text
_
u S. wuCLEM RiovLAroav _
aseC Per. me N
Arraovt) osse ano 3t30.(1o4 UCENSEE EVENT REPORT (LER)
PACILITv =Aase EH occEST asuaeeR (23 FAEBE W Washington Nuclear P1 ant - Unit 2 o is Io lo Io 0 $ 17 1loFh12 raTLE s.4 Spurious Control Room Emerg. Filtration System Actuation Due to CL ffonitor Tape Depletion sve=r oars =
l Lan muusen m aeront care m ornan e C,urias invoLvso it, "gp.
.Og oo.,r,e o.,
vaan
. ciury..un oocair uon..
mo=t=
omv vsaa vena 0l5l0logo l
0 ]2 0l9 8 6 8%
0 l1
- ) l0 0 l3 43 8l6 o is o 3 0e og i i s
twee necoat is suomirreo runeuaser to rue asovimense=vs os i can 6. scnne
.a sa. <mm w nH
= = * *
m.1=>an.
n.rme m..semmm ummm m.7=>mw rs.nw g
n.,
i7 i 2 m..eewmm
=ags-pyg e..=wm m.rmunn >
m.mmm<.i m,mieni m,=,.
u.i m-,
m..eedsHUD.,
e. 73ssH2Hs) se.734semtvestiel m..masimM m.73ssGHas es.73(eH2Hal s
LBCtsueEE Co= TACT Poa This LER n2)
=AME TELEPMO=t peuwstm 4m44 cOct 2 5 p il W. S. Davison, Compliance Engineer 5p1 9 3
7 i
i 7-i i
comekste one u e roa saca compone=v em Luas oseenioso = rues asaoat us. Ext. 2279
cause
avsysu couro a r
"*ic a$y,"J,^jj' M
caves systsu couro=e=r
"^1C-
"$7"J.'!!'
ry y
I I I I I I I I
I I f f f 1 l
I l I l l l I
l l l i I I o.,lvean sue tame =ral me, oar emnerio n.
wo=v-
]vis ur.
eurerro sue <ssion o4rei "T] =o l
l l
r r cr,o
,.oi.
..-,n.,
On February 9,1986 a spurious actuation of the Control Room Emergency Filtration system occurred when the chlorine monitor in sample rack WOA-SR-15 (Rad Waste Building Outside Air Sample Rack 15) ran out of tape. The root cause was attributed to inadequate design in that no alarn function exists to warn of impending tape depletion.
A contributing cause was the occurrence of a cognitive personnel error in that the procedure calling for addition of new tape was not followed.
The tape was replaced and the Control Room Emergency Filtration Systen was returned to normal. These monitors are to be eliminated when the method of circulating water treatment is changed from gaseous chlorination to chemical addition of sodium hypochlorite.
NO SDON h(
7 s
g
)g g
asAC Perm 3BSA U S NUCLEAR REGutAfonY --- __:
UCENSEE EVENT REPORT (LER) TEXT C"NTINUATION Areaovss ome =o sino-owa txPIR$5 8/3148 pacaufe seamst tu DoCalT Nuessen t2t LtR NUnseGR (G)
PAGE IN 88 4'
y*b vsam Washington Nuclear Plant - Unit 2
,,,,,,,,, 3,9, 7 8,6 _0 p ;l 00 0 2 0 ;2 9
g o,
Plant Conditions
a) Power Level - 72%
b) Plant tiode 1
Event On February 9,1986, the chlorine detector on the inlet of the Control Room Ventilation System, WOA-SR-15, ran out of tape causing a Hi Chlorine signal to be generated which started the Control Room Emergency Filtration System.
The paper tape in the detector is chemically treated to react with chlorine in the air. When the tape is depleted the last piece remains in the flow stream and becomes discolored as dirt and moisture accumulate.
This discoloration was sensed as an increasing chlorine concentration which reached the alarm setpoint and actuated the emergency filtration system.
