|
---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19343C2181975-12-23023 December 1975 AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized ML20090C9991975-12-12012 December 1975 AO 75-33:on 751212,125-volt Dc Distribution Ctr of Station a Battery Inadvertently de-energized.Caused by Failure to Establish Proper Breaker Lineup Preparation for Conducting Battery Load Test.Procedure changed.W/751219 Memo ML19343C2191975-12-11011 December 1975 AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature ML20126E8281975-12-0303 December 1975 AO 50-219/75-31:on 751124,during Operability Test of Torus to Drywell Vacuum Breakers,Alarm Sys 2 Failed to Annunciate in Control Room When V-26-4 Opened.Caused by Failure of Relay Due to Contacts Being Detective.Relay Replaced ML20090D0071975-11-25025 November 1975 AO 75-31:on 751124,drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-4 Opened. Caused by Component Failure.Corrective Action Under Investigation ML20090D0161975-11-0707 November 1975 AO 75-30:on 751106,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17 a & C Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability.Pressure Switches Recalibr ML20090D0601975-11-0606 November 1975 AO 75-29:on 751027,torus Drywell Vacuum Breakers Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened. Caused by Sticking Microswitch ML20090D0761975-10-28028 October 1975 AO 75-29:on 751027,torus to Drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened.Caused by Component Failure.Corrective Action Under Investigation ML20090D0941975-10-24024 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil Replaced ML20090D1141975-10-17017 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1041975-10-16016 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil replaced.W/751016 ML20090D1341975-10-0808 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressures Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1501975-09-23023 September 1975 AO 75-26:on 750923,emergency Svc Water Pump 52C Failed to Start Automatically During Routine Surveillance Test of Containment Spray Sys Ii.Caused by Failure of Contact Switch in Time Delay Relay 16 K4B.Relay Replaced ML20090D2071975-09-0808 September 1975 AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset ML19291C2641975-09-0808 September 1975 AO 73-19:when Closing Signal Was Applied to Breaker S1A,loss of Power Occurred at 4160-volt Ac Bus 1A Causing Trip of Various Pumps.Caused by Incorrect Setting of Current Transformer Ratio Matching Taps.Taps Set Properly ML20090D1941975-09-0808 September 1975 AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset ML20090D2151975-09-0202 September 1975 AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset ML20090D2011975-09-0202 September 1975 AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset ML20090D2241975-08-21021 August 1975 AO 75-23:on 750817-20,stack Effluent for Iodine & Particulates Not Monitored.Caused by Personnel Error.Filter Installed in Operating Stack Gas Sampling Train ML20090D2261975-08-11011 August 1975 Preliminary AO-50-219/75-22:on 750810,stack Gas Sample Line Low Flow Alarm Received.Caused by Stack Gas Sample Pump a Not Running.Thermal Overload Protection Reset ML20090D2471975-08-0404 August 1975 Preliminary AO-50-219/75-21:on 750801,during Routine Surveillance on B Isolation Condensor Sys,Steam Line Valve V-14-32 Failed to Close on Simulation of Steam Line High Flow.Caused by Low Torque Switch Setting.Torque Increased ML20090D2521975-07-17017 July 1975 AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D, A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr ML20090D2561975-07-0909 July 1975 Preliminary AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D,A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr ML20084E1151975-07-0101 July 1975 RO 50-219/75-18:on 750623,two 8-1/2 Inch Handhole Covers in Standby Gas Treatment Filter Train Not in Place.Cause Unknown.Handhole Covers Repositioned & Secured ML20090D2741975-06-27027 June 1975 AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced ML20090D2661975-06-24024 June 1975 Preliminary AO 50-219/75-18:on 750623,handhole Covers in Standby Gas Treatment Filter Train 1-1 Not in Place.Cause Under Investigation.Covers Repositioned & Secured ML20090D2781975-06-24024 June 1975 AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83P & E Tripped at Pressures Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset ML20090D2731975-06-19019 June 1975 Preliminary AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced ML20090D2901975-06-16016 June 1975 Preliminary AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83B & E Tripped at Pressure Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset ML20090D6561975-06-0606 June 1975 AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned & Repaired ML20090D2971975-06-0606 June 1975 AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading ML20090D2981975-06-0202 June 1975 Preliminary AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading ML20090D6581975-05-30030 May 1975 Preliminary AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned ML20090D6611975-05-14014 May 1975 AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced ML20090D6641975-05-0707 May 1975 Preliminary AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced ML20090D6531975-05-0606 May 1975 AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17B & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatablilty.Switches Recalibr ML20090D6701975-04-28028 April 1975 Preliminary AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 178 & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatability.Switches Recalibr ML20090D6751975-04-18018 April 1975 AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked ML20090D7001975-04-14014 April 1975 AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure.Valves Adjusted &/Or Repaired ML20090D6811975-04-11011 April 1975 Preliminary AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked ML20090D7131975-04-0808 April 1975 AO-50-219/75-09:on 750329,breaker 1C Tripped Resulting in Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced ML20090D7061975-04-0707 April 1975 Preliminary AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure. Valves Adjusted &/Or Repaired ML20090D7271975-04-0303 April 1975 AO-50-219/75-08:on 750325,power Operation Continued W/ Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate.Caused by Failure to Properly Monitor Reactor Core.Rate Reduced ML20090D7211975-03-31031 March 1975 Preliminary AO-50-219/75-09:on 750329,breaker 1C Tripped Due to Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced ML20090D7651975-03-27027 March 1975 AO-50-219/75-07:on 750319,during Standby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Differential Relay Installed ML20090D7361975-03-26026 March 1975 Preliminary AO-50-219/75-08:on 750325,power Operation Continued W/Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate. Caused by Improper Reactor Core Monitoring.Rate Reduced ML20090D7761975-03-20020 March 1975 Preliminary AO-50-219/75-07:on 750319,during Stanby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Relay Installed ML20090D7801975-03-19019 March 1975 AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Continuously Monitor Stack Releases While Reactor in Unisolated Condition.Caused by Circuit Design.Request to Modify Circuit for Stack Gas Sample Pumps Submitted ML20090D7901975-03-13013 March 1975 AO-50-219/75-05:on 750306,during Monthly Surveillance Test, Containment Spray Pump 51A Failed to Start When Subjected to Simulated Signals.Caused by Breaker Trip Bar Failing to Reset After Previous Breaker Trip.Trip Bar Bushings Cleaned ML20090D7811975-03-11011 March 1975 Preliminary AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Monitor Stack Releases While Reactor in Unisolated Condition.Caused by faulty-circuit Design 1975-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station ML20236R0511998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station ML20249B2981998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F1891998-05-0505 May 1998 Risk Evaluation of Post-LOCA Containment Overpressure Request ML20247G0581998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station ML20216K0341998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station ML20151Y4651998-03-31031 March 1998 Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216J0841998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station ML20203B2781998-02-16016 February 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures ML20203A3801998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station ML20198P1791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station ML20217C7591997-12-31031 December 1997 1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station ML20197E9131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20199D4381997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station ML20202E8511997-10-21021 October 1997 Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included ML20211M9481997-10-0303 October 1997 Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification ML20198J7361997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station ML20211B7461997-09-24024 September 1997 Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl ML20210V0181997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station ML20210L2961997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20196H0111997-07-11011 July 1997 Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc ML20210L3081997-06-30030 June 1997 Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station ML20141H2051997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station 1999-09-30
[Table view] |
Text
. _ . _ _ . _ . _
,- n -.
t_=r_
O O r .
- .[*
- g\
.'s,' . -
s
- p. - ,4
'g v .,
u
> k.'uL APRH ' 574 - {cy To:
James P. O'Reilly Directorate of Regulatory Operations k '
permedust a, } 7,23 e 4
f 1, Region I '-
sam.tes k
631 Park Avenue King of Prussia, Pennsylvania 19406 j g'p -
From: Jersey Central Power 6 1.ight Company Oyster Creek Nuclear Generating Station, Docket #50-219 Forked River, New Jersey 08731 a
e
Subject:
Abnormal Occurrence Report No. 50-219/74/28 The following is a p ra l i mi n a ry rapa rt haing n'bmitted in compliance with the Technical Specifications, paragraph 6.6.2.
Preliminary Approval:
/
.b / ( .. /// /d'[' 4/19/74
[T. Carroll, Jr. '# Date cc: Mr. A. Giarrhusso/
( '
([
f
\\
\h.',!'.p b f\
Q ./ .
b 0304110009 740419 PDR ADOCK 05000219
/
6 PDR
. COPY SENT RMd 0 -
(. .
