Similar Documents at Salem |
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LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl |
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O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 6, 1982 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 83-013/03L 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 83-013/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours, 4f U/l j
J.
M.
Zupko, Jr.
General Manager -
Salem Operations RF:kshd[
CC:
Distribution 8305160052 830506 PDR ADOCK 05000311 8
PDR The Energy People p-(fr2!h # Cr '! 1181
O Report Number:
83-013/ 03L 1 Report Date:
05-04-83 Occurrence Date:
04-09-83 Facility:
Salem Generating Station Unit 2 Public Service Electric & Gas Company 4
Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
r Reactivity Control Systems - No. 22 Charging Pump - Inoperable.
This report was initiated'by Incident Report 83-067.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 6 - RX Power 0 % - Unit Load 0 MWe.
DESCRIPTION OF OCCURRENCE:
At 1618 hours0.0187 days <br />0.449 hours <br />0.00268 weeks <br />6.15649e-4 months <br />, April 9, 1983, du' ring routine shutdown operation, an operator observed increasing lube oil temperatures on No. 22 Charging Pump.
At the time of the occurrence. the redundant charging pumps were unavailable due to maintenance activities associated with the shutdown.
No. 22 Charging Pump was declared inoperable and Technical Specification Action Statement 3.1.2.3 was entered.
Investigation of the problem indicated that service water flow was 1
being restricted to the charging pump as well as several other safety-related components; the components were all supplied by a common 4 inch branch of the No. 21 Service Water Header.
Other components affected included No.
21 Containment Spray Pump Room Cooler, No. 22 Charging Pump Room Cooler, No. 21 Safety Injection Pump Lube Oil Cooler, and No. 21 Residual Heat Removal Pump Room Cooler.
Suspecting the flow may be restricted by shells of American oysters released during maintenance and cleaning of portions of the service water system earlier in the shutdown period, a backflush of the affected components was performed.
The backflush path was through the Service Water System auxiliary feedwater pump cross-connect line.
4 Upon opening the cross-connect line, silt was observed deposited in the end of the line; the silt and approximately 1/2 cubic feet of shells of oysters and other miscellaneous mollusks were removed in the process of flushing the line.
All operations involving core alteration and positive reactivity changes were suspended until the backflushing operation was completed j
and No. 22 Charging Pump was restored to an operable status.
Several weeks later, on April 21, 1983, investigation of a high jacket water temperature condition on No. 2C Emergency Diesel Generator revealed loose shells in the diesel jacket water and lube oil coolers.
The diesel is also supplied by No. 21 Service Water Header, which had been completely rafilled following the previous flushing evolution.
LER 83-013/03L.
DESCRIPTION OF OCCURRENCE: (cont'd)-
i No; problems were evident with Nos. 2A and 2B Diesel Generators.
t however, and surveillance'of the generators has been satisfactorily
' completed to date (No. 2A Diesel Generator is normally supplied byDNo.
22 Service Water Header).
Only two' operable generators are required by the Technical Specifications during shutdown' operation, and therefore compliance with the applicable limiting condition for operation was maintained.
APPARENT CAUSE OF OCCURRENGE:
In both cases the reduced service water flow was evidently caused by mollusk shells plugging the tubes of the coolers.
Both living i
organisms and unattached shells were. observed in the backflushes.
Specimens of shells collected were unusually thin, and appeared to have=been subjected to erosion.
1 Although problems with oysters restricting flow to the containment fan-coil units (CFCUs) have been previously noted (see LERs 82-041/03L, 82-046/03L, 82-049/03L, 82-050/03L, 82-058/03L, and 82-117/03L). the i
events were random and.relatively low in frequency.
No problems with I
other safety related components had been observed during previous operation of-the unit.
As-noted in previous reports, oyster spat were apparently-drawn into the Service Water System during operation, and were able to pass e
through the' system strainers.
They cemented themselves to piping i
walls in areas of moderate or reduced flow and developed. shells.
The
- - oysters or shells-were evidently released somewhat randomly during 4
i
. system operational events (pump shif ts, lineup changes, etc.) and periodic chlorinations.
The top shells of dead organisms would also be carried away following decay of the' hinge.
Due to.the previous problems, the No. 21 Service Water Header had been
' drained'and manually cleaned where accessible.
The 8' inch ~ header upstream of all components involved except the. diesels'had been hydrolazed prior to the incident.. Shells had been removed from.the
. header, and reverse flow of the hydrolazing' nozzle would likely have deposited a.small volume of the shells in the 4 inch branch line which supplied the components.
