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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
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ag NRC FORM 306 U.5 NUCLE A3i f.80ULtTORY COMMisstLN APf R0vt0 0Mt NO 31604104 -
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OOCKti NUM01R 121 FA03 4 7 ACILITY NAME 01 Shoreham Nuc] ear Power Station Unit 1 o 16 l 010 l 01317 l 3 1 loFl n 13 7'T'8 **l RBCLCW unplanned automatic system-split while Instrument & Controls Technicians were perfonning a Surveillanm Test EVENT DAff tel LER NUMSIR (6 AtPORT DATE (76 OTHEfl F ACILITitt INVOLVED let MONTM OAY YEAR YEAR " OM ,
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0l5 0l 4 87 8l7 0l1 l2 0_ l1 ols 3 ls ojo o isto io ici l l TMis REPORT is susMITTED PURSUANT 70 THE RhoulmtMtNTS OF 10 Cf R i ten.ca on. er me,e e, ,ne ,ou. ,r (116 OPE R ATING M005 m 4 59 402tti 20 4061st < to.736aH2Hevi 73 7Hel n 20 405teHillil 60MtHu 50.73tell2Het 73.71tel n0, oi oio 20 0. ntn.n
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N1Mt TELEDMONE NUM9tR Amt A CODE George D.-Schnaars, Operational Compliance Encineer l l l l l 1 1 1 l COMPLETE ONE LINE FOR S ACM COMPONENT F ALLURE DESCRitt0 IN TMit REPORT H3i U AC yo PR'
$' CAUSE Sv8 TEM COMPONENT 0Ria i CAUS$ SYSTEM COMPONENT MA%AC g pp l i I I I I I I I I I I I I i 1 l l l l I l 1 I I l l I SUPPLEMENT AL REPORT EXPECTSD not MONTM DAY vtAR 8v0 Mis $10N i Yt$ II9P... comor. EX9ECTED SUOn,1$$10N Da ril NO l l l A , Ae, w -.,,,,a ,,-.,...... . . , ,, ,. .,, . ,,. ~ .,,v.,
On May 4, 198? at 1548, an unplanned actuation of an Engineered Safety Feature occurred. The plant was in Operational Condition 4 with the mode switch in Shutdown and all rods inserted in the core.
While Instrument & Controls technicians were performing a surveillance test of the Reactor Building Closed Loop Cooling Water (RBCLCW) head tank level switches, a technician lost his footing and accidentally hit the outside cover of a level switch. This caused the level switch to change state which resulted in a RBCLCW system split. Operators verified the signal as false and . .
imrediately took the appropriate action to return the system to its rormal configuration. Plant Management was notified of the event and the NRC was notified at 1652 per 10CFR50.72. Corrective actions
-included installing permanent ladders and platforms at the head tank level switches. This provides easier access to the switches ~and greatly reduces the risk of technicians losing their footing while Performing surveillance tests. This Supplemental Report is being submitted to inform the Commission of the status of corrective actions taken, m gooM 6 5 hl 050%f, NGC Form 366 46491 h
y 5 Xt11ES- 4/300 r LICENSEE EVENT REPORT (LER) 5 f,6"#Mo'fs'MWoi;'!;%"v ',Tio.c?T,7,T"Je's j TEXT CONTINUATION cN n'",'o'di$ig"oi'yl#',"d"c'n,'N M u '"!$ "n l PAPf RWD K Rt TION t'3 to ! I - i Of MANAGEMENT AND DVDGET,wAsMINGTON.DC 30603.
PACILITv esAMg up DOCKET NUMBER (31 PA06 (31 LIR NUMBER ($1 Y'A" ' NMn -
NNaN Shoreham Nuclear power Station Unit 1
, o l5 j o l 0 l 0 l 312 l 2 817 -
0 lll? -
n 11 nl9 OF nb Tax m . . me w maunn FLANT AND_ SYSTEM IDENTIFICATION Ganeral Electric - Boiling Water Reactor Energy Industry Identification System (EIIS) codes are identified
- in the' text as [xx).
IDENTIFICATION OF THE EVENT f
- Raactor Building Closed Loop Cooling Water (RBCLCW) [CC) unplanned automatic system split while Instrument & Controls (I&C) technicians were performing a surveillance test.
Event Date: 5/4/87-r l'
Raport Date: 5/16/90 l CQNDITIONS PRIQB TO THE EVENT Operational Condition 4 (Cold Shutdown) '
Mode Switch - Shutdown RPV Pressure = 0 psig
~
RPV Temperature = 170 Degrees F I All-rods inserted in the core.
