LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl |
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DUKE POWER Goxiwxy l'.o. nox 33180 ClfAltLOTTE, N.C. 28242 IIAL II. TUCKER TELEPHONE
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April 29, 1983 3
Mr. James P. O'Reilly, Regional Administrator y
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U. S. Nuclear Regulatory Commission c
Region II N
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$h 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 to N :u
,i O "M
Re: McGuire Nuclear Station Unit 1 6
d Docket No. 50-369 p r7 N
Dear Mr. O'Reilly:
Please find attached Reportable Occurrence Report R0-369/83-13. This report concerns T.S. 3.5.1.2, "Each upper head injection accumulator system shall be operable...".
This incident was considered to be of no significance with respect to the health and safety of the public.
Very truly yours, C
& k 4 u a~
Hal B. Tucker PBN:jfw Attachment cc: Document Control Desk U. S. Nuclear Regulatory Commission i
Washington, D. C.
20555 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station 8305110281 830429 OFF fIM' [DRADOCK 05000369 PDR h~ }.*2 J
l 1
DUKE POWER COMPANY McGUIRE NUCLEAR STATION REPORTABLE OCCURRENCE REPORT NO. 369/83-13 REPORT DATE: April 29, 1983 FACILITY: McGuire Unit 1, Cornelius, NC IDENTIFICATION: UHI Level Switches Found Out of Tolerance During Calibration
DESCRIPTION
McGuire Technical Specification 4.5.1.2.c.1 requires "Each Upper Head Injection (UHI) Accumulator System shall be demonstrated OPERABLE at least once per 18 months by verifying that each accumulator isolation valve closes automatically when the water level in the accumulator is 76.6 1 0.5 inches for atmospheric pressure (72.5 1 0.5 inches for blowdown pressure) above the bottom inside edge of the water-filled accumulator...".
Contrary to this requirement, the maintenance history of the four Unit 1 UHI level switches demonstrates that the instrument setpoints have not been maintained within the 1 0.5 inch tolerance.
Unit 1 was in Mode 5 and 6 during the latest switch calibrations of February 23 through April 23, 1983; however, the switches are presumed to have been out of tolerance during power operation.
This incident is attributed to Design Deficiency, since the switches are not capable of the accuracy required.
Additionally, Unit 1 UHI level switches were found out of tolerance during the July 3, 1982 calibratione. This incident was not reported to the NRC due to an inadvertent administra' ive error.
EVALUATION: McGuire has experienced a continuing problem meeting the Technical Specification 4.5.1.2.c.1 level switch setpoint tolerance of 76.6 1 0.5 inches (at atmospheric pressure) for the Barton Model 288A differential pressure indicating switches. A long term accuracy of i 0.5 inches must be attainable to meet this l
tolerance throughout the calibration interval.
Instrument history has demonstrated that this has not been achieved, and that short term accuracy may realistically be placed at i 2.0 inches.
Discussions with Westinghouse personnel and a review of available documents indicates that the problem may have originated in the initial Technical Specification switch tolerance of i 0.25 inches (specification was changed March 3, 1983).
This value corresponded to a switch ' setting tolerance' of 0.2%, not the accuracy of the instrument.
(This ' setting tolerance' is identified in FSAR Volume 10 Table 15.4.1-7 as i 5 ft3, which corresponds to 1 0.25 inches at the specified level setpoint.)
The manufacturer's specifications for this switch (0-120 inch range) are as follows:
INDICATION ACCURACY (At the point of switch actuation): 11.5% of Full Scale (11.8 inches)
SWITCH REPEATABILITY: 1 0.2% of Full Scale (
0.2 inches)
i s
Report No. 369/83-13 Page 2 It is the opinion of Duke Power Company that components of the Indication Accuracy Tolerance, such as drift and temperature effects (not included in Switch Repeat-ability), would nonetheless affect the switch setpoint accuracy, since the same mechanism which drives the indicator also actuates the switch. It therefore appears that the indication accuracy and switch repeatability tolerance should be added to obtain the long term switch accuracy.
Until February 1983, the calibration of the switches was performed using a piece of tubing filled with water to simulate the tank, and the installed reference leg on the opposite side of the differentail pressure unit was used for reference.
This was done at the recommendation of Westinghouse. The July 1982 calibration repeatability problems led to the discovery of gas pockets forming in the reference leg when the instruments were depressurized for calibration; similar problems had been identified at Sequoyah. A new procedure was written for the February 1983 calibrations. This procedure, "UHI Level Switch Calibration", isolates the instru-ment from the tank and reference leg.