L._ _. - a wq Initial Telephone Date of v Report ,Date: 4 /19/74 Occurrence: 4/19/74 Initial Written Time of Report Date: 4/19/74 Occurrence: _
0715 l
OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/74/28 IDENTIFICATION Violation of the Technical Specifications, paragraph 3.4. A.1, OF OCCURRENCE:
which requires the core spray system to be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specification 3.4. A.3 and 3.4. A.4. Suction valve (V-20-4) to the "B" core spray pump was stuck in the closed .
position for a period of approximately 15 minutes thereby ;
causing a loss of core spray pump redundancy in system II. In :
addition, core spray system I was tagged out of service for ,
maintenance at this time.
1his event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15B and D.
CONDITIONS PRIOR Steady State Power Routine Shutdown TO OCCURRENCE: llot Standby Operation Cold Shutdown Load Changes During :
X Refueling Shutdown Routine Power Operation Routine Startup Other (Specify)
Operation The reactor mode switch was in the REFUEL position with reactor coolant temperature approximately 104 F.
l DESCRIITION At approximately 0715 on Apri.1 19,1974, while performing sur-0F OCCURRENCE:
veillance testing on core spray system II, motor-operated valve V-20-4 failed to open electrically after having closed cicctrically in a normal manner. This surveillance testing was being performed
,-,r-,-_,. .-.--,-,-y,,---, . . < ~ - - - . - , , . _ - - - - - - - - . . . - . - - -
e .. - . - _ _ - . -
J O
Q~
l ' Abnorma1 Occurrence . .
Raport No. 50-219/74/28 Page 2
] .
1' .
] i' j
}
on core spray system II after system I was tagged out of ser-
! vice for maintenance. (liydraulic shock and sway arrestor units 1
were being replaced on components of system I.) V-20-4 was l manually opened approximately 15 minutes after this valve prob-4 1em was identified.
l
[
APPARENT CAUSE Design Procedure l Unusual Service Condition i 0F OCCURRENCE: F!anufacture I Installation / Inc. Environmental Construction Component Failure
- i Operator Other (Specify)
I j The apparent cause of this occurrence has not been identified i
at this time.
i j swidliSIS OF iiutui-upezated valve V-::0-4 pivvidcs sucticr. to the "::" ccrc OCCURRENCE:
. spray pump in core spray system II. This valve is normally i maintained in the open position but is closed whenever required
! for isolation purposes, llad core spray system operation been required, the "B" core spray pump would have functioned nor-1 mally both before performance of the surveillance testing and l
I after the valve was locked in the open position. Only the l isolation function of the valve was lost.during these two time I
s l periods . The safety significance of this event is that for a i, period of approximately 15 minutes core spray pump redundancy
,l was lost in system II. Since" system I was tagged out of service during this time period, a further degradation in core spray 4
system capability resulted. ,
4 4
i
_ . . . _ , . . . _ . . _ _ . . , _ , , , ,4 _ _ . . _ _ , . . . . , . , , . _ . . _ _ ~ ,- -, ~ , - . ,_ . . . . . . _ _ , . _ , . . , .
_____-.__--_.._--._-.____._____, ___-____-.-___-._m .
- o. o -
i Ahnormal Occurrence .
~
j
~
Repo'rt No. 50-219/74/29 Page 3
+
-i . ;
, CORRECTIVE Immediate corrective action involved manually opening the motor . --
i ACTION: .
, operated valve (V-20-4) and tagging open the associated ' circuit .
~
breaker to prevent subsequent closing. Additional corrective ,
r actions will be determined following the completion of mainten-
.i ance and review of this incident by the Plant Operations Review j
} Committee. .
l .
l FAILURE DATA: To be supplied at a later dato. s 1-3 4 ;
\ 1 s i j
s i
I
,t.
t.
'\
- s j . s 1 1 , s , ,
'~.y.
! , e -
x,
. 1 1 j -: ,
-2 ,
' 4 s
s *
'. ~ .? ..
s 1. .u . ,
'b '
' . i ( N Y, i
.ss\ \ (j ,a _
~
\7 m %.
I m w ,,
- b. [Y \
, (\
, 3 , s
\
. b' , ,
k v.
j i
\ , , , ^
w.
l
' 't
_ +
y
- 't ,.
-;, '%e .
Prepared by. . \. %\,. ,
Da e:
- ,7-A gYihn s ',
ar*-
~
_..__,..,_.1 - , _ , _ , , .
