|
---|
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-2087-022, |
Event date: |
|
---|
Report date: |
|
---|
3222087022R00 - NRC Website |
|
text
. - . .
L, i c,'omu 26 u s LuctitA istut&t04v 50Mwastich ,,,,,pyg g op, g pp, miais .m Np MAT ON C L 8 51 85 8 alsam
. LICENSEE EVENT REPORT (LER) co uisn aic =o tci 0~o evants tsiiu.tip55 o tot tascomos ,
AlTv7!*,o"'v e"o'u' S"ol"isU.'5",f="$n'u"Q@
s' oui'c"a.'iu *,n%'n'af0.Reeft'c%e"'
. .clut , .... .u oocale numeia ai ==a Shoreham Nuclear power Station Unit 1 oisIol0l0l3l2 2 1 1 loFl Og 3 titti .
Voluntary Report on fOV Dynamic 'Ibsting Failure of the 54pCI Recirculation Valves IVth, Datt ill sta Numsta 16i htP0ht Datt 47: OtHth 8 ACititill #WVOLVID tei DOckt1 NUW6t ht&>
~
MON 1H Dar vlam vtAR 58,y,$ ('4 [l,*,$ MONim DAY vtAR .acuvv hawls 016l0l0lo1 l l
~ ~
0 l6 O! 4 R 7 8 l7 0l2l2 0l1 0l 5 1l6 4 l0 _
, c :. .. ., . ., ,a. ,..... i n u o g6 io l0 io l l tuis aimont is iv untto evaiva=, to t t Loviniutun oe a ce p,, ,,, ,,,o "00' "' 2 n .catoi no .ooi.: 6e n unn i n vuoi so mi.ini g n mewinno
. n oi.,.,
oo n iun.i n n.n.n..,
n tu.i
=,g,;.,.g,,,
, , O i ni 4 .in n.:
_ _ t ,
. i.in n.i eo ni..no n n. i. ii..n., m.,
n essain n. son.nin.: n noun..nei ro m.in n.i
~
so n.nsu o
~
so ni.innii
'oluntary Report uctwant coutmet som tuis sta nei nim 4 18ttPHOht huv9th anta CODE George D. Schnaars, Operational Ccripliance Engineer 51116 ol?Io1 IA h Inin Compttfi DNt 44NI 90R I ACM COM*0 Nth? 9 Altunt DItchittD th tMit htPORT Hai at> ""[g$C 0ata C1W58 Sv41t M 00M*0ht 41 Waj8jc 1,A Lt CAult tvtTiv COMPohl41 p hpp i I i 1 1 1 1 1 1 1 1 I i 1 1 I I I I I I I I I I I I I SUPettMINtat alpDat luttetID H.' MON 1r Dat vlam SgDwilliDN l vt S CH v.s ..*wer, ik9tCilO SV0VIS$ lok Da TEI %D l l l
.n t ac t n -, > = < , . . ,. . ~.,,, ,.,, . ., . <. ... . . . . . n . ,
On 6/4/87 at 0400, while conducting MOV Dynamic Testing, the High Pressure Coolant Injection (HPCI) test valve to the Condensate Storage Tank (CST) 1E41*MOV-037, a globe valve, and the HPCI/ Reactor l
Core Isolation Cooling (RCIC) test valve to the CST, IE41*MOV-038, a l gate valve, failed to close against the system operating pressure of l
the High Pressure Coolant Injection (HPCI) system. The valves are I required to close on a HPCI automatic initiation signal. Testing
! was discontinued and the valves verified closed. The Nuclear Engineering Department determined corrective action for this condition. A modification to the disc of MOV-37 to alleviate a local pressure build-up was implemented and for MOV-38, new gearing was installed. This Supplemental Report is being submitted to inform the Commission of the completion of these modifications and that testing of this work has been deferred indefinitely due to the New York State - LILCO Shoreham Settlement Agreement.
l 9005240078 900516 PDR
~'
AcoCK OD000322 PDC I
nc e.- m an,
IIest.C 90AM 3064 U.S ofUCLiAR 4 80UL.TD8 V COMustt:0N g,p py, pp pppg N' tx7684 W3012 LICENSEE EVENT REPORT (LER) Sp;'?,ffg,pJJ'8;pjijo.ff';'fg ;T,",'g!
