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UCENSEE EVENT REPORT ILERI
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Shoreham Nuclear Power Station 11 nit #1 e is I o to I o 131212 1 lopl012 YI,,, t.,
r RBCLCV Split While I&C Technician was Performing a Surveillance
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.h4a Coat Robert W. Grunseich. _ Operational Coa;*11ance Engineer 5l 1,6 9,2,9,
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% n e n.w r y 14, l' JOE, c.t 1320, a Heactor Lui1 ding C l o s tnj t.<.o n l
Coolifa Wateze (9DCLCW) Setten 901it occut me whon an t r e, t r* um a n t ond Controls (JAC) toc 5ntelen accident 1" tumped the "fi' Rfh CW Head Tans l oue low Invel witch whilo imttanc uo to t r r f o,*m a
r i
nuevun11anro o r o n t'd u r e.
The alant w m. 'n G a s.ra t l ona l C r. vi l t t o n G with tbn foodo switch 11 Siutde+wn for nr> o u t e e>
ar all roo%
ir6 urtird in the core.
Ti m
- 6. or 5 n t e t o ri, by pr,sc ed o -e.
wJ r e r.1 0 v o a j
the wi t ch co ver fer the low 1 0,,
Icvel ureitch (tPaa*W 2iED) wd,
becauw o f lim 2ted accermtbility. i ncal ve n t ant l y Dun,ued t t,E r.w i t : n l
c a u '; t. o kho 9DCLCW u n t ura to sollt a rit o its n ec' tit r.t configuroti0n.
The n ur vt< i;ance war. utnoped until the 2 r t itJt. n t, was t rivr 7 t i p a t er.'
avoj tite riyid mri wain r e t ie r r e'd to Itu nur,131 i
confagneative.
pl 'nt v m e n en~ n t w a r, not2tned of the 1.w n t a ra thn NRC w.m retified ct 147) r. rm 10C'R5 0. 7.7.
4 orevent P l?t ' t, r' r f !riC,3, the u d evie ) ] 1,, fir t, fe r Q C,3 'j u r fd WA% r,* V i b e d tO pr OV1ds' re rot e rm t t o r>
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LICENSEE EVENT REPORT (LER) TEXT CON 71NUAT60N
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i Shoreha Nucleeir Power Station t' nit #1,o alolo16l3l2l 2' g{s 0 l0 (9 0 l 0, 012 o' 0l2 61,.
am... m On Fe tn"in r y 14 1%C at ID.
a Reactor Ih t i. ; int C2 of ec
!.c o p Cem]in:
Wter ( 9E CL Cel) Lysttw 301it occ. a ^ red wher. an I r u t rurrent a.M Contro1n (IdC) technician w c u.t'r.t l y L:uo v-d the " 1/ '
RDCLCW Wend look lew Icw lovel switch wh i lt- :ettinr up to corporm a
surveilltr.ce procodure.
The plant wa; i n Oswrat tor ei Co ^t' i t t o n ",
with the modo uwitch in Shutdun for an o ' r: a w and oli rudo i rc.or t ed in the cor9 The I E ": t rechn 2 ca n n w n.
t>etting ein the r.ecimsary
- m. t r u m e n t.i t t a n to p e r f o rr,1 Otat1on proceduru 4 4.1 ' G. 01, RECL C.J F-r:ati Tank unvv 4 L c.*
Low Chor nei Cal 2bratien and Fur.c t t e n a l
- Teat, to nat m'v 7eich n i c a l Lpecificetco reci. come r.t r.
Mt rw
.,t t a c h t r a
Tyton Tubirm tett wt up to t t- +. rJ i 'a i n o > p ed f sr t. F o level
.WitCS (1D4f2.LW 1 N,
t h a-W u dure then celion fc r r o M ov ; n t' the cove r from th* Unitch.
Than ii vm w i t e), is l oc x; c ti m e j y;e r,t t'
tv f
"B" R E "'L C W haad inr+,
a p tn y : ta a t e l y ter tv feet ame tne f l o.v.
In schj a t i c n tc t o ; r rj nut. f-ro. e rii T I
- reach, ccin.utt r u n r.
ric ruonurt2 havoor a.ce": stb 1: 2ty to the invol twitch.
