LER-1981-004, /01T-0:on 810116,studies Indicated That Emergency Diesel Generators May Exceed Load Rating During Accident Conditions.Caused by Using Different & More Conservative Methods to Calculate Load.Actions to Reduce Load Underway |
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.1el d [ Recent s+m ies have indicated that during a loss of coolant accident I
a I with a loss of off-site powr plus a single bus failure the load on the l
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- ;;; ; rating of 2750 KW the operators have been provided guidance.via a stand-
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. OYSTER CREEK NUCIEAR GENERATING STATION Ebrked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-04/0lT Peport Date i
January 30, 1981 Occu m. Date i
i January 16, 1981 1
Identification of Occurrence 2
i Becent studies have indicated that the load on the Butu.yacy Diesel Generators,-
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l during an actual Ioss of Coolant Accident (IDCA) with a loss of off-site power plus a single bus failure, oculd exceed the full load rating of 2500 KW.
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'Ihis event is considered a reportable occurrence as defined in the Technical
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Specifications, paragraph 6.9.2.a(9).
Conditions Prior to Occurrence
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Not applicable.
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Description of Occurrence Due to future anticipated load expansion at the Oyster Creek Station a study was 3
l undertaken to document the present load profiles on all power buses throughout-1 the plant under several operating configurations. One aspect of this ' study performed for Jersey Central Power and Light included Maxinun Denand Safety Bus i
loading during the IOCA and Ioss of Offsite pcwer scenario. Preliminary data pre-sented to JCP&L indicated that a potE.ntial' exists for substantially overloading the diesel generator above its emergency rating of 2750 KW.
'Ihis result disagrees with measured inMing during annual testing and previously subnitted analysis to the NBC.
The primary differences are attributed to the use of nameplate data in addition to the inclusion of all non-safety connected load in the maximtrn demand study, therefore, resulting in highly ccnservative projections. Since the new calculational method introduces recognized conservatisms due to estimated or j
nameplate load vs actual load conditions it was determined necessary to use demonstrated loss of power test results with aMM factors accounting for single i
failures and possible runout values. - The maxinun load experienced during any loss of power test at Oyster Creek was 2460 KW under postulated IOCA conditions, with loss of offsite power,. and one assuned diesel generator failure. To this L
load an additional 219.4 KW was aMM to account for the aMM ' load resulting l-fran runout flows expected on Core Spray and Con + aim =nt Spray Systems for a t total of 2679.4 KW on Diesel Generator #2 (which is the most limiting case).
This calculated total exceeds the continuous full load rating of 2500 KW for the a
diesel generators.
Apparent Cause of Occurrence 1
'Ihe cause of.this occurrence was attributed to differences in-the methods used 3'
to calculate the diesel generator loads,'during a IDCA with a loss of offsite power and 'a single bus failure, during a recent study as ccupared to _an analysis perfhmM during the Oyster Creek ECCS modification in 1975.
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Reportable Occurrence Page 2 Report No. 50-219/81-04/0lT Analysis of Occurrence The nest limiting diesel generator load was found to be 2460 W on DG 2 which was detemined during loss of power testing. The procedure used to perform the loss of somr test is set up such that it reflects expected load conditions seen during a IDCA with a single failure. This single failure is a simulation of one faulted bus or diesel generator. However, certain pumps in the safety related systems muld be operating at " runout" ficw under accident conditions (approximated by using nameplate ratings) instead of rated systs flows which are those measured during the test. Assuming this occurs the difference between design pump load and nameplate load must be added to the actaal load of 2460 KW.
Another factor that must be included in the analysis is the load addal by smaller power panels in the distribution systs. Since these power panels will nomally transfer to other buses during the loss of pomr tests, these loads are not included in the expected value of 2460 KW.
The total of these power panel loads was determined to be 80 KW.
The suntrary of these calculations is as follows:
Actual Largest Diesel Ioad (with single failure) 2460 KW Transferable Power Panels 80 KW Two (2) Core Spray Booster Pumps (runout differential) 62.4 KW Two (2) Core Spray Main Pump (runout differential) 24.6 KW one (1) Containment Spray Pump (runout differential) 52.4 KW Total I. cad 2679.4 KW
'Ihis value compares satisfactorily with an allowable peak load rating of 2750 KW.
Although the manufacturer will allow operation at 2750 KW for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year (a virtual " continuous" rating as applied at Oyster Creek), aaaitional margin was provided by issuing a Standing Order requiring the cperators to trip the Peactor Building Closed Cooling Water Pumps and Service Water Pumps, follow-ing diesel generator. load sequencing, in the event of a IDCA with a loss of off-site power, since these loads are unnecessary in that scenario. The net effect of these actions would be to reduce the load on the diesel generator by 336 KW to a total of 2343.4 KW which is less than the continuous load rating of 2500 KW for the diesel generators.
