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LER-1983-018, Forwards LER 83-018/03L-0.Detailed Event Analysis Encl |
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o psuc Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 4
Salem Generating Station March 24, 1983 Mr.
R. C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Haynes:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 83-018/03L Pursuant to the requirements of Salem Generating Station Unit No. 1, Technical. Specifications, Section 6.9.1.9.b, l
we-are submitting Licensee Event Report for Reportable Occurrence 83-018/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours, 1
l b
J. M General Manager -
Salem Operations l
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Distribution l
8304010353 830324 PDR ADOCK 05000272 S
PDR The Energy People gp
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Report Number:
83-018/03L Report Date:
03-23-83 Occurrence Date:
02-23-83 Facility:
Salem Generating Station Unit 1 Public Service Electric & Gas Company Hancock's Bridge, liew Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Reactivity Control Systems - Boric Acid Storage System - Inoperable.
This report was initiated by Incident Report 83-051.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 3 - RX Power 0 % - Unit Load 0 MWe.
DESCRIPTIOfLQF OCCURRENCE:
At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br />, February 23, 1983, during routine operation, sample results for the Boric Acid Tanks (BATS) indicated that the boric acid concentrations for both tanks were below the Technical Specification limit of 20,100 ppm.
Concentrations were 19,725 and 19,364 ppm for Nos.
11 and 12 tanks respectively.
One of the tanks with proper contained volume and boric acid concentration is required for operability of a boric acid storage system as a borated water source.
With both tanks out-of-specification, the boric acid storage systems were both declared inoperable, and Technical Specification Action Statement 3.1.2.8a was entered.
The redundant borated water source, the Refueling Water Storage Tank (RWST), was operable throughout the occurrence.
APPARENT CA_QSE OF OCCURRENGE:
Investigation of the incident revealed that the tanks contents had apparently been diluted during recovery from a Safety Injection, which had occurred at 2204 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.38622e-4 months <br />, February 22, 1983.
The Safety Injection was associated with a loss of feedwater and reactor trip, which had originated with the failure of the No. 1F Group Bus to automatically transfer to the Auxiliary Power Transformer (see LER 83-012/01T).
During a Safety Injection, the Boron Injection Tank (BIT) is realigned from recirculation with the BATS to the RWST.
The BIT contents are injected into the Reactor Coolant System being displaced by less borated water from the RWST (2,000 ppm).
Restoration of a diluted BIT to recirculation can result in dilution of the BATS.
Review of the procedures involved in recovery from a Safety Injection, and in restoring the BIT to service, revealed that insufficient procedural guidance was provided to insure proper completion of the evolution.
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LER 83-018/03L ANALYSIS OF OCCURRENCE:
Borated water sources are part of the Boron Injection System, which insures negative reactivity control is available during each mode of f acility operation.
Above 200 F, a minimum of two redundant boron injection systems are provided to ensure single functional capability in the event one system is inoperable due to an assumed failure.
Allowable out-of-service periods insure that corrective action may be completed without undue risk of injection system failures during the period.
The boration capability of either system is sufficient to provide a shutdown margin of 1.6 delta k/k after xenon decay and cooldown to 200 F.
Since, as noted, the redundant injection system was operable, no risk to the health and safety of the public was involved.
Due to the loss of redundancy, the occurrence constituted operation in a degraded mode permitted by a limiting condition for operation.
The event is reportable in accordance with Technical Specification 6.9.1.9b.
Action Statement 3.1.2.8a requires:
With the boric acid storage system inoperable, restore the storage system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a shutdoun margin equivalent to at least 1% delta k/k at 200 degrees F; restore _the boric acid storage system to operable status within the next 7 days or be in cold shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
CORRECTIVE ACTION
Boric acid was added and recirculated.
Samples of the BATS showed that the concentrations were within specification.
At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, February 23, 1983, the. boric acid storage systems were declared operable, and Action Statement 3.1.2.8a was terminated.
