|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045B3551993-06-11011 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 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 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 ML20012C5131990-03-16016 March 1990 LER 86-029-02:on 860718,19,21 & 870508,loss of Reactor Protection Sys Power Occurred Due to Spurious Tripping of Alternate Feed EPA Breakers.Caused by Low Output Voltage of Alternate Feed Transformer.Output adjusted.W/900316 Ltr ML20006E1571990-02-0909 February 1990 LER 90-001-00:on 900117,unplanned Actuation of ESF Reactor Bldg Standby Ventilation Sys B Occurred,Causing Interlocking Relays in Control Circuits to Deenergize.Caused by Transient Voltage Dip.Procedures Re Bus Loads modified.W/900209 Ltr ML19354D8331990-01-12012 January 1990 LER 89-011-00:on 891222,unplanned Actuation of ESF Primary Containment Isolation Sys Occurred When Performing Sys Layup Implementation Package for Hpci.Caused by Inadequate Procedure.Breaker Positions changed.W/900112 Ltr ML20005F8641990-01-11011 January 1990 LER 89-010-00:on 891212,unplanned Actuation of ESF Control Room Air Conditioning Train a Occurred.Caused by Removal of Leads from Relay During Test to Prevent ESF Sys Actuations. Electrical Relay Replaced & Wiring Mod made.W/900111 Ltr ML20011D2371989-12-15015 December 1989 LER 89-009-00:on 891115,notification Received of Potential Failure Mechanism of Four 3-way Solenoid Operated Pilot Valves.Caused by Incorrect Mounting of Valves.Valves Remounted Vertically & Field Walkdown done.W/891215 Ltr ML19332C5591989-11-15015 November 1989 LER 89-008-00:on 891016,control Room Alarms Received Indicating Fire Pump Had Started & Deluge Valve Had Opened. Caused by Actuation of Manual Pull Station.Deluge Sys Restored to Normal & Personnel interviewed.W/891115 Ltr 1993-06-11
[Table view] Category:RO)
MONTHYEARML20045B3551993-06-11011 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 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 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 ML20012C5131990-03-16016 March 1990 LER 86-029-02:on 860718,19,21 & 870508,loss of Reactor Protection Sys Power Occurred Due to Spurious Tripping of Alternate Feed EPA Breakers.Caused by Low Output Voltage of Alternate Feed Transformer.Output adjusted.W/900316 Ltr ML20006E1571990-02-0909 February 1990 LER 90-001-00:on 900117,unplanned Actuation of ESF Reactor Bldg Standby Ventilation Sys B Occurred,Causing Interlocking Relays in Control Circuits to Deenergize.Caused by Transient Voltage Dip.Procedures Re Bus Loads modified.W/900209 Ltr ML19354D8331990-01-12012 January 1990 LER 89-011-00:on 891222,unplanned Actuation of ESF Primary Containment Isolation Sys Occurred When Performing Sys Layup Implementation Package for Hpci.Caused by Inadequate Procedure.Breaker Positions changed.W/900112 Ltr ML20005F8641990-01-11011 January 1990 LER 89-010-00:on 891212,unplanned Actuation of ESF Control Room Air Conditioning Train a Occurred.Caused by Removal of Leads from Relay During Test to Prevent ESF Sys Actuations. Electrical Relay Replaced & Wiring Mod made.W/900111 Ltr ML20011D2371989-12-15015 December 1989 LER 89-009-00:on 891115,notification Received of Potential Failure Mechanism of Four 3-way Solenoid Operated Pilot Valves.Caused by Incorrect Mounting of Valves.Valves Remounted Vertically & Field Walkdown done.W/891215 Ltr ML19332C5591989-11-15015 November 1989 LER 89-008-00:on 891016,control Room Alarms Received Indicating Fire Pump Had Started & Deluge Valve Had Opened. Caused by Actuation of Manual Pull Station.Deluge Sys Restored to Normal & Personnel interviewed.W/891115 Ltr 1993-06-11
[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] |
Text
'
ge LONG 18 LAND LIGHTING COM PANY t kN
.SHOREHAM NUCLEAR POWER STATION P.O. 00X 610. NORTH COUNTRY ROAD + WADING MlVER. N.Y.11792 ,
Direct Dial Numbers December 15, 1989 FM 89-219 l U.S. Nuclear Regulatory Commission ;
Document Control' Desk !
