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| 1 9 @l10 NA 7910080 .3 FR l 7 8 9 80 PUB L ICITY NRC USE ONLY iSSUEC DESCRIPTION 2 n l Y j 44 l Weekiv news release - October 2. 1974 l d'Illllll lll e 9 1C 68 69 go, teAME OF PRED ARER Donald A. Ross PHONE: 20'-455-8784 | | 1 9 @l10 NA 7910080 .3 FR l 7 8 9 80 PUB L ICITY NRC USE ONLY iSSUEC DESCRIPTION 2 n l Y j 44 l Weekiv news release - October 2. 1974 l d'Illllll lll e 9 1C 68 69 go, teAME OF PRED ARER Donald A. Ross PHONE: 20'-455-8784 |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20028E7741983-01-20020 January 1983 LER 82-061/03L-0:on 821216,offgas Isolation Valve Failed to Close Fully on Independent Closure Signal.Caused by Defective Pilot Solenoid Valves Due to Foreign Matter on Solenoid Valve Seat Prohibiting Termination of Air Supply ML20042A2941982-03-0505 March 1982 LER 81-071/01T-0:on 811231,radwaste Liquid Effluent Monitor Found Inoperable.Proper Surveillance Not Performed.Caused by Personnel Error & Lack of Administrative & Procedural Controls.Control Procedures Written & Parts Replaced ML20041D8021982-02-25025 February 1982 LER 82-007/03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered ML20039C3021981-12-17017 December 1981 LER 81-059/03L-0:on 811116,APLHGR Not Checked for Type Iiif Fuel During Daily Core Checks.Caused by Engineer Failure to Assign Alternate Core Location to Take Traveling in-core Probe Truce After Problems Arose at Current Location ML20011A8961981-10-21021 October 1981 LER 81-046/03L-0:on 810920,three Hydraulic Snubbers in Shutdown Cooling Sys Could Not Obtain Drag Load within Acceptable Limits.Caused by Dirty Oil,Cracked Brass Head Ring,Faulty O-ring & Seals.Snubbers Replaced ML19345E9311981-01-30030 January 1981 LER 81-002/03L-0:on 810102,gaseous Releases to Stack Found Not Continuously Monitored as Required by Tech Spec.Caused by Tripping of Stack Gas Sample Pump Due to Normal Wear.Pump Replaced W/Spare ML19345B8101980-11-25025 November 1980 LER 80-047/03L-0:on 801101,while Performing Core Spray Sys Instrument Channel Calibr & Test,High Drywell Pressure Switches Tripped Above Tech Spec Limit.Cause Attributed to Instrument Repeatability.Switches Adjusted ML19294C0581980-02-28028 February 1980 LER 80-005/03L-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 ML19352A0961977-03-23023 March 1977 LER 77-001/01T-0:on 770310,both Personnel Airlock Doors Doors to Reactor Bldg Northwest Corner Found Open at Same Time.Caused by Personnel Failure to Recognize Possible Tech Specs Violation.Secondary Containment Integrity Stressed 1983-01-20
[Table view] Category:RO)
MONTHYEARML20028E7741983-01-20020 January 1983 LER 82-061/03L-0:on 821216,offgas Isolation Valve Failed to Close Fully on Independent Closure Signal.Caused by Defective Pilot Solenoid Valves Due to Foreign Matter on Solenoid Valve Seat Prohibiting Termination of Air Supply ML20042A2941982-03-0505 March 1982 LER 81-071/01T-0:on 811231,radwaste Liquid Effluent Monitor Found Inoperable.Proper Surveillance Not Performed.Caused by Personnel Error & Lack of Administrative & Procedural Controls.Control Procedures Written & Parts Replaced ML20041D8021982-02-25025 February 1982 LER 82-007/03L-0:on 820126,main Steam Line High Flow Sensor RE-22H Tripped at Greater Value than Given in Tech Specs. Caused by Instrument Repeatability & Drift.Sensor Reset & Setpoints Lowered ML20039C3021981-12-17017 December 1981 LER 81-059/03L-0:on 811116,APLHGR Not Checked for Type Iiif Fuel During Daily Core Checks.Caused by Engineer Failure to Assign Alternate Core Location to Take Traveling in-core Probe Truce After Problems Arose at Current Location ML20011A8961981-10-21021 October 1981 LER 81-046/03L-0:on 810920,three Hydraulic Snubbers in Shutdown Cooling Sys Could Not Obtain Drag Load within Acceptable Limits.Caused by Dirty Oil,Cracked Brass Head Ring,Faulty O-ring & Seals.Snubbers Replaced ML19345E9311981-01-30030 January 1981 LER 81-002/03L-0:on 810102,gaseous Releases to Stack Found Not Continuously Monitored as Required by Tech Spec.Caused by Tripping of Stack Gas Sample Pump Due to Normal Wear.Pump Replaced W/Spare ML19345B8101980-11-25025 November 1980 LER 80-047/03L-0:on 801101,while Performing Core Spray Sys Instrument Channel Calibr & Test,High Drywell Pressure Switches Tripped Above Tech Spec Limit.Cause Attributed to Instrument Repeatability.Switches Adjusted ML19294C0581980-02-28028 February 1980 LER 80-005/03L-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 ML19352A0961977-03-23023 March 1977 LER 77-001/01T-0:on 770310,both Personnel Airlock Doors Doors to Reactor Bldg Northwest Corner Found Open at Same Time.Caused by Personnel Failure to Recognize Possible Tech Specs Violation.Secondary Containment Integrity Stressed 1983-01-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-011, :on 980914,three Small Bore Pipe Lines Did Not Meet Design Bases for Seismic & Thermal Allowables.Caused by Inadequate Structural Piping Analysis.Two 1/2 Sdcs Lines Were Modified During 17R RFO & 3rd Was Modified During 19991999-09-30030 September 1999