The root cause of this event was evaluated as inadequate design, in that the chlorine detection system does not provide an alarm for paper tape depletion which results in a spurious initiation of an ESF system. A contributing cause was the occurrence of a cognitive personnel error by a utility maintenance technician in that the procedure mandating periodic addition of new tape was not complied with.
Imediate Corrective Action The tape in WOA-SR-15 was replaced, the alarm reset and the Control Room Emergency Filtration System returned to its normal condition.
Further Evaluation and Corrective Action As a result of an engineering study, the method of circulating water treatment will be changed from gaseous chlorination to chemical addition of sodium hypochlorite. This design modification will result in removal of the requirement for the intake header chlorine detectors to automatically isolate the Control Room. The removal of the chlorine detectors will eliminate the problem of spurious ESF actuations caused by paper tape depletion.
The utility maintenance technician involved in this event was counselled and reinstructed.
Safety Significance
This event carries no safety significance as there was no actual high chlorine concentration and all equipment operated correctly to place the Control Room Ventilation System in an isolation condition.
Similar Events
Refer to LERs84-057, 84-093,84-128, and 85-026.
g,o..
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509)372-5000 Docket No.
50-397 Marcy 3, 1986 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Subject: NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.86-001
Dear Sir:
Transmitted herewith is Licensee Event Report No.86-001 for WNP-2 Plant.
This report is submitted in response to the report requirements of 10CFR50.73 and discusses the item of reportability, corrective action taken, and action taken to preclude recurrence.
This is the follow-up report to the verbal notification given at 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br /> on February 9,1986.
Very truly yours, C.M. Powers (M/D 927M)
WNP-2 Plant Manager CMP:mt Encl osure:
Licensee Event Report No.86-001 cc: Mr. John B. Martin, NRC - Region V Mr. R.C. Barr, NRC - Site (901 A)
Ms. Dottie Sherman, ANI INP0 Records Center - Atlanta, GA Mr. C.R. Bryant, BPA (M/D 399) o i
i
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000397/LER-1986-001, :on 860209,spurious Actuation of Control Room Emergency Filtration Sys Occurred Due to Chlorine Monitor Tape Depletion.Caused by Inadequate Design & Personnel Error.Tape Replaced |
- on 860209,spurious Actuation of Control Room Emergency Filtration Sys Occurred Due to Chlorine Monitor Tape Depletion.Caused by Inadequate Design & Personnel Error.Tape Replaced
| | | 05000397/LER-1986-002, :on 860226,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal Under Normal Conditions.Cause Unknown.Method of Circulating Water Treatment Will Be Changed |
- on 860226,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal Under Normal Conditions.Cause Unknown.Method of Circulating Water Treatment Will Be Changed
| | | 05000397/LER-1986-003, :on 860314,reactor Scram Occurred Due to Incorrect Switch Position During APRM Channel a Functional Test.Caused by Personnel Error.Technicians Counseled & Trained in Proper Actions |
- on 860314,reactor Scram Occurred Due to Incorrect Switch Position During APRM Channel a Functional Test.Caused by Personnel Error.Technicians Counseled & Trained in Proper Actions
| | | 05000397/LER-1986-004, :on 860316,during Reactor Shutdown,Reactor Scram Occurred & Pressure Transient Caused Nuclear Instrumentation intermediate-range Monitor Channels to Exceed High Upscale Trip Setpoint |
