LER-1980-030, /03L-0:on 800716,during Valve Operability Test, Electromagnetic Relief Valve D Failed to Open.Plant Shut Down.Caused by Deficient Maint Procedure.Valve Plunger & Pilot Valve Operating Lever Clearance Adjusted |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2191980030R03 - NRC Website |
|
text
U. S. NUCLEAR ReiGul.AToHY CoMMISSloh
V LICENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l l
l@
(PLEASE PRINT OR TYPE ALL REQL.tD INFORMATION) 1 6
- - l0 l t l-l N l J l(t l C l P l 1 l@l Ol 0l -l' 0l 0l 0l 0l 0 l -l 0l 0 l@l 4 l I l 1 l I l 1 l@l l
l@
7 8 9 LICf %5EE COOE 14 15 LICENSE NUMBER 26 26 LICENSE TYPE J0 57 CAT $8 CON'T IOlil
$O,%lLl@l0l5l0l010l2ll l9 l@l 0171 I l 6l fd O l@l 018 l I I il 81 o I@
7 8
60 61 DOCKET NUMgER 68 69 EVENT QATE 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROSABLE CONSEQUENCES h 10121 l On July 16, 1980, Electromatic Relief Valve "D" did not ocen during a l
i01ai l valve operabl1ity test. The other four EMRV's operated satisfact6-Ilv l
10141 l during the test.
The plant was shutdown and depressurized.
An Invest-I lois] I igation revealed that the distance between the "D" EMRV solenoid plunoer I
10l6l l and the pilot valve operating lever was excessive.
Acoarentiv the l
l0l7ll clearance had not been adjusted properly followino the removal and I
i O ia i i the repair of the valve in January, 1980.
I 80 7
8 9 Y$$"
"#$E S8Ci$E COMPONENT CODE SLS OO'E S
C0 10191 l Sl Fl@ d@ l Z l@ l V l A l L l V l 0 l P l@ ldG LZ_J '@
7 8
9 to 11 12 13 18 i9 23 SEQUENTIAL OCCURRENCE REPORT REVISIOP' LER RO EVENT YEAR R EPORT NO.
CODE TYPE NO.
@s,*jg 18l01 l-l 10l3l0l M
I 01 31 lLI L-1 l 0l as 21 22 23 24 26 27 N
M 30 31 32 K N AC O P NT M
HOURS S8 i POR 8.
SUP Li MANUP CTURER LE_j@lGl@
[Aj@
l M i@
l010l2l4l l Yl@
l N l@
lN l@
l D l Z l h I'3 l@.
3J 34 35 M
37 40 41 42 43 44 47 CAUSE OESCRIPTioN AND CORRECTIVE ACTIONS h
.tilOIl The cause of this occurrence is attributed to a daffetant maintananca l
1i ii l i procedure.
The clearance between the "D" EMRV olungar and nile univ.
I [Tl 7] l operating lever was adjusted to the proper distance.
The valve was act-1 i,i3l l uated and found to operate correctly.
The maintenance orocedure will be I
ti#4i l revised to incorporate a reouirement to verify the orocer distance.
I 7
8 g 80 STA
'6 POWER OTHER STATUS 015 RY DISCOVERY QESCRIPTION y [C_,,j@ l 0 l 216 l@l NA J
lBl@l Valve Operability Test l
48TiviTY CO$ TENT RELEASEO OPRELEASE AMOUNT OP ACTivtTY LOCATION OP RELEASE NA l
l NA l
l i I s l (Z_,,j @ l Z l@l 7
8 9 10 11 44 45 80 PERSONNEL EXPOSURES NU*.18 E R TYPE
DESCRIPTION
lt l 7 l 10 l0 l0 l@l Zl@l NA l
8 PE RSONNE L iNau' dies oESCRiPTiONh Nuv8ER Ii l l l0 l0 10 l@l NA l
7 8 9 11 12 80
'NS ' $EsCNPT om h
T E
(.__l 2 l (_,Z_jh! -
NA l
7 a 9 10 80 M l Y lhl ESCRIPTION ISSUE D
Weekiv News Release l
lllllllll1ll l5 8'uo ddi o@ 7 "1
201-4 M-8784 g
[
uAusAsone.Anan. Donald _A.
Ross PHONE:
r Jersey Central Power & Light Company N. --
ff ()
Madison Avenue at Punch Bowl Road 3rnstown. New Jersey 07960
'd (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Repo.-t Reportable Occurrence No. 50-2i9/80-30/3L Report Date e
August 11, 1980 Occurrence Date July 16, 1980 Identi fication of Occurrence Operation in a degraded mode permitted by Technical Specifications, paragraph
- 3. 4. 2. b. 2 when "D" Eli
- omatic Relief Valve (EMRV) failed to open during testing following a refueling shutdown.
