Similar Documents at Cook |
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LER-1982-022, Requests LER 82-022/01T-0 Be Rescinded |
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| 3161982022R00 - NRC Website |
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tres INDIANA & MICHIGAN ELECTRIC COMPANY vst,,,
DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman. Michigan 49106 (616) 465-5901 April 4, 1983 Mr. J. G. Keppler, Regional Administrator United States Nuclear Regulatory Commission Region III, 799 Roosevelt Road Glen Ellyn, Illinois 60137 Operating License DPR-74 Docket No. 50-316
Dear Mr. Keppler:
The purpose of this letter is to request that Licensee Event Report 316/82-022/01T-0 be rescinded. This request is based upon a conversa-tion between Mr. D. Wigginton of the Nuclear Regulatory Commission and myself regarding definition of the term " effective date" assigned to Technical Specification amendments.
The Licensee Event Report in question identifies a situation where the implementation of several amended Technical Specification paragraphs appeared to have been compromised due to the method of issuance of the amendments. On March 27,1982, Unit 2 Technical Specification Amend-ment No. 39 was received at the Plant with an effective date of March 11, 1982. At the time of receipt, the Plant staff believed that the effective date specified by the Nuclear Regulatory Comission was synonymous with the required / expected implementation date. Therefore, the Plant was in ap-parent, unavoidable violation of the Tech. Spec., as amended, upon receipt.
The referenced discussion with the Nuclear Regulatory Commission resulted in the understanding that the " effective date" of Technical Specification amendments represents the date that the amendment (s) may be placed into effect, but that actual implementation may allow a reasonable period of time following receipt of the amendment to provide for proper review, training and implementation. Further, it is understood that the NRC Resident Inspector should be kept apprised of planned implementation dates, if other than "immediate," in order to eliminate any confusion in regards to our intent versus the NRC's expectations. The Plant wishes to express appreciation for the NRC's efforts in clarifying this issue.
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m J. G. Keppler April 4,1983 Page Two
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A copy of the aforementioned Licensee Event Report is attached which fully describes the Plant conditions during the time period under discussion.
l Sincerely, LO 3
W. G. Smith, Jr.
Plant Manager WGS:frb cc:
J. E. Dolan R. S. Hunter M. P. Alexich R. F. Kroeger B. Germano E. R. Swanson/N. E. DuBry, R0:III R. C.- Callen, MPSC G. Charnoff, Esq.
J. M. Hennigan R. O. Bruggee, EPRI INP0 PNSRC J. F. Stietzel E. L. Townley D. Wigginton Dir., IE (40 copies)
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60 al DoCKe7 NUMS&R 68 b3 event DATe 74 74 REPORT oATi 60 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 1o : 211 AMENDMENT 39 TO TECH. SPEC. WAS RECEIVED ON MARCH 27, 1982. WITH A RETROACTIVE I
gi EFFECTIVE DATE OF 11 ARCH 11,1982. AS A RESULT THE FOLLOWING NONCONFORMANCES TO I
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SUPPLEMENT TO LER 82-022/0 1T-0 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10) h AMENDMENT 39 0F TECH. SPECS. WAS ISSUED ON MARCH 11, 1982. THIS AMENDMENT 1.'s WAS RECEIVED AT THE PLANT MARCH 27, 1982, AT WHICH TIME UNIT 2 HAD BEEN IN THE MODE 5 COLD SHUTDOWN CONDITION FOR ABOUT 16 DAYS AND 20 HOURS.
THE OPERATING PROCEDURES AND SURVEILLANCES IN USE FOR OPERATING IN MODE 5 DID NOT REFLECT THE CHANGES OF AMENDMENT 39 AS WE WERE UNAWARE IT HAD BEEN APPROVED AND ISSUED WITH AN EFFECTIVE DATE OF MARCH 11, 1982 UNTIL IT WAS RECEIVED ON SITE. ADDITIONALLY, AMENDMENT 39 CONTAINED MODIFICATIONS TO THE ORIGINAL SUBMITTAL REQUEST FOR TECHNICAL SPECIFICATION CHANGE ON WHICH WE HAD NOT RECEIVED PRIOR NOTIFICATION AND WERE NOT PREPARED TO IMPLEMENT INSTANTANEOUSLY. AS A RESULT OF THIS SITUATION THE FOLLOWING NONCONFORMANCES TO THE LATEST AMENDED TECHNICAL SPECIFICATIONS;. _..
