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LER-1983-012, Forwards LER 83-012/03L-0.Detailed Event Analysis Encl |
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r c0 PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 28, 1983 Mr. J. Allan Acting Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 Dear Mr. Allan LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 83-012/03L Pursuant to the requirements of Salem Generating Station Unit No.
2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 83-012/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours, 2.1 p
J.
M.
Zupko, Jr.
General Manager -
Salem Operations I
RF:ksfdp i
CC:
Distribution 8305160096 830428 PDR ADOCK 05000311 S
PDR g.
h The Energy People
% uncy, o m
9-Report Number:
~83-012/03L
- - Report Date:-
04-27-83 Occurrence Date:
04-06-83 Facility:-
Salem Generating Station Unit 2=
Public Service Electric & Gas Company Hancock's Bridge,.New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Plant Systems - Low Pressure CO2 Systems - Improper Valve Lineup.
This report was initiated by Incident Report 83-062.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 6 - RX Power 0 5 - Unit Load 0 MWe, DESCRIPTION OF OCCURRENCE:
LAt 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, April 6, 1983, during routine shift rounds, an Equipment Operator discovered the 10 Ton Cardox System pilot valve in the_ closed position.
The valve is normally locked open to insure pilot gas is available for actuation of the individual system master and master selector valves.
All low pressure CO2 systems were declared inoperable, and Technical Specification 3.7.10.3a was entered.
At 1756 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.68158e-4 months <br />, April 6, 1983, the pilot valve was opened and locked-in position, restoring the low, pressure CO2 systems-to an operable status.
APPARENT CAUSE OF OCCURRENCE:
Investigation of the occurrence revealed that a check of the position of the pilot valve was not' included in routine surveillance testing.
On March 8, 1983, the selector valve for the Diesel Fuel Oil ~ Transfer Pump Rooms had been opened twice for testing of system alarm and automatic damper actuation features.
No problems were noted at that time, although subsequent' testing revealed that, due to residual pilot l
line pressure, a master or master selector valve could be opened four times following isolation of the pilot valve.
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A search of the Tagging Request and Inquiry System revealed no tagging requests issued for the system since November 2, 1982.
System recharging had been performed on March 4, 1983; the investigation revealed that no procedure was in effect for the evolution.
As l
indicated by subsequent testing, selector valve operation on March 8 could have been completed with the pilot. valve being closed during the i
i' recharging operation on March 4.
The valve may therefore have been inadvertently manipulated at the time of the recharging, although no l
other evidence. supporting this conclusion was identified.
t i
'LER 83-012/03L '
AMALYSIS OF OCCURRENCE:
The' operability of the fire suppression systems ensure that adequate fire suppressiog,in any portion of the facility where safety related capability is available to confine and extinguish fires occurring equipment is located.
The collective capability of the fire
. suppression systems is adequate.to minimize the potential damage to safety related equipment and is a major element in the facility fire protection-program.-
The' fire protection program is a design feature which insures that redundant engineered safety features are not rendered inoperable by.a fire.
Since a coincidental low probability fire must occur before adverse ' performance. results, however, degradation of the program does not of itself imply adverse performance during accident conditions As demonstrated, a CO2. system could have operated upon receipt of a valid' actuation signal following. isolation of the pilot line.
Due to maintenance-associated with a refueling outage, the Diesel Generator Area automatic actuation feature was disabled, and a continuous fire watch was already in effect in the area (see LER 83-00 8/ 99X-0 ).
As the result of the inoperability of various fire barriers, roving watches were patrolling all other affected spaces.
Finally,_. protection was restored in a timely fashion, in compliance with the action statement.
The occurrence therefore involved no risk
- - to the health and safety of the public.
Due to the possible
- - inoperability of required fire suppression systems, the event involved operation in a degraded mode permitted by a limiting condition for operation.
The occurrence is therefore reportable in accordance with-Technical Specification 6.9.1.9b.
CORRECTIVE ACTION
As noted, the pilot valve was opened at 1756 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.68158e-4 months <br />. April 6, 1983, and Action Statement 3.7.10.3a was terminated.
To ensure the valve is maintained locked open, a check of the valve status was incorporated into the monthly surveillance test.
A procedure for recharging the i
.Cardox. system will be written to ensure only the required valves are operated during the evolution.
FAILURE DATA:
Not Aplicable Prepared By R.
Frahm 14)
[/
GeVieral Man (rier -
Salem Operations SORC Meeting No.89-056 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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