DESCBIEI1QN OF THE EYENT l
On May 4,=1987 at 1548 an unplanned automatic Reactor Building Closed Loop Cooling Water (RBCLCW) system split occurred while Instrument & Controls (I&C) technicians were performing surveillance tost:SP' 44.118.03 (RBCLCW Head-Tank Level Low-Low Channel Functional Test).- An I&C technician was climbing up to the head tank level . ,
switches.to perform a step in the procedure when he.~ accidentally hit -
l the'outside' cover of level switch'1P42*LS013B causing the switch to i change state. .This caused a faise low-low "B" RBCLCW head tank
~ level signal resulting in a system split. The RBCLCW system split into two separate and independent loops "A" and "B", shedding nonessential loads as designed in' response to the low-low tank level l- L signal .- Operators verified the signal as false and immediately returned the-system to its normal configuration. Plant Management was notified of the event and the NRC was notified at 1652 per 10CFR50.72.
f
- NZC Fenn assA (6491
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f MFIXE4 4/300 LICENSEE EVENT REPORT (LER) $st'!,*o',uigR,pfol'@j',,To.cf'2,v TJ"Jg TEXT CCNTINUATION M*,'n'oM0fM"d 8
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TEM lk 9?'et OF MANAGEMENT AND SUDGET,1N ASHINGTON.DC 20603 e
F ACittiV KAME (U DOCILET NUMSER (23 4tn NUMeth (Si FAOL (31 n** " % C ." M3:
Shoreham Nuclear power Station Unit 1 I I
0F O 1510 l01013 l2 l 2 8 l7 -
011l2 -
01 1 0 13 0 14 text w . - m . w. .e m ,w w eF ,aav. m CAUSE OF THE EVENT Level switch 1P42*LSO13B is located adjacent to the "B" RBCLCW head !
tank in the reactor Building, approximately 20 feet abeve the floor l of elevation 150 ft. By procedure, it is required that the leve) '
switch identification tag numbers be checked to verify that the proper level switch will be tested during subsequent steps in the !
procedure. The identification tags are located on the outside of ,
the level switches. The level switches are out of normal reach. An !
Instrument & Controls (I&C) technician was climbing into position to i read an identification tag when he accidentally hit level switch l i
1P42*LS013B. While holding a flashlight in one hand, and holding
- onto a pipe with the other hand, the technician lost his footing and ;
accidentally hit the outside cover of 1P42*LS013B with the flashlight, i' This action caused the switch to change state. This resulted in a false low-low "B" RBCLCW head tank level signal resulting in a ,
RBCLCW system split whereby nonessential loads were shed as i i
designed. The technicians were adequately trained and qualified to perform their required tasks. l The root cause of the problem was the poor accessibility of the l level-switches. A contributing factor may be oversensitivity of the level switch. It should be noted that in November of 1985, a -
Station Modification (SM #85-064) replaced and upgraded several ,
parts in the-RBCLCW head tank level switches in order to ensure Environmental- Qualification. A review of the Environmental Qualification Report reveals that switch contact chatter was noted during seismic testing of the rebuilt level switches. This undesirable characteristic was accepted since " spurious operation of the switch can only cause the associated control circuit to assume its " fail safe" operating position".
ANALYSIS.SE_lHE EVENT ,
This event was an unplanned actuation of an Engineered Safety Feature (ESF). There was no safety significance to the event. The RBCLCW system operated as designed by splitting into two independent loops and was capable of performing its safety function. Had the event occurred under a more severe set of circumstances (5% power) there would still be no safety significance.
CORRECTIVE ACTIQHS
- 1. An investigative plan was developed to determine the need to modify or replace the RBCLCW head tank level switches to reduce sensitivity. Implementation of this plan has been deferred indefinitely due to the New York State-LILCO Shoreham Settlement Agreement.
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extixEs e/3052 LICENSEE EVENT REPORT (LER)- $;ittjy oAugff,y,0'l;g$i,%cg;7 yga, gig -
TEXT CONTINUATlON g;y,To$jgio,* Igg 30(M5lJ"fll3'o ;",' RMoag P APE RWO R4 Tio J l'3 600 .l IC OF MANAGEMENT AND BUDGET WASHINCTON DC 20603-
'a FACILirY NAME (1) DOCKET NUM0ER (2t ggg gggggn gg) PAgt (31 vlam 5E g,QA4 -
",EJyssm
' Shoreham Nuclear power Station Unit 1 .
0 16l0lol0 b l2l 2 817 -
01 1l 2 -
011 014 OF n ja rixv in N w. we i asuw mi 2.- Permanent ladders and platforms have been installed at the head tank level switches to provide easier access.
- 3. Identification tags were installed on the level switch piping m assemblies where they may be reached more easily than the tags that were' installed on the level switches. ~The necessary l verifications are now made by reading'the tags at the more accessible locationn which will reduce the possibility of disturbing the level switches. The appropriate procedure-changes were also made.
- 4. Caution statements were added to appropriate places in Station l Procedure 44.118.03 "RBCLCW Head Tank Level Low-Low Channel Functional Test" to caution technicians of the sensitivity of the level switches.
- 5. A report describing the incident was read by all Instrument &
Controls (I&C) technicians.
ADDITIQHAL_INFORMATION
- a. Manufacturer and model numbgr_2f_ failed SQmponent_Lal None
- b. LEB_ numbers _.of_ previous similar_ events
,86-008 (Event date 2/14/86)
L l 86-024 (Ev'ent date 5/22/86) l 6
l .', '
l l'
NIC Penn 306A 16491
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05000322/LER-1987-009 | 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-1987-012 | 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-1987-014, Forwards LER 87-014 & Rev 1 to LER 86-029 | Forwards LER 87-014 & Rev 1 to LER 86-029 | | 05000322/LER-1987-022 | 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-1987-035 | 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 | |
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