Wnon the sulten
- c ur wa. tw i r. r e
- r o v ed,
the switch wu 91the-terreJ ce Lontacted d rect:y by tan cu er.
re%1 ting i t, the 5f'CLCW "O"
,tde 1 ".o l a t t o n.
tno M"LCR ryi:em nolit intc two tecar at e and i nd e or2 nd e M Ic < su by cat enat ically closint the honder c r o w-connett valvos ori *!n vtrtion
.m d tiucnarge headert of the FDCL~W Heat Fatbangorn and c a n n t.
- n t h e "4"
side.
The carve 111anen was ttoonci until inve2",tip tjen of a r.c a tNnt wac completen.
The uyttem was t h t.en re' tar ned "o its nwnal con f i c. ira t l er:.
There was no
<.a f e t y s a a n. r '. wc re t<
tr e event.
%o FDCLCel svnt ern
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operated a,
d o n t [ r,r. d.
C; 9 ext om carried c.u t all roautrec actiorm.
No 2CC
. g t i, v~
w f ra thhllef>ted or roquared
Plant N'a n nsrrst n t was nottfir'c of the o v ey n t and the NRC wan not1 Ptod at 1LCS ov 12CF fM. 72.
To orovent r ec u rror.co. TO 04.I111.01 hat o& en evited to uta11::e P r o r.h Pecorder io prov drs r r W> t U Canit.on ind2:ctton of tha level o
cwitchnn without havir; to re"Ovo the lim n i r.r.tch covnru.
In arid i t t e n.
o report cov e; 5 2 % tho i r,c, i d en t wil! Lttove recuired t
rearJing for all I6C t Echni c 2 *r.a, f orerr e n aw mw vvinort.
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| 05000322/LER-1986-001, :on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements |
- on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements
| | | 05000322/LER-1986-002, :on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired |
- on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired
| | | 05000322/LER-1986-004, :on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging |
- on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging
| | | 05000322/LER-1986-005, :on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency |
- on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency
| | | 05000322/LER-1986-007, :on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised |
- on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised
| | | 05000322/LER-1986-008, :on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised |
- on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised
| | | 05000322/LER-1986-009, :on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed |
- on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed
| | | 05000322/LER-1986-011, :on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220 |
- on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220
| | | 05000322/LER-1986-011-02, Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | | | 05000322/LER-1986-012, :on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication |
- on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication
| | | 05000322/LER-1986-013, :on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated |
- on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated
| | | 05000322/LER-1986-015, :on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed |
- on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed
| | | 05000322/LER-1986-016, :on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines |
- on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines
| | | 05000322/LER-1986-018, :on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised |
- on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised
| | | 05000322/LER-1986-019, :on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised |
- on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised
| | | 05000322/LER-1986-020, :on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector |
- on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector
| | | 05000322/LER-1986-021, :on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves |
- on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves
| | | 05000322/LER-1986-022, :on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps |
- on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps
| | | 05000322/LER-1986-023, :on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised |
- on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised
| | | 05000322/LER-1986-024, :on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress |
- on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress
| | | 05000322/LER-1986-025, :on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples |
- on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples
| | | 05000322/LER-1986-026, :on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised |
- on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-027, :on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer |
- on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer
| | | 05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced |
- on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
| | | 05000322/LER-1986-030, :on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists |
- on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-031, :on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities |
- on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities
| | | 05000322/LER-1986-033, :on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve |
- on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve
| | | 05000322/LER-1986-034, :on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down |
- on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000322/LER-1986-035, :on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc |
- on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc
| | | 05000322/LER-1986-036, :on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised |
- on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised
| 10 CFR 50.73(a)(2)(i) | | 05000322/LER-1986-037, :on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished |
- on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished
| 10 CFR 50.73(a)(2)(i) | | 05000322/LER-1986-039, :on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated |
- on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-040, :on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced |
- on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-042, :on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010 |
- on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010
| | | 05000322/LER-1986-044, :on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal |
- on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-045, :on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled |
- on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|