This event is considered to be a reportable occurrence as defined in the Tech-nical Speci fications, paragraph 6.9.2.b(2).
Conditions Prior to Occurrence The plant was being restarted following a refueling / maintenance outage.
Plant Parameters at the time of occurrence were:
Power:
Core, 502 MWt Electrical, O MWe 4
Flow:
Reci rculation, 5 3 x 10 gpm 6 lb/hr Feedwater, 0.9 x 10 Pressure:
1002 psig Level:
73" Stack Gas: 7.6 x 103 pci/sec Description of Occurrence On July 16, 1980 at approximately 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br /> while performing the Electromatic Relief Valve ' Operabili ty Tes t, "D" EMRV did not open.
The valve open light was on, however, an accompanying increase in the torus downcomer line temperature and an audible indication of steam flow were not obtained.
The other four EMRV's operated satis factorily during the test.
The plant was shutdown and depressurized to less than 110 psig by 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on July 17, 1980.
Jersey Central Power & ught Company is a Member of the General Public Utihties System
46.
. Reportable Occurrence tha. 50-219/80-30/3L Ptga 2 August-8, 1980 Upon further ' investigation i t.was found that the distance between the "D" EMRV
- - solenoid plunger and the pilot valve operating lever was excessive.
This pre-sented the solenoid plunger from contacting and actuating the EMRV pilot valve.
Apparently,:the clearance had not been adjusted properly following removal and repai r of the "D" EMRV In: Janua ry,1980.
Apparent Cause of Occurrence The "D" EMRV pilot valve operating lever to solenoid plunger clearance was not adjusted properly following maintenance.
~ Analysis of Occurrence LThe relief valves of the automatic depressurization system enables the core spray system to provide protection against the small break In the event the feedwater system is not active.. Since the "D" EMRV was inoperable, the A.D.S.
was considered to be operable in a degraded mode.
The loss of one EMRV has been addressed in the loss of cooling accident analysis.
Also, the relief ' valves are provided to remove sufficient energy f rom the pri-mary system to prevent the safety valves from lifting during a transient.
The t ' iting pressure transient is a turbine trip from rated design power with a failure of the bypass to function. The, fi ve rel ief val ves a re requi. sd to operate to prevent reaching the lowest. setpoint of the primary system safety valves. With core thermal power below 1740 MWt, only four operable EMRV's are requi red to perform this. function. The re fo re, the safety significance of the event.are considered minimal.
Corrective Action
The clearance between the "D" EMRV solenoid plunger and pilot valve operating lever was adjusted to the proper distance. The clearance on the other four
~
EMRV's was checked and veri fied to be correct.
During subsequent operations, the "D" EMRV was actuated and determined,to operate correctly.
The maintenance procedure (702.1.007) will be revised to incorporate a require-ment to verify the 'pror4 r-distance between the pilot valve opersting lever and the solenoid plunger.
Fa i l u re Da ta ~
Not applicable.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000219/LER-1980-001-01, /01T-o:on 800105,while Performing Electromatic Relief Valve Operability Test,Emergency Releie Valve D Failed to Open.Caused by Component Failure Due to Retainer Ring Being Backed Off Approx Six Threads | /01T-o:on 800105,while Performing Electromatic Relief Valve Operability Test,Emergency Releie Valve D Failed to Open.Caused by Component Failure Due to Retainer Ring Being Backed Off Approx Six Threads | | | 05000219/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000219/LER-1980-002-03, /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised | /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised | | | 05000219/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000219/LER-1980-003-01, /01T-0:on 800116,during Inservice Insp on Core Spray Sparger Piping for Sys Ii,Two Indications of Cracks Discovered.Ultrasonic Test Revealed through-wall Cracks. Possibly Caused by Sparger Installation Method | /01T-0:on 800116,during Inservice Insp on Core Spray Sparger Piping for Sys Ii,Two Indications of Cracks Discovered.Ultrasonic Test Revealed through-wall Cracks. Possibly Caused by Sparger Installation Method | | | 05000219/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000219/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000219/LER-1980-004-03, /03L-0:on 800125,on 800125,29 & 0213,radioactive Water Discovered Leaking from Severely Pitted Aluminum