Letter Sequence ' |
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Results
Other: ML14107A285, ML19246B407, ML19338D128, ML19340E368, ML19343C402, ML19343C405, ML19345G219, ML20002B328, ML20003E420, ML20010E472, ML20011A237, ML20031G927, ML20037D564, ML20070V605, ML20071E469, ML20071G877, ML20073R547, ML20083A206, ML20090A057, ML20101T745, ML20207L352
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MONTHYEARML19246B4071979-07-0303 July 1979 Submits Requested Info Re Testing of AFW Pumps NPSH/DB-1 & HPI Line Break Analysis Project stage: Other ML14107A2851980-05-23023 May 1980 Memorandum & Order on Ucs 771104 Petition for Remedial Relief Re Fire Protection of Electrical Cables & Environ Qualification of Electrical Components.Reaffirms Commission 780413 Decision Re Possible Shutdown of Operating Reactors Project stage: Other ML19338D1281980-08-29029 August 1980 Order for Mod of License NPF-3 to Add Info Which Fully Responds to NRC Request for Info Re Environ Qualification of safety-related Electrical Equipment.Info Should Be Submitted by 801101 Project stage: Other ML19340E3681980-10-21021 October 1980 Responds to IE Bulletin 80-19 Re Failures of Mercury Wetted Matrix Relays.Tabulated History of Matrix Relay Failures Encl.Requests Exemption from Requirement Ordering Replacement of Relays Project stage: Other ML20002B3281980-12-0505 December 1980 Requests,On Behalf of Util,Extension Until 810108 to Request Hearing Re NRC 801118 Order for Mod to License.Requested Extension Would Allow for Better Understanding of Order Requirements Project stage: Other ML20207L3521981-01-29029 January 1981 Informs That 810116 Extension for Time to Request Hearing Re 801024 Order for Mod of Lisense Acceptable & Consistent W/ 810108 Request Project stage: Other ML19345G2191981-01-30030 January 1981 Forwards Revision 3 to Response to IE Bulletin 79-01B,Suppl 3, Environ Qualification of Class IE Equipment. Revision 3 Encompasses Boron Precipitation Control Sys,Ie Pressurizer Heaters Sys & post-TMI Mods.W/O Encl Project stage: Other ML19343C4021981-03-16016 March 1981 Forwards Environ Qualification of Safety-Related Electrical Equipment, Partial Review.Several Deficiences Identified Re Lack of Proper Documentation Project stage: Other ML19343C4051981-03-16016 March 1981 Environ Qualification of Safety-Related Electrical Equipment, Partial Review Project stage: Other ML20003E4201981-03-27027 March 1981 Responds to Re NRC 801024 Order Modifying OL Re Environ Qualification of safety-related Equipment.Review Identified All Items Previously Noted in 800403,0814,1031 & 810130 Response to IE Bulletin 79-01B Project stage: Other ML20004F6641981-06-12012 June 1981 Extends 30-day Abeyance Period for Requesting Hearing to 90 Days After Safety Evaluation Issuance Project stage: Approval ML20037D5641981-08-14014 August 1981 Informs of NRC 810731 Recommendation to Extend 820630 Deadline for Hearing Re Environ Qualification of safety- Related Equipment to 830630 W/Limited Provisions for Further Extensions.Response Requested by 810901 Project stage: Other ML20010E4721981-08-31031 August 1981 Responds to Re Environ Qualificatiion of safety- Related Electrical Equipment.Nrc Action of Holding Util Hearing Request in Abeyance Until 30 Days After Commission Action on Industry Petition Acceptable Project stage: Other ML20011A2371981-10-0505 October 1981 Advises That Resolutions of Deficiencies Identified in Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment Will Be Submitted by 811016 Project stage: Other ML20031G9271981-10-12012 October 1981 Forwards Equipment Qualification Manual Discussion Highlighting Methodology & SER Discrepancies, & Environ Qualification of Safety Related Electrical Equipment, Vols 1-6 Project stage: Other ML20049J6211982-03-0404 March 1982 Forwards Request for Addl Info on Util Response to Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Response Should Be Submitted in 30 Days Project stage: Approval ML20050C7201982-04-0505 April 1982 Advises That Response to 820304 Request for Addl Info Re Environ Qualification of safety-related Electrical Equipment Will Be Submitted by 820507.Manpower Requirements During Current Refueling Outage Preclude Earlier Submittal Project stage: Request ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info Project