseled
| | | 05000528/LER-1989-006-01, :on 890731,containment Purge Isolation Actuation Signal Initiated Due to Loss of Power to Panel 1E-PNB-D26.Cause Not Identified.Power Restored & Radiation Monitor RU-38 Placed Back on Line |
- on 890731,containment Purge Isolation Actuation Signal Initiated Due to Loss of Power to Panel 1E-PNB-D26.Cause Not Identified.Power Restored & Radiation Monitor RU-38 Placed Back on Line
| 10 CFR 50.73(e)(2) | | 05000530/LER-1989-007, :on 890503,deficiencies Found During Installation of Relays Constituted Reportable Condition. Caused by Inadequate Methodology of Applying Epoxy Matl to Relay Coils.Relays Replaced.Part 21 Related |
- on 890503,deficiencies Found During Installation of Relays Constituted Reportable Condition. Caused by Inadequate Methodology of Applying Epoxy Matl to Relay Coils.Relays Replaced.Part 21 Related
| 10 CFR 21.21(b)(3) 10 CFR 21.21(b)(2) | | 05000528/LER-1989-007, :on 890412,discovered Two of Four Pressurizer Code Safety Valves Out of Tech Spec Tolerance of 2,500 Psia Plus or Minus 1%.Caused by Performance Limitation.Valves Adjusted & Retested Satisfactorily |
- on 890412,discovered Two of Four Pressurizer Code Safety Valves Out of Tech Spec Tolerance of 2,500 Psia Plus or Minus 1%.Caused by Performance Limitation.Valves Adjusted & Retested Satisfactorily
| 10 CFR 50.73(e)(2) | | 05000528/LER-1989-008-02, :on 890714,internal Audit Revealed Cooling Tower Sludge Contained Low Level Amounts of Radioactivity. Caused by Lack of Sludge Sampling Before Landfill Disposal. Approval to Dispose of Sludge Requested |
- on 890714,internal Audit Revealed Cooling Tower Sludge Contained Low Level Amounts of Radioactivity. Caused by Lack of Sludge Sampling Before Landfill Disposal. Approval to Dispose of Sludge Requested
| 10 CFR 50.73(c)(2) | | 05000530/LER-1989-008, :on 890630,maint Personnel Identified Sixth Trip Lever Arm on 10-ton Fuel Handling Crane Rails Instead of Only Five Trip Lever Arms for Crane Interlocks.Cause Under Investigation.Sixth Level Arm Removed |
- on 890630,maint Personnel Identified Sixth Trip Lever Arm on 10-ton Fuel Handling Crane Rails Instead of Only Five Trip Lever Arms for Crane Interlocks.Cause Under Investigation.Sixth Level Arm Removed
| | | 05000529/LER-1989-008, :on 890509,calculational Error Identified in Surveillance Test That Would Have Resulted in Boron Dilution Alarm Channel 2 Being Inoperable.Caused by Personnel Error. Technician Counseled & Procedure Revised |
- on 890509,calculational Error Identified in Surveillance Test That Would Have Resulted in Boron Dilution Alarm Channel 2 Being Inoperable.Caused by Personnel Error. Technician Counseled & Procedure Revised
| 10 CFR 50.73(s)(2) | | 05000529/LER-1989-008-01, :on 890509,calculational Error Identified in Surveillance Test That Would Have Resulted in Boron Diluted Alarm Channel 2 Being Inoperable.Caused by Personnel Error. Technicians Counseled & Test Procedure Revised |
- on 890509,calculational Error Identified in Surveillance Test That Would Have Resulted in Boron Diluted Alarm Channel 2 Being Inoperable.Caused by Personnel Error. Technicians Counseled & Test Procedure Revised
| | | 05000529/LER-1989-009, :on 890712,reactor Trip Occurred on Calculated Low DNBR Due to Low Reactor Coolant Flow.On 890713,portion of Main Feedwater Sys Overpressurized.Caused by Failed Fuse in Potential Transformer.Fuse Replaced |
- on 890712,reactor Trip Occurred on Calculated Low DNBR Due to Low Reactor Coolant Flow.On 890713,portion of Main Feedwater Sys Overpressurized.Caused by Failed Fuse in Potential Transformer.Fuse Replaced
| | | 05000530/LER-1989-009-01, :on 890728,inadvertent Train a Fuel Bldg Essential Ventilation Actuation Signal Initiated on Balance of Plant ESF Actuation Sys.Caused by Personnel Error. Individual Counseled |
