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LER-1991-008, Forwards LER 91-008-00 Re Missed Surveillance for Core Flood Tank Samples.Ler Submitted Per Interim Util Policy Issued in Response to Violations Noted in Insp Rept 50-289/92-20 |
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| 2891991008R00 - NRC Website |
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i OPU Nuclear Corporation NggIgf Post Office Don 480
.f Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Witter's Direct Olal Numbet:
(717) 948-8005 January 29, 1993 C311-93-2013 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Dear Sir:
Subject: Three Mile Island Nuclear Station, Unit 1 (THI-1)
Operating License No. DPR-50 Docket No. 50-289 LER 91-008-00 This letter transmits voluntary Licensee Event Report (LER) 91-008-00 concerning a missed surveillance for Core Flood Tank Samples.
Public health and safety were not affected.
This voluntary LER is submitted pursuant to an-Interim GPUN policy issued in response to a Notice of Violation contained in Inspection Report 92-20.
Attached is an abstract which provides a brief description-of the event. 'For a complete understanding of the event, refer to the full text of tho. report provided on Form 366A.
Sincerely,
.jtj L
T. G. Br ughton i
050019 Vice President and Director, THI-l AWM/mkk Attachment Region I Administrator cc: '. TMl-1 Senior Project Manager TMI Senior Resident Inspector 9302100039 930129 PDR-ADOCK 05000289 S
PDR GPU Nuclear Corporation is a subsidiary of General PutAc Utihties Corporation -
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| 05000289/LER-1991-001-02, :on 910707,inoperability of Degraded Grid Voltage Relays Resulting from Reinstallation of Volt Breaker.Caused by Physical Configuration of Switchgear Cubicle.Engineering Evaluation Performed |
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| 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(b)(2)(ii) | | 05000320/LER-1991-001, :on 910121,quarterly Checks Not Performed on Penetration Isolation Valve SGC-FV-2.Caused by Personnel Error.Temporary Change Notice Initiated & Independent Reviews of Procedures Completed |
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| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1991-002-02, :on 910724,reactor Tripped on Low RCS Pressure Due to Control Rod Group 7 Dropping Into Reactor Core.Caused by Personnel Error & Equipment Failure.Components Repaired & Maint Personnel Trained |
- on 910724,reactor Tripped on Low RCS Pressure Due to Control Rod Group 7 Dropping Into Reactor Core.Caused by Personnel Error & Equipment Failure.Components Repaired & Maint Personnel Trained
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1991-003-02, :on 910927,turbine Control Valves Started Opening rapidly,once-through Steam Generator Pressure Began to Drop & Reactor Trip Occurred During Testing.Caused by Inadequate Procedure.Procedure Revised |
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| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1991-004, :on 911008,irradiated Fuel to Test Hoist Interlocks W/O Full Containment Isolation.Caused by Staff Error & Procedural Inadequacy.All Licensed Operators to Receive Addl Training & Procedures Revised |
- on 911008,irradiated Fuel to Test Hoist Interlocks W/O Full Containment Isolation.Caused by Staff Error & Procedural Inadequacy.All Licensed Operators to Receive Addl Training & Procedures Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000289/LER-1991-004-02, :on 911008,irradiated Fuel Assembly Moved W/O Verification of Containment Integrity During Performance of Main Fuel Bridge Hoist Test.Caused by Procedural Weaknesses/ Personnel Error.Incident Reviewed W/Personnel |
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| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(b)(2)(ii) | | 05000320/LER-1991-004, :on 910412,processed Water Disposal Sys Sample Valve Misaligned.Caused by Personnel Error.Addl Training for Evaporator Operators & Rev to Pwds Operating Procedure & Areas of Responsibility Addressed |
- on 910412,processed Water Disposal Sys Sample Valve Misaligned.Caused by Personnel Error.Addl Training for Evaporator Operators & Rev to Pwds Operating Procedure & Areas of Responsibility Addressed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1991-005-02, :on 911101,in Process of Bypassing Train a, Operator Depressed Incorrect Pushbutton,Causing ESAS Actuation of Channel A.Caused by Personnel Error.Operator Counseled & Plant Incident Rept Written |
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| 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1991-006-01, :on 911104,discovered Increased Potential for post-LOCA Boron Precipitation.Caused by Error in NSSS Vendor Licensing Basis Analysis.Util Will Confirm Calculations to Support Conclusions within 1 Month |
- on 911104,discovered Increased Potential for post-LOCA Boron Precipitation.Caused by Error in NSSS Vendor Licensing Basis Analysis.Util Will Confirm Calculations to Support Conclusions within 1 Month
| 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1991-007-01, :on 911113,main Feedwater Pump Intentionally Tripped During Plant Heatup to Verify Stop Valve Closure. Both motor-driven ESF Pumps Started.Caused by Personnel Error.Event Reviewed W/Personnel |
- on 911113,main Feedwater Pump Intentionally Tripped During Plant Heatup to Verify Stop Valve Closure. Both motor-driven ESF Pumps Started.Caused by Personnel Error.Event Reviewed W/Personnel
| 10 CFR 50.73(b)(2)(ii) | | 05000289/LER-1991-008, Forwards LER 91-008-00 Re Missed Surveillance for Core Flood Tank Samples.Ler Submitted Per Interim Util Policy Issued in Response to Violations Noted in Insp Rept 50-289/92-20 | Forwards LER 91-008-00 Re Missed Surveillance for Core Flood Tank Samples.Ler Submitted Per Interim Util Policy Issued in Response to Violations Noted in Insp Rept 50-289/92-20 | | | 05000289/LER-1991-008-01, :on 911223,discovered Misfiled Surveillance Notification Form Specifying Core Flood Tank Monthly Boron Sample Days Beyond Latest Date.Caused by Personnel Error. Surveillance Tracking Practice Revised |
- on 911223,discovered Misfiled Surveillance Notification Form Specifying Core Flood Tank Monthly Boron Sample Days Beyond Latest Date.Caused by Personnel Error. Surveillance Tracking Practice Revised
| 10 CFR 50.73(b)(2)(ii) |
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