- on 980914,three Small Bore Pipe Lines Did Not Meet Design Bases for Seismic & Thermal Allowables.Caused by Inadequate Structural Piping Analysis.Two 1/2 Sdcs Lines Were Modified During 17R RFO & 3rd Was Modified During 1999
ML20216H5141999-09-24024 September 1999 Safety Evaluation Supporting Amend 209 to License DPR-16 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 05000219/LER-1999-001, :on 990208,prolonged Operation of TB with Condenser & Heater Bay Pressure Less than Design Was Noted. Caused by Lack of Clearly Documented Design Description. Placed Alternate Exhaust Fan in Service.With1999-07-29029 July 1999
- on 990208,prolonged Operation of TB with Condenser & Heater Bay Pressure Less than Design Was Noted. Caused by Lack of Clearly Documented Design Description. Placed Alternate Exhaust Fan in Service.With
ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1999-004, :on 990510,determined That Configurations of Two Pipe Supports in Spent Fuel Pool Cooling Sys Do Not Meet Design Requirements for Deadweight Loads.Caused by Inadequate Analysis.Pipes Upgraded.With1999-06-22022 June 1999
- on 990510,determined That Configurations of Two Pipe Supports in Spent Fuel Pool Cooling Sys Do Not Meet Design Requirements for Deadweight Loads.Caused by Inadequate Analysis.Pipes Upgraded.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 ML20195C8141999-06-0202 June 1999 Safety Evaluation Supporting Amend 208 to License DPR-16 ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206U9511999-05-18018 May 1999 Safety Evaluation Supporting Amend 207 to License DPR-16 ML20206P0241999-05-13013 May 1999 Safety Evaluation Supporting Amend 206 to License DPR-16 ML20206P0881999-05-12012 May 1999 Safety Evaluation Supporting Amend 205 to License DPR-16 ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1999-003, :on 990402,cable Trays Did Not Meet Separation Criteria.Caused by Inadequate Engineering Review.Fire Watch Was Stationed Immediately Upon Discovery.With1999-04-30030 April 1999
- on 990402,cable Trays Did Not Meet Separation Criteria.Caused by Inadequate Engineering Review.Fire Watch Was Stationed Immediately Upon Discovery.With
05000219/LER-1999-002-01, :on 990330,fire Protection Deluge Sys Isolation Valve Was Found Out of Position.No Root Cause Determined. Technical Assessment Was Performed.With1999-04-29029 April 1999
- on 990330,fire Protection Deluge Sys Isolation Valve Was Found Out of Position.No Root Cause Determined. Technical Assessment Was Performed.With
ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20205A7451999-03-17017 March 1999 Safety Evaluation Supporting Amend 204 to License DPR-16 05000219/LER-1999-001-02, :on 990208,noted Prolonged Operation of TB with Condenser & Heater Bay Pressure.Caused by Loss of Integrity of Ventilation Envelope (Physical Boundaries).Alternate Exhaust Fan Was Placed in Service.With1999-03-0808 March 1999
- on 990208,noted Prolonged Operation of TB with Condenser & Heater Bay Pressure.Caused by Loss of Integrity of Ventilation Envelope (Physical Boundaries).Alternate Exhaust Fan Was Placed in Service.With
ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-016, :on 981028,single DG Start,Occurred.Caused by Loss of One Source of Offsite Power.Generator Relay Surveillance Revised to Eliminate Possibility of Inadvertent Procedural Breaker Trips.With1999-01-0505 January 1999
- on 981028,single DG Start,Occurred.Caused by Loss of One Source of Offsite Power.Generator Relay Surveillance Revised to Eliminate Possibility of Inadvertent Procedural Breaker Trips.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 ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-019, :on 981118,missed TS Required Surveillance Test.Caused by Inadequate Administrative Controls.Revised Related Surveillance Task Descriptions to Provide Improved Ref.With1998-12-18018 December 1998
- on 981118,missed TS Required Surveillance Test.Caused by Inadequate Administrative Controls.Revised Related Surveillance Task Descriptions to Provide Improved Ref.With
ML20196E2741998-11-30030 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-16 ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-017, :on 981027,discovered That Station Battery Racks Did Not Comply with Seismic Design Basis.Caused by Inadequate Engineering Review.Restored Battery Rack Retainer Plates to Appropriate Configuration.With1998-11-25025 November 1998