OCCURRED DURING THE PERIOD'0F MARCH ~12,' 1982'TO MARCH 27, 1982:
3.1.2.3.b.
4.1.2.3.2, 3.5.3 - ACTION C, 4.4.1.1.2a & b, 4.4.9.3.la, c & e, AND 4.5.3.2.~ ~
AMENDMENT 39 TO THE TECHNICAL. SPECIFICATIONS WAS RECEIVED AT THE PLANT ~
ON SATURDAY, MARCH 27, 1982 AT ABOUT 1030 HOURS. ATpiATTIMETHEUNIT WAS IN MODE 5 AT A TEMPERATURE SLIGHTLY LESS THAN-152 F.
A FILL AND VENT OF THE REACTOR COOLANT SYSTEM WAS IN PROGRESS WITH A SUBSEQUENT HEAT-UP PLANNED. UPON RECEIPT OF AMENDMENT 39 AN EFFORT WAS MADE TO LOG THE APPLICABLE SURVEILLANCE REQUIREMENTS AND COMPLY WITH THE TECHNICAL SPECIFICATIONS. DUE TO THE COMPLEXITY OF THE AMENDMENT WE WERE yNSUCCESSFUL
. IN INSURING ALL ITEMS OF THE SPECIFICATION WERE COMPLIED WITH. EXCEPT AS NOTED BELOW THE REACTOR COOLANT SYSTEM WAS RAISED ABOVE 152 F REMOVING MOST OF THE REQUIREMENTS OF THIS AMENDMENT BY 1600 HOURS ON MARCH 27.
}-
FROM THAT PERIOD UNTIL WE ENTERED MODE 4 AT 2313 HOURS ON MARCH 28,.THE i
SURVEILLANCE.REQUIREMENTTOMgNITORREACTORCOOLANTSYSTEMTEMPERATURE T0. CONFIRM IT TO BE AB0VE 152 F WAS NOT ACCOMPLISHED AT THE FREQUENCY SPECIFIED.
DUE TO THE RCS TEMPERATURE BRIEFLY DIPPING BELOW 152 F DURING FILL AND
' VENT OPERATIONS ON MARCH 27, THE CHANNEL FUNCTIONAL TEST OF THE PORV ACTUATION CHANNELS FOR TECHNICALESPECIFICATION 4.4.9.3.14 WAS PERFORMED ON MARCH 28, 1982 AS WAS THE SURVEILLANCE REQUIREMENT OF 4.4.9.3.le2 TO DETERMINE THE PORY AIR TANK PRESSURE INSTRUMENTATION OPERABLE. THE ALARM SETPOINT FOR ONE OF THE AIR TANKS WAS FOUND TO BE 897 PSIG INSTEAD OF 900 PSI AND WAS ADJUSTED T0 THE CORRECT VALUE.
i A DETAILED STUDY OF THE TECHNICAL SPECIFICATIONS WAS STARTED ON MONDAY, MARCH 29, TO DETERMINE THE NECESSARY-PROCEDURAL CHANGES AND TO IDENTIFY NONCONFORMANCES WHICH HAD RESULTED. THIS REVIEW, ON APRIL 6, 1982, IDENTIFIED THE l
NONCONFORMANCES TO BE REPORTABLE.
AN "0PERATIONS STANDING ORDER" HAS BEEN ISSUED FOR BOTH UNITS WHICH PREVENT EITHER UNIT FROM BEING OPERATED ~
IN CONDITIONS WHERE THE SPECIFICATIONS ARE APPLICABLE UNTIL PROCEDURES i
CAN BE REVISED TO REFLECT THE REQUIREMENTS OF THIS TECHNICAL SPECIFICATION AMENDMENT.
1 i
.THE EVENT DID NOT ENDANGER THE PUBLIC HEALTH AND SAFETY AS THERE WERE NO EVENTS THAT REQUIRED MITIGATION OF OVER-PRESSURIZATION EVENTS AT LOW
- 3 TEMPERATURE DURING THIS PERIOD.