Corrective Action
i A Standing Order has been issued which reqaires the operators to trip the Reactor Building Closed Cooling Water (RBOCW) and Service Water (SW) pumps after load sequencing following a TACA with a loss of offsite power. This action reduces the load on the most limiting Diesel Generator to less than the full load rating of 2500 KW (assuming one diesel generator fails).
- - her anticipated corrective actions include performing a study to install under voltage devices on non-essential loads and to install a modification which will prevent the RBCrW and SW pumps from starting during load sequencing under IDCA conditions.
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| 05000219/LER-1981-001-03, /03L-0:on 810102,containment Spray Sys High Drywell Pressure Indicating Switch IP-15C Tripped Above Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset & Study Examining Causes of Repeatability Undertaken | /03L-0:on 810102,containment Spray Sys High Drywell Pressure Indicating Switch IP-15C Tripped Above Tech Spec Limits.Caused by Instrument Repeatability.Switch Reset & Study Examining Causes of Repeatability Undertaken | | | 05000219/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000219/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000219/LER-1981-002-03, /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 | /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 | | | 05000219/LER-1981-003-03, /03L-0:on 810112,during Visual Insp of Fire Hydrants,Hydrant 2 Found to Contain Frozen Water in Barrel, Rendering Hydrant Inoperable.Caused by Water Leaking from Hydrant Valve & Freezing in Barrel.Hydrant Thawed | /03L-0:on 810112,during Visual Insp of Fire Hydrants,Hydrant 2 Found to Contain Frozen Water in Barrel, Rendering Hydrant Inoperable.Caused by Water Leaking from Hydrant Valve & Freezing in Barrel.Hydrant Thawed | | | 05000219/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000219/LER-1981-004, Forwards LER 81-004/01T-0 | Forwards LER 81-004/01T-0 | | | 05000219/LER-1981-004-01, /01T-0:on 810116,studies Indicated That Emergency Diesel Generators May Exceed Load Rating During Accident Conditions.Caused by Using Different & More Conservative Methods to Calculate Load.Actions to Reduce Load Underway | /01T-0:on 810116,studies Indicated That Emergency Diesel Generators May Exceed Load Rating During Accident Conditions.Caused by Using Different & More Conservative Methods to Calculate Load.Actions to Reduce Load Underway | | | 05000219/LER-1981-005-03, /03L-0:on 810106,emergency Svc Water Pump 52B Current & Discharge Pressure Found Outside Tech Spec. Probably Caused by Clogged Pump Suction Strainer.Strainer Cleared | /03L-0:on 810106,emergency Svc Water Pump 52B Current & Discharge Pressure Found Outside Tech Spec. Probably Caused by Clogged Pump Suction Strainer.Strainer Cleared | | | 05000219/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000219/LER-1981-006-03, /03L-0:on 810115,during Surveillance Testing, Reactor Triple Low Water Level Indicator Switch RE-18B Tripped at Monometer Reading Higher than Allowed by Tech Spec Table 3.1.1.Caused by Instrument Drift.Switch Reset | /03L-0:on 810115,during Surveillance Testing, Reactor Triple Low Water Level Indicator Switch RE-18B Tripped at Monometer Reading Higher than Allowed by Tech Spec Table 3.1.1.Caused by Instrument Drift.Switch Reset | | | 05000219/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000219/LER-1981-007-03, /03L-0:on 810202,water-tight Door to Containment Spray Sys I Compartment Not Closed & Verification of Closed Door Not Performed.Caused by Personnel Error & Lack of Controls to Ensure Doors Are Closed After Passage | /03L-0:on 810202,water-tight Door to Containment Spray Sys I Compartment Not Closed & Verification of Closed Door Not Performed.Caused by Personnel Error & Lack of Controls to Ensure Doors Are Closed After Passage | | | 05000219/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000219/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000219/LER-1981-008-03, /03L-0:on 810210,water Seepage Observed Along West Wall of Nrw Bldg.Direct Survey Showed Detectable Ground Contamination Only within 6 Inches of Wall.Caused by High Levels in Tank Vaults.Herculite Secured & Sealed to Wall | /03L-0:on 810210,water Seepage Observed Along West Wall of Nrw Bldg.Direct Survey Showed Detectable Ground Contamination Only within 6 Inches of Wall.Caused by High Levels in Tank Vaults.Herculite Secured & Sealed to Wall | | | 05000219/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted | Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted | | | 05000219/LER-1981-009-03, /03L-0:on 810213,snubber 23/3 Found W/Very Low Oil Level & Oil Discovered on Floor at Base Connection During NRC walk-around Insp.Caused by Failure of Inner Shaft Seal Due to Deterioration.Snubber Replaced W/Operable Spare | /03L-0:on 810213,snubber 23/3 Found W/Very Low Oil Level & Oil Discovered on Floor at Base Connection During NRC walk-around Insp.Caused by Failure of Inner Shaft Seal Due to Deterioration.Snubber Replaced W/Operable Spare | | | 05000219/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000219/LER-1981-010-03, /03L-0:on 810202,during Routine Surveillance Testing,Main Steamline High Radiation Monitor RN-06B Tripped at Value Higher That Tech Spec Limits.Caused by Failure to Revise Trip Settings.Trip Settings Lowered | /03L-0:on 810202,during Routine Surveillance Testing,Main Steamline High Radiation Monitor RN-06B Tripped at Value Higher That Tech Spec Limits.Caused by Failure to Revise Trip Settings.Trip Settings Lowered | | | 05000219/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Encl | Forwards LER 81-011/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-011-03, /03L-0:on 810309,isolation Condenser Condensate Return Line Pipe Break Sensor IB11B2 Found to Trip at Value Greater than That Specified in Tech Specs.Caused by Instrument Repeatability.Replacement Recommended | /03L-0:on 810309,isolation Condenser Condensate Return Line Pipe Break Sensor IB11B2 Found to Trip at Value Greater than That Specified in Tech Specs.Caused by Instrument Repeatability.Replacement Recommended | | | 05000219/LER-1981-012-03, /03L-0:on 810313,electromatic Relief Valve High Pressure Actuation Switches 1A83C & 1A83E Tripped Higher than Limit Specified in Tech Spec.Caused by Instrument Repeatability.Pressure Sensors Reset to Trip within Limits | /03L-0:on 810313,electromatic Relief Valve High Pressure Actuation Switches 1A83C & 1A83E Tripped Higher than Limit Specified in Tech Spec.Caused by Instrument Repeatability.Pressure Sensors Reset to Trip within Limits | | | 05000219/LER-1981-012, Forwards LER 81-012/03L-0.Detailed Event Analysis Encl | Forwards LER 81-012/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-013-03, /03L-0:on 810319,core Spray Hi Drywell Pressure Switch RV46B Tripped in Excess of 2 Psi Tech Spec.Caused by Sensor Repeatability.Sensor Recalibr.Replacement of Sensors Recommended by PORC | /03L-0:on 810319,core Spray Hi Drywell Pressure Switch RV46B Tripped in Excess of 2 Psi Tech Spec.Caused by Sensor Repeatability.Sensor Recalibr.Replacement of Sensors Recommended by PORC | | | 05000219/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl | Forwards LER 81-013/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-014, Forwards LER 81-014/01T-0.Detailed Event Analysis Encl | Forwards LER 81-014/01T-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-014-01, /01T-0:on 810401,containment Oxygen Concentration Was Not Reduced to Less than 5% within 24-h After Placing Reactor Mode Switch in Run.Caused by Inerting at Significantly Reduced Rates | /01T-0:on 810401,containment Oxygen Concentration Was Not Reduced to Less than 5% within 24-h After Placing Reactor Mode Switch in Run.Caused by Inerting at Significantly Reduced Rates | | | 05000219/LER-1981-015-03, /03L-0:on 810324,main Steam Line High Flow Sensors Tripped at Values Greater than Tech Specs Limit.Caused by Instrument Repeatability.Both Sensors Reset | /03L-0:on 810324,main Steam Line High Flow Sensors Tripped at Values Greater than Tech Specs Limit.Caused by Instrument Repeatability.Both Sensors Reset | | | 05000219/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Encl | Forwards LER 81-015/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-016-03, /03L-0:on 810421,approx 10,000 Gallons of Leakage from Condensate Transfer Pump Bldg Was Discovered on North & South Sides of Bldg.Caused by Loss of Valve Packing on V-2-88.Leakage Was Diked & Valve Repacked | /03L-0:on 810421,approx 10,000 Gallons of Leakage from Condensate Transfer Pump Bldg Was Discovered on North & South Sides of Bldg.Caused by Loss of Valve Packing on V-2-88.Leakage Was Diked & Valve Repacked | | | 05000219/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000219/LER-1981-017, Forwards LER 81-017/03L-0.Detailed Event Analysis Encl | Forwards LER 81-017/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-017-03, /03L-0:on 810415,one Containment Spray Sys Loop Considered Inoperable During Normal Operation.Caused by Large Amount of Sea Lettuce in Intake Canal,Overwhelming Trash Removal