- on 981027,discovered That Station Battery Racks Did Not Comply with Seismic Design Basis.Caused by Inadequate Engineering Review.Restored Battery Rack Retainer Plates to Appropriate Configuration.With
05000219/LER-1998-018, :on 981023,DG 2 Failed to Start from App R Local Shutdown Panel During Functional Test.Caused by Incorrectly Designed Wiring.Incorrect Wiring Was Modified & Demonstrated by Testing to Be Correct.With1998-11-23023 November 1998
- on 981023,DG 2 Failed to Start from App R Local Shutdown Panel During Functional Test.Caused by Incorrectly Designed Wiring.Incorrect Wiring Was Modified & Demonstrated by Testing to Be Correct.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 ML20155G9311998-11-0404 November 1998 Safety Evaluation Supporting Amend 201 to License DPR-16 ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-014, :on 980928,noted Failure of Isolation Condenser Tube Bundles.Caused by Thermal Stresses/Tgscc Due to Leaky Valve.Replaced Failed Tubes Bundles & Repaired Condensate Return Valve.With1998-10-29029 October 1998
- on 980928,noted Failure of Isolation Condenser Tube Bundles.Caused by Thermal Stresses/Tgscc Due to Leaky Valve.Replaced Failed Tubes Bundles & Repaired Condensate Return Valve.With
05000219/LER-1998-015, :on 980929,SDC Isolation Occurred Due to Equipment Failure.Caused by Damaged Conduit That Appeared to Have Been Damaged by Personnel Error.Instrument Was Repaired & Bypass Was Removed.With1998-10-28028 October 1998
- on 980929,SDC Isolation Occurred Due to Equipment Failure.Caused by Damaged Conduit That Appeared to Have Been Damaged by Personnel Error.Instrument Was Repaired & Bypass Was Removed.With
05000219/LER-1998-013-01, :on 980926,LLRT Results Indicated That MSIV NS03B Exceeded TS Leak Rate Limit.Caused by Component Wear. Maint Was Performed on Subject Valve to Restore Seat Integrity & as-left LLRT Was Acceptable.With1998-10-26026 October 1998
- on 980926,LLRT Results Indicated That MSIV NS03B Exceeded TS Leak Rate Limit.Caused by Component Wear. Maint Was Performed on Subject Valve to Restore Seat Integrity & as-left LLRT Was Acceptable.With
ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R 05000219/LER-1998-012-01, :on 980916,unplanned Actuation of Esfs Occurred.Caused by Written Communication.Procedure Revised to Include Signature Verifications to Install & Subsequently Remove Ohmmeter1998-10-16016 October 1998
- on 980916,unplanned Actuation of Esfs Occurred.Caused by Written Communication.Procedure Revised to Include Signature Verifications to Install & Subsequently Remove Ohmmeter
ML20154M6311998-10-15015 October 1998 Safety Evaluation Supporting Amend 200 to License DPR-16 05000219/LER-1998-011-01, :on 980914,discovered That Three Small Bore Piping Lines Did Not Meet Design Basis Seismic &/Or Thermal Allowables.Caused by Design Deficiency.Subject Lines Will Be Modified During Present Refueling Outage.With1998-10-15015 October 1998
- on 980914,discovered That Three Small Bore Piping Lines Did Not Meet Design Basis Seismic &/Or Thermal Allowables.Caused by Design Deficiency.Subject Lines Will Be Modified During Present Refueling Outage.With
ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With 05000219/LER-1998-010, :on 980724,DG Switchgear Was Found Beyond Design Bases.Caused by Inadequate Installation During Original Construction.Evaluated Temporary Mod to Determine If It Should Be Reclassified as Permanent Mod1998-08-24024 August 1998
- on 980724,DG Switchgear Was Found Beyond Design Bases.Caused by Inadequate Installation During Original Construction.Evaluated Temporary Mod to Determine If It Should Be Reclassified as Permanent Mod
ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B7331998-08-13013 August 1998 Safety Evaluation Supporting Amend 196 to License DPR-16 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 1999-09-30
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l t l@l 5 l 0 l 0 l 0 l0 12 l 1 l 9 l@l 0 l 8 l 21917 l9 74l@l075 l 9 REPORT 60 61 DOCKET NUMBER 68 69 EVENT DATE I? l 8DATE l 7 l 9 fJl(I,)
EVENT DESCRIPTION AND PROBABLE ' CONSEQUENCES h O 2 l During normal operation, CRD pump was removed from service due to ,
I 0 3 1 excessive leakage from a seal water pipina connection. The pipino was I o !4 1 found to be cracked on a short pipe nipple section where it is threaded l
[TE l into the seal cartridge. The safety significance of this event is con- I t o is I sidered minimal because of the availability o' a redundant pump. 1 0 12 l 1 1
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,,_ SEQUE NTI AL OCCUR R E NCE REFORT REVISION EVENT YE A R R EPORT NO. CODE TYPE NO.