TEXT CSNTINUATION tog A %8/foy fpij g ! g gyllh;o!"l g ,aff M7 Ale"Jo!?"fs'jNeo"'Wo*ll?iA*oE?b0?il?
. 0F MAN AGEMENT AND DVDGET.W ASMiWGTON.DC 706&3 DOCESTeduMelttai g gp , pg ,
8&Cebett hAut m ma 5'tuit' "Uf,f:
Shoreham Nuclear p wer Station Unit 1 o p j o j o j o l3 l2 (2 0l1 0 l2 0F 0l3 8l7 .-
0 l2 l 2 -
vartn -o.-.. = w.o.o we %ana m, DESCRIPTIQN_QE_THE_EYEHI A Voluntary Report was originally submittod to inform the Commission of the following condition which was discovered at the Shoreham Nuclear Power Station:
On 6/4/87 at 0400, while conducting MOV Dynamic Testing, the High Pressure Coolant Injection (HPCI) test valve to the Condensate Storage Tank (CST) 1E41*MOV-037, a globe valve, and the HPCI/ Reactor Core Isolation Cooling (RCIC) test valve to the CST, 1E41*MOV-038, a gate valve, failed to close against the operating pressure of the High Pressure Cooolant Injection (HPCI) system. The valves are in the recirculation loop to the CST. The system was in the recirculation mode, taking suction from and' discharging to the CST.
These valves receive an isolation signal in the event of an outomatic HPCI initiation. As such, they are required Both to close MOV's failed to against system design differential pressure. l do ao when tested individually, although when actuated simultaneously, they were able to close against system pressure.
Testing was discontinued and the valves were verified closed. This condition has been reviewed and has been determined to be not reportable under 10CFR50.73.
This Supplemental Report le being submitted to inform the Commission of the actions taken to correct the above condition.
CAUSE OF THE EVENI The failure of MOV-037 to close was due to higher than expected differential pressure forces resulting from the large valve disk guide area. These forces were not taken into account in the vendor's calculations. Additionally, the actual gear ratio (124:1) is less than the ratio used in the actuator sizing calculations (150:1). This resulted in a faster stroke time but reduced the available stem torque.
The failure of MOV-038 to close was due to the actuator gear ratio being too low. In this case, the vendor's calculations for actuator sizing and torque switch setting did not include sufficient margin to account for uncertainties.
l l
l yetCPosen3e6A16491 l--____-.
g _ ,
s=, ass en,
' f,Us*0%'f3!*d%*f,",l',,' .!fQl ,T"J"'!
UCENSEE EVENT CEPORT (LER)
TEXT C3NTINUATION R" tit #,Po'"Mi 'is?',* R'c'Sl# 'vR'jf,"f! ,
S.tv,Wa".'Ji",7.t'al,', Ret;?%c m'A 'stai o ,
g O WANAOLMSNT AND DVDC(t Wal**lNGTON DC 20b03
$ ACt4tf V hAML H) DOCh41 NVM0LR Lil W NMk @ W@
uma "b'alt' W *.72 Shoreham Nuclear Pcuer Station Unit 1 0 610 l 0 0l3 2 l2 47 -
Ol2l2 -
Ol 1 0 13 0F 0 13 vertu== . w. =c % muv mi CQERECTIVE_ACHQHS 1E414MOV-037 - 1 Based on discussions with the vendor, inspection of the valve '
i internals, review of the disk geometry, and vendor test results on a smaller but similar valve, a modification was implemented which involved drilling holes in the top and bottom valve disc guides. This will reduce the differential pressure across the valve disc guide and consequently reduce the force necessary to close the valve.
1E41*MOV-038 Based on a review of the motor operator sizing calculations, a valve internal inspection and discussions with the valve vendor, new actuator gearing was installed. This change raised t the gearset ratio from $6.64:1 to 77.25.1. This increased the stroke time but reduced the amount of motor torque required to close the valve.
Testing of these modifications to the two valves requires closing the valves against full system pressure and flow. This has been deferred indefinitely due to the New York State - LILCO Shoreham Settlement Agreement.
L t
I l
i 1
i C;CPennse6A16491
!
|
---|
|
|
| | Reporting criterion |
---|
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 | |
|