stage: Request ML20052H5681982-05-17017 May 1982 Forwards Response to 820304 Request for Info Re Environ Qualification of safety-related Electrical Equipment.Sys Component Evaluation Worksheets & Master List for NUREG-0737 Component Encl Project stage: Request ML20070V6051983-02-0808 February 1983 SER Re Environ Qualification of safety-related Electrical Equipment Project stage: Other ML20071E4691983-03-10010 March 1983 Responds to NRC Re safety-related Electrical Equipment.Justification for Continued Operation Encl Project stage: Other ML20073R5471983-04-29029 April 1983 Responds to NRC Re safety-related Electrical Equipment.Justification for Continued Operation Exists for All Equipment Which May Not Be Qualified.Response Submitted 830310 Contains No Changes or Proprietary Info Project stage: Other ML20071G8771983-05-20020 May 1983 Forwards Info Re Environ Qualification of Electrical Equipment Important to Safety,Per 10CFR50.49.List of Activities to Resolve Technical Evaluation Rept Open Items Encl.Namco Limit Switches Scheduled for Replacement Listed Project stage: Other ML20085J3351983-10-10010 October 1983 Discusses 831013 Meeting to Resolve Deficiencies Noted in Franklin Research Ctr Technical Evaluation Rept Re Environ Qualification of safety-related Electrical Equipment.Agenda & Supporting Documentation Encl Project stage: Meeting ML20082G3431983-11-23023 November 1983 Forwards Agenda for 831213 Meeting W/Nrc in Bethesda,Md to Discuss & Resolve Outstanding Issues Re Environ Qualification of Electrical Equipment Project stage: Meeting ML20083A2061983-11-29029 November 1983 Forwards Equipment Qualifications Manual,Rev 2 Project stage: Other ML20088A9051984-04-0303 April 1984 Forwards Generic Issues,Resolution of Open Items & Justifications for Continued Operations Per 831213 Meeting Re Environ Qualifications for safety-related Electrical Equipment Deficiencies Project stage: Meeting ML20090A0571984-06-26026 June 1984 Forwards Sys Component Evaluation Worksheets & Justifications for Continued Operation Re Environ Qualification of Electrical Equipment,In Response to NRC .Methodology Used to Create Master List Described Project stage: Other ML20101T7451985-02-0101 February 1985 Responds to Generic Ltr 84-24 Re Certification of Compliance w/10CFR50.49, Environ Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. Appropriate Actions Taken to Correct Potential Deficiencies Project stage: Other 1981-08-31
[Table View] |
LER-1980-061, /03L-0:on 800812,during Calibr & Maint Records Check,Personnel Found Valve SV5005 Installed on 760826 for Temporary Use Was Not Replaced.Caused by Inadequate Administrative Control.Replacement for SV5005 Requested |
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| 3461980061R03 - NRC Website |
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text
NRC FORM Q U.S. NUCL EAR RE JULATORY COMr.iiSSION (7 77)
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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h ITTTI I (NP-33-80-73) On 8/12/80 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, I&C personnel were checking their calibration l g lcnd maintenance records and discovered that valve SV5005 was instal.i.ed on 8/26/76 for l l temporary use and never replaced. This valve controls the contr.inment purge isolation l o 4 lo i s i l damper CV5005 and was not qualified for nuclear; service.
Being a Safety Features l
lo is I l Actuation System level 1 valve, it must be operable in all modes.
Therefore the l
jol7lletation entered the action statement of T.S. 3.3.2.1.
There was no danger to the l
l o t a l l public or station personnel. The installed valve functioned properly since installed.l 80 7
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9 10 11 12 13 18 19 20 MQUENTIAL OCCURRENCE REPORT REVISION LER EVENT YEAR REPORT NO.
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l0l0l0lDl [YJ Q l N l g l Zl g lZ l9 l9 l9 lg 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li l o l l The cause was an inadequate implementation of an administrative control.
SV5005 was l
1 i l originally installed for temporary use. however there are no records to indicate anv I
i 2 l followup. When SV5005 was determined unqualified, CV5005 was declared inoperable and I i 3 l secured in its closed position.