- on 860316,during Reactor Shutdown,Reactor Scram Occurred & Pressure Transient Caused Nuclear Instrumentation intermediate-range Monitor Channels to Exceed High Upscale Trip Setpoint
| | | 05000397/LER-1986-005, :on 860401,refueling Mode 5 Entered Prior to Completing Instrument Surveillances Required by Tech Specs. Caused by Inadequate Procedures.Tech Specs Received & Surveillances Performed |
- on 860401,refueling Mode 5 Entered Prior to Completing Instrument Surveillances Required by Tech Specs. Caused by Inadequate Procedures.Tech Specs Received & Surveillances Performed
| 10 CFR 50.73(a)(2)(1) | | 05000397/LER-1986-006, :on 860421,reactor Protective Trip Occurred During Installation of Shorting Links for Reactor Protection Sys.Caused by Operator Error,Resulting in Short Circuit. Operator Counseled & Procedure Enhanced |
- on 860421,reactor Protective Trip Occurred During Installation of Shorting Links for Reactor Protection Sys.Caused by Operator Error,Resulting in Short Circuit. Operator Counseled & Procedure Enhanced
| | | 05000397/LER-1986-007, :on 860217,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Undetermined.Method of Circulating Water Treatment Will Be Changed |
- on 860217,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Undetermined.Method of Circulating Water Treatment Will Be Changed
| | | 05000397/LER-1986-008, :on 860505,potential Transformer Secondary Fuse Blew,Resulting in Spurious Voltage Loss Signal to SM-8 Undervoltage Protection Cricuitry.Caused by Electrical Maint Technician Error.Technician Counseled |
- on 860505,potential Transformer Secondary Fuse Blew,Resulting in Spurious Voltage Loss Signal to SM-8 Undervoltage Protection Cricuitry.Caused by Electrical Maint Technician Error.Technician Counseled
| | | 05000397/LER-1986-009, :on 860426,secondary Containment Sys Emergency Operation Initiated When Control Power Fuse in Reactor Bldg Ventilation High Radiation Monitoring Circuitry Blew.Cause Undetermined |
- on 860426,secondary Containment Sys Emergency Operation Initiated When Control Power Fuse in Reactor Bldg Ventilation High Radiation Monitoring Circuitry Blew.Cause Undetermined
| | | 05000397/LER-1986-010, :on 860513,Diesel Generator 1 Fuel Storage Tank Below Min Inventory.Caused by 24 H Diesel Generator Run When Diesel Generator 2 Out of Svc.Fuel Storage Tank Filled & in Compliance |
- on 860513,Diesel Generator 1 Fuel Storage Tank Below Min Inventory.Caused by 24 H Diesel Generator Run When Diesel Generator 2 Out of Svc.Fuel Storage Tank Filled & in Compliance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000397/LER-1986-011, :on 860509,nuclear Steam Supply Shutoff Sys Actuated Due to Momentary Loss of Instrument Power. Cause Unknown.Reactor Protection Sys Half Scram & Isolation Signals Reset |
- on 860509,nuclear Steam Supply Shutoff Sys Actuated Due to Momentary Loss of Instrument Power. Cause Unknown.Reactor Protection Sys Half Scram & Isolation Signals Reset
| | | 05000397/LER-1986-012, :on 860512,isolation Function of Nuclear Steam Supply Shutoff Sys Actuated Due to Deenergization of Reactor Protective Sys Supply Bus A.Caused by Inadequate Procedures. Inboard Isolation Valves Restored |
- on 860512,isolation Function of Nuclear Steam Supply Shutoff Sys Actuated Due to Deenergization of Reactor Protective Sys Supply Bus A.Caused by Inadequate Procedures. Inboard Isolation Valves Restored
| | | 05000397/LER-1986-014, :on 860523,discovered That Two Containment Exhaust Purge Sys Test Connection Isolation Valves Not Tested at 24-month Interval.Caused by Personnel Error. Surveillance Procedure Modified |
- on 860523,discovered That Two Containment Exhaust Purge Sys Test Connection Isolation Valves Not Tested at 24-month Interval.Caused by Personnel Error. Surveillance Procedure Modified
