|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000322/LER-1989-0051990-05-16016 May 1990 LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1988-0171990-05-16016 May 1990 LER 88-017-01:on 881025,discovered That Seismic Monitoring Instrumentation Returned to Svc Prior to Verifying Sys Operability & Special Rept Not Written.Caused by Personnel Error.Surveillance Engineer Reassigned 05000322/LER-1988-0151990-05-16016 May 1990 LER 88-015-02:on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed 05000322/LER-1988-0031990-05-16016 May 1990 LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked 05000322/LER-1987-0351990-05-16016 May 1990 LER 87-035-02:on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired 05000322/LER-1987-0221990-05-16016 May 1990 LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified 05000322/LER-1987-0121990-05-16016 May 1990 LER 87-012-01:on 870504,uplanned Actuation of ESF Occurred. Caused by Technician Loosing Footing & Accidently Hitting Outside Cover of Level Switch.Permanent Ladders & Platforms Installed at Head Tank Level Switches 05000322/LER-1986-0391990-05-16016 May 1990 LER 86-039-01: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 05000322/LER-1986-0321990-05-16016 May 1990 LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys 05000322/LER-1986-0141990-05-16016 May 1990 LER 86-014-01:on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 1153 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 1990-05-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20080G4691995-01-26026 January 1995 Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 ML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20044C1181993-02-28028 February 1993 Shoreham Nuclear Power Station Updated Decommissioning Plan. ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20128B9641992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20114A6311992-07-28028 July 1992 Shoreham Decommissioning Plan ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station1991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station1991-06-30030 June 1991 Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station1991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 19901991-04-15015 April 1991 Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station1991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station1991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station1991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 19901990-12-31031 December 1990 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,19901990-12-31031 December 1990 Shoreham Nuclear Power Station Annual Operating Rept,1990 SNRC-1799, Lilco 1990 Annual Rept1990-12-31031 December 1990 Lilco 1990 Annual Rept ML20069Q3901990-12-31031 December 1990 Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station 05000322/LER-1988-0151990-05-16016 May 1990 LER 88-015-02:on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed 05000322/LER-1986-0391990-05-16016 May 1990 LER 86-039-01: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 05000322/LER-1986-0321990-05-16016 May 1990 LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 05000322/LER-1987-0221990-05-16016 May 1990 LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified 05000322/LER-1989-0051990-05-16016 May 1990 LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 05000322/LER-1987-0351990-05-16016 May 1990 LER 87-035-02:on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired 05000322/LER-1988-0031990-05-16016 May 1990 LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked 1997-05-01
[Table view] |
LER-2088-003, |
Event date: |
|
---|
Report date: |
|
---|
3222088003R00 - NRC Website |
|
text
' - '
1 i
e gCy0Rw30s v.s. Nuct tins 0wt AT0 w COMwissiON a,,,nysp py ,No gigogip.
E XPIRil 4'30/22 i acATs0N L ECT O st 6t Mas F m AmI I LICENSEE EVENT REPORT (LER) covules itoAnoiNO.oUR0iNistiuATETOTHERiconos
'Mv"L #0R v' e"0u'u'?ss E". IUiNE EN oE Ei E"Ad5 %"
j s'autit fan %E'"!MaRfC%e'" .
, ACitif y AMi nl -o0CatiNvMein m An a !