It was not possible to prevent ~a small amount of shells from entering the line, and it was assumed that the l
amount involved would have no significant impact on operating-l-
equipment.
l According to the Environmental Department and biological consultants, i
living oysters removed by hydrolazing would likely survive in an unattached state.
Draining of major portions of the header may have resulted: in mortality of some oysters; increased mortality would also occur in stagnant portions of the system.
Refilling and restoration of the system to operation could then result in the release of some
~
I top shells and carrying of unattached live organisms into portions of the system which were normally trouble-free.
It should be noted that i
'the problems are apparently related to shutdown activities and are not likely to occur during operation at power.
l
.LLER 83-013/03L APPARENT CAUSE'OF 0CCURRENCE: (cont'd)
Settling of ' silt in low 1 flow portions of the service water system has also1been documented, particularly in the case of plugging of CFCU flow' transmitter. sensing lines (see LERs 82-028/01X-1 and 82-038/03L).
The presence of silt in the normally blanked auxiliary feedwater pump
~
supply cross-connect-line is consistent with previously observed problems.
ANALYSIS OF OCCURRENCE:
' Operability of the Service Water System ensures that sufficient cooling. capacity is available for. continued operation of safety related equipment during accident conditions.
A boron injection system is required to be operable during Mode 6 operations to insure reactivity control. capability is maintained.
The Auxiliary Feedwater System ensures that the Reactor' Coolant System can.be. cooled to less than~350 F from normal operating conditions, in the event of a total loss of offsite power.
The cross-connect to the Auxiliary Feedwater System is required to be available in.30 minutes in the event of a complete loss of A.C.
power coincident with tornado missile damage to all redundant-normal auxiliary feedwater supplies (auxiliary feedwater storage tank, demineralized water storage tanks, and fire protection / domestic water storage tanks).
As mentioned, the. occurrences were apparently. the result of shutdown maintenance activities, and would.not have likely occurred during operation in; elevated moder.
Based on the initial results of an evaluation by the system Sponsor. Engineer, - the silt present in the auxiliary'feedwater supply cross-connect would not have interfered.
with the availibility of the supply or the proper function of the Auxiliary Feedwater System.
Action. Statement'3.1.2.3 applies in-Mode 6 and' requires:
With no charging pump operable, suspend all operations involving core alterations or positive reactivity changes until at least one charging pump is restored to' operable status.
As-noted no core alterations or reactivity changes were conducted.. in compliance with the action statement.
Due to this and the general confinement of the problems to shutdown modes. no risk to the health or safety of the ' public was involved.
Because of operation in a degraded mode permitted by a limiting condition for operation, the occurrence is reportable in accordance with Technical Specification 6.9.1.9b.
CORRECTIVE ACTION
~As stated, core alterations and reactivity changes were suspended
.during inoperability of the charging pump.
Remedial action was taken to clean or flush out the shells-from the portions of the Service Water System involved.
At 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br />, April 10, 1983, No. 22 Charging Pump was restored'to operation and was satisfactorily tested.
The pump was declared operable and Action Statement 3.1.2.3 was w.-..- - - - - -, - -, -.
,an-,.-
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%m--.-%,-.,ww.w
..-----.--,*--wc,%,,-e,
-=----,---,,,,=e%,-,mo---w--,---wm 9w e,-
c, 3,-w e t,, v,,
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- - LE'R 83-013/03L CORRECTIVE ACTION: (cont'd) terminated.
The other safety related components involved were also satisfactorily tested and demonstrated to be operable.
Development of a chlorination program to fully eliminate the oysters from the Service Water System and to prevent reinfestation is in progress.
Design Change Request 2EC-1327 has been submitted to provide continuous chlorine monitoring at the Circulating Water System discharge.
The modification will allow increased levels and durations of chlorination.
Due to concern over the overall problem of oysters in the Service Water System, a formal Safety Evaluation will be performed prior to the unit startup.
Initial results of engineering investigation indicate that operation may safely proceed with only minor modification of the existing chlorination program.
A one-time, increased chlorination will be performed to kill soft-bodied organisms, followed by a flush and inspection of the system.
Any plugged components will be cleaned as necessary.
A commitment to submit a Supplemental Report upon resolution of the oyster problem in general was made in LER 82-041/03L.
With respect to the accumulation of silt in the Auxiliary Feedwater System supply cross-connect, a Design Change Request will be issued to relocate the cross-connect isolation valve to eliminate future deposition of silt in the line.
FAILURE DATA:
Not Applicable Prepared By R.
Frahm I
4N! # /
/ ' G6neral Manager -
F Salem Operations SORC Meeting No.83-060 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. 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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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