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@ ,ajg'RO 17 19I l-l 10l3111 1/l IOl3l lL l l-l l0 l 21 22 23 24 26 27 28 29 30 31 32 T EN A ON ON PLANT HOURS SB i FO b. SU PLIE MANUFA TURER l32A l@'34X l@ lZl@ lZ l@ l010l0l0l lY l@ lYl@ l43Z l@ lZ l9 19 19 l 2 25 36 J7 40 41 42 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 1 ;O l The cracking appears to be caused by an operator usina the 1/2" oicina as 1 i i i a foot support. The affected short pipe nipple in the line was reolaced i i ,2 1 and the pump returned to service. I I
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1 9 @l10 NA 7910080 .3 FR l 7 8 9 80 PUB L ICITY NRC USE ONLY iSSUEC DESCRIPTION 2 n l Y j 44 l Weekiv news release - October 2. 1974 l d'Illllll lll e 9 1C 68 69 go, teAME OF PRED ARER Donald A. Ross PHONE: 20'-455-8784
- Jersey Central Power & Light Company
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yp g-) 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. 50-219/79-31/3L-C Report Date September 26, 1979 Occurrence Date August 29, 1979 Identification of Occurrence "B" CRD hydraulic pump was removed from service to repair leaking seal water piping. This event is considered to be a recortable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.
Conditions Prior to Occurrence Load changes during routine power operation were being made.
Power: Core, 1704.3 MWt Electric, 554 MVe Flow: Recirculating 15.4 x 10 gpm 4 Feedwater, 6.341 x 10 6 lb/hr Stack Gas Activity: 32,100 pCi/sec.
Description of Occurrence "B" CRD hydraulic pump seal water piping connection on the outboard seal was found to be leaking on Wednesday, August 29, 1979, at approximately 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />.
The "A" control rod drive pump was placed into service and the "B" pump removed from service and isolated for the purpose of performing corrective maintenance.
On August 30, 1979, at 1602 hours0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br />, the "B" control rod drive pump was placed into service and considered operable.
Apparent Cause of Occurrence The seal water piping was found to be cracked on a short pipe nipple section where it is threaded into the seal cartridge. Failure of the piping is attributed to use of the 1/2" piping as a support by operators during valving operations in the area.
17',2 296 Jersey Central Power & Light Compey is a Member of the Genera! Pub'c Ut '.t.es System
Reportable Occurrence No. 50-219/79-31/3L-0 Page 2 September 26, 1979 Analysis of Occurrence in addition to supplying drive cooling and accumulator charging pressure, the control rod drive hydraulic system can provide high pressure coolant injection capability. For break sizes up to 0.002 ft.2, a single control rod drive pump with flow of 110 gpm is adequate for maintaining the reactor water level nearly five feet above the core, thus alleviating the necessity for electromatic relief valve actuation. The safety significance of this event is considered to be minimal, since the redundant pump was operable.
Corrective Action The "B" control rod drive pump was removed from service, isolated, and the pipe nipple replaced. Af ter completion of the corrective maintenance, the "B" control rod drive pump was placed into service. A memorandum has been issued to operations and maintenance personnel to stress the importance of not using small pipes as a suppo.*t when climbing or rigging equipment.
Failure Data 1/2" pipe Material - Carbon Steel 7
1::2 299