Shoreham Nuclear poder Station Unit 1 0 l5 l 0 l010 l3 i 2l2 i lor l0 l 3
"' . Unplanned autcxmtic initiation of RBSVS "A" Train during an Instrument and Controls surveillance tarocedure when a technician inadvertantiv deenercized a m1w SYtatT DAf t ill i tt R NUM9t R 161 REPott DAf f 171 CTMER f ACILetill INv0Lvt0 401 -
Mold M DAY YE AP' l YE AR ."'f,*,$ MONTM Dat
- EAR ' A C'b't v h a ve s pocast Nowetaisi
bY '" n 0161010101 1 I
~ ~ '
O l3 2 l2 8 8 8l8 0l0 l 3 0l1 0l 5 1h 9 l0 0 1 6 1 0 toioi i I g,gggg g THIS fitP0 fit IS SUDMITTSD PUR$UANT TO TME AkoutRIMENTS Of 10 CF A $ Icaeca ene e, spece er rae tone .ap) e1:
MODE m 4 M 402M 20 4061el g W.734.l4Hwi 73 f tthi g _
n .csi.HiHa _
.0 mi.ini eo.,3i.H: H.,
. H, H.. ,
13w.i n0, o i O 10 n .0 6.Hin.,
.0 =i.n I
_ _ =g,,;.,Ag M 405telt1Hn6t 60 73isH2tfel to 73ialGHea4Hal J66As M 400(sHi Havl 60.73neH2Han to ?$isH2He*6iHSI
- 0 4061aH1Het 50.? $6eH2 Heill to 73leH2Hal LICEN8tt CONTACT FOR THIS Lim n21 Navt TitlPMONE NUM9t h ARE A CODE George D. Schnaars, Operational Ccmpliance Engineer 5 i l6 i 92;9;i g 8,3 l0 ; O ,
COM*Lif t ONE IINE 80R EACM COMPONENT f ALLURE DitchistD IN TMit AtPORT H3)
CAust stsfiv Cowa0Nf *:? "'[X','C "fo Pm s CAvst 8vstiu cov>0NENT W yANd AC at POR T agt i i i i l I I i I i I I i !
I I I I I I I I I I I I I I SUPPLEMENT AL REPORT tmPECTED (14 MONTM Dev YEAR tti II9 vee te*neset. ik9tCTIO SUOnetsSION De tti ko l l l Au ra.C, ,s . a .e o .x ~ . . . .ne. . , r~.. ,,, nu. , e.-~n., u.,> n s ,
On March 22, 1988 at 1436, an unplanned automatic initiation of the Reactor Building Standby Ventilation System (RBSYS) "A" side occurred when an Instrument and Controls (I&C) technician l Anadvertently deenergiced a relay during a surveillance test. The plant was in Operational Condition 4 (Cold Shutdown) with the mode switch in shutdown and all rods inserted in the core. The technician was performing a channel functional test on the i instrument loop which initiates RBSYS on a low reactor building differential pressure signal. He had begun to reterminate the leads which he had lifted on Relay 3B-1T46A19 prior to the start of the test. However, while he was performing this step one of the leads slipped out of his hand causing the deenergization of the relay, resulting in a RBSVS "A" train initiation. After the leads were l
reterminated, the procedure was halted. Operators verified the I
signal and took the necessary steps to return the RBSYS to its normal configuration. Plant Management was notified of the event l and the NRC was notified at 1459 per 10CFR50.72. This Supplemental Report is being submitted to inform the commission of the status of corrective actions taken, h$
S bob '
,f N. C 7 eem 3661649)
- us wucteam a soutet.av consensesion grones ses' IDIMS of3092 [
LICENSEE EVENT REPORT (LER) $sy'gAu;gR,M?oMRj',,'%egnjt,v 7gygg TEXT CONTINUATION $"*g,'o'ji',odguinM',ufl/"fltR;1'Wefif!
- 'it'JA"Jon*te'a*;'00iaWA M!,li ce ua=aos weut awo avocit.womustow. oc poa. l
,*cwv won m oocut avuesa m tin wousin isi emos c > ;
viaa "htW. "'J,*.TO Shoreham Nuclear pwer Station Unit 1 0F 0 13 0 l6 l 0 l 0 l 0 l 3 l 2l 2 8 l8 -
0 1013 -
Ol 1 O l2 meu . - =c % m.wim f.
PLANT AND SYSTEM _ IDENTIFICATION ,
General Electric - Boiling Water Reactor ,
t Energy Industry Identification System (EIIS) codes are identified in the text as [xx).
IDENTIFICAIION OF_THE_EVEHI ,
An unplanned automatic initiation of an Engineered Safety Feature (ESF), Reactor Building Standby Ventilation System (RBSYS) (BH] l occurred when a lead being lifted by an Instrument and Controls .
(I&C) technician while performing a surveillance test, slipped out of his hands, deenergizing a relay.
Event Date: 3/22/88 Report Date: 5/16/90 l CONDITIONS PRIQB IQ THE EVEBI Operational Condition 4 (Cold Shutdown)
Mode Switch - Shutdown RPV Pressure : O psig RPV Temperature : 111 degrees F POWER LEVEL - 0 I
All rods inserted in the core.
