Letter Sequence Other |
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Results
Other: 05000346/LER-1980-090-03, /03L-1:on 801205,setpoints for Borated Water Storage Tank Low Level Bistable BA312 & Containment Pressure Bistable BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr, ML19340E991, ML19341B813, ML20002C776, ML20010J123, ML20069E493, ML20141N821, ML20265E231, ML20265E237, ML20265E241, ML20265E246, ML20265E251
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MONTHYEARML20002C7761980-12-24024 December 1980 Informs That Engineered Safety Features Actuation Sys Does Not Conform to IEEE Std 279.1971 & Constitutes Potential Failure Mode.Recommends Short Term Corrective Actions Project stage: Other 05000346/LER-1980-090-03, /03L-1:on 801205,setpoints for Borated Water Storage Tank Low Level Bistable BA312 & Containment Pressure Bistable BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr1981-01-0202 January 1981 /03L-1:on 801205,setpoints for Borated Water Storage Tank Low Level Bistable BA312 & Containment Pressure Bistable BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr Project stage: Other ML19340E9911981-01-0909 January 1981 Forwards marked-up Electrical Drawings as Update to 810105 Request to Deautomate Incident Level 5 of Safety Features Actuation Sys.Procedure Mod Details,License Amend Request & Safety Evaluation Will Follow.W/O Encl Project stage: Other ML20002D1341981-01-15015 January 1981 Proposed Tech Specs Sections 3 & 4,to Permit Deautomation of Valve Shifts Caused by Incident Level 5 of Safety Features Actuation Sys.Draft Emergency & Sys Operating Procedures & Functional Description Encl Project stage: Draft Other ML20002D1291981-01-15015 January 1981 Application to Amend License NPF-3,changing Tech Specs to Permit Deautomation of Valve Shifts Caused by Incident Level 5 of Safety Features Actuation Sys Project stage: Request 05000346/LER-1980-090, Forwards LER 80-090/03L-1 W/Supplemental Info Sheets1981-02-13013 February 1981 Forwards LER 80-090/03L-1 W/Supplemental Info Sheets Project stage: Supplement ML19341B8111981-02-24024 February 1981 Application for Amend to License NPF-3 Changing Tech Spec Section 4.5.2.d.2 & Tables 3.3-3,3.3-5 & 4-3.2 Project stage: Request ML19341B8051981-02-24024 February 1981 Forwards Application to Amend License NPF-3 Changing Tech Specs to Provide Consistency in Terminology W/Plant Design & to Ensure Adequate Surveillance Requirements Project stage: Request ML19341B8131981-02-24024 February 1981 Revised Tech Spec Section 4.5.2.d.2 & Tables 3.3-3,3.3-5 & 4.3-2 Changing Surveillance Requirements Per Amend 36 to License NPF-3 Project stage: Other ML20010J1231981-09-15015 September 1981 Forwards Response to NRC Re 801205 Inadvertent Safety Features Actuation Sys Actuation Project stage: Other ML20069E4931983-03-11011 March 1983 Forwards Response to Re Safety Features Actuation Sys Shared Power Supply Returns.Permanent Grounding of Power Supply Commons to Instrument Ground Will Be Provided to Resolve Channel Independence Issue Project stage: Other ML20265E2411985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 3 of 5.Drawing Consists of Four Aperture Cards Project stage: Other ML20265E2371985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 1 of 5.Drawing Consists of Three Aperture Cards Project stage: Other ML20265E2311985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 2 of 5.Drawing Consists of Four Aperture Cards Project stage: Other ML20265E2461985-11-0101 November 1985 Schematic Diagram:Davis Besse Safety Features Actuation System. Sheet 4 of 5.Drawing Consists of Three Aperture Cards Project stage: Other ML20265E2511985-11-0101 November 1985 Schematic Diagram:Davis-Besse Safety Features Actuation System. Sheet 5 of 5.Drawing Consists of Five Aperture Cards Project stage: Other ML20138Q5501985-12-17017 December 1985 Summary of 851126 Meeting W/Util,Beta & Consolidated Controls Corp in Bethesda,Md Re Proposed Changes to Safety Features Actuation Sys.Viewgraphs & List of Attendees Encl Project stage: Meeting ML20141N8211986-03-11011 March 1986 Confirms 860307 Submittal of Drawings 7749-E-30-5-6, Analog Module Assembly & 7749-E-30-19-7, Bistable 2 & Forwards Addl Copies,Per NRC Response to Re Safety Features Actuation Sys Project stage: Other ML20203N7921986-04-17017 April 1986 Forwards Safety Evaluation Accepting Proposed Mods to Safety Features Actuation Sys as Result of 801205 Actuation, Pending Successful Completion of post-mod Tests Project stage: Approval ML20203N9141986-04-17017 April 1986 Safety Evaluation Accepting Proposed Mods to Safety Actuation Sys Re Shared Power Supply Returns as Result of 801205 Actuation Project stage: Approval 1981-02-24
[Table View] |
LER-1980-090, /03L-1:on 801205,setpoints for Borated Water Storage Tank Low Level Bistable BA312 & Containment Pressure Bistable BA309 Found Out of Tolerance.Caused by Component Failure.Bistables Recalibr |
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| 3461980090R03 - NRC Website |
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text
U. S. NUCLE AR REGULATORY COMidlSSION NRC FORM 366 87-7 7)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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60 61 DOCKET NLVBER 68 63 EVENT DATE 74 75 REPORT DATE 83 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l (NP-33-80-115) On 12/5/80 at 1730 hot:rs during surveillance testing, the setpoint forl
! the Borated Water Storage Tank low level bistable BA312 was found out of tolerance.
l Io lal l0 l4 l l On 12/6/80 at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> during testing, the setpoint for the containment pressure I
l o I s l l bistable BA309 was also found out of tolerance. Both occurrences placed the unit in l Io is ] l Action Statement 9 of Technical Specification 3.3.2.1.