- on 890728,inadvertent Train a Fuel Bldg Essential Ventilation Actuation Signal Initiated on Balance of Plant ESF Actuation Sys.Caused by Personnel Error. Individual Counseled
| 10 CFR 50.73(o)(2) | | 05000530/LER-1989-010-01, :on 890923,discovered That Surveillance Testing Interval for Radioactive Effluent Monitoring Sys Exceeded. Caused by Personnel Error.Human Performance Evaluation Sys Analysis of Error Initiated |
- on 890923,discovered That Surveillance Testing Interval for Radioactive Effluent Monitoring Sys Exceeded. Caused by Personnel Error.Human Performance Evaluation Sys Analysis of Error Initiated
| 10 CFR 50.73(e)(2) | | 05000530/LER-1989-011-01, :on 891206,discovered That Quarterly ASME Surveillance Testing on Train a of Air Start Sys Check Valve for Train B Emergency Diesel Generator Not Performed.Caused by Insufficient Controls.Procedure Revised |
- on 891206,discovered That Quarterly ASME Surveillance Testing on Train a of Air Start Sys Check Valve for Train B Emergency Diesel Generator Not Performed.Caused by Insufficient Controls.Procedure Revised
| 10 CFR 50.73(e)(2) | | 05000528/LER-1989-011, :on 890425,instrument & Control Technician Exited High Radiation Area W/O Using Alarm Dosimeter.Caused by Personnel Error.Technician Barred from Entry to Radiological Controlled Area |
- on 890425,instrument & Control Technician Exited High Radiation Area W/O Using Alarm Dosimeter.Caused by Personnel Error.Technician Barred from Entry to Radiological Controlled Area
| | | 05000528/LER-1989-012, :on 890510,determined That Emergency Lighting Did Not Meet Design Bases or 10CFR50 App R Requirements. Cause Under Investigation.Emergency Lighting Will Be Installed &/Or Modified Prior to Restart |
- on 890510,determined That Emergency Lighting Did Not Meet Design Bases or 10CFR50 App R Requirements. Cause Under Investigation.Emergency Lighting Will Be Installed &/Or Modified Prior to Restart
| 10 CFR 50.73(a)(2) | | 05000530/LER-1989-012, Informs That LER 89-012 for Unit 3 Not Used,Per NUREG-1022 | Informs That LER 89-012 for Unit 3 Not Used,Per NUREG-1022 | | | 05000528/LER-1989-013, Forwards Suppl 1 to LER 89-013-00.Rept Being Submitted to Include Info Requested by Part 21 | Forwards Suppl 1 to LER 89-013-00.Rept Being Submitted to Include Info Requested by Part 21 | 10 CFR 50.73(a)(2)(iii) 10 CFR 21.21(b)(2) | | 05000530/LER-1989-013-01, :on 890926,control Room Operator Inadvertently Turned Wrong Handswitch During post-maint Testing Which Resulted in ESFAS Actuation.Caused by Personnel Error. Disciplinary Measures Taken |
- on 890926,control Room Operator Inadvertently Turned Wrong Handswitch During post-maint Testing Which Resulted in ESFAS Actuation.Caused by Personnel Error. Disciplinary Measures Taken
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(v) | | 05000528/LER-1989-014, :on 890622,discovered That Seismic Monitor Had Been Disconnected & Inoperable Since 890422.Caused by Procedural Failure.Procedure for Removal of Reactor Coolant Pump Motor Being Revised to Alert Personnel |
- on 890622,discovered That Seismic Monitor Had Been Disconnected & Inoperable Since 890422.Caused by Procedural Failure.Procedure for Removal of Reactor Coolant Pump Motor Being Revised to Alert Personnel
| 10 CFR 50.73(c)(2) 10 CFR 50.73(s)(2)(iv) | | 05000528/LER-1989-015, :on 890901,phase B Shunt Reactor on Devers Transmission Line Failed,Causing Ground Fault on 500 Kv Line & Release of Large Vol of Oil & Fire.Caused by Failure of Winding to Bushing.Fire Extinguished |
- on 890901,phase B Shunt Reactor on Devers Transmission Line Failed,Causing Ground Fault on 500 Kv Line & Release of Large Vol of Oil & Fire.Caused by Failure of Winding to Bushing.Fire Extinguished
| 10 CFR 50.73(s)(1) | | 05000529/LER-1989-015, :on 881203,discovered New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Personnel Error.Radiation Monitoring Sys Surveillance Procedure Being Revised to Clarify Instructions |