DESCRIPTION OF THE EVENT On. March 22, 1988 at 1436, an unplanned automatic initiation of the RBSYS "A" train occurred during an I&C surveillance test. A technician had removed the leads from the terminals of Relay l 3B-1T46A19 to prevent the initiation of the RBSVS "A" train to perform a channel functional test on 1T46*PDT043A (Reactor Building Differential Pressure Transmitter) in accordance with SP 44.650.16 I (Reactor Building Differential Pressure - Low Channel Functional Test).
After the test was performed, the tech. relanded one set of '
leads on the relay and was preparing to reland the second set.
While attempting to insert the screw through the lugs into the terminal, one of the leads came loose and made contact with an ;
adjacent terminal causing the 3B relay to deenergize. Deenergizing the relay resulted in the initiation of the RBSYS "A" train only.
After the leads were reterminated, the procedure was halted.
Operators verified the signal and proceeded to return the system to its normal configuration. Plant Management was notified of the !
event and the NRC was notified at 1459 per 10CFR50.72. !
esRC Penn 30sA (6491
gc,,. a oumu auso.v oo . .oh , , , , , , , , , , , , , , , ,
t RPICL$ 4130'92 LICENSEE EVENT HEPORT (LERI S';*^4',D,,* ug,%l',5l%"54,'%CfT' is"dQ TEXT CONTINUATICN j74*,M!"dgni*i,W'AlflC'**/l#'u"'0',C{'iff P Ptf WO I T eo J (3 60 BC l Of MANA0lMit(1 AND DVDGET,W ASHINGTON.DC 70603.
8 ACILITY hAML 01 DOCali NuMtL A L2t Ltk hum 0th (Si Pact (3) 9 sam f
- Lfi,[*4 ."'d?,'N Shoreham Nuclear Poder Station Unit 1 Ol3 0F 0 13 0 l5 l 0 l 0 l 0 l 3 l 2l 2 8 l 8 -
0l 0l 3 -
0 l1 Text rn = w. wwwc a smuunn CAUSE_DE_IHE_EYESI This event occurred because the accessibility to the terminals is extremely difficult. The relay is located in the lower portion of the panel (1H21*PNL-VX1) forcing the technician to crouch in order to perform the procedure. Lifting the leads at the relay terminals is difficult since the terminals are located very close together.
Caution steps already exist in the procedure for lifting the leads from the terminals and for reterminating them. The technician was fully aware of the consequences and was using extreme care while performing the procedure.
l ANALYSIS _DE_IHE EVENT This event resulted in an unplanned automatic initiation of an Engineered Safety Feature (RBSVS) and is reportable per 10CFR50.73(a)(2)(iv). There is no safety significance to the event.
The RBSVS operated as designed and operators carried out all reguired actions. No other systems were challenged or required as a result of the event. Had this event occurred under a more severe set of circumstances (5% power) there would still be no safety significance.
l COBBECI1YE_ACIl0SS
- 1. A wiring change has been made which reworked the wiring inside the electrical panels. This ch'.nge allows leads to be lifted
, from a terminal strip rather than the relay in order to prevent an RBSVS actuation.
- 2. A modification has been prepared which will install keylock l switches in the front portions of the associated electrical panels. These switches will disable the RBSYS initiation logic l
! and will allow performance of the surveillance test without l having to lift any leads. Implementation of this modification l has been deferred indefinitely due to the New York State -
l LILCO Shoreham Settlement Agreement.
ADDITIONAL INFORMATION
- a. tianniacturer_and_mndel_ number _ni_f ailed _comnonent_Lal l None l
- b. LEB_ numbers _of_ previous _similar_eyents85-050, 86-026,86-038 86-044,89-010 I CIC Fe,m 3e6A (6401
|
---|
|
|
| | Reporting criterion |
---|
05000322/LER-1988-003 | LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked | | 05000322/LER-1988-015 | LER 88-015-02:on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed | | 05000322/LER-1988-017 | LER 88-017-01:on 881025,discovered That Seismic Monitoring Instrumentation Returned to Svc Prior to Verifying Sys Operability & Special Rept Not Written.Caused by Personnel Error.Surveillance Engineer Reassigned | |
|