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| 05000316/LER-1982-001-04, /04T-0:on 820110,during Deicing,Circulating Water Sys Discharge Temp Exceeded Tech Specs.Caused by Inability to Open Discharge Gates WMO-25A & WMO-25B Electrically.Valve Positions Changed Manually | /04T-0:on 820110,during Deicing,Circulating Water Sys Discharge Temp Exceeded Tech Specs.Caused by Inability to Open Discharge Gates WMO-25A & WMO-25B Electrically.Valve Positions Changed Manually | | | 05000316/LER-1982-001, Forwards LER 82-001/04T-0 | Forwards LER 82-001/04T-0 | | | 05000315/LER-1982-001-99, /99T-0:on 820107,two Addl Fire Doors Identified Having Potential Problems as Followup to Dv Shaller Re Problem W/Ul Ratings of 16 Fire Doors.Design Change Initiated on 780329.Awaiting Addl Info from Contractor | /99T-0:on 820107,two Addl Fire Doors Identified Having Potential Problems as Followup to Dv Shaller Re Problem W/Ul Ratings of 16 Fire Doors.Design Change Initiated on 780329.Awaiting Addl Info from Contractor | | | 05000315/LER-1982-002, Forwards LER 82-002/99T-1 | Forwards LER 82-002/99T-1 | | | 05000315/LER-1982-002-99, /99T-1:on 820107,review of Documentation Associated W/Reactor Vessel Water Level Indication Sys Revealed That Physical Work Had Exceeded Limitations Stated in Approved Design Change Authorization | /99T-1:on 820107,review of Documentation Associated W/Reactor Vessel Water Level Indication Sys Revealed That Physical Work Had Exceeded Limitations Stated in Approved Design Change Authorization | | | 05000316/LER-1982-002, Forwards Updated LER 82-002/01X-1 | Forwards Updated LER 82-002/01X-1 | | | 05000316/LER-1982-002-01, Essential Svc Water Valves WMO-734 & 738 Were Not Tested as Required by Tech Specs.Caused by Valves WMO-734 & 738 Being Inadvertently Omitted During Oct 1979 Procedure Revision | Essential Svc Water Valves WMO-734 & 738 Were Not Tested as Required by Tech Specs.Caused by Valves WMO-734 & 738 Being Inadvertently Omitted During Oct 1979 Procedure Revision | | | 05000315/LER-1982-003-04, /04X-1:on 820115,unplanned Gas Release Detected by Elevated Vent Stack Gaseous Monitor Reading.Cause Undetermined.Procedure for Helium Gas Test Changed to Allow One Portion of Waste Gas to Be Tested | /04X-1:on 820115,unplanned Gas Release Detected by Elevated Vent Stack Gaseous Monitor Reading.Cause Undetermined.Procedure for Helium Gas Test Changed to Allow One Portion of Waste Gas to Be Tested | | | 05000315/LER-1982-003, Corrected LER 82-003/04T-1:on 820115,unplanned Gas Release Detected by Elevated Vent Stack Monitor Reading.Exact Cause Undetermined.Helium Leak Testing of Waste Gas Sys Probable Cause.Test Procedure Changed | Corrected LER 82-003/04T-1:on 820115,unplanned Gas Release Detected by Elevated Vent Stack Monitor Reading.Exact Cause Undetermined.Helium Leak Testing of Waste Gas Sys Probable Cause.Test Procedure Changed | | | 05000316/LER-1982-003-01, /01X-1:on 820119,leak Discovered in Attachment Weld on Upstream Side of Suction Strainer for West Containment Spray Pump.Caused by Residual & High Cycle Alternating Stress.Design Change Initiated | /01X-1:on 820119,leak Discovered in Attachment Weld on Upstream Side of Suction Strainer for West Containment Spray Pump.Caused by Residual & High Cycle Alternating Stress.Design Change Initiated | | | 05000316/LER-1982-003, Forwards LER 82-003/01T-0 | Forwards LER 82-003/01T-0 | | | 05000315/LER-1982-004-03, /03L-0:on 820105,while Performing Surveillance Test,One Tape Was Found Inoperable.Caused by Failure to Advance Tape on 811204.Control & Instrumentation Personnel Have Received Addl Training | /03L-0:on 820105,while Performing Surveillance Test,One Tape Was Found Inoperable.Caused by Failure to Advance Tape on 811204.Control & Instrumentation Personnel Have Received Addl Training | | | 05000315/LER-1982-004, Forwards LER 82-004/03L-0 | Forwards LER 82-004/03L-0 | | | 05000316/LER-1982-004-03, /03L-0:on 820116,RCS Dose Equivalent I-131 Concentration Exceeded 1.0 Uci/G steady-state Limit & Unit Experienced 100% Trip | /03L-0:on 820116,RCS Dose Equivalent I-131 Concentration Exceeded 1.0 Uci/G steady-state Limit & Unit Experienced 100% Trip | | | 05000316/LER-1982-005-03, /03L-0:on 820117,steam Generator Steam 3 Flow Channel 1 (MFC-131)found to Be Indicating Low.Caused by Sensing Lines Losing Fill.Sensing Lines Refilled | /03L-0:on 820117,steam Generator Steam 3 Flow Channel 1 (MFC-131)found to Be Indicating Low.Caused by Sensing Lines Losing Fill.Sensing Lines Refilled | | | 05000315/LER-1982-005-03, /03L-0:on 820115,during Surveillance Testing, Leakage Rate on Inner Door of Personnel Air Lock at 650 Ft Elevation Exceeded Tech Specs Limit.Caused by Broken Threaded Nipple Where Air Supply Line Enters Door Seal Area | /03L-0:on 820115,during Surveillance Testing, Leakage Rate on Inner Door of Personnel Air Lock at 650 Ft Elevation Exceeded Tech Specs Limit.Caused by Broken Threaded Nipple Where Air Supply Line Enters Door Seal Area | | | 05000316/LER-1982-006-03, /03L-0:on 820116,containment Air Particulate & Gaseous Radiation Monitoring Sys R-11/R-12 Sample Pump Tripped on Low Flow.Caused by Paper Jam.Filter Paper Replaced | /03L-0:on 820116,containment Air Particulate & Gaseous Radiation Monitoring Sys R-11/R-12 Sample Pump Tripped on Low Flow.Caused by Paper Jam.Filter Paper Replaced | | | 05000315/LER-1982-006-03, /03L-0:on 820123,during Surveillance Testing, Valve 1-WMO-737,emergency Svc Water Discharge from W Component Cooling Water Heat Exchanger Would Not Close. Cause Could Not Be Determined.Valve Cycled Manually | /03L-0:on 820123,during Surveillance Testing, Valve 1-WMO-737,emergency Svc Water Discharge from W Component Cooling Water Heat Exchanger Would Not Close. Cause Could Not Be Determined.Valve Cycled Manually | | | 05000315/LER-1982-007-03, /03L-0:on 820126,containment Air Particulate & Gaseous Radiation Monitoring Sys R-11/R-12 Sample Pump Tripped on Low Flow.Caused by Filter Paper Winding Up Incorrectly on Takeup Reel.Filter Paper Replaced | /03L-0:on 820126,containment Air Particulate & Gaseous Radiation Monitoring Sys R-11/R-12 Sample Pump Tripped on Low Flow.Caused by Filter Paper Winding Up Incorrectly on Takeup Reel.Filter Paper Replaced | | | 05000316/LER-1982-007-03, /03L-0:on 820122,during Surveillance Test,Valve 2-CMO-429,component Cooling Water Discharge from W RHR HX, Failed to Close.Caused by Binding of Valve Shaft in Stuffing Box Bore Below Packing Due to Buildup of Corrosion | /03L-0:on 820122,during Surveillance Test,Valve 2-CMO-429,component Cooling Water Discharge from W RHR HX, Failed to Close.Caused by Binding of Valve Shaft in Stuffing Box Bore Below Packing Due to Buildup of Corrosion | | | 05000315/LER-1982-007, Forwards LER 82-007/03L-0 | Forwards LER 82-007/03L-0 | | | 05000315/LER-1982-008, Forwards Updated LER 82-008/03X-1 | Forwards Updated LER 82-008/03X-1 | | | 05000315/LER-1982-008-03, Containment Sump Flow Monitoring Recorder 1-CS-001 Found Out of Paper.New Roll Put in Recorder.Procedure Revised to Change Chart Paper When Less than 3-ft Remain | Containment Sump Flow Monitoring Recorder 1-CS-001 Found Out of Paper.New Roll Put in Recorder.Procedure Revised to Change Chart Paper When Less than 3-ft Remain | | | 05000316/LER-1982-008, Forwards LER 82-008/03L-0 | Forwards LER 82-008/03L-0 | | | 05000316/LER-1982-008-03, /03L-0:on 820118,at 100% Power,Scan Errors on Axial Power Distribution Monitoring Sys Prompted Operators to Use Flux Mapping Sys & Plant Computer P-250 to Monitor Axial Power Distribution.Caused by Procedure Error | /03L-0:on 820118,at 100% Power,Scan