The calibration is then performed using the differential pressure that would be seen by the level switch at the setpoint due to the difference in the height of the reference leg and the water level in the tank.
Calibrations performed April 5 through April 23, 1983 were performed by Barton and McGuire technicians using optimum techniques in order to check repeatability.
To improve repeatability, Unit 1 microswitches were replaced in all instruments except level switch 1 NILS 5740. Additionally, the microswitch plunger screw tip was filed flat to provide a larger contact surface on all switbhes of Unit I and 2 during the calibrations.
Level switch 1 NILS 5740 demonstrated the largest errors using the new procedure.
During the April 6 calibration the jewel bearing was found loose in its mount.
This problem was repaired and the instrument repeatability was then checked and verified to be adequate.
Disregarding 1 NILS 5740 due to the mechanical problems, the maximum change during the vendor assisted calibrations was 11.33 inches on 1 NILS 5720. From this data, Duke Power Company believes that a 12 inches repeatability is achievable. This figure does not include long term drift, since long term data has not been gathered using the new calibration technique.
ADDITIONAL INCIDENT: The Unit 1 UHI level switches were found out of tolerance during the July 3, 1982 calibration, but were not reported to the NRC.
The Preven-tative Maintenance / Periodic Test (PM/PT) work requests which documented the out of l
tolerance conditions were incorrectly signed off by Operations personnel.
(Only l
the Licensing section is authorized to sign PM/PT work requests.) The completed l
work requests were then sent to planning. This prevented Licensing personnel from l
obtaining a copy for review by the Licensing Engineer in order to determine report-ability.
CORRECTIVE ACTION
A proposed change to Technical Specification No. 4.5.1.2.c.1 has been submitted to the NRC revising the level switch setpoint to 76.25 1 4.5 inches. Until this amendment is approved, the heat flux hot channel factor, Fq(Z),
Report No. 369/83-13 Page 3 i
for McGuire Units 1 and 2 will be administratively limited to 2.20.
(This is a continuation of the administrative limit for Unit 1 as stated in Reportable Occurrence Report No. R0-369/82-38, and is hereby extended to include Unit 2.)
To ensure that reportable out of tolerance conditions are identified, Operations personnel will be reminded, through review of this report in crew meetings, that only Licensing personnel may sign the final acceptance of PM/PT work requests.
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SAFETY ANALYSIS
Reportable Occurrence Report No. R0-369/82-38 stated that the UHI level switch instrument accuracy was 2.04 inches and that per Westinghouse recommendations, a F (Z) reduction of 0.12 (resulting in a limit of 2.20) was Q
being observed.
Based upon the recent vendor assisted calibrations using the new procedure, this limit is adequate. Additionally, the UHI Water Volume t
Uncertainty Analysis in FSAR Vol. 10, Table-15.4.1-7 provides a margin of i 24 ft3 (i 1.2 inches) for level instrumentation accuracy (includes drift and a
repeatability), even though Technical Specifications require a tolerance of 10.5 inches.
The health and safety of the public were unaffected by this event.
l I