Washington, D.C. 20555 ,
Dear Sir:
In accordar.ce with 100FR50.73, enclosed is Shoreham Nuclear Power
. Station's-Licensee Event Report ?lR 09-003.
2f i
. Sin orely ours-
./ fg / ffp Jac A. Notaro Plant Maneger y- CN/RP/jp i
f, Enclosure !
cc s - William T. Russell, Regional Administrator Frank Crescenzo, Senior Resident Inspector i Institute of liuclear Power Operations, Records Center
'American Nuclear Insurers SR.A21.0200 i
l-l l
8912260028 891213 PDR S ADOCK 05000322 PDC yp
' FC 8935.2
- . . - - . . ~
g ,, -. i
..c ,. aos . u . .ucts:s kalu62io., ton.nesion, l
~
AP'9tovt) Cast so atto.etts '
LICENSEE EVENT REPORT (LER) '*"'"
j
~
..cio,. n. ooc. , .u . u, ... a goreham Nuclear Ptwer Station Unit 1 0 ]6 l 0 t o 10 l 31719 1brlo15 Improper Installation of Solenoid Operated Valves i
_',,i',"*^" u..uuu. ,
.. . n in o, .. ..cio,in .=vo6vio i o.v. uv vi.. n .. -
ump ,.. ,g ,,,,,,,, o, ,,,,, ...u,,... mu i .,u . ..., ;
O15101010 1 1 I j
~
1 l1 1l 5 89 5l9 0l0%
~
0p 1l 2 1j5 8l9 o,6,oio,o, ; ; )
..., ,asme**, aus.im. u u. ,so, ...ui....n.,i.c,.,,c.. ., enu
., I pt.ast.tl St eettel 00,1),elttHevi ,3.,1161
. Se eetteHHfG gg.gpg,ng go pgesygne ,3 ,g gi e.,
oio o ,n H., ,,,, ,,,,, , , , , , , , , _ . . . , ,
(.[D[ [hg ,,,,,,,,
'8 8'*l'80H81 90.994 19110 98.76.sH8HesNHal .)
' ~
khx %
3.[ _
n esetsHille,l go,pgg,ygygg go gg,ygig,egig; ,
90 ess,sitiHet afi,Ns HSHealt to.,3leH3Het t.cs.eas cowi.e ,o. ,nis te. nu I
,$ 4 8 9Hof,( IguM$ $ .
-David A.~ Smithroperational Compliance-Enginer
.1 h' 939, y % 3 pp m . . . .. .n. . .... .a ._. ;w... . .. .... .. r.,,, = -
1 cavu mnv eewowm uage. Tg,,,y ggq/# c uu ,,m, ce,,o .m l..ag,* yp,*,,ig gQ )
- .__.q _
_I.
i i -
- p i . @%1 s ; i ,,I i i )
lQikq l
l 1 I I I l.u_6...cu L _,_ _ ,_ 1 I I I I i I i
.p., eeno n., _ ,,,,,,,,
.mi ... u .. I w ..u o. 1
J m ew= mnw s u,.,,um u,,, ~] ,- '^""" '
l g ; l Tsii. i et = ..T ~. :"T;;, . .., .,% .,p;.. .,, .. , n., ----
On November 15, 1980 at 3500, the Watch Engineer was notified of a :
potential f ailure mcch.nism of four 3-stay solencid operated pilot i valves, 1T46*SOV-036A, 035B, 037A and 037B. These SOVs are the pilot valves for the Reactor Building Standby Ventilation System (RBSYS) inlet and outlet air operated isolation valves 1T46*AOV-035A, 035B. 037A and 037B. During an accident situation, a concurrent failure or malfunction of these SOVs could prevent or slow down the closing of the isolation valves and result in the ,
potential atmospheric release of effluent gas from the Reactor '
Building. The SOVs were mounted horizontally rather than vertically which was justified by their Engineering Design Basis but which may have contributed to operational reliability problems. This event was determined to be reportable per 10CFR50.72 (b) (2) (iii) (C) and the NRC was notified at 1532. This Licensee Event Report is being submitted per 10CFR50.73 (a) (2) (v). The SOVs are made by Automatic Switch Co.; their catalog numbers are HV206-832-6F,
.L206-380-6F and L206-832-6F. Corrective actions include remounting the four SOVs vertically, conducting a field walkdown of similar SOVs to verify their proper installation, modifications, and I continue to do frequent testing of the AOV's to monitor and reestablish reliability.