_ - _ _ _ _ _ _ .- . . ~ _ . . --_ _. - -._ . __-
4 ,
O O J
! OYSTER CREEK NUC1. EAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 t
l Abnormal Occurrence Report No. 50-219/74/28 l
Renort Date April 26, 1974 a
Occurrence Date April 19, 1974 i ,
Identification of Occurrence Violation of the Technical Specifications, paragraph 3.4.A.'1, which requires the core spray system to be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specification 3.4.A.3 and 3.4. A.4.
Suction valve (V-20-4) to the "B" core spray pump was stuck in the closed position for a period of approximately 15 minutes, thereby causing a loss of core spray pump redundancy in system II. In addition, core spray system I i was tagged out of service for maintenance at this time. This event is considered '
to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15E and D.
l Conditions Prior to Occurrence The plant was shut down for refueling.
4 The reactor mode switch was in the REFUEL position with reactor coolant tem-perature approximately 104*F.
s Description of Occurrence At approximately 0715 on April 19, 1974, while performing surveillance testing on core spray system II, motor-operated valve V-20-4 failed to open electrically
- < after having closed electrically in the normal manner. This surveillance test-ing ws being performed on core spray system II after system I was tagged out i of service for maintenance. (Hydraulic shock and sway arrestor units were being replaced on components of system I.) V-20-4 was manually opened approximately 15 minutes after this valve problem was identified.
Apparent Cause of Occurrence
\ '
The apparent cause of this occurrence has not been identified at this time.
cl b E i d' ipf )d i
u.
^
vJ
,..e , , , , - , . _ _ , _ . . - _ . _ _ , _ , ,
we- w-* - - - -- ,,
__ ,, ,, - -. _ , _ ._ . . _ _ _ . ,, . __ s
c 4 .
- O O i Abnormal Occurrence No. 50-219/74/28 Page 2 1
i l
i Analysis of Occurrence Motor-operated valve V-20-4 provides suction to the "B" core spray pump in 1
core spray system II. This valve is normally raintained in the open position.
j Had core spray system operation been required, the "B" core spray pump would l
have functioned normally both before performance of the surveillance testing and after the valve was locked in the open position. The safety significance of this event is that for a period of cpproximately 15 minutes, core spray pump redundancy was lost in system II. Since system I was tagged out of i service during this time period, a further degradation in core spray system capability resulted.
Corrective Action Immediate corrective action involved manually opening the motor-operated valve (V-20-4) and tagging open the associated circuit breaker to prevent subsequent closing. Additional corrective actions will be determined following the completion of the investigation into the cause of this event and a review of the surveillance requirements for this valve will be performed.
4 Failure Data I The cause for this failure has not been identified at this time.
h v
1 l
q t
4 l
i A
E l l
I
. . ._ ~. _ ,,, , _ . . .__
b h m : . ,
ll O O 3l"}.
!/D l .ersey Centra Power & Lig7t Company [sl[
i W
MADISON AVENUE AT PUNCH BOWL ROAD
- 201-539-6111 GlNonRtd THE General ,'o{ Public Utilitics Corporation SF378 er d
U 1, ;
April 26, 1974 s +, 0 g SEClWLO c I,iAY 1 1974 o
-to 9 u. ce;mn:n mne mur A.
re:ditrr /sN 4, m:i scma
,4 bir. A. Giambusso f, I l,-
d.
- Deputy Director for Reactor Projects Directorate of Licensing i United States Atomic Energy Commission
! Washington, D. C. 20545 Dear bir. Giuduussu.
Subject:
Oyster Creek Station i Docket No. 50-219 Abnormal Occurrence Report No. 50-219/74/28 The purpose of this letter is to forward to you the attached Abnormal Occurrence Report in compliance with paragraph 6.6.2.a of the
- Technical Specifications.
i Enclosed are forty copies of this submittal.
Very truly yours,
.., , ?
QLO< SL J 's & @ <' -
Donald A. Ross blanager, Nuclear Generating Stations cs
- Enclosures ,
1 cc: Mr. J. P. O'Reilly, Director j Directorate of Regulatory Operations, Region I .t L
V
/ {]
(
/h 1
3851
/ l CUPY SENT REGION M_ .. . . .
O r
\
v
Abnornal Occurrence Report No. 50-219/74/28 Abnormal Occurrence Report No. 50-219/74/28, occurrence date April 19, 1974, reported that motor-operated valve V-20-4 failed to open c1cetrically after closing electrically in a normal manner during the performance of surveil-lance testing on core spray system II. Since valve V-20-4 provides suction to the "B" core spray pump, core spray pump redundancy was lost in system II during the period of time that the valve was stuck in the i:losed position. Immediate corrective action involved manually opening the motor-operated valve (V-20-4) and tagging open the associated circuit breaker to prevent subsequent closing.
