05000482/LER-1993-006, Forwards LER 93-006-00 Re Exposure of Individual in Excess of Applicable Limits in 10CFR20.101

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Forwards LER 93-006-00 Re Exposure of Individual in Excess of Applicable Limits in 10CFR20.101
Person / Time
ML20134B456
Site:	Wolf Creek
Issue date:	04/30/1993
From:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20133F974	List: 05000482/LER-1993-006, Forwards LER 93-006-00 Re Exposure of Individual in Excess of Applicable Limits in 10CFR20.101 05000482/LER-1993-006-01, :on 930402,hot Particle Picked Up During Filling & Venting of SI Sys Resulted in Exposure Exceeding 10CFR 20.101 Requirements.Operations Qualification Card Checklist Procedures Will Be Revised IA-96-536, Final Response to FOIA Request for Documents.Forwards App a Records.Records Being Withheld in Part (Ref FOIA Exemption 6) ML20133F970
References
FOIA-96-536 WO-93-0094, WO-93-94, NUDOCS 9305070208
Download: ML20134B456 (1)
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LER-1993-006, Forwards LER 93-006-00 Re Exposure of Individual in Excess of Applicable Limits in 10CFR20.101

Event date:
Report date:
4821993006R00 - NRC Website
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Licensee Event Report 93-006-00

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D' ' U Gentlemen:

Tha attached Licensee Event Report (LER) in submitted pursuant to 10 CTR 20.405taltl)!11 concerning an exposure of an individual in excess of the

.ipp; a cabic !tmtts in 10 crA 20.101.

In accerdance with 10 CFR 2.790 the attachment to the LER provides personal inforration and should not be disclosed.

- Ver'y truly yours, Otto 'L'.' Maynard Vice President Plant operations 0 :.'. t / j a n