Facility Change Request 80-206 has been written to l
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8 9 10 68 69 80 g DVR 80-133 Thomas Isley PHONE:
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NAME OF PREPARER i
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- - TOLEDO EDISON COMPANY
.iDAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-73 2
'DATE OF EVENT: August 12, 1980, FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:.'Non-Qualified ~ Solenoid Valve Operator Installed on Containment Purge Valve Conditions Prior to Occurrence: The unit was 'in Mode 5 with Poser (MWT) = 0 and Load (Gross MRE) w 0.
Description of Occurrence: On August 12, 1980 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, Inscrument and Controls (I&C) personnel were comparing a suspected bad solenoid valve with a known good one, SV5005.- This good valve,-.SV5005, controls the Containment Purge Inlet Isolation Damper CV5005.- A check of I&C calibration and maintenance records showed that SV5005 was installed August 26, 1976 for temporary use and was never replaced with the proper valve. -This temporary valve is not qualified for nuclear service and is not accepta-ble in this application.
Therefore, CV5005 was declared inoperable and secured in its closed position.
Being a Safety Features Actuation System (SFAS) incident icyc1 1 valve, CV5005 must be operable in all modes, and therefore, the station entered the action statement of Tech-nical Specification 3.3.2.1.
This action statement required the valve to be secured in its safety position, closed.
Designation of Apparent Cause of Occurrence: The cause was an inadequate implementation of an administrative control during the initial plant testing and system turnover. At -
the time.the valve was installed, it was known that it wat for temporary use. I&C's Instrument Information Sheet shows that at the time of the installation, it was known that this solenoid-valve was installed for temporary use until a proper valve -was received. The installation of this temporary valve without proper documentation was not in complianceDwith the administrative requirements of AD 1844.00, " Maintenance".
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The installed valve did function properly in all testing since it was installed.
Corrective Action
An ongoing review of I&C records is being conducted to verify that there.had been no other maintenance activities conducted during initial startup and testing that'were completed without conforming to the administrative requirements
~
ofLAD~1844.00. No additional discrepancies have been found.
On: August 12,;1980 when it was determined that the installed SV5005 solenoid valve i
. as not qualified for its application, CV5005 was declared inoperable and secured
~
w in.its closed position'.- The valve will remain closed until a suitable replacement is installed. Nonconformance Report 292-80 was-issued to ensure a qualified solenoid LER 180-061 q
m
W
...i- }
' TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER' STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-80-73
- valve is used. ' Facility Change Request 80-206 has been written to replace SV5005-
.with-an available nuclear service grade solenoid valve.
Failure Data: There have L$en no previous reports of this type damper being declared' inoperable due.to the installation of a non-qualified solenoid valve.
LER #80-061 4
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| 05000346/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000346/LER-1980-001-01, /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | | | 05000346/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000346/LER-1980-002-03, /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | | | 05000346/LER-1980-003-03, /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | | | 05000346/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000346/LER-1980-004-03, /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | | | 05000346/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000346/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000346/LER-1980-005-03, /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | | | 05000346/LER-1980-006-03, /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | | | 05000346/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000346/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000346/LER-1980-007-03, /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | | | 05000346/LER-1980-008-03, Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | | | 05000346/LER-1980-008, Forwards Revised LER 80-008/03L-1 | Forwards Revised LER 80-008/03L-1 | | | 05000346/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000346/LER-1980-009-03, /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | | | 05000346/LER-1980-010-01, /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | | | 05000346/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000346/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000346/LER-1980-011-03, /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | | | 05000346/LER-1980-012-03, /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Reposition | /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Repositioned | | | 05000346/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000346/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | | | 05000346/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000346/LER-1980-014-03, /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | | | 05000346/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000346/LER-1980-015-03, /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | | | 05000346/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000346/LER-1980-016-03, /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | | | 05000346/LER-1980-017-03, /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | | | 05000346/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000346/LER-1980-018-03, /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | | | 05000346/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000346/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000346/LER-1980-019-01, /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | | | 05000346/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000346/LER-1980-020-03, /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | | | 05000346/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000346/LER-1980-021-03, /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | | | 05000346/LER-1980-022-03, /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | | | 05000346/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000346/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000346/LER-1980-023-03, /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | | | 05000346/LER-1980-024-03, /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | | | 05000346/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000346/LER-1980-025-03, /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | | | 05000346/LER-1980-025, Forwards LER 80-025/03X-1 | Forwards LER 80-025/03X-1 | |
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