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| 05000369/LER-1983-001-03, /03L-0:on 830105,during Review of 791220 Safety Injection (SI) Pumps & Flow Adjustment Functional Test II, Discrepancy Discovered Between Test Data & Omitted Acceptance Criteria.Caused by Procedure Error | /03L-0:on 830105,during Review of 791220 Safety Injection (SI) Pumps & Flow Adjustment Functional Test II, Discrepancy Discovered Between Test Data & Omitted Acceptance Criteria.Caused by Procedure Error | | | 05000369/LER-1983-002-03, /03L-0:on 830110,while in Mode 1,pressurizer Heater Group 1B Failed to Energize in Manual & Declared Inoperable.Cause Under Investigation.Design Defect Indicated in Vacuum Breaker Contractor Coil Circuit | /03L-0:on 830110,while in Mode 1,pressurizer Heater Group 1B Failed to Energize in Manual & Declared Inoperable.Cause Under Investigation.Design Defect Indicated in Vacuum Breaker Contractor Coil Circuit | | | 05000369/LER-1983-002, Forwards LER 83-002/03L-0 | Forwards LER 83-002/03L-0 | | | 05000369/LER-1983-003-03, /03L-0:on 830117,during Mode 1 Weekly Sampling Collection,Conventional Waste Water Treatment Composite Sampler Found Inoperable.Caused by Frozen Sample Line Due to Improper Installation of Insulation.Insulation Reinstalled | /03L-0:on 830117,during Mode 1 Weekly Sampling Collection,Conventional Waste Water Treatment Composite Sampler Found Inoperable.Caused by Frozen Sample Line Due to Improper Installation of Insulation.Insulation Reinstalled | | | 05000369/LER-1983-003, Forwards LER 83-003/03L-0 | Forwards LER 83-003/03L-0 | | | 05000369/LER-1983-004-03, /03L-0:on 830121,during Monthly Battery Insp,Cell 9 of Battery Evca Had Specific Gravity Below Tech Spec Limit.Caused by Normal Degradation.Bus Evda Tied to Operable Battery Bank.Cell 9 Jumpered Out & Battery Returned to Svc | /03L-0:on 830121,during Monthly Battery Insp,Cell 9 of Battery Evca Had Specific Gravity Below Tech Spec Limit.Caused by Normal Degradation.Bus Evda Tied to Operable Battery Bank.Cell 9 Jumpered Out & Battery Returned to Svc | | | 05000369/LER-1983-004, Forwards LER 83-004/03L-0 | Forwards LER 83-004/03L-0 | | | 05000369/LER-1983-005-03, /03L-0:on 830127,while in Mode 5,evaluation of Initial Ice Condenser Basket Weights Found Numerous Accessible Row 8 & 9 Baskets Had Net Ice Weights Below Tech Specs.Caused by Heat Loading & Air Current | /03L-0:on 830127,while in Mode 5,evaluation of Initial Ice Condenser Basket Weights Found Numerous Accessible Row 8 & 9 Baskets Had Net Ice Weights Below Tech Specs.Caused by Heat Loading & Air Current | | | 05000369/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1983-006-03, /03L-0:on 830131,unit Changed from Mode 5 to 6 W/ Control Room Area Outside Air Pressure Filter Train 2 (VC-B) Inoperable.Subj Train & VC Train a Inoperable on 830125,26 & 29.Caused by Misinterpretation of Tech Specs | /03L-0:on 830131,unit Changed from Mode 5 to 6 W/ Control Room Area Outside Air Pressure Filter Train 2 (VC-B) Inoperable.Subj Train & VC Train a Inoperable on 830125,26 & 29.Caused by Misinterpretation of Tech Specs | | | 05000369/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1983-007-03, /03L-0:on 830131,vent Radiation Monitors 1EMF-35, 36 & 37 Declared Inoperable Following Loss of Sample Flow Alarm.Caused by Clogged Charcoal Filter.Filter Replaced | /03L-0:on 830131,vent Radiation Monitors 1EMF-35, 36 & 37 Declared Inoperable Following Loss of Sample Flow Alarm.Caused by Clogged Charcoal Filter.Filter Replaced | | | 05000369/LER-1983-007, Forwards LER 83-007/03L-0 | Forwards LER 83-007/03L-0 | | | 05000369/LER-1983-008-03, /03L-0:on 830124,weekly Composite Sample Analysis Not Performed for Conventional Waste Water Treatment Sys Continuous Discharge.Caused by Personnel Error & Procedural Deficiency.Procedures Will Be Changed by 830331 | /03L-0:on 830124,weekly Composite Sample Analysis Not Performed for Conventional Waste Water Treatment Sys Continuous Discharge.Caused by Personnel Error & Procedural Deficiency.Procedures Will Be Changed by 830331 | | | 05000369/LER-1983-008, Forwards LER 83-008/03L-0 | Forwards LER 83-008/03L-0 | | | 05000369/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1983-009-03, /03L-0:on 821112,during Troubleshooting & Checkout Activities Following Diesel Generator Mod Work,Diesel Generator 1B Experienced Failures.Caused by Wires on Wrong Terminal,Burned Diodes & Spurious Low Crankcase Signals | /03L-0:on 821112,during Troubleshooting & Checkout Activities Following Diesel Generator Mod Work,Diesel Generator 1B Experienced Failures.Caused by Wires on Wrong Terminal,Burned Diodes & Spurious Low Crankcase Signals | | | 05000369/LER-1983-010, Forwards LER 83-010/03L-0 | Forwards LER 83-010/03L-0 | | | 05000369/LER-1983-010-03, /03L-0:on 830216,while in Mode 6,control Room Outside Air Intake Radiation Monitors 1EMF-43A &43B Declared Inoperable.Caused by Personnel Error.Monitors Returned to Svc & Inlet Valves Opened After Testing | /03L-0:on 830216,while in Mode 6,control Room Outside Air Intake Radiation Monitors 1EMF-43A &43B Declared Inoperable.Caused by Personnel Error.Monitors Returned to Svc & Inlet Valves Opened After Testing | | | 05000369/LER-1983-011-01, While Core Unloaded During Fuel Assembly insp,21 of 94 Nonfuel Bearing Components Equipped W/Same Spring Design Discovered W/Broken Holddown Springs.Caused by Design Deficiency | While Core Unloaded During Fuel Assembly insp,21 of 94 Nonfuel Bearing Components Equipped W/Same Spring Design Discovered W/Broken Holddown Springs.Caused by Design Deficiency | | | 05000369/LER-1983-011, Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | | | 05000369/LER-1983-012-03, /03L-0:on 830302,four Existing Auxiliary Feedwater Flow Transmitters Determined Not Environmentally Qualified for 330 F Main Steam Break Environ.Transmitter Overlooked in Review Response to NUREG-0588 | /03L-0:on 830302,four Existing Auxiliary Feedwater Flow Transmitters Determined Not Environmentally Qualified for 330 F Main Steam Break Environ.Transmitter Overlooked in Review Response to NUREG-0588 | | | 05000369/LER-1983-012, Forwards LER 83-012/03L-0 | Forwards LER 83-012/03L-0 | | | 05000369/LER-1983-013-03, /03L-0:on 830315,during Upperhead Injection Level Switch Calibr,Switches Found Out of Tolerance.Caused by Design Deficiency.Rev to Tech Specs Changing Switch Setpoint Submitted | /03L-0:on 830315,during Upperhead Injection Level Switch Calibr,Switches Found Out of Tolerance.Caused by Design Deficiency.Rev to Tech Specs Changing Switch Setpoint Submitted | | | 05000369/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1983-014-03, /03L-0:on 830303,routine Surveillance on Conventional Waste Water Sys Radiation Monitor 1EMF-31 Found Channel Out of Tolerance.Caused by Cracked Detector Crystal. Crystal Replaced W/High Temp Crystal | /03L-0:on 830303,routine Surveillance on Conventional Waste Water Sys Radiation Monitor 1EMF-31 Found Channel Out of Tolerance.Caused by Cracked Detector Crystal. Crystal Replaced W/High Temp Crystal | | | 05000369/LER-1983-014, Forwards LER 83-014/03L-0 | Forwards LER 83-014/03L-0 | | | 05000369/LER-1983-015, Forwards LER 83-015/03L-0 & 83-003/03L-0 | Forwards LER 83-015/03L-0 & 83-003/03L-0 | | | 05000369/LER-1983-015-03, /03L-0:on 830319 & 31,reactor Trip Breaker a Failed to Open on Undervoltage (UV) Trip Signal & Bypass Breaker B Failed to Trip on UV Signal,Respectively.Caused by Mechanical Problems W/Uv Mechanisms.Logic Modified | /03L-0:on 830319 & 31,reactor Trip Breaker a Failed to Open on Undervoltage (UV) Trip Signal & Bypass Breaker B Failed to Trip on UV Signal,Respectively.Caused by Mechanical Problems W/Uv Mechanisms.Logic Modified | | | 05000369/LER-1983-016-03, /03L-0:on 830327,hanger 1MCA-ND-H260 Discovered Pulled Loose from Wall Anchors & Snubbers 1MCA-ND-H177 & H317 Found Locked Up During Subsequent full-stroking.Caused by Water Hammer Event Resulting in Void Formation | /03L-0:on 830327,hanger 1MCA-ND-H260 Discovered Pulled Loose from Wall Anchors & Snubbers 1MCA-ND-H177 & H317 Found Locked Up During Subsequent full-stroking.Caused by Water Hammer Event Resulting in Void Formation | | | 05000369/LER-1983-016, Forwards LER 83-016/03L-0 | Forwards LER 83-016/03L-0 | | | 05000369/LER-1983-017-03, /03L-0:on 830405,during Draining of Refueling Cavity RHR (Nd) Pumps Began to Cavitate & Eventually Both Nd Pumps Stopped.Caused by Level Gauge Isolation.Cavity Refilled.Nd Sys Vented.Procedures Revised | /03L-0:on 830405,during Draining of Refueling Cavity RHR (Nd) Pumps Began to Cavitate & Eventually Both Nd Pumps Stopped.Caused by Level Gauge Isolation.Cavity Refilled.Nd Sys Vented.Procedures Revised | | | 05000369/LER-1983-017, Forwards LER 83-017/03L-0 | Forwards LER 83-017/03L-0 | | | 05000369/LER-1983-018-03, /03L-0:on 830407,following Identification of Inoperable RHR Sys (Nd) Hanger & Snubbers,Sys Walkdown Revealed Addl Hanger Failure.Caused by Nd Sys Water Hammer. Hangers Repaired & Procedures Revised | /03L-0:on 830407,following Identification of Inoperable RHR Sys (Nd) Hanger & Snubbers,Sys Walkdown Revealed Addl Hanger Failure.Caused by Nd Sys Water Hammer. Hangers Repaired & Procedures Revised | | | 05000369/LER-1983-019-03, /03L-0:on 830413,representative Fuel Pool Ventilation Sys Carbon Filter Sample Analysis Indicated Sample Failed to Meet Methyl Iodide Penetration Criteria. Sample Analyses Made to Determine Cause | /03L-0:on 830413,representative Fuel Pool Ventilation Sys Carbon Filter Sample Analysis Indicated Sample Failed to Meet Methyl Iodide Penetration Criteria. Sample Analyses Made to Determine Cause | | | 05000369/LER-1983-020-01, /01T-0:on 830503,soap Bubble Test of 47 Secondary Containment Bypass Leakage Paths Not Performed During Initial Integrated Leak Rate Test.Caused by Procedural Deficiency.Procedures Revised | /01T-0:on 830503,soap Bubble Test of 47 Secondary Containment Bypass Leakage Paths Not Performed During Initial Integrated Leak Rate Test.Caused by Procedural Deficiency.Procedures Revised | | | 05000369/LER-1983-021-03, /03L-0:on 830419,while in Mode 5,nuclear Svc Water Sys Valve 1RN-69 Actuator W/Mechanical Latch Replaced by Actuator Requiring Electrical Antihammer Circuit.Caused by Deficient Procedure | /03L-0:on 830419,while in Mode 5,nuclear Svc Water Sys Valve 1RN-69 Actuator W/Mechanical Latch Replaced by Actuator Requiring Electrical Antihammer Circuit.Caused by Deficient Procedure | | | 05000369/LER-1983-022-03, /03L-0:on 830421,bellows Leak Test Not Performed on Penetration M354 After Initial Integrated Leak Rate Test.Caused by Procedural Deficiency Since Penetration Not Listed in Initial Procedures | /03L-0:on 830421,bellows Leak Test Not Performed on Penetration M354 After Initial Integrated Leak Rate Test.Caused by Procedural Deficiency Since Penetration Not Listed in Initial Procedures | | | 05000369/LER-1983-023-01, /01T-0:on 830506,discovered That RHR Sys (Nd) Train a Improperly Declared Operable on 830423 & Subsequent Change from Mode 5 to Mode 4 Occurred on 830428.Caused by Water Hammer Failures | /01T-0:on 830506,discovered That RHR Sys (Nd) Train a Improperly Declared Operable on 830423 & Subsequent Change from Mode 5 to Mode 4 Occurred on 830428.Caused by Water Hammer Failures | | | 05000369/LER-1983-024-03, /03L-0:on 830426,Fire Door 1000B Declared Inoperable When Damage,Consisting of Bent Door,Broken Hinge, Bent Hinge,Broken Door Lock & Broken Door Closer Discovered. Cause Unknown.Fire Watch Established | /03L-0:on 830426,Fire Door 1000B Declared Inoperable When Damage,Consisting of Bent Door,Broken Hinge, Bent Hinge,Broken Door Lock & Broken Door Closer Discovered. Cause Unknown.Fire Watch Established | | | 05000369/LER-1983-025-03, /03L-0:on 830508,while in Mode 2,fire Detection Sys Zones 72 & 149 Declared Inoperable Due to Alarms Remaining in Alarm Condition.Fire Watch Patrols Established. Caused by Control Interface Module failure.W830527 Ltr | /03L-0:on 830508,while in Mode 2,fire Detection Sys Zones 72 & 149 Declared Inoperable Due to Alarms Remaining in Alarm Condition.Fire Watch Patrols Established. Caused by Control Interface Module failure.W830527 Ltr | | | 05000369/LER-1983-026-03, /03L-0:on 830430,performance of RCS