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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000219/LER-1990-0081990-07-23023 July 1990
LER 90-008-00:on 900625,reactor Scram Occurred on Low Condenser Vacuum.Caused by Failure of Backwash Outlet Valve to Open,Causing Loss of Circulating Water to Condenser A. Plant Stabilized & Taken to Cold shutdown.W/900723 Ltr
05000219/LER-1984-020, Errata to LER 84-020-01,consisting of Page 4 Re Corrective Actions.Preventive Maint Request Initiated to Store Overload Devices in Vertical Position1985-09-23023 September 1985
Errata to LER 84-020-01,consisting of Page 4 Re Corrective Actions.Preventive Maint Request Initiated to Store Overload Devices in Vertical Position
05000219/LER-1982-0261982-06-0707 June 1982
LER 82-026/03L-0:on 820507,thermocouple for Safety Valve NR28J Found Open During Surveillance Testing.Caused by Broken Lead Wire at Thermocouple.One of Adjacent Valve Acoustic Monitor Setpoints Reduced.Thermocouple Replaced
05000219/LER-1981-061, Updated LER 81-061/03X-1:on 811223,of 11 Deficient Hydraulic Snubbers,Nine Found to Be Inoperable During Functional Testing.Caused by Seal Degradation &/Or Worn Poppet Valves. Snubbers Replaced W/Operable Spares1982-05-25025 May 1982
Updated LER 81-061/03X-1:on 811223,of 11 Deficient Hydraulic Snubbers,Nine Found to Be Inoperable During Functional Testing.Caused by Seal Degradation &/Or Worn Poppet Valves. Snubbers Replaced W/Operable Spares
ML20064J2011978-12-22022 December 1978
/03L-0 on 781126:during Testing Containment Spray Pumps 51C & 51A Failed to Start on Signal Due to Excess Friction in Circuit Breaker Trip Bar Bearings.Bearings Were Cleaned & Lubricated
ML20147H5331978-12-21021 December 1978
/03L-0 on 781125:switch RE03C Was Found to Trip at Pressure Less conservative(1075 Psig)Than Specified in Tech Specs 2.3.3.Cause of Pressure Switch Tripping Is Attributed to Sensor Repeatability
ML20064H3441978-12-14014 December 1978
/01T-0 on 781129:during Test,Noted That Containment Leakage Rate Greater than Allowable.Discovered That Vent Valves Were Leaking.Caused by Leakage Past the Seating Surfaces
ML20064H1871978-12-13013 December 1978
/01T-0 on 781129:during Test,Main Steam Line Drain Valve V-1-106 Did Not Close 2 Incore Probes,Did Not Fully W/Draw & Reactor Coolant Valve Did Not Indicate Closed.Due to Jammed Armature,Faulty Fuse Holder & Incorrect Settings
ML20064F0691978-11-16016 November 1978
/03L-0 on 781018:isolation Valve V-7-31 Had Damaged Rubber Seat & Drain Valve V-7-29 Obstructed by Piece of Cork & Filter F-1-58 Medium Disintegrated.Cause of V-7-31 & F-7-58 Degradations Due to Detonations in Sys
ML20064E7071978-11-15015 November 1978
/03L-0 on 781019:IRM 12 Became Inoperative While Cable to IRM 14 Was Disconnected.Irm 12 Failure Attributed to Maint Activities Under Vessel.Subesquent Inspec Showed IRM 12 Cable Damaged
ML20064E5561978-11-15015 November 1978
/03L-0 on 781017:during Routine Surveillance Test of Standby Gas Treatment Sys,The Sys II Discharge Valve Failed to Open,Due to Stuck Solenoid in Control Air Supply to Operator for V-28-30
ML20064C2501978-10-12012 October 1978
/03L-0:on 780914,circuit Breaker for motor- Operated Valve Tripped When Valve Closed by Isolation Signal.Caused by Component Failure Allowing Switch Setting to Shift.Setting Corrected & Set Screw Tightened
ML20064B7391978-09-29029 September 1978
/01T-0 on 780916:3 MSIVs(NS03A,NS04A,NS04B) Had Leakage Rates in Excess of Maximum Allowable Due to Stem Packing,Cracked Stellite Weld & Failure of Main Poppet to Seat Properly.Msiv Failures Being Investigated
1990-07-23
[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
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LICENSEE EVENT REPORT CONTROL BLOCK: l 1
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(PLEASE PRINT oR T YPE ALL REQUIRED INFORMATION) lo l1l8 9lN lJ LICENSEE 7
l0 lC CODE lP l1 l@l 0 l Ol -l O l 0LICENSE 14 15 l 0 lNUMBER O l 0 l - l O l 025 l@l4 26 l1LICENSE l1 11 TYPEl1JOl@!$7 CATl 68 l@
CON'T 10111 ,"En"clltj@l015l0l0 10 l2 l1 19 l@ll 11 12 E9 1517.18l@ll 12 REPORT EVENT DATE 74 76 12 l1DATEl7 1880l@
7 8 60 61 DOCKET NUMBE R 68 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 121 l On November 25. 1978. while oerforming the monthly surveillance test on I 10131 I the reactor high pressure scram switches, switch RE03C was found to trip l 10141 [ at a pressure that was less conservative than that specified in paragraph l 10 I 6 I I 2.3 3 of the Technical Specifications. The as found trip pressure was l 1075 psia. 9 psi creater than the desired value. l 10 ls 1 l l0l7ll l l
1018] l 80 I
7 8 0 DE CODE SUBCO E COMPONENT CODE SU8C DE SU E l0l9] l t l A l@ lX l@ l Xl@ l l l N l S l T l R l U l@ l E j@ l20Zl @
7 8 9 10 11 12 13 18 19 SEQUENTI AL OCCURPENCE REPORT REVISION EVENT YE A R REPORT NO. CODE TYPE NO.