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Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000482/LER-1993-001, :on 930304,determined That All Time Delays for RCP Undervoltage Trip Function Not Included in Response Time Testing of Reactor Trip Circuit.Caused by Inadequate Westinghouse TS Development Procedures Revised	on 930304,determined That All Time Delays for RCP Undervoltage Trip Function Not Included in Response Time Testing of Reactor Trip Circuit.Caused by Inadequate Westinghouse TS Development Procedures Revised
05000482/LER-1993-002, :on 930310,CPIS & CR Ventilation Isolation Signal Generated by Signal from Containment Purge Radiation Monitor.Caused by Design Misapplication of Target Rock Sovs. Target Rock Valves Will Be Replaced	on 930310,CPIS & CR Ventilation Isolation Signal Generated by Signal from Containment Purge Radiation Monitor.Caused by Design Misapplication of Target Rock Sovs. Target Rock Valves Will Be Replaced	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1993-004, :on 930316,discovered That Broken Fuel Rod Segment Protruding Out of Fuel Assembly F67 at Core Position H-6 Due to grid-to-rod Fretting.Detailed Remote Visual Insp Conducted	on 930316,discovered That Broken Fuel Rod Segment Protruding Out of Fuel Assembly F67 at Core Position H-6 Due to grid-to-rod Fretting.Detailed Remote Visual Insp Conducted	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)(B)
05000482/LER-1993-004-01, :on 930316,broken Fuel rod,11-12 Inches in Length,Protruded Out of Fuel Assembly F67 at Core Position FH-6.Caused by Grid to Rod Fretting Failures.Util Evaluating Fluid Elastic Instability	on 930316,broken Fuel rod,11-12 Inches in Length,Protruded Out of Fuel Assembly F67 at Core Position FH-6.Caused by Grid to Rod Fretting Failures.Util Evaluating Fluid Elastic Instability	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000482/LER-1993-005, :on 930322,maint Electrician Skipped Step in Suppl Work Instruction to Replace/Refurbish Actuator for Centrifugal Charging Pumps.Caused by Personnel Error. Electrican Counseled & Will Be Disciplined	on 930322,maint Electrician Skipped Step in Suppl Work Instruction to Replace/Refurbish Actuator for Centrifugal Charging Pumps.Caused by Personnel Error. Electrican Counseled & Will Be Disciplined	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000482/LER-1993-006, Forwards LER 93-006-00 Re Exposure of Individual in Excess of Applicable Limits in 10CFR20.101	Forwards LER 93-006-00 Re Exposure of Individual in Excess of Applicable Limits in 10CFR20.101
05000482/LER-1993-006-01, :on 930402,hot Particle Picked Up During Filling & Venting of SI Sys Resulted in Exposure Exceeding 10CFR 20.101 Requirements.Operations Qualification Card Checklist Procedures Will Be Revised	on 930402,hot Particle Picked Up During Filling & Venting of SI Sys Resulted in Exposure Exceeding 10CFR 20.101 Requirements.Operations Qualification Card Checklist Procedures Will Be Revised
05000482/LER-1993-007, :on 930413,determined That Surveillance Test Procedure Re RHR Sys Inservice Pump B Test Not Accomplished by 930410.Caused by Lack of Oversight of Surveillance program.Past-due Notice Proceduralized	on 930413,determined That Surveillance Test Procedure Re RHR Sys Inservice Pump B Test Not Accomplished by 930410.Caused by Lack of Oversight of Surveillance program.Past-due Notice Proceduralized	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000482/LER-1993-008, :on 930416,flux Doubling Circuit Blocked Due to Personnel Error Re Misunderstanding of Applicability of Ts. Issued Memo & Initiated Change to TS Bases	on 930416,flux Doubling Circuit Blocked Due to Personnel Error Re Misunderstanding of Applicability of Ts. Issued Memo & Initiated Change to TS Bases	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000482/LER-1993-009, :on 930504,noted That Supervising Operator Erroneously Instructed RO to Reset Steamline LP SI Signal Rather than Block SI Signal.Caused by Personnel Error. Personnel Have Been Directed to Review Event	on 930504,noted That Supervising Operator Erroneously Instructed RO to Reset Steamline LP SI Signal Rather than Block SI Signal.Caused by Personnel Error. Personnel Have Been Directed to Review Event	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1993-010, :on 930508,Mode 3 Entered from Mode 4 W/Both MDAFWPs Rendered Inoperable by Handswitches Being Placed in pull-to-lock.Caused by Failure to Control Work Activity.Mgt Expectations Clarified	on 930508,Mode 3 Entered from Mode 4 W/Both MDAFWPs Rendered Inoperable by Handswitches Being Placed in pull-to-lock.Caused by Failure to Control Work Activity.Mgt Expectations Clarified	10 CFR 50.73(a)(2)(1)
05000482/LER-1993-011, :on 930518,nuclear Plant Instrumentation Sys Axial Flux Difference Limits Were Not Updated W/Ts Due to Inadequate Review of Colr.Initiated WR & Computer Software Mod Request	on 930518,nuclear Plant Instrumentation Sys Axial Flux Difference Limits Were Not Updated W/Ts Due to Inadequate Review of Colr.Initiated WR & Computer Software Mod Request	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)(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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000482/LER-1993-012-01, Forwards LER 93-012-01 Re Noise Event Experienced During heat-up Following Sixth Refueling Outage.Ler Addresses Results of Thermal Expansion Monitoring Program.New Info Noted by Rev Bars	Forwards LER 93-012-01 Re Noise Event Experienced During heat-up Following Sixth Refueling Outage.Ler Addresses Results of Thermal Expansion Monitoring Program.New Info Noted by Rev Bars
05000482/LER-1993-012, :on 930510,reported Unusual Noise Due to Small Frictional Force Release in RCS During heat-up.Implemented Thermal Expansion Monitoring Program in Refuel Viii to Aid in Identification of Locations of Restraint on RCS	on 930510,reported Unusual Noise Due to Small Frictional Force Release in RCS During heat-up.Implemented Thermal Expansion Monitoring Program in Refuel Viii to Aid in Identification of Locations of Restraint on RCS
05000482/LER-1993-013, :on 930809,meteorological Tower de-energized for Mods & Declared Inoperable.Caused by Personnel Error. Meteorological Tower Drawing as-builts Established to Reflect Correct Field Wiring Configuration	on 930809,meteorological Tower de-energized for Mods & Declared Inoperable.Caused by Personnel Error. Meteorological Tower Drawing as-builts Established to Reflect Correct Field Wiring Configuration	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000482/LER-1993-014, :on 900501,essential Svc Water Low Flow Prior to Refueling Outage Occurred.Cause Unknown.Reportability Determination Process Revised,Rers Logged & Entered Into Tracking Database	on 900501,essential Svc Water Low Flow Prior to Refueling Outage Occurred.Cause Unknown.Reportability Determination Process Revised,Rers Logged & Entered Into Tracking Database	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000482/LER-1993-015, :on 930317,breech of Containment Noted During Refueling Operations Due to Inadequate Procedural Guidance. Issued Procedure Change Mi 93-1274	on 930317,breech of Containment Noted During Refueling Operations Due to Inadequate Procedural Guidance. Issued Procedure Change Mi 93-1274	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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000482/LER-1993-016, :on 931101,individual W/Lapsed Fire Brigade Qualification Served as Member of Fire Brigade.Caused by Inadequate Verifying Qualifications Process.Verification Program Consolidated Under Fire Program	on 931101,individual W/Lapsed Fire Brigade Qualification Served as Member of Fire Brigade.Caused by Inadequate Verifying Qualifications Process.Verification Program Consolidated Under Fire Program	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

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