t
( .-
i l'
ee . mea
- u s cucaen muuioar ca wio=
UCENSEE EVENT REPORT (LER) TEXT CONTINUAT.*0N *=ovio ove =o siw-osos expiais sti se i enciusv mana m >oc=" au=** a m ua aume a iii eau m
%*a "RO;P t'#.72
! Shorehan Nuclear power Station Unit 1 o p jololol3l2 p 8l9 -
0l0l9 -
l 0p or 0 l5 :
mv . mewanmm l l ELANI_.AND_SYSIEtLIDENIlEIC AT ION E
General Electric - Boiling Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as (xx).
IDENIIEICAIIDH_DE_.IHE_EYEHI l
Event Date: 11/15/89 Report Date: 12/15/89 CONDJT10HS_fB10B_IO._IBE_EYENT Reactor Defueled - All fuel sesembifes stored in the Spent Fuel Pool i
(Mode t Switch - Chutcown i RPV Pressure = 0 peig RPV Temperature : 84 Pogrees F POWER LEVEL - 0% 1 DESDBIEIION_DL':'UE_EYENI On November 15,1989 at 1500, tne Watch Engineer was notif$ed of a potential failure mechanism of four 3-way solenoid operated pilot valves (SOVs) in the Reactor Building Standby Ventilation System (RBSYS) [EH). These 4 SOVs hac' been mounted with their solenoids in ;
o horizontal position rather than vertical and upright as per the manufacturer's preferred orientation. The valves had been the subject of recent investigations of Surveillance problems with their i essociated AOVs. This event was determined to be reportable per-10CFR50.72 (b) (2) (iii) (C). Plant management personnel were ;
notified and the NRC was notified at 1532.
The SOVs (IT46*SOV-35A/B and 37A/B) are pilot valves for the' Reactor Building inlet and outlet air operated isolation valves, IT46*AOV-035A/B and IT46*AOV-37A/B. The SOVs are normally energized to allcw instrument air to hold open the isolation valves which permits outside air to be supplied to and exhausted from the Reactor Buildins. - In the event of a power fallure or other accident oenditions, these isolation valves are designed to close cutomatically.
1 eoav 3.ee e u s oro isse nets as j
r 1
U $ I'UCLli3 $tipl1 TORY COMMC$tD=
008BC Dees > Mee LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ***aovio ove =o no-oio.
(KPihtS. t 31's
- AceLeiv haast n, pocali seuMeta ut Lim NunettR ($1 PA06 E3'
,t., u o ,. w .. ...e i Shoreham Nuclear power Station Unit 1 o 15101010 h 1919 a lo -
,Inlo -
nIn 0 13 M 0 15 viu - . % an.v nn This event was discovered while investigating the root cause of the periodic failures of the Reactor Building Automatic Isolation Valves IT46*AOV35A/B and IT46*ACV37A/B, to meet their 10 second closure times as required by Technical Specification Table 3.6.5.2-1. It is now believed that the horizontal mounting of the SOVs may have contributed to these periodic failures.
Because a verbal report to the NRC was made per 10CFR50.72 and because of the submission of this Licensee Event Report per 10CFR50.73(a)(2)(v)(C), LILCO considers this report to fulfill any reporting requirements that may be required by 10CFR21.
CAUSE QE_IBE_EYENI The SOVs were installed with solenoidt mounted horizontally. '.'h i s is contrary to the preferred configuration which states that the SOVs should be mounted with their soienoida verticsl and upright.
The fact that the SOVr were mounted in an Orientation 90 deg/ees off of the vertical was previously approved. The air-operated isolation valves (AOVs) supplied by Fisher Controls came with ASCO SOVs premounted. When these AOVs were ir, stalled the SOVs ended up horizontal. Thir was noted during the Torrey-Pines Independent Review of the Shorobam Nuclear Power Station (September 30, 1982).
It was also noted during the Environmental Qualification Status Report verification walkdown perf ormed n.id-1983. Because the generic qualification testing performed by ASCO for the HV206-832-6F SOVs did not meet the more stringent seismic test requirements for Shoreham, ASCO was requested to perform additional seismic >
qualification testing of tho.SOVs when mounted horizontal 1r. The test results are documellted in ASCO's Test Report No. AQR-67594, dated Jan. 8, 1985. The horizontnl mounting of the SOVs was accepted based upon the following items: 1) ASCO,s Test Report No.
