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LER-1983-017, Forwards LER 83-017/03L-0.Detailed Event Analysis Encl |
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O PSEG l
Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 11, 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 83-017/03L Pursuant to the requirements of Salem Generating Station Unit No.
1, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 83-017/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours,
\\, )g #
V H.
J. Midura General Manager -
Salem Operations RF:ksfd CC:
Distribution M032!0627 833031
{DRADOCK 05000272 PDR nW
/)' V The Energy People m %,,, n -
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- Report 9 Number
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83-017/03LL q
Report Date:-
03-07 !
iOccurrence Date: 102-15 -
/
- Facility:
' Sales Generating I Station ' Unii 1 LPublic. Service Electric;&. Gas Company 1-
.Hancock's Bridge, New Jersey,,08038 IDENTIFICATION OF OCCURRENCE:.
' Reactor: Coolnt Systems-Leakage Detection Systems - Containment Sump a
Monitoring' System.- Inoperable..
LThis report'wasjinitiated by'IncidentLReportsB3-044.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 2 - RX? Power 3.5 - Unit' Load'O MWe.
DESCRIPTION OF' OCCURRENCE:
At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, February-15..1983,-during routine operation, tne Control ' Room Operator discovered that.-both 'Nos. 11 and 12.. Containment Sump' Pumps were running continuously.
To prevent ~ damage to the pumps, they were de-energized.and their power supplies tagged out.
This.
rendered the Containment' Sump Monitoring System inoperable, and Technical. Specification Action Statement 3.4.6.1 was entered.
Redundant Reactor Coolant-System (RCS)-leakage detection systems were operable throughout the occurrence.
APPARENT CAUSE OF OCCURRERGE:
. Investigation of the problem. revealed that Containment Sump Level
= Detector LD-7749 was malfunctioning, apparently due to binding in the i
magnetic sleeve assembly.
The problem was intermittant in nature, periodically preventing the. automatic de-energization of No. 11
' Containment. Sump Pump.
No other problems were evident; no recent, similar occurences were noted.
The problem was therefore assumed to be--isolated in nature.
ANALYSIS Of OCCURRENCE:
The-Containment-Sump' Monitoring System is utilized as an RCS leakage n
detection system to1 monitor and detect leakage from the Reactor Coolant Pressure Boundary.
The boundary is one of multiple fission
. product boundaries required to contain radioactive fission products
- - during accident conditions.
L 1Since-the redundant leakage detection systems were operable, and no degradation offthe boundaries occurre.4, the event involved no risk to the' health and safety.of the public.
Due to the loss of redundancy,
~
ithe.. event; constituted operation in a degraded mode permitted by a
+ 3;
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____._,.,.._.._._.__,,..___...,.I
LER~83-017/03L
- ANALYSIS OF OCCURRENCE: (cont'd) limiting condition for operation.
The occurrence is reportable in accordance with Technical Specification 6.9.1.9b.
Action Statement 3.4.6.1 requires:
With only two of the above required leakage detection systems operable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring system is inoperable; otherwise, 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 in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
CORRECTIVE ACTION
The -level sensing device was replaced, and containment sump pump operation was satisfactorily tested.
No further problems were observed.
The Containment Sump Monitoring System was declared operable, and Action Statement 3.4.6.1 was terminated at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />, February-16, 1983.
No further action was deemed necessary in view of the isolated nature of the occurrence.
FAILURE DATA:
Magnetrol Tandem Style Displacement Type Liquid Level Control Model A103FEP Erratic operation of Level Detector LD7750 on January 29, 1981, documented in LER 81-09/03L, resulted in replacement of the device.
Due to the difference in the failure symptoms, however, the occurrences are apparently unrelated.
Prepared By R.
Frahm
/
b[t'
<C
' Ge'nersl Manager -
SORC Meeting No. _83-028
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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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