Operating Instruction OI II-4.3.5 " Flushing, Draining and Filling the BIT" was revised to provide detailed guidance for restoring the BIT to recirculation following either dilution or draining.
FAILURE DATA:
A similar dilution of the BATS occurred January 26, 1982, following maintenance and refilling of No. 12 BAT (see LER 82-008/03X-1).
I 1
Prepared By R.
Frahm j
'V Generai" Manager -
Salem Operations SORC Meeting No.89-038 l
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| 05000272/LER-1983-001-03, /03L-0:on 830104,vital Bus 1B Tripped,Rendering RHR Loop Inoperable.Caused by Differential Relay Protection. Redundant RHR Loop Immediately Placed in Operation | /03L-0:on 830104,vital Bus 1B Tripped,Rendering RHR Loop Inoperable.Caused by Differential Relay Protection. Redundant RHR Loop Immediately Placed in Operation | | | 05000311/LER-1983-001, Forwards LER 83-001/03L-0.Detailed Event Analysis Encl | Forwards LER 83-001/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-001-03, /03L-0:on 830106,reactor Trip Breaker a Failed to Open Following Reactor Trip.Caused by Malfunctioning Breaker Undervoltage Relay Due to Binding of Relay Mechanism by Dirt or Corrosion.Breaker Replaced.Periodic Insp Initiate | /03L-0:on 830106,reactor Trip Breaker a Failed to Open Following Reactor Trip.Caused by Malfunctioning Breaker Undervoltage Relay Due to Binding of Relay Mechanism by Dirt or Corrosion.Breaker Replaced.Periodic Insp Initiated | | | 05000311/LER-1983-002, Forwards LER 83-002/03L-0.Detailed Event Analysis Encl | Forwards LER 83-002/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-002-03, /03L-0:on 830314,discovered Pressurizer Code Safety Valves 2PR3,2PR4 & 2PR5,tested by Wyle Labs During 830224-25,lifted Below 2,485 Psig Plus/Minus 1% Pressure Range & Displayed Heavy Audible & Visual Seat Leakage | /03L-0:on 830314,discovered Pressurizer Code Safety Valves 2PR3,2PR4 & 2PR5,tested by Wyle Labs During 830224-25,lifted Below 2,485 Psig Plus/Minus 1% Pressure Range & Displayed Heavy Audible & Visual Seat Leakage | | | 05000272/LER-1983-002-01, /01T-0:on 830106,station Power Transformer 12 de-energized for Planned Maint.Loss of Power to Automatic Starting Feature on Both Diesel Fire Pumps Resulted.Caused by Oversight Due to Human Error.Personnel Counseled | /01T-0:on 830106,station Power Transformer 12 de-energized for Planned Maint.Loss of Power to Automatic Starting Feature on Both Diesel Fire Pumps Resulted.Caused by Oversight Due to Human Error.Personnel Counseled | | | 05000272/LER-1983-003, Forwards LER 83-003/04L-0.Detailed Event Analysis Encl | Forwards LER 83-003/04L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-003-04, /04L-0:on 830121,during Commencement of Refueling Shutdown for Unit 2,Unit 1 Restart Delayed Approx 7 Wks. Caused by Problems W/Steam Generator Nozzle Dams & Degradation of Welds in Svc Water Piping | /04L-0:on 830121,during Commencement of Refueling Shutdown for Unit 2,Unit 1 Restart Delayed Approx 7 Wks. Caused by Problems W/Steam Generator Nozzle Dams & Degradation of Welds in Svc Water Piping | | | 05000311/LER-1983-003-03, /03L-0:on 830111,rod Position Indicator Channel 1SA2 Indicated Approx Half Scale,Contrary to Flux Map Indication That No Change in Rod Position Occurred.Caused by Failed Signal Conditioner.Module Replaced | /03L-0:on 830111,rod Position Indicator Channel 1SA2 Indicated Approx Half Scale,Contrary to Flux Map Indication That No Change in Rod Position Occurred.Caused by Failed Signal Conditioner.Module Replaced | | | 05000311/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-004-04, /04L-0:on 