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000397/LER-1986-015, :on 860606,RWCU Sys Isolated During Leak Detection Sys Temp Indicator Calibr.Caused by Technician Incorrectly Lifting Lead.Technician Counseled & Training Package Modified to Include Calibr Procedure |
- on 860606,RWCU Sys Isolated During Leak Detection Sys Temp Indicator Calibr.Caused by Technician Incorrectly Lifting Lead.Technician Counseled & Training Package Modified to Include Calibr Procedure
| | | 05000397/LER-1986-016, :on 860612,RWCU Sys Isolation Occurred.Caused by Instrument Technician Using Wrong Switch While Performing Channel Functional Test for RWCU High Delta Flow.Labels for Test Switches Will Be Improved |
- on 860612,RWCU Sys Isolation Occurred.Caused by Instrument Technician Using Wrong Switch While Performing Channel Functional Test for RWCU High Delta Flow.Labels for Test Switches Will Be Improved
| | | 05000397/LER-1986-017, :on 860608,RWCU Sys Automatically Isolated Due to High Differential Flow.Caused by Personnel Error.Rwcu Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow.Personnel Counseled |
- on 860608,RWCU Sys Automatically Isolated Due to High Differential Flow.Caused by Personnel Error.Rwcu Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow.Personnel Counseled
| | | 05000397/LER-1986-018, :on 860526 & 29,diesel Generator 2 Failed During post-mod Diagnostic Testing.Cause Undetermined. Procedure Will Be Written to Provide More Detailed Guidance Re post-mod Retesting |
- on 860526 & 29,diesel Generator 2 Failed During post-mod Diagnostic Testing.Cause Undetermined. Procedure Will Be Written to Provide More Detailed Guidance Re post-mod Retesting
| | | 05000397/LER-1986-019, :on 860415,deficiencies Identified in RHR Valve 9 in Limitorque motor-operated Valve During Insp.Similar Environ Qualification Deficiencies Found in 27 Valves.All Deficiencies Corrected |
- on 860415,deficiencies Identified in RHR Valve 9 in Limitorque motor-operated Valve During Insp.Similar Environ Qualification Deficiencies Found in 27 Valves.All Deficiencies Corrected
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vi) | | 05000397/LER-1986-020, :on 860610,while Recovering from Overspeed Trip Test,Reactor Scrammed.Caused by Inadequate Turbine Operating Procedure.Procedure Modified to Include Addl Info Re Tv/Gv Transfer & Expected Plant Response |
- on 860610,while Recovering from Overspeed Trip Test,Reactor Scrammed.Caused by Inadequate Turbine Operating Procedure.Procedure Modified to Include Addl Info Re Tv/Gv Transfer & Expected Plant Response
| | | 05000397/LER-1986-021, :on 860620,plant Shutdown Commenced Due to Leakage from RCS Pressure Isolation Valve Exceeding 1 Gpm. Caused by Damage to Valve Seat,Disk & Internal Surfaces from Cavitation.Valve Replaced |
- on 860620,plant Shutdown Commenced Due to Leakage from RCS Pressure Isolation Valve Exceeding 1 Gpm. Caused by Damage to Valve Seat,Disk & Internal Surfaces from Cavitation.Valve Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000397/LER-1986-022, :on 860627,during Planned Outage While Electrical Loads Supplied by Offsite Power Source,Standby Diesel Generators Automatically Started.Caused by Momentary Loss of Power from nonplant-related Trip |
- on 860627,during Planned Outage While Electrical Loads Supplied by Offsite Power Source,Standby Diesel Generators Automatically Started.Caused by Momentary Loss of Power from nonplant-related Trip
| | | 05000397/LER-1986-023, :on 860710,reactor Scram Occurred Following Opening of Incorrect Circuit Breaker During Electrical Ground Isolation.Caused by Personnel Error.Engineer Drawing & Circuit Breaker Labeling Will Be Changed |