- on 881203,discovered New Fuel Area Radiation Monitor RU-19 Inoperable.Caused by Personnel Error.Radiation Monitoring Sys Surveillance Procedure Being Revised to Clarify Instructions
| | | 05000528/LER-1989-017, :on 891023,four Unsealed Penetrations in Unit 3 Seismic Gap Area Discovered During Visual Insp of 94 Ft Elevation Diesel Bldg Pipe Trenches.Fire Watches Established in All Units.Sealing of Penetrations Underway |
- on 891023,four Unsealed Penetrations in Unit 3 Seismic Gap Area Discovered During Visual Insp of 94 Ft Elevation Diesel Bldg Pipe Trenches.Fire Watches Established in All Units.Sealing of Penetrations Underway
| 10 CFR 50.73(e)(1) 10 CFR 50.73(e)(2)(ix) | | 05000528/LER-1989-018, :on 891026,discovered That Containment Purge Valves Did Not Meet Local Leak Rate Testing Acceptance Criteria.Caused by Intergranular Stress Fracture.Spiral Pins Replaced.Reportable Per Part 21 |
- on 891026,discovered That Containment Purge Valves Did Not Meet Local Leak Rate Testing Acceptance Criteria.Caused by Intergranular Stress Fracture.Spiral Pins Replaced.Reportable Per Part 21
| 10 CFR 50.73(e)(2) 10 CFR 21.21(b)(3) 10 CFR 21.21(b)(2) | | 05000528/LER-1989-019, :on 890929,Train B of Fuel Bldg Essential Ventilation Actuation Sys Spuriously Actuated.Caused by Loose Connection Between Radiation Monitor Remote Indication & Control Unit Instrument Drawer & Cabinet |
- on 890929,Train B of Fuel Bldg Essential Ventilation Actuation Sys Spuriously Actuated.Caused by Loose Connection Between Radiation Monitor Remote Indication & Control Unit Instrument Drawer & Cabinet
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(iv) | | 05000528/LER-1989-020, :on 890907,emergency Diesel Generator B, Essential Spray Pond Pump B & Essential Cooling Water Pump B Started During Removal of Jumpers.Caused by Personnel Error. Maint Procedure Revised |
- on 890907,emergency Diesel Generator B, Essential Spray Pond Pump B & Essential Cooling Water Pump B Started During Removal of Jumpers.Caused by Personnel Error. Maint Procedure Revised
| 10 CFR 50.73(e)(2) 10 CFR 50.73(s)(2)(v) | | 05000528/LER-1989-021, :on 891106 & 09,discovered That Locked High Radiation Area Gate Open & Unguarded,Contrary to Tech Spec 6.12.2 Requirements.Caused by Personnel Error.Gates Secured & Addl Locking Mechanisms Installed on Doors |
- on 891106 & 09,discovered That Locked High Radiation Area Gate Open & Unguarded,Contrary to Tech Spec 6.12.2 Requirements.Caused by Personnel Error.Gates Secured & Addl Locking Mechanisms Installed on Doors
| 10 CFR 50.73(c)(2)(9) | | 05000528/LER-1989-023, :on 891208,ESF Equipment Room Essential Ventilation Fans Declared Inoperable When Turning Valves Determined Not to Be Seismically Qualified.Caused by Inadequate Program.Bracing Installed on Duct |
- on 891208,ESF Equipment Room Essential Ventilation Fans Declared Inoperable When Turning Valves Determined Not to Be Seismically Qualified.Caused by Inadequate Program.Bracing Installed on Duct
| | | 05000528/LER-1989-024, :on 891212,test on Reactor Coolant Pump Motor 2A Caused Voltage Perturbation in Electrical Sys,Tripping Radiation Monitors.Caused by Abnormal Electrical Alignment. Operating Procedures for Pump Motors Revised |
- on 891212,test on Reactor Coolant Pump Motor 2A Caused Voltage Perturbation in Electrical Sys,Tripping Radiation Monitors.Caused by Abnormal Electrical Alignment. Operating Procedures for Pump Motors Revised
| 10 CFR 50.73(e)(2) | | 05000528/LER-1989-025, :on 891103,discovered That Radiant Energy Fire Barrier Missing from One of Two Pressurizer Auxiliary Spray Valves in Pressurizer Room.Caused by Incomplete Drawings.Engineering Evaluation Underway |
- on 891103,discovered That Radiant Energy Fire Barrier Missing from One of Two Pressurizer Auxiliary Spray Valves in Pressurizer Room.Caused by Incomplete Drawings.Engineering Evaluation Underway
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