Leakage Calculation Determined Unidentified Leakage Greater than 1 Gpm.Caused by Leakage Past Bonnet Seal Ring on Valves 1NC-18 & 1NV-239.Valves Sealed | /03L-0:on 830430,performance of RCS Leakage Calculation Determined Unidentified Leakage Greater than 1 Gpm.Caused by Leakage Past Bonnet Seal Ring on Valves 1NC-18 & 1NV-239.Valves Sealed | | | 05000369/LER-1983-027-03, /03L-0:on 830505,discovery of Water in Outside Air Pressure Filter Train 2 Led to Control Area Ventilation Sys Train B Inoperability.Caused by Water Backflow Through Drain Lines Into Filter Package.Filter Cleaned | /03L-0:on 830505,discovery of Water in Outside Air Pressure Filter Train 2 Led to Control Area Ventilation Sys Train B Inoperability.Caused by Water Backflow Through Drain Lines Into Filter Package.Filter Cleaned | | | 05000369/LER-1983-028-01, /01T-0:on 830525,impulse Lines for Two Redundant Steam Generator 1D Level Instruments Came within 2 Inches of Each Other at One Point.Caused by Const/Installation Deficiency.One Line Rerouted | /01T-0:on 830525,impulse Lines for Two Redundant Steam Generator 1D Level Instruments Came within 2 Inches of Each Other at One Point.Caused by Const/Installation Deficiency.One Line Rerouted | | | 05000369/LER-1983-029-03, /03L-0:on 830510 & 15,boron Concentration Dropped Below 1,900 Ppm in Cold Leg Injection Accumulator.Caused by Leakage Into Accumulator from RCS Through Check Valves 1NI70 & 1NI71.Valves Repaired | /03L-0:on 830510 & 15,boron Concentration Dropped Below 1,900 Ppm in Cold Leg Injection Accumulator.Caused by Leakage Into Accumulator from RCS Through Check Valves 1NI70 & 1NI71.Valves Repaired | | | 05000369/LER-1983-029-01, /01T-0:on 830601,Westinghouse Notified Util That Extended Operation at Low Power & Subsequent Escalation to Power in Same Fuel Cycle Would Result in Heat Flux Hot Channel Factor Limit Violations for LOCA Analysis | /01T-0:on 830601,Westinghouse Notified Util That Extended Operation at Low Power & Subsequent Escalation to Power in Same Fuel Cycle Would Result in Heat Flux Hot Channel Factor Limit Violations for LOCA Analysis | | | 05000369/LER-1983-030-01, /01T-0:on 830526,discovered Monthly Test of Containment Pressure Control Sys Failed to Satisfy Surveillance Requirements to Check Permissive/Termination Setpoint Accuracy.Alarm Modules Recalibr | /01T-0:on 830526,discovered Monthly Test of Containment Pressure Control Sys Failed to Satisfy Surveillance Requirements to Check Permissive/Termination Setpoint Accuracy.Alarm Modules Recalibr | | | 05000369/LER-1983-031-03, /03L-0:on 830512,reactor Coolant Pump Taken Out of Svc Following Sporadic Low Oil Level Alarms from Pump Motor 1D Upper Reservoir.Level Found Slightly Low.Cause Not Determined.Oil Added.Pump Restarted | /03L-0:on 830512,reactor Coolant Pump Taken Out of Svc Following Sporadic Low Oil Level Alarms from Pump Motor 1D Upper Reservoir.Level Found Slightly Low.Cause Not Determined.Oil Added.Pump Restarted | | | 05000369/LER-1983-032-03, /03L-0:on 830513,control Area Ventilation Sys Train a Failed to Meet Pressurization Criteria.Caused by Degradation of Door Seals & Lack of Trip Interlocks.Door Seals Taped & Later Replaced.Test Rerun | /03L-0:on 830513,control Area Ventilation Sys Train a Failed to Meet Pressurization Criteria.Caused by Degradation of Door Seals & Lack of Trip Interlocks.Door Seals Taped & Later Replaced.Test Rerun | | | 05000369/LER-1983-033-03, /03L-0:on 830701,two Programmed Setpoint Circuit Cards of Each Steam Generator Water Level low-low Channel Not Tested During Required Monthly Surveillance.Cause Not Known.Monthly Surveillance Procedure Revised | /03L-0:on 830701,two Programmed Setpoint Circuit Cards of Each Steam Generator Water Level low-low Channel Not Tested During Required Monthly Surveillance.Cause Not Known.Monthly Surveillance Procedure Revised | |
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