- on 860710,reactor Scram Occurred Following Opening of Incorrect Circuit Breaker During Electrical Ground Isolation.Caused by Personnel Error.Engineer Drawing & Circuit Breaker Labeling Will Be Changed
| | | 05000397/LER-1986-024, :on 860721,standby Diesel Generator 2 (DG2) Started.Caused by Internal Electrical Fault on One of Three Condensate Booster pumps.DG2 Secured Per Plant Procedure & Returned to Normal Backup |
- on 860721,standby Diesel Generator 2 (DG2) Started.Caused by Internal Electrical Fault on One of Three Condensate Booster pumps.DG2 Secured Per Plant Procedure & Returned to Normal Backup
| | | 05000397/LER-1986-026, :on 860725,following Reactor Scram,Containment Isolation at RWCU Sys Actuated Due to High Differential Flow.Caused by Inadequate Design.Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow |
- on 860725,following Reactor Scram,Containment Isolation at RWCU Sys Actuated Due to High Differential Flow.Caused by Inadequate Design.Sys Returned to Svc in Blowdown Mode W/Reduced Blowdown Flow
| | | 05000397/LER-1986-027, :on 860903,evaluation Concluded That Engineering Criteria Supplied by Burns & Roe,Inc,In Electrical Spec 2808-218 Nonconservative.Procedures Utilizing Faulty Data Will Be Modified |
- on 860903,evaluation Concluded That Engineering Criteria Supplied by Burns & Roe,Inc,In Electrical Spec 2808-218 Nonconservative.Procedures Utilizing Faulty Data Will Be Modified
| 10 CFR 21.21(b)(3) | | 05000397/LER-1986-029, :on 860822,drywell Hydrogen Analyzers Calibr Using 2% & 6% by Vol Hydrogen Gas Rather than 0% & 25% Required by Tech Specs.Caused by Personnel Error.Analyzers Recalibr.Tech Spec Amend Requested |
- on 860822,drywell Hydrogen Analyzers Calibr Using 2% & 6% by Vol Hydrogen Gas Rather than 0% & 25% Required by Tech Specs.Caused by Personnel Error.Analyzers Recalibr.Tech Spec Amend Requested
| 10 CFR 50.73(a)(2)(i) | | 05000397/LER-1986-030, :on 860903,reactor Scram Occurred Due to Low Reactor Water Level.Caused by Reactor Feedwater Pump Trip & Failure of Recirculation Flow Control Valve to Run Back. Preventive Maint Procedure Will Be Written |
- on 860903,reactor Scram Occurred Due to Low Reactor Water Level.Caused by Reactor Feedwater Pump Trip & Failure of Recirculation Flow Control Valve to Run Back. Preventive Maint Procedure Will Be Written
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000397/LER-1986-031, :on 860910,RCIC Inboard Steam Line Isolation Valves Closed on Erroneous RCIC Equipment Area High Temp Signal.Caused by Technicians Inadvertently Connecting Test Equipment to Wrong Circuit.Personnel Counseled |
- on 860910,RCIC Inboard Steam Line Isolation Valves Closed on Erroneous RCIC Equipment Area High Temp Signal.Caused by Technicians Inadvertently Connecting Test Equipment to Wrong Circuit.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000397/LER-1986-032, :on 861007,review of Plant Records Revealed That Control Rod Block intermediate-range Neutron Monitoring Quarterly Calibr Not Performed.Caused Insufficient Programmatic Controls.Items Now Tracked |
- on 861007,review of Plant Records Revealed That Control Rod Block intermediate-range Neutron Monitoring Quarterly Calibr Not Performed.Caused Insufficient Programmatic Controls.Items Now Tracked
| | | 05000397/LER-1986-034, :on 861017,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.No Cause Established.Tech Spec Amend Requested to Delete Chlorine Detection Requirements.W/Undated Ltr |
- on 861017,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.No Cause Established.Tech Spec Amend Requested to Delete Chlorine Detection Requirements.W/Undated Ltr
| | | 05000397/LER-1986-035, :on 861101 & 08,emergency Filtration Sys Initiated on High Chlorine Signal.No Root Cause Determined. Chlorine Detectors Will Be Removed After Tech Spec Approval |