830317,during Gaseous Effluent Testing, Iodine/Particulate Collection Device Sample Pump Deenergized.Caused by Not Including Pump on Electrical Distribution List.Tagging Sys Will Be Revised | /04L-0:on 830317,during Gaseous Effluent Testing, Iodine/Particulate Collection Device Sample Pump Deenergized.Caused by Not Including Pump on Electrical Distribution List.Tagging Sys Will Be Revised | | | 05000311/LER-1983-004, Forwards LER 83-004/04L-0.Detailed Event Analysis Encl | Forwards LER 83-004/04L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-004, Forwards LER 83-004/03L-0.Detailed Event Analysis Encl | Forwards LER 83-004/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-004-03, /03L-0:on 830124,equipment Operator Discovered Leak on Diesel Generator 1B Jacket Water Sys.Caused by Cracked Piping Nipple Due to Personnel Standing on Jacket Water Sys Piping.Cracked Nipple Replaced | /03L-0:on 830124,equipment Operator Discovered Leak on Diesel Generator 1B Jacket Water Sys.Caused by Cracked Piping Nipple Due to Personnel Standing on Jacket Water Sys Piping.Cracked Nipple Replaced | | | 05000311/LER-1983-005-03, /03X-1:on 830122,both Channels of Pressurizer Overpressurization Protection Sys Declared Inoperable Due to Leakage in Pressurizer Relief Lines.Porv Plugs Replaced & PORV Circuitry Modified | /03X-1:on 830122,both Channels of Pressurizer Overpressurization Protection Sys Declared Inoperable Due to Leakage in Pressurizer Relief Lines.Porv Plugs Replaced & PORV Circuitry Modified | | | 05000311/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-005-03, /03L-0:on 830121,RHR Sys Automatic Isolation Function Not Tested Prior to Placing RHR Sys in Operation. Caused by Procedure Problems & Personnel Inexperience. Procedures Revised | /03L-0:on 830121,RHR Sys Automatic Isolation Function Not Tested Prior to Placing RHR Sys in Operation. Caused by Procedure Problems & Personnel Inexperience. Procedures Revised | | | 05000311/LER-1983-006-04, /04L-0:on 830408,decreased Sensitivity of Channel 2R41C Plant Vent Noble Gas Monitor Rendered Waste Gas Discharge Line Automatic Isolation Feature Inoperable.Caused by Leakage on Monitor Sample Lines & Internal Connections | /04L-0:on 830408,decreased Sensitivity of Channel 2R41C Plant Vent Noble Gas Monitor Rendered Waste Gas Discharge Line Automatic Isolation Feature Inoperable.Caused by Leakage on Monitor Sample Lines & Internal Connections | | | 05000311/LER-1983-006, Forwards LER 83-006/04L-0.Detailed Event Analysis Encl | Forwards LER 83-006/04L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-006-03, /03L-0:on 830126 & 28 Nonseismically Qualified Components & Power Boxes Discovered Installed in Dc Control Power Feeds to Emergency Diesel Generators.Caused by Personnel Oversight.Power Box Components Replaced | /03L-0:on 830126 & 28 Nonseismically Qualified Components & Power Boxes Discovered Installed in Dc Control Power Feeds to Emergency Diesel Generators.Caused by Personnel Oversight.Power Box Components Replaced | | | 05000272/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-007, Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days | Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days | | | 05000272/LER-1983-007-03, /03L-0:on 830129,control Room Operator Discovered Low Flow Through Number 14 Reactor Coolant Loop Resistance Thermometer Detector Bypass.Caused by Obstruction in Hot Leg Flowpath.Hot Leg Cycled & Bypass Flow Restored to Norm | /03L-0:on 830129,control Room Operator Discovered Low Flow Through Number 