There was no danner to the l
l o l 7 l l health and safety of the public or station personnel. The remaining three Safetv l
I I o 18 I l Features Actuation System channels were operable.
SYSTEM
CAUSE
CAUSE COUP.
VALVE CODE CODE SUBCODE COMPONENT CODE SU8 CODE SUBJoOE lol9!
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35 36 31 40 43 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li l o l ] The cause of these occurrences can be attributed to a component failure. The bistahic);
I i 11 I l are subject to instrument drif t.
Upon finding BA312 and BA309 out of calibration.
1 [TJ q l they were immediately recalibrated as per the test (ST 5031.01) procedure to within I
i l l3l3)l the technical specification limit. The voltage between common and ground will be i
1 I Ii 14 I l checked on a monthly basis to ensure an AC voltage does not go undetected.
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'*'isS S1 sPOwER OTHER STATUS ISC RY DISCOVERY DESCRIPTION lt l s l y@ l 0 l 0 l 0 l@l NA l
l B l@l Surveillance Test ST 5031.01 l
ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTivtTY LOCATION OF RELEASE l
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Tom Isley PHONE:
l M*R 80-205 & y)flE OF PREPAHER
TOLEDO EDISON COMPANY I5 AVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-115 DATE OF EVENT: December 5, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Safety Features Actuation System (SFAS) Bistables
,l Out of the Technical Specification Allowable Value Conditions Prior to Occurrence: The unit was in Mode 3 with Power (MRT) = 0 and Load (Gross MUE) = 0.
, Description of Occurrence: On December 5, 1980 at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> during the performance of the SFAS Monthly Test, ST 5031.01 on SFAS Channel 3, the setpoint for the Borated Water Storage Tank (BUST) low level bistable (BA 312) was found to be out of toler-The bistable as found value was 0.552 V and the allowable value is less than ance.
or equal to 0.551 V.
On December 6, 1980 at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, ST 5031.01 was performed on SFAS Channel 3 to verify operability after troubleshooting to find the cause of the 120 VAC potential between power supply common and ground (see Licensee Event Report NP-33-80-113).
Thel i
containment pressure 38.4 psia bistable (BA 309) was found out of tolerance.
The bistable as found value was 1.428 V and the allowable value is less than or equal to 1.427 V.
See attached tables for additional information.
Both occurrences placed the unit in Action Statement 9 of Technical Specification 3.3.2.1.
The action statement requires the inoperable channel to be placed in the tripped condition within one hour. Both bistables were immediately recalibrated per tbe test procedure (ST 5031.01), removing the station from the action statement.
Designation of Apparent Cause of Occurrence: The cause of these-occurrences can be y
attributed to a component failure. The bistables are subject to instrument drift.
The instrument drift was probably aggravated by the 120 VAC problem on the cabinet Common.
I Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The remaining three SEAS Channels were operable and capable of performing their designed function.
Corrective Action
Upor finding the BWST level bistable BA 312 and'the containment pressure bistable BA 309 out of calibration they were immediately recalibrated as per the test (ST 5030.01) procedure to within the Technical Specification limits.
To be sure that an AC voltage on common does not exist for an extended period of time 3
the voltage between common'and. ground will be checked on a monthly basis per i-ST 5031.01, SFAS Monthly Test.
LER #80-090
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-115 PAGE 2 Failure Data: There have been three previous similar occurrences of bistable drift, l
see Licensee Event Reports NP-33-78-84 (78-070), HP-33-78-140 (78-119) and NP-33-79-50 (79-045).
LER #S0-090 G
G
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-115 PAGE 3 CONTAINMENT PRESSURE BA 309 (After 120 VAC Removed)
Pressure (psia)
Volts (1) 60 2.00 Full Range 38.55 1.428 9
9 As Found A 1.875 in. o7.5 in.
2 Allowable Value (TS)
- - 38.52 1.427 (O.3125%)
(1.25%)
Y 38.4 1.425 V
Trip Setpoint Trip Setpoint y_.37.65 1.404 v
Zero O
C.4 Worst case drift 1.5%
(1) V=psiax1.6)+0.4 60
/
1 BWST LEVEL (BA 312) (With 120 VAC on Common)
Level (inches)
Volts (1)
Full Range 600 2.00 As Found 57 0.552 9
d 0.15 psi i
Allowable Value (TS)
/_56.7 0.551 (0.25%)
d 0.9 psi (1.5%)
Trip Setpoint
{-55.0 0.547
% /
1 di Trip Setpoint
.Z.49.5 0.532 Allowable Value (TS)
Z 48.3 0.529 Zero 0
0.4 Worst case drift 1.25% of full scale (1)
V=
level (in) x 1.6 + 0.4 600 LER #80-090
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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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