Errors on Axial Power Distribution Monitoring Sys Prompted Operators to Use Flux Mapping Sys & Plant Computer P-250 to Monitor Axial Power Distribution.Caused by Procedure Error | | | 05000316/LER-1982-009-03, /03L-0:on 820122,during Normal Operation,Mounting Bracket for Turbine Stop Valve D,Train a Proximity Switch Discovered Broken.Caused by Excessive Vibration.Bracket Repaired & Switch Remounted | /03L-0:on 820122,during Normal Operation,Mounting Bracket for Turbine Stop Valve D,Train a Proximity Switch Discovered Broken.Caused by Excessive Vibration.Bracket Repaired & Switch Remounted | | | 05000315/LER-1982-009-03, /03L-0:on 820128,leak Discovered in Essential Svc Water Pipe Downstream of Outlet Valve from East Heat Exchanger.Caused by Cavitation Due to Throttling of Butterfly Valve.Mod Initiated | /03L-0:on 820128,leak Discovered in Essential Svc Water Pipe Downstream of Outlet Valve from East Heat Exchanger.Caused by Cavitation Due to Throttling of Butterfly Valve.Mod Initiated | | | 05000315/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000315/LER-1982-010, Forwards LER 82-010/04T-0 | Forwards LER 82-010/04T-0 | | | 05000315/LER-1982-010-04, /04T-1:on 820311 & 12,unplanned Gas Release of Approx 94.7 Ci Occurred W/O Sampling & Analysis Per Tech Specs.Caused by Lifting of Safety Valve 2-SV-38 at 63 Psi Below Correct Level of 140 Psi.Valve Replaced | /04T-1:on 820311 & 12,unplanned Gas Release of Approx 94.7 Ci Occurred W/O Sampling & Analysis Per Tech Specs.Caused by Lifting of Safety Valve 2-SV-38 at 63 Psi Below Correct Level of 140 Psi.Valve Replaced | | | 05000316/LER-1982-010-03, /03L-0:on 820122,during Surveillance Test,Valve 2-CO-420,W Component Cooling Water HX Discharge Would Not Close Remotely.Caused by Binding of Valve Shaft in Stuffing Box Bore Below Packing & in Area of Upper Shaft Bushing | /03L-0:on 820122,during Surveillance Test,Valve 2-CO-420,W Component Cooling Water HX Discharge Would Not Close Remotely.Caused by Binding of Valve Shaft in Stuffing Box Bore Below Packing & in Area of Upper Shaft Bushing | | | 05000315/LER-1982-011-03, /03L-0:on 820223,during Surveillance Per Tech Spec 4.8.2.5.2B,three Cells of N Train Battery Found to Have Electrolyte Gravity Less than 1.200 Min Limit.Caused by Low Readings & Loss of Acid.Acid Added & Battery Tested | /03L-0:on 820223,during Surveillance Per Tech Spec 4.8.2.5.2B,three Cells of N Train Battery Found to Have Electrolyte Gravity Less than 1.200 Min Limit.Caused by Low Readings & Loss of Acid.Acid Added & Battery Tested | | | 05000316/LER-1982-011-03, /03L-0:on 820128,leak Discovered in Essential Svc Water Pipe Downstream of Outlet Valve from East Component Cooling Water Heat Exchanger.Caused by Cavitation Due to Throttling of Butterfly Valve.Mod Initiated | /03L-0:on 820128,leak Discovered in Essential Svc Water Pipe Downstream of Outlet Valve from East Component Cooling Water Heat Exchanger.Caused by Cavitation Due to Throttling of Butterfly Valve.Mod Initiated | | | 05000316/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000315/LER-1982-012-03, /03L-0:on 820303,turbine Driven Auxiliary Feedwater Pump Trip/Throttle Valve Tripped Shut When Manually Started.No Problems Found.Surveillance Test Completed.Pump Returned to Svc.No Further Action Planned | /03L-0:on 820303,turbine Driven Auxiliary Feedwater Pump Trip/Throttle Valve Tripped Shut When Manually Started.No Problems Found.Surveillance Test Completed.Pump Returned to Svc.No Further Action Planned | | | 05000316/LER-1982-012-03, /03L-0:on 820224,boron Injection Tank Inlet Valve Breaker Found in Off Position.Probably Caused by Accidental Bump by Personnel Using Area as Shortcut.Area Will Be Blocked Off to Prevent Passage | /03L-0:on 820224,boron Injection Tank Inlet Valve Breaker Found in Off