Similar Documents at Byron |
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LER-1993-005, Advises That LER 93-005 Will Not Be Used |
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| 4551993005R00 - NRC Website |
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ON C:mm:nwsalth Edis n O / Byron Nuclear Station C'>
4450 North Gerrnan Church Road Byron, Illinois 61010 October 27, 1993 LTR:
BYRON 93-0586 FILE:
3.03.0800 (1.10.0101) i U.S.
Nuclear Regulatory Commission Document Control Desk i
Washington, D.C.
20555
Dear Sir:
For Docket Number 50-455, Licensee Pvent Report Number 93-005 from Byron Generating Station will not be used.
5 Sincerely, O
kl%>x:emy G.K. Schwartz /
Station Manager Byron Nuclear Power Station GKS/DSK/ng cc:
J. Martin, NRC Region III Administrator NRC Senior Resident Inspector j
INPO Record Center CECO Distribution List
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j (9986R/WPF/101593 -7) 9311010169 931027 PDR ADDCK 05000456 ',
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PDR m;
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| 05000455/LER-1993-001-09, :on 930223,wiring Discrepancy in Ssps Cabinet Discovered.Caused by Incorrect Wiring of Cabinet Prior to Delivery by Mfg.Vendor Manual Update Submitted to Correct Terminal Board Wiring List |
- on 930223,wiring Discrepancy in Ssps Cabinet Discovered.Caused by Incorrect Wiring of Cabinet Prior to Delivery by Mfg.Vendor Manual Update Submitted to Correct Terminal Board Wiring List
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000454/LER-1993-001-06, :on 930201,discovered Concern Re Potential Nonconservatism in Determining LTOP Sys Setpoints Used in TS & in Implementing Use of 10CFR50,App G Limits.Appropriate Procedures Will Be Revised |
- on 930201,discovered Concern Re Potential Nonconservatism in Determining LTOP Sys Setpoints Used in TS & in Implementing Use of 10CFR50,App G Limits.Appropriate Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000455/LER-1993-002-08, :on 930311,determines Unit 1 Essential Svc Water Pump Availability to Unit 2 Surveillance Not Complete. Caused by Failure to Complete Requirements of Shift/Daily Operating Surveillance.Surveillance Revised |
- on 930311,determines Unit 1 Essential Svc Water Pump Availability to Unit 2 Surveillance Not Complete. Caused by Failure to Complete Requirements of Shift/Daily Operating Surveillance.Surveillance Revised
| | | 05000454/LER-1993-002-07, :on 930226,train B Valves Failed to Actuate When Train B Portion of Surveillance Performed.Caused by Jumper Dislodged by Unknown Individual After Surveillance Completed on 930220.New Jumpers Mfg |
- on 930226,train B Valves Failed to Actuate When Train B Portion of Surveillance Performed.Caused by Jumper Dislodged by Unknown Individual After Surveillance Completed on 930220.New Jumpers Mfg
| 10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000455/LER-1993-003-09, :on 930511,turbine Emergency Trip Oil Header Pressure Low Alert Received Followed by Reactor Trip & Turbine Trip Above P-8.Caused by Actuation of Overspeed Trip Relay.Faulty Power Supply Board Replaced |
- on 930511,turbine Emergency Trip Oil Header Pressure Low Alert Received Followed by Reactor Trip & Turbine Trip Above P-8.Caused by Actuation of Overspeed Trip Relay.Faulty Power Supply Board Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000454/LER-1993-003-06, :on 930306,experienced Difficulty Latching Rcca at Core Location.Caused by Upper Internals Package Fuel Assembly Guide Pins Not Properly Engaged in Top Nozzle. Changes Evaluated Re Top Nozzle Clearance |
- on 930306,experienced Difficulty Latching Rcca at Core Location.Caused by Upper Internals Package Fuel Assembly Guide Pins Not Properly Engaged in Top Nozzle. Changes Evaluated Re Top Nozzle Clearance
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000454/LER-1993-004-10, :on 931208,notified of Potential Inoperability of AFW Switchover Due to Inadequate Design Change.Temporary Alteration Installed to Move Feeds for 4 Seconds SW Switchover Time Delay Relay |
- on 931208,notified of Potential Inoperability of AFW Switchover Due to Inadequate Design Change.Temporary Alteration Installed to Move Feeds for 4 Seconds SW Switchover Time Delay Relay
| | | 05000455/LER-1993-005, Advises That LER 93-005 Will Not Be Used | Advises That LER 93-005 Will Not Be Used | | | 05000455/LER-1993-006-08, :on 930924,identified That Surveillance for Source Range Instrumentation Missed Due to Incorrect Computer Status Update.Changes Made to Update Process.W/ |
- on 930924,identified That Surveillance for Source Range Instrumentation Missed Due to Incorrect Computer Status Update.Changes Made to Update Process.W/
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | | 05000455/LER-1993-008-01, :on 931123,reactor Trip/Turbine Trip Occurred Due to Solid State Protection Sys Universal Logic Card Intermittent Failure.Further Testing of Removed Cards A218, A316 & A517 Completed W/No Definitive Results |
- on 931123,reactor Trip/Turbine Trip Occurred Due to Solid State Protection Sys Universal Logic Card Intermittent Failure.Further Testing of Removed Cards A218, A316 & A517 Completed W/No Definitive Results
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000455/LER-1993-008-07, :on 931123,reactor Trip Occurred.Cause Suspected to Be Failure of One of Circuit Cards for Train a of Solid State Protection Sys SG Level.Suspect Circuit Cards Replaced |
- on 931123,reactor Trip Occurred.Cause Suspected to Be Failure of One of Circuit Cards for Train a of Solid State Protection Sys SG Level.Suspect Circuit Cards Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
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