Li R O neg/RO y l7 l8l l-l [0 l 2l 7l l/l l0 l3 l lL l l-l l0 l
_.21 22 23 24 26 27 28 29 30 31 32 TAK N ACT ON PL NT M HOURS S B IT FOR B. SUPPLIE MANUFACTURER l33E l@l34Z l@ l Z j@ l36Z l@ l 0 l 0l 0l 0l l41 Y l@ lYl@ lNl@ lBl0l6l9l@ ,
3b 37 40 42 43 44 47 CAUsE DESCRIPTION AND CORRECTIVE ACTIONS l1 l0ll The cause of pressure switch RE03C tripping at 1075 psig is attributed l to sensor repeatability. The switch was reset to trip within the pre- I liiil l i,ipi l scribed limits. Recognizing that the repeatability of the sensor was l within the manufacturer's specification, no further corrective action l iii3i l ii l4l l Is deemed necessary. l 7 8 9 80 ST S % POWER OTHE R STATUS 01S O RY DISCOVERY DESCRIPTION l1 15j l H l@ l 0 l 0 l 0 l@l NA l QJ@l Operator Observation l ACTIVITY CO TENT RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA NA l 1 l" c l l Z l @D OF RELE ASEQJ@l l l l PERSONNEL EXPOS E$
NUMBER TYPE DESCRIPTION NA l l i l 7 l l 0 l 0 l 0 l@l Z l@l PERSONNE L INJU IES NUMBE R DESCRIPTION NA l
[1 l a l l 0 l 0 l 0 l@l12 80 7 8 9 11 LOSS OF OR DAMAGE TO FctLITY Q TYPE DESCRIPTION N./
NA l l 1 l 9 l l Z l@l 80
'7 8 9 10 15$u f l 7 l o l l Y f@l ESCRIPTIONWeekly press release - December 27. 197R l lllllllIlIlll5 7 10 68 69 80. ;
MR py7CO23 NAME OF PREPARER Donald A. Ross PHONE: 201-455-8784 t 0
m1 - Jersey Central Power & Light Company
- A- - .. ..
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$ ( Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/78-27/3L-0 R_epo r t Date December 21, 1978 Occurrence Date November 25, 1978 (dentification of Occurrence Violation of the Technical Specifications, paragraph 2.3.3, when the reactor high pressure sensor RE03C failed to trip at the required value. This e ve.- t is considered to be a reportable occurrence as defined in the Technical Speelfications, paragraph 6.9.2.b.l.
Conditions Prior to Occurrence The plant was in a refueling shutdowr .
Reactor mode switch - refuel position Source range monitor - 25 cps All control rods - fully inserted Reactor water level - 110 inches i Reactor water temperature - 167*F l
Description of Occurrence On Saturday, November 25, 1978, at approximately 0040, while performing monthly surveillance testing on the reactor high pressure scram sensors, RE03C was found to be less conservative than that specified in the Technical Specifications. Test on all reactor high pressure switches revealed the I following data:
Pressure Switch Desired Designation Setpoint As Found As Left l l
System i RE03A 1068 1068 1068 l RE03C 1066 1075 1066 System 2 RE03B 1068 1067 1067 RE03D 1066 1065 1065 l l
l l
Jersey Central Power & Light Company is a Member of the General Pubhc UtSties System o 1
y a
c.
Reportable Occurrence No. 50-219/78-27/3L-0 Page 2 December 21, 1978 Apparent Cause of Occurrence The cause of switch RE03C tripping at 1075 psig is attributed to sensor
- repeatability.
Analysis of Occuirence' !
\
Failure of the RE03C. pressure switch to actuate at its prescribed value of 1066 psig would have prevent d operation of the lK4 relay. The 1K4 relay contacts contained in the automatic operating. logic. for the reactor j high pressure' scram' sensors would, therefore, fall to actuate. Due to the configuration of this logic, failure of this pressure switch would not l affect reacter high pressure ' scram initiation, but would remove the redundancy I of the logic. .The safety significance of the event is considered to be minimal since the redundcnt sensor RE03A in reactor protection System I would have operated at the require 6 value.
Corrective Action Reactor high pressure sensor RE03C was reset to trip within the prescribed I limits. Recognizing the repeatability of the sensor was within the man-ufacturer's specification, no further corrective action 'is deemed necessary.
Failure Data Barksdale pressure actuated switch l Switch #B2T-Al2SS l Proof 1800 psi .
1 Adjustable range 50-1200 psi l
l l
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