14 Reactor Coolant Loop Resistance Thermometer Detector Bypass.Caused by Obstruction in Hot Leg Flowpath.Hot Leg Cycled & Bypass Flow Restored to Normal | | | 05000272/LER-1983-007, Forwards LER 83-007/03L-0.Detailed Event Analysis Encl | Forwards LER 83-007/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-007-01, /01T-0:on 830210 & 11,during Routine Surveillance Testing,Two Steam Generator Snubbers Failed to Meet Acceleration & Bleed Test Requirements.Caused by Aging of Snubber Piston Seal Rubber Matl.Seals Will Be Rebuilt | /01T-0:on 830210 & 11,during Routine Surveillance Testing,Two Steam Generator Snubbers Failed to Meet Acceleration & Bleed Test Requirements.Caused by Aging of Snubber Piston Seal Rubber Matl.Seals Will Be Rebuilt | | | 05000272/LER-1983-008, Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions | Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions | | | 05000272/LER-1983-008-03, /03L-0:on 830311,discovered Pressurizer Code Safety Valves Tested for Lift Set Pressure & Seat Leakage by Wyle Labs During 821102-13 Lifted in Excess of Tech Specs & Exhibited Heavy Seat Leakage.Cause Undetermined | /03L-0:on 830311,discovered Pressurizer Code Safety Valves Tested for Lift Set Pressure & Seat Leakage by Wyle Labs During 821102-13 Lifted in Excess of Tech Specs & Exhibited Heavy Seat Leakage.Cause Undetermined | | | 05000311/LER-1983-008-99, /99X-0:on 830218,diesel Generator Area Low Pressure Carbon Monoxide Sys Automatic Initiation Feature Disabled & Tagged Out for Planned Maint.Continuous Fire Watch Established.On 830131,event Became Reportable | /99X-0:on 830218,diesel Generator Area Low Pressure Carbon Monoxide Sys Automatic Initiation Feature Disabled & Tagged Out for Planned Maint.Continuous Fire Watch Established.On 830131,event Became Reportable | | | 05000311/LER-1983-008, Forwards LER 83-008/99X-0.Detailed Event Anaysis Encl | Forwards LER 83-008/99X-0.Detailed Event Anaysis Encl | | | 05000272/LER-1983-009-99, /99X-0:on 830130,during Routine Plant Cooldown, Inadvertent Safety Injection Occurred Due to Low Pressurizer Pressure.Caused by Operator Overlooking Decreasing Pressure. All safety-related Equipment Functioned as Designed | /99X-0:on 830130,during Routine Plant Cooldown, Inadvertent Safety Injection Occurred Due to Low Pressurizer Pressure.Caused by Operator Overlooking Decreasing Pressure. All safety-related Equipment Functioned as Designed | | | 05000272/LER-1983-009, Forwards LER 83-009/99X-0.Detailed Event Analysis Encl | Forwards LER 83-009/99X-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-009-03, /03L-0:on 830203,during Shutdown Operation,Sample Analysis of RCS Boron Concentration Revealed Concentration Less than Tech Spec Limit.Caused by Hydrolazing Steam Generators.Rcs Boration Performed to Maintain Concentration | /03L-0:on 830203,during Shutdown Operation,Sample Analysis of RCS Boron Concentration Revealed Concentration Less than Tech Spec Limit.Caused by Hydrolazing Steam Generators.Rcs Boration Performed to Maintain Concentration | | | 05000272/LER-1983-010-03, /03L-0:from 821016-830205,during Testing of Type B & C Components,Three Containment Isolation Valves Exhibited Leakage Rates in Excess of Test Equipment Range. Valves 1CC215 & 1VC8 Restroked.Valve 14GB4 Reworked | /03L-0:from 821016-830205,during Testing of Type B & C Components,Three Containment Isolation Valves Exhibited Leakage Rates in Excess of Test Equipment Range. Valves 1CC215 & 1VC8 Restroked.Valve 14GB4 Reworked | | | 05000311/LER-1983-010-03, /03L-0:on 830126,during Shutdown Operations, Control