Sys.Circulating Water Pump Stopped | /03L-0:on 810415,one Containment Spray Sys Loop Considered Inoperable During Normal Operation.Caused by Large Amount of Sea Lettuce in Intake Canal,Overwhelming Trash Removal Sys.Circulating Water Pump Stopped | | | 05000219/LER-1981-018, Forwards LER 81-018/01T-0.Detailed Event Analysis Encl | Forwards LER 81-018/01T-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-018-01, /01T-0:on 810417,equipment Operator Found Valves Were Blocked from Fully Opening by Scaffolding Placed by Contractor Personnel.Caused by Personnel Error.Scaffolding Repositioned | /01T-0:on 810417,equipment Operator Found Valves Were Blocked from Fully Opening by Scaffolding Placed by Contractor Personnel.Caused by Personnel Error.Scaffolding Repositioned | | | 05000219/LER-1981-019-03, /03L-0:on 810328,during Normal Shutdown Sequence, IRM Calibr Was Not Performed as Required by Tech Specs. Caused by Procedural Inadequacy.Procedures Will Be Revised | /03L-0:on 810328,during Normal Shutdown Sequence, IRM Calibr Was Not Performed as Required by Tech Specs. Caused by Procedural Inadequacy.Procedures Will Be Revised | | | 05000219/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000219/LER-1981-020-03, /03L-0:on 810501,isolation Condenser Shell Level Instrument IGO6B Found Reading High During Annual Calibr. Caused by Evaporation of Instrument Ref Column.Column Backfilled W/Water to Normal Operating Level | /03L-0:on 810501,isolation Condenser Shell Level Instrument IGO6B Found Reading High During Annual Calibr. Caused by Evaporation of Instrument Ref Column.Column Backfilled W/Water to Normal Operating Level | | | 05000219/LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-021, Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-021-03, /03L-0:on 810603,high Pressure Sensor Switches RE03B, C & D Were Found Tripping within 8 Lb of Setpoint. Caused by Sensor Repeatability.Switches Reset.Switches Will Be Replaced During Next Refueling Outage | /03L-0:on 810603,high Pressure Sensor Switches RE03B, C & D Were Found Tripping within 8 Lb of Setpoint. Caused by Sensor Repeatability.Switches Reset.Switches Will Be Replaced During Next Refueling Outage | | | 05000219/LER-1981-022-01, /01T-0:on 810520,secondary Containment Integrity Not Maintained Due to Personnel Access Airlock Doors Ajar. Caused by Personnel Error & Loosened Striker Plate on Inside Door.Outside Door Closed & Striker Plate Repaired | /01T-0:on 810520,secondary Containment Integrity Not Maintained Due to Personnel Access Airlock Doors Ajar. Caused by Personnel Error & Loosened Striker Plate on Inside Door.Outside Door Closed & Striker Plate Repaired | | | 05000219/LER-1981-022, Forwards LER 81-022/01T-0 | Forwards LER 81-022/01T-0 | | | 05000219/LER-1981-023-03, /03L-0:on 810603,drywell Vented to Reduce Drywell Torus Differential Pressure.Caused by Moisture Buildup in Sensing Line Resulting in Erroneous Indication of Increased Oxygen Concentration.Procedures Will Be Reviewed | /03L-0:on 810603,drywell Vented to Reduce Drywell Torus Differential Pressure.Caused by Moisture Buildup in Sensing Line Resulting in Erroneous Indication of Increased Oxygen Concentration.Procedures Will Be Reviewed | | | 05000219/LER-1981-023, Forwards LER 81-023/03L-0.Detailed Event Analysis Encl | Forwards LER 81-023/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-024-03, /03L-0:on 810608,while Operating in Degraded Mode, Two Emergency Water Pumps Found Inoperable.Caused by Faulty Ammeter,Clogged Pump Suction Bells & Inadequate Administrative Controls.Ammeter Replaced & Bells Cleaned | /03L-0:on 810608,while Operating in Degraded Mode, Two Emergency Water Pumps Found Inoperable.Caused by Faulty Ammeter,Clogged Pump Suction Bells & Inadequate Administrative Controls.Ammeter Replaced & Bells Cleaned | | | 05000219/LER-1981-024, Forwards LER 81-024/03L-0.Detailed Event Analysis Encl | Forwards LER 81-024/03L-0.Detailed Event Analysis Encl | | | 05000219/LER-1981-025-01, /01T-0:on 810617,secondary Containment Was Broken When Both Reactor Bldg Railroad Airlock Doors Were Opened Together.Caused by Failure of Top Inner Door Latch & Operator Error.Operators Will Be Reinstructed | /01T-0:on 810617,secondary Containment Was Broken When Both Reactor Bldg Railroad Airlock Doors Were Opened Together.Caused by Failure of Top Inner Door Latch & Operator Error.Operators Will Be Reinstructed | | | 05000219/LER-1981-025, Forwards LER 81-025/01T-0.Detailed Event Analysis Encl | Forwards LER 81-025/01T-0.Detailed Event Analysis Encl | |
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