Since core spray syst'em I was tagged out for maintenance at the time of this abnormal occurrence, it was not immediately possibic to troubleshoot and determine the cause of the V-20-4 failure. Consequently, the initial abnormal occurrence report did not identify the cause of the valve failure.
The purpese of this addendum is to report the apparent cause of the failure, additional items of corrective action and pertiner.t failure data.
Apparent Cause of Occurrence Refer to the attached schematic diagram of the opening and closing control circuitry for V-20-4 (Figure 1) . Torque swite,. TS-0 is provided to inicitupi LLv svn ti vi slicuitry if a ;;.cchnical cverl ad cc:urs during the opening cycle. Position suitch 20-C is provided to override the function of TS.-0 during the initial stages of the opening cycle. This position switch (20-C) is normally adjusted to open at approximately 10'6 of valve travel.
Investigation of the control circuitry after the abnormal occurrence revealed that 20-C was opening prematurely at 6'6 to 7'6 of valve travel. It has, therefore, been concluded that 20-C opened before torque switch TS-0 closed, thereby preventing V-20-4 from opening.
Additional Corrective Action Position switch 20-C was readjusted to open at approximately 10'6 of valve travel. ,
Failure Data blanufacturer data pertinent to the V-20-4 valve control are as follows:
blanufacturer: Limitorque tiodel No.: 391667-ES Flotor llP: .67 l M' C
l
m gj u)
Figure 1
. Opening And Closing Control Circui try I or V-20-4
- e. . _. . . . . _ . . _
120VAC . . . _ .....__..;. .- _
20-IC 73-0 110 fc C 30L 201,10L
~.._.
-..-1 s 1 . ., .
j j. . _ _ . . , _ . .
j . ___. _ . . g...g / . . . _
i 6A 6 4 3
)6K101D
'-l--- . . (11 } j . (12) l> l
~ 20- C i
. ..(7) .. ] I ._(8)_ .;
II I 305 B l l 4: i i
~ij i 1
' i TS-C 16K107D 305B .FIO l I
'.. T' % . . _ . . .
- 1) i;ir iL <T a i (s)
.I (6) ll-- "-~~ .f p 1.go~
16K1071) 11C 6D 6C 20-0 (1) (2) 6L 20-10
/
.._ _ l l-._.__..- .. . . . . . . . . . . _ _ .
g _. , _ . _ _ _ _ . _ ,
/ !
20-IC '
....l_l.. . . . . .
g i M .
IC - Closed 'during ist 90", of Travel 10 - Open after 1st 10".i of . Travel TS Torque Suitch Open TS-C - Torque Switch Closed F10 - Flotor Open F:C - Flotor Closed l
. l O O l i .. l j , Jersey Central Power & Light Company l MADISON AVENUE AT PUNCH OOWL ROAR
.. . . . ru yE';.j'j*,,
cenerai Pubhc Utihties Co'poration j ,,,,..
1
[ July 11,1974 ,3 10-i l!),
- . z .>.
i , El y[f) 4'.
,1 Nl.15 1974 i Mr. A. Giambusso ;
/[Rn: rf C
I Deputy Director for Reactor Projects * #-
Directorate of Licensing ih *2:[$ $7 fe s ;
h/[
l United States Atomic Energy Commission be -%
Washington, D. C. 20545 N dM_. q
Dear Mr. Giambusso:
Subject:
Oyster Creek Station Docket No. 50-219
- Addendum to Abnormal Occurrence
. No. 50-219/74/28 In my report of Abnormal Occurrence No. 50-219/74/28 dated
- April 26, 1974, complete infomation on the Apparent Cause of the
- Occurrence, Corrective Action, and Failure Data was not furnished since
.t the investigation of this occurrence had not been completed on April 26.
This investigation hr.s now been completed. Tne attached report is an
- addendum to Abnormal Occurrence No. 50-219/74/28 and serves to complete i the original report, ,
- l Enclosed are forty copics of this submittal.
1 I
il Very tre.ly yours, W (a g 1
. Donald A. Ross Manager, Nacicar Generating Statior.s Cs t's Enclosures i
!g m\
,b/r (z. .w. , . .
i
\\ y up h }{ .
l j COPY SLNT REGION m
-