Air Header 21 Isolated & Tagged for Leak Rate Testing.Porv 2PR1 Closed Resulting in Loss of RCS Vent Path. Caused by Surge in Header 22 Due to Failed Valve | /03L-0:on 830126,during Shutdown Operations, Control Air Header 21 Isolated & Tagged for Leak Rate Testing.Porv 2PR1 Closed Resulting in Loss of RCS Vent Path. Caused by Surge in Header 22 Due to Failed Valve | | | 05000311/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-011, Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-011-03, /03L-0:on 830401,discovered That Monthly Testing of Control Room Emergency Air Conditioning Sys Was Overlooked.Caused by Insp Order Sys Card Requiring Testing Being Erroneously Stated.Card Revised | /03L-0:on 830401,discovered That Monthly Testing of Control Room Emergency Air Conditioning Sys Was Overlooked.Caused by Insp Order Sys Card Requiring Testing Being Erroneously Stated.Card Revised | | | 05000311/LER-1983-011, Forwards LER 83-011/03L-0.Detailed Event Analysis Encl | Forwards LER 83-011/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-012-01, /01T-0:on 830222,during Startup,Reactor Manually Tripped.Caused by Rapidly Decreasing Steam Generator Levels. Manual Trip Obscured Failure of Trip Breakers to Open Automatically.Plant Cooldown Commenced | /01T-0:on 830222,during Startup,Reactor Manually Tripped.Caused by Rapidly Decreasing Steam Generator Levels. Manual Trip Obscured Failure of Trip Breakers to Open Automatically.Plant Cooldown Commenced | | | 05000311/LER-1983-012-03, /03L-0:on 830406,10-ton Cardox Sys Pilot Valve Found in Closed Position & All Low Pressure Sys Declared Inoperable.Caused by Inadequacies in Sys Recharging Operation on 830304.Procedures Revised | /03L-0:on 830406,10-ton Cardox Sys Pilot Valve Found in Closed Position & All Low Pressure Sys Declared Inoperable.Caused by Inadequacies in Sys Recharging Operation on 830304.Procedures Revised | | | 05000311/LER-1983-012, Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1983-013-99, /99T-0:on 830215,calculated Moderator Temp Coefficient (Mtc) Value for All Control Rods Withdrawn Found More Positive than Tech Spec Allowance But within Expected Deviation.Limitation on Withdrawal Will Be Maintained | /99T-0:on 830215,calculated Moderator Temp Coefficient (Mtc) Value for All Control Rods Withdrawn Found More Positive than Tech Spec Allowance But within Expected Deviation.Limitation on Withdrawal Will Be Maintained | | | 05000311/LER-1983-013-03, /03L-0:on 830409,during Routine Shutdown,Lube Oil Temp Increases Observed on Charging Pump 22.Caused by Restricted Svc Water Flow to Pump Due to Oyster Shells & Miscellaneous Mollusks.Shells Removed | /03L-0:on 830409,during Routine Shutdown,Lube Oil Temp Increases Observed on Charging Pump 22.Caused by Restricted Svc Water Flow to Pump Due to Oyster Shells & Miscellaneous Mollusks.Shells Removed | | | 05000272/LER-1983-013, Forwards LER 83-013/99T-0.Detailed Event Analysis Encl | Forwards LER 83-013/99T-0.Detailed Event Analysis Encl | | | 05000311/LER-1983-014-03, /03L-1:on 830413 & 18,operating Loads on 2A 4kV & 460-volt Vital Buses Observed to Trip.Caused by Spurious Operation of Safeguards Equipment Control Sys Due to Design Deficiencies.Equipment Restarted | /03L-1:on 830413 & 18,operating Loads on 2A 4kV & 460-volt Vital Buses Observed to Trip.Caused by Spurious Operation of Safeguards Equipment Control Sys Due to Design Deficiencies.Equipment Restarted | | | 05000272/LER-1983-014, Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | |
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