Piping of Condensate Transfer Sys.Caused by Galvanic Corrosion.Leaks Temporarily Repaired & Piping to Be Replaced | /03L-0:on 800125,on 800125,29 & 0213,radioactive Water Discovered Leaking from Severely Pitted Aluminum Piping of Condensate Transfer Sys.Caused by Galvanic Corrosion.Leaks Temporarily Repaired & Piping to Be Replaced | | | 05000219/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000219/LER-1980-005-03, /03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift | /03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift | | | 05000219/LER-1980-006-03, /03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift | /03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift | | | 05000219/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000219/LER-1980-007-03, /03L-0:on 800213,while Performing 10-h Test on Standby Gas Treatment Sys 1,flow Was Less than Tech Spec Limit.Caused by Slipping Drive Belts on Exhaust Fan EF1-8. Drive Belts Replaced | /03L-0:on 800213,while Performing 10-h Test on Standby Gas Treatment Sys 1,flow Was Less than Tech Spec Limit.Caused by Slipping Drive Belts on Exhaust Fan EF1-8. Drive Belts Replaced | | | 05000219/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000219/LER-1980-008-01, /01T-0:on 800215,during Insp for IE Bulletin 79-14,discovered Nine Pipe Clamps Installed W/O Restraining Welded Lugs.Caused by Oversight During Const.Welded Lugs to Be Installed | /01T-0:on 800215,during Insp for IE Bulletin 79-14,discovered Nine Pipe Clamps Installed W/O Restraining Welded Lugs.Caused by Oversight During Const.Welded Lugs to Be Installed | | | 05000219/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000219/LER-1980-009-03, During Annual Insp of Containment Spray Heat Exchanges,Leaks Discovered in Four Heat Exchangers.Caused by Component Failure & Design.Heat Exchangers to Be Retubed W/Titanium | During Annual Insp of Containment Spray Heat Exchanges,Leaks Discovered in Four Heat Exchangers.Caused by Component Failure & Design.Heat Exchangers to Be Retubed W/Titanium | | | 05000219/LER-1980-009, Forwards Revised LER 80-009/03L-1 | Forwards Revised LER 80-009/03L-1 | | | 05000219/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000219/LER-1980-010-01, /01T-0:on 800220,during IE Bulletin 79-14 Insp, Pipe hangers,NP-2-R8A & NP-2-R8B Found Improperly Installed. Cleanup Sys Restraint Mod & Nonrigid Restraint Added | /01T-0:on 800220,during IE Bulletin 79-14 Insp, Pipe hangers,NP-2-R8A & NP-2-R8B Found Improperly Installed. Cleanup Sys Restraint Mod & Nonrigid Restraint Added | | | 05000219/LER-1980-010-03, /03L-1:on 790417,excavation Was Started to Repair Leak Near Inside Penetration within Pipe Tunnel.Activity Was Detected in Soil Near Dedt Line.Dedt Line Rerouted on 800316.Line Will Be Repaired | /03L-1:on 790417,excavation Was Started to Repair Leak Near Inside Penetration within Pipe Tunnel.Activity Was Detected in Soil Near Dedt Line.Dedt Line Rerouted on 800316.Line Will Be Repaired | | | 05000219/LER-1980-011-03, /03L-0:on 800219,during Surveillance Test,Trip Occurred on Standby Gas Treatment Sys 1.Caused by Cracked Flow Sensing Line Which Was Probably Stepped On.Line Replaced | /03L-0:on 800219,during Surveillance Test,Trip Occurred on Standby Gas Treatment Sys 1.Caused by Cracked Flow Sensing Line Which Was Probably Stepped On.Line Replaced | | | 05000219/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000219/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000219/LER-1980-012-03, /03L-0:on 800228,discovered That Weekly Surveillance Tests for Main Station & Diesel Generator Batteries Not Performed During Seventh Wk.Caused by Error in Personnel.Evaluation Will Be Made to Determine Improvements | /03L-0:on 800228,discovered That Weekly Surveillance Tests for Main Station & Diesel Generator Batteries Not Performed During Seventh Wk.Caused by Error in Personnel.Evaluation Will Be Made to Determine Improvements | | | 05000219/LER-1980-013, Forwards LER 80-013/01T-0 | Forwards LER 80-013/01T-0 | | | 05000219/LER-1980-013-01, /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation | /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation | | | 05000219/LER-1980-014-01, /01T-0:on 800302,emergency Diesel Generator 1 Failed to Synchronize & Tripped When Generator 2 Was Tagged for Mod.Caused by Component Failure.Fuse F7,found Loose in Holder.Fuseholder Repaired | /01T-0:on 800302,emergency Diesel Generator 1 Failed to Synchronize & Tripped When Generator 2 Was Tagged for Mod.Caused by Component Failure.Fuse F7,found Loose in Holder.Fuseholder Repaired | | | 05000219/LER-1980-014, Forwards LER 80-014/01T-0 | Forwards LER 80-014/01T-0 | | | 05000219/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000219/LER-1980-015-03, /03L-0:on 800403,piston Rod on Closure Mechanism for Reactor Bldg Ventilation Automatic Isolation Valve Was Found Broken,Making Valve Inoperable.Caused by Component Failure.New Piston Rod Eye Stud Was Fabricated & Installed | /03L-0:on 800403,piston Rod on Closure Mechanism for Reactor Bldg Ventilation Automatic Isolation Valve Was Found Broken,Making Valve Inoperable.Caused by Component Failure.New Piston Rod Eye Stud Was Fabricated & Installed | | | 05000219/LER-1980-016, Forwards LER 80-016/01T-0 | Forwards LER 80-016/01T-0 | | | 05000219/LER-1980-016-01, /01T-0:on 800512,util Recognized That 800420 Discovery of Defective Pressure Switch,Psl D,Constituted Immediate Rept.Caused by Cocked Teflon Actuator.Switch Removed & Will Be Replaced | /01T-0:on 800512,util Recognized That 800420 Discovery of Defective Pressure Switch,Psl D,Constituted Immediate Rept.Caused by Cocked Teflon Actuator.Switch Removed & Will Be Replaced | | | 05000219/LER-1980-017-01, /01T-0:on 800516,while Performing Control Rod Interference checks,green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Caused by Operator & Procedure in Bypass & Component Failure | /01T-0:on 800516,while Performing Control Rod Interference checks,green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Caused by Operator & Procedure in Bypass & Component Failure | | | 05000219/LER-1980-017, /03L-0:on 800520,during Investigation of LER 80-17/1T, One Rod Free Travel Interlock Surveillance Requirements Not Performed as Required.Causec by Failure to Perform Procedure & Schedule Surveillance | /03L-0:on 800520,during Investigation of LER 80-17/1T, One Rod Free Travel Interlock Surveillance Requirements Not Performed as Required.Causec by Failure to Perform Procedure & Schedule Surveillance | | | 05000219/LER-1980-018-03, /03L-0:on 800507,during Monthly Surveillance Testing of Reactor High Pressure Scram sensors,RE03D Found to Be Less Conservative than Specified.Caused by Sensor Repeatability.Sensor Reset | /03L-0:on 800507,during Monthly Surveillance Testing of Reactor High Pressure Scram sensors,RE03D Found to Be Less Conservative than Specified.Caused by Sensor Repeatability.Sensor Reset | | | 05000219/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000219/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000219/LER-1980-020-01, /01T-0:on 800605,following Insp of Fire Barriers Protecting safety-related Areas,Several Penetrations Found in Degraded Condition.Caused by Deficiencies in Installation Specs & Personnel Error Re Delay in Establishing Watche | /01T-0:on 800605,following Insp of Fire Barriers Protecting safety-related Areas,Several Penetrations Found in Degraded Condition.Caused by Deficiencies in Installation Specs & Personnel Error Re Delay in Establishing Watches | | | 05000219/LER-1980-021, Has Been Cancelled | Has Been Cancelled | | | 05000219/LER-1980-022-03, /03L-0:on 800603,reactor High Pressure Isolation Condenser Initiation Switch Trip Points Found Less Conservative than Specified.Caused by Unusual Svc Condition. Pressure Switches Reset & Exercised to Ensure Operation | /03L-0:on 800603,reactor High Pressure Isolation Condenser Initiation Switch Trip Points Found Less Conservative than Specified.Caused by Unusual Svc Condition. Pressure Switches Reset & Exercised to Ensure Operation | | | 05000219/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000219/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000219/LER-1980-023-03, /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint | /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint | | | 05000219/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000219/LER-1980-025, Forwards LER 80-025/01T-0 | Forwards LER 80-025/01T-0 | | | 05000219/LER-1980-025-01, /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow | /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow | | | 05000219/LER-1980-026, Forwards LER 80-026/03L-0 | Forwards LER 80-026/03L-0 | | | 05000219/LER-1980-026-03, /03L-0:on 800709,during Routine Testing Insp of Hydraulic Snubbers Installed in safety-related Sys,Snubber 75/5 Failed to Lock Up in Compression Direction.Caused by Foreign Matl in Snubber Fluid.Snubber Flushed & Refilled | /03L-0:on 800709,during Routine Testing Insp of Hydraulic Snubbers Installed in safety-related Sys,Snubber 75/5 Failed to Lock Up in Compression Direction.Caused by Foreign Matl in Snubber Fluid.Snubber Flushed & Refilled | | | 05000219/LER-1980-027, Forwards LER 80-027/01T-0 | Forwards LER 80-027/01T-0 | |
|