AQR-67594, 2) the architect engineer's seismic calculation which verified SOV operability when mounted horizontally, and 3) the fact that the associated air-operated isolation valves met their closure time requirements.
The mounting of the SOVs was not changed in 1988 when the four SOVs were replaced with models L206-380-6F and L206-832-6F at the end of their environmentally qua]ified life. The modification design process used for this work took credit for the original installation design basis; therefore the work only involved replacing SOVs with similar ones, go. .u w oi m o m m m
c i e. .
ac e aina u a tve6in novmonv couuinsio
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ** aovtoousno 3 % eio.
t xPsRt s. 0 '31 '06 taceuty han,g p, Docneiasveesta m Lan huneet A 46 Pact (31 taa " t'.Wt' ;'A*.,3 Shoreham Nuclear power Station Unit 1 o p jolojo12 b 19 nb -
n h Io -
nl n n la " oI5 m, oa ,.,. e a .,., nama ec o anw nn The Plant had experienced reliability problems with the AOVs to which the SOVs may have contributed. Continuing investigation of these problems led to issuance of LILCO Deficiency Report 89-189.
Upon dispositioning of the LDR a reportability determination was initiated for a potential mounting discrepancy with the Environmental Qualification Documentation Package. This problem was reported per 50.72(b)(2)(iii)(C).
The Nuclear Engineering Department also began reviewing the design basis of the valves. The engineering design basis review determined that the valves would fulfill their design basis safety function in their original configuration. Due to the physical construction of the SOVs, the horizontally mounted SOVs may be more sus'eptible c to problems due to mechanical friction. The valves have been oriented in the vertical penition to alleviate this ocncern.
ANALEIS_ MIL 1HE_E71HI The two Reactor Building Ventilation m:.pply velvas, IT4 6
- AOV-036A and B, and the two exhaust valv m 1T46*AOV-037A and B are arranged in series so thar, the SOVs f or both supply or i'or both exhaust isolation valves would have to malfunction concurrent with an accident to allow a potential release path. But, because all SOVs were mounted in the same configuration this double isolation valve arrangement may be susceptible to the same failure mechanism.
Daring the pe riod coveu-d by this event, the rcactor accumulated slightly ov9r 2 effective l'ull power de.ys of operation. This was accumulated while operating under a license that J imited reactor thermal power to 5% of rata 6.
COREECIIYE ACTIONS
- 1. The SOVs were mounted in the vertical position. The Reactor Building supply and isolation valves were tested per SP 24.418.02, HVAC Reactor Building - Secondary Containment Isolation Valves Operability Test, with satisfactory results.
- 2. During the investigation it was noted that an Environmental Qualification Engineers approval was not always required for all safety related modifications. To address this concern Nuclear Engineering Department (NED) Procedure 3.11, Control of LILCO Engineering Change Reports for Modification of Shoreham Design Documents, has been revised to require a review of safety-related Engineering Change Reports by an Environmental Qualification Engineer. NED Procedure 3.10, Preparation, Review and Approval of L-Series E&.DCRs will be revised with the same intent.
,,y,,,,,,,, .uanaoim on usas na
r 1
. = . . .
WK Seem M
- U $ NUCL112 ESOUL&IDhY COMMISSION LICEN8EE EVENT REPORT (LERI TEXT CONTINUATION apaovio ows No v60-cio.
ex*ints : n is 9&CtLily es&act tti DMEtt hu.00t n (28 gga gpugge q01 Pa06 (3) viaa "St.;;'. "'A*.T Shoreham Nuclear Power Station Unit 1 015101010 h 12 l2 819 -
0 1019 --
1 lo oI; 0' o I; ven, .. . .- - c = =. w m>
r
- 3. To ensure that other SOVs are mounted acceptably a field walkdown of other appropriate SOVs was completed with no other discrepancies noted.
- 4. The AOVs will continue to be monitored through frequent testing of the valves. This frequency is greater than required by Technical Specifications. Testing will be performed until it is established that their' reliability is adequate.
ADDlil0NAL_lHFORMATIQB
- a. Manufacturer _and_mndeknumber_QL failed _comnenent_.Lal: None
- b. LER numbern_of prey 1oun_nimilar_eyenta: None r.
)
r WTC somw seen e U $ 0% 1986 0-624 636 466 CQi
. . -. . . - . -, - -