Position.Probably Caused by Accidental Bump by Personnel Using Area as Shortcut.Area Will Be Blocked Off to Prevent Passage | | | 05000316/LER-1982-012, Forwards LER 82-012/03L-0 | Forwards LER 82-012/03L-0 | | | 05000316/LER-1982-013, Forwards LER 82-013/03L-0 | Forwards LER 82-013/03L-0 | | | 05000316/LER-1982-013-03, /03L-0:on 820222,following Reactor Trip,Rcs Dose Equivalent I-131 Concentration Exceeded Tech Spec Limit. Caused by I-131 Concentration Spiking to Max of 2.33 Uci/G. Unit Returned to Operation & Iodine Values Leveled | /03L-0:on 820222,following Reactor Trip,Rcs Dose Equivalent I-131 Concentration Exceeded Tech Spec Limit. Caused by I-131 Concentration Spiking to Max of 2.33 Uci/G. Unit Returned to Operation & Iodine Values Leveled | | | 05000315/LER-1982-013-03, /03L-0:on 820302,control Switch for Containment Pressure Equalization Fan in Stop & Backdraft Damper for Opposite Fan Was Open.Cause Could Not Be Determined.Startup Procedures Revised | /03L-0:on 820302,control Switch for Containment Pressure Equalization Fan in Stop & Backdraft Damper for Opposite Fan Was Open.Cause Could Not Be Determined.Startup Procedures Revised | | | 05000316/LER-1982-014-03, /03L-0:on 820217,radiation Monitors R-11 & R-12 Sample Pump Would Not Develop Sufficient Flow During Normal Operation.Cause Not Stated.Entire Radiation Monitor Sys Scheduled for Replacement by 30 Days After 1982 Refueling | /03L-0:on 820217,radiation Monitors R-11 & R-12 Sample Pump Would Not Develop Sufficient Flow During Normal Operation.Cause Not Stated.Entire Radiation Monitor Sys Scheduled for Replacement by 30 Days After 1982 Refueling | | | 05000316/LER-1982-014, Forwards LER 82-014/03L-0 | Forwards LER 82-014/03L-0 | | | 05000315/LER-1982-014-03, /03L-0:on 820305,during Reactor Trip Coincident W/Low Tavg,Feedwater Isolation Valve FMO-203 Failed to Close.Caused by Buildup of Corrosion Products within Limitorque Actuator Connection Box.Contacts Cleaned | /03L-0:on 820305,during Reactor Trip Coincident W/Low Tavg,Feedwater Isolation Valve FMO-203 Failed to Close.Caused by Buildup of Corrosion Products within Limitorque Actuator Connection Box.Contacts Cleaned | | | 05000316/LER-1982-015, Forwards LER 82-015/04L-0 | Forwards LER 82-015/04L-0 | | | 05000316/LER-1982-015-04, /04L-0:on 820222,flow Indicator SFR-201 for Turbine Gland Seal Leakoff Failed Low.Probably Caused by Moisture in Sys.Replacement Probes Found Calibr to Incorrect Range.New Sys to Be Installed | /04L-0:on 820222,flow Indicator SFR-201 for Turbine Gland Seal Leakoff Failed Low.Probably Caused by Moisture in Sys.Replacement Probes Found Calibr to Incorrect Range.New Sys to Be Installed | | | 05000315/LER-1982-015-03, /03L-0:on 820305,during Power Increase,Turbine Would Not Accept Addl Load at 46%.Turbine Runback Occurred. Caused by Problems in Initial Pressure Limiter Circuits. Circuitry Removed from Control Sys B | /03L-0:on 820305,during Power Increase,Turbine Would Not Accept Addl Load at 46%.Turbine Runback Occurred. Caused by Problems in Initial Pressure Limiter Circuits. Circuitry Removed from Control Sys B | | | 05000315/LER-1982-016, Forwards LER 82-016/03L-0 | Forwards LER 82-016/03L-0 | | | 05000316/LER-1982-016-03, Pinhole Leak Discovered on Suction Strainer for West Containment Spray (CTS) Pump. Caused by Fatigue.Pinhole Removed by Grinding & Rewelding | Pinhole Leak Discovered on Suction Strainer for West Containment Spray (CTS) Pump. Caused by Fatigue.Pinhole Removed by Grinding & Rewelding | | | 05000316/LER-1982-016, Forwards Updated LER 82-016/03X-1 & LERs 83-121/03L-0 & 83-122/03L-0 | Forwards Updated LER 82-016/03X-1 & LERs 83-121/03L-0 & 83-122/03L-0 | | | 05000315/LER-1982-017, Forwards LER 82-017/03L-0 | Forwards LER 82-017/03L-0 | |
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