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LER-1983-003, Forwards LER 83-003/04L-0.Detailed Event Analysis Encl |
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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station February 16, 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 83-003/04L Pursuant to the requirements of Salem Generating Station Unit No. 1, Environmental Technical Specifications, Section 5.6.2.1, we are submitting Licensee Event Report for Reportable Occurrence 83-003/04L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours, H. J. Midura l
General Manager -
Salem Operations RF:ks 4[
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Distribution Saa as8u'O 888$g S
I The Energy People pW
% 2189 (20A01181
Report Number:
83-003/04L Report Date:
02-09-83 Occurrence Date:
01-21-83 Facility:
Salem Generating Station Unit 1 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCHRRENCE:
Concurrent Shutdown of Salem Generating Station Units 1 and 2.
This report was initiated by Incident Report 83-017.
CONDITIONS PRIOR TO OCCURRENCE:
Unit 1 - Mode 5 - RX Power 0 % - Unit Load 0 MWe.
Unit 2 - Mode 1 - RX Power 52 5 - Unit Load 520 MWe.
DESCRIPTION OF OCCURRENCE:
At 2028 hours0.0235 days <br />0.563 hours <br />0.00335 weeks <br />7.71654e-4 months <br />, January 21, 1983, a plant shutdown for refueling of Salem Generating Station Unit 2 was commenced. -The shutdown followed a normal power coastdown to 50% power and had been scheduled since early in the previous year, based on the desired level of fuel burnout and to provide a minimum four week period of operation following the Unit 1 refueling shutdown.
Unanticipated problems with steam generator eddy current testing and service water piping to No. 12 Component Cooling Heat Exchanger delayed the Unit 1 restart for approximately 7 weeks.
Due to the delay, an unintentional concurrent shutdown of both units occurred, resulting in possible thermal stress to the aquatic environment.
APPARENT CAUSE OF OCCURRER_GE:
The Unit 1 refueling was set back approximately 16 days when steam generator dams failed to perform satisfactorily.
A further delay of 5 weeks involved the discovery of degradation of a number of welds in the Service Water System piping to No. 12 Component Cooling Heat Exchanger.
Repair of the system prior to plant startup was necessary to meet safety requirements of the Technical Specifications.
The weld degradation apparently involved corrosion of the weld materials in the service water environment.
The Unit 2 coastdown had been planned to separate the shutdowns of the two units.
A safety analysis for extended fuel burnup of 16.8 MWD /MTM had been performed; calculation of burnup on January 21, 1983, revealed 16.73 MWD /MTM.
Continued oper.ation would have resulted in l
LER 83-003/04L.
APPARENT CAUSE OF OCCURRENCE: (cont'd) less conservative peaking factors, putting the core closer to thermal limits and necessitating further analysis.
Unit 2 also had several equipmer.t problems which individually were not significant but which overall made continued operation less desirable from the standpoint of safety.
Finally, a number of 18 month surveillance requirements were coming due, several already requiring license changes for continued operation.
Overall, timely surveillance of plant safety systems is important to insure that the systems are operable, and to insure no risk to the health and safety of the public is incurred.
ANALYSIS OF OCCURRENCE:
Section 2.1.3.2 of the Environmental Technical Specifications (ETS) requires:
Both units shall not be intentionally shut down concurrently during the period of November through April.
The specification is not applicable if the shutdown is required to protect the health and safety of the public.
The ETS limit is based on preventing " cold shock" to aquatic organisms of the Delaware River.
The phenomenon has been found to be most severe during the period of low ambient water temperatures.
The potential for cold shock is minimized by maintaining one unit in operation.
As noted, the Unit 2 shutdown was necessitated by overall safe operating practice.
Problems with Unit 1 were unexpected, and also required keeping the unit shutdown for safety.
All reasonable efforts were made to prevent a concurrent shutdown, and the occurrence was not intentional.
Since the event further involved protection of the health and safety of the public, no violation of the specification occurred.
The ETS limits define adverse impact on the environment; since no limits were exceeded, no adverse impact was involved.
The occurrence constituted an unusual event that affects potential environmental impact from plant operation and that has high potential public interest.
The incident is therefore reportable in accordance with ETS Section 5.6.2.1.
CORRECTIVE ACTION
All degraded welds on No. 12 Component Cooling Heat Exchanger were repaired utilizing improved materials.
Due to additional delays, Unit 1 is still shutdown and is expected to return to operation on February 18, 1983.
The Unit 2 refueling outage is underway and is scheduled to be completed May 10, 1983.
Since all reasonable efforts were taken to
LER 83-003/04L.
CORRECTIVE ACTION
(cont'd) prevent the occurrence, and since the problems involved were apparently isolated in nature, no corrective action was deemed.
necessary to prevent recurrence.
FAILURE DATA:
Problems with No. 12 Component Cooling Heat Exchanger are outlined in LER 82-091/01T.
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Prepared By R.
Frahm Gen'eral Manager -
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SORC Meeting No.
89-15 I
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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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