- on 861101 & 08,emergency Filtration Sys Initiated on High Chlorine Signal.No Root Cause Determined. Chlorine Detectors Will Be Removed After Tech Spec Approval
| | | 05000397/LER-1986-036, :on 861110,control Room Emergency Filtration Sys Automatically Initiated on False High Chlorine Signal. Caused by Broken chlorine-sensitive Paper Tape.Chlorine Monitor Investigated & Tape Replaced |
- on 861110,control Room Emergency Filtration Sys Automatically Initiated on False High Chlorine Signal. Caused by Broken chlorine-sensitive Paper Tape.Chlorine Monitor Investigated & Tape Replaced
| | | 05000397/LER-1986-037, :on 861120,plant Shut Down After Connector for Signal Cable of Acoustic Monitoring Channel 5C Determined to Be Not Environmentally Qualified.Caused by Inadequate Maint Work Request.Vital Work Requests Reviewed |
- on 861120,plant Shut Down After Connector for Signal Cable of Acoustic Monitoring Channel 5C Determined to Be Not Environmentally Qualified.Caused by Inadequate Maint Work Request.Vital Work Requests Reviewed
| | | 05000397/LER-1986-038, :on 861120,reactor Scram Occurred.Caused by Rapid Decrease in Reactor Water Level Upon Incorrect Alignment of Condensate Cleanup Block Valves & Feedwater Diversion to Empty Line.Operators Counseled |
- on 861120,reactor Scram Occurred.Caused by Rapid Decrease in Reactor Water Level Upon Incorrect Alignment of Condensate Cleanup Block Valves & Feedwater Diversion to Empty Line.Operators Counseled
| | | 05000397/LER-1986-039, :on 861123,control Room Emergency Filtration Sys Initiated on False High Chlorine Signal.Caused by Incorrect Lamp (5.6V) Inadvertently Installed.Lamp Replaced |
- on 861123,control Room Emergency Filtration Sys Initiated on False High Chlorine Signal.Caused by Incorrect Lamp (5.6V) Inadvertently Installed.Lamp Replaced
| | | 05000397/LER-1986-040, :on 861125,technicians Failed to Obtain Drywell Samples Every 12 H as Required.Caused by Failure of Personnel to Follow Procedures.Personnel Counseled |
- on 861125,technicians Failed to Obtain Drywell Samples Every 12 H as Required.Caused by Failure of Personnel to Follow Procedures.Personnel Counseled
| | | 05000397/LER-1986-041, :on 861126,1202,05 & 06,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal for No Apparent Reason.Investigation of Chlorine Monitor Did Not Reveal Any Malfunctions |
- on 861126,1202,05 & 06,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal for No Apparent Reason.Investigation of Chlorine Monitor Did Not Reveal Any Malfunctions
| | | 05000397/LER-1986-042, :on 861201,plant Nonconformance Rept Issued to Document Omission of Fire Door C228 from Two Surveillance Procedures.Caused by Personnel Error.Door Verified Operable & Locked & All Surveillance Procedures Checked |
- on 861201,plant Nonconformance Rept Issued to Document Omission of Fire Door C228 from Two Surveillance Procedures.Caused by Personnel Error.Door Verified Operable & Locked & All Surveillance Procedures Checked
| | | 05000397/LER-1986-043, :on 861217 & 19,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Unknown.Control Room Emergency Filtration Sys Returned to Normal Lineup |
- on 861217 & 19,control Room Emergency Filtration Sys Automatically Initiated on High Chlorine Signal.Cause Unknown.Control Room Emergency Filtration Sys Returned to Normal Lineup
| | | 05000397/LER-1986-044, :on 861222,liquid Radwaste Effluents Discharged W/Radioactive Liquid Effluent Monitor Inoperable & Only One Predischarge Batch Sample Obtained & Analyzed.Caused by Personnel Error.Personnel Counseled |
- on 861222,liquid Radwaste Effluents Discharged W/Radioactive Liquid Effluent Monitor Inoperable & Only One Predischarge Batch Sample Obtained & Analyzed.Caused by Personnel Error.Personnel Counseled
| |
|