05000301/LER-1992-007, Forwards LER 92-007-00 for Point Beach Nuclear Plant Re Automatic Starting of Emergency DG G02 Following de-energization of 4,160 Volt Safeguards Bus

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Forwards LER 92-007-00 for Point Beach Nuclear Plant Re Automatic Starting of Emergency DG G02 Following de-energization of 4,160 Volt Safeguards Bus
Person / Time
ML20127N134
Site:	Point Beach
Issue date:	11/23/1992
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20127N137	List: 05000301/LER-1992-007, Forwards LER 92-007-00 for Point Beach Nuclear Plant Re Automatic Starting of Emergency DG G02 Following de-energization of 4,160 Volt Safeguards Bus 05000301/LER-1992-007-01, :on 921026,inadvertent ESF Actuation Occurred as Result of Improper Surveillance Testing.Caution Label Installed in Vicinity of Undervoltage Relay Test Button
References
CON-NRC-92-137 VPNPD-92-358, NUDOCS 9212010005
Download: ML20127N134 (1)
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LER-1992-007, Forwards LER 92-007-00 for Point Beach Nuclear Plant Re Automatic Starting of Emergency DG G02 Following de-energization of 4,160 Volt Safeguards Bus

Event date:
Report date:
3011992007R00 - NRC Website
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Wisconsin L Electnc POMER COMPANY ni w ucun Po em Xe wous.ee vmx'i giamt nas VPHPD 358 NRC-92-137 i

November 23, 1992 1

Document Control Desk i

U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen DOCKET S0-301 LICENSEE EVENT REPORT 92-007-00 INADVERTENT ESF ACTUATION _AS A RESULT OF IMPROPER SURVEILLANCE TESTIl{Q POINT BEACH NUCLEAR PLANT. UNIT 2 Enclosed is Licensee Event Report 92-007-00 for Point Beach Nuclear Plant, Unit 2.

This report is being submitted in accordance with the requirements of 10 CFR 50.73(2) (iv), "Any event or condition i

that resulted in manual or automatic actuation of any Engineered Safety Feature (ESP), including the Reactor Protection System (RPS)."

This report describes the automatio starting of emergency i

diesel generator G02 following the de-energization of a 4160= volt-safeguards bus.

The safeguards bus was de-energized as a-result of-a personnel error that occurred during the performance of monthly-surveillance testing.

Please contact us if there'are any questions.

Sincerely,

<W/h

Bob Link Vice President Nuclear Power FDP/jg-Enclosure cc:

NRC' Regional Administrator, Region _III NRC Resident-Inspector f

92120100051921123-ADOCK.'OSOOg1

, DR-AsaWhntliimhiDwan Giquatsw -

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Licensee Event Report

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		Reporting criterion
05000266/LER-1992-001, :on 920120,automatic Runback of Unit 1 Turbine Occurred.Caused by Improper Installation of Interlock Jumper by Two Personnel Performing post-maint Testing.Electricians Counseled	on 920120,automatic Runback of Unit 1 Turbine Occurred.Caused by Improper Installation of Interlock Jumper by Two Personnel Performing post-maint Testing.Electricians Counseled	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000301/LER-1992-001, Forwards LER 92-001-00.Rept Initially Submitted on 920317 as Improperly Numbered LER 92-003-00.Requests That LER 92-003-00 Be Withdrawn & Replaced W/Encl	Forwards LER 92-001-00.Rept Initially Submitted on 920317 as Improperly Numbered LER 92-003-00.Requests That LER 92-003-00 Be Withdrawn & Replaced W/Encl	10 CFR 50.73(a)(2)(i)
05000301/LER-1992-001-01, :on 920217,one Channel of Overtemp Delta T Protection Rendered Inoperable During Performance of power- Range Axial Offset Calibr.Caused by Personnel Error.Channel Restored to Svc & Procedure Revised	on 920217,one Channel of Overtemp Delta T Protection Rendered Inoperable During Performance of power- Range Axial Offset Calibr.Caused by Personnel Error.Channel Restored to Svc & Procedure Revised	10 CFR 50.73(c)(2)(1)
05000266/LER-1992-002, Forwards Response to NRC 921116 Request for Info Re CCW Sys & Ccvs,Per LER 92-002-00 & GL 83-28.Info Covers Classification of Auxiliary Sys Necessary to Ensure Safe Plant Shutdown	Forwards Response to NRC 921116 Request for Info Re CCW Sys & Ccvs,Per LER 92-002-00 & GL 83-28.Info Covers Classification of Auxiliary Sys Necessary to Ensure Safe Plant Shutdown
05000301/LER-1992-002-01, :on 920828,discovered That CCW Sys Isolation Valves LW-63 & 64 Not Capable of Performing Intended Function.Caused by Inadequate Design Review.Ccw Sys Boundary Outside Containment Reestablished	on 920828,discovered That CCW Sys Isolation Valves LW-63 & 64 Not Capable of Performing Intended Function.Caused by Inadequate Design Review.Ccw Sys Boundary Outside Containment Reestablished	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1992-003, Comments on Preliminary Draft of NUREG/CR-4674, Precursors to Potential Severe Core Damage Accidents:1992,Status Rept. Section B.14 of Draft NUREG Based on Unit 2 of LER 92-003	Comments on Preliminary Draft of NUREG/CR-4674, Precursors to Potential Severe Core Damage Accidents:1992,Status Rept. Section B.14 of Draft NUREG Based on Unit 2 of LER 92-003
05000301/LER-1992-003, :on 920918,Train a of Unit 2 Containment Spray Sys Rendered Inoperable.Caused by Spray Pump Impeller Suction Blocked by Foam Rubber Plug.Containment Spray Sys & Safety Injection Sys Remained Operable	on 920918,Train a of Unit 2 Containment Spray Sys Rendered Inoperable.Caused by Spray Pump Impeller Suction Blocked by Foam Rubber Plug.Containment Spray Sys & Safety Injection Sys Remained Operable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000301/LER-1992-003-02, :on 920918,abnormal Noise Heard Emanating from Containment Spray Pump P-14A During Test IT-06 Due to Pump Impeller Being Blocked.Pump Disassembled & Foam Rubber Plug Removed.Pump Reassembled & Declared Operable	on 920918,abnormal Noise Heard Emanating from Containment Spray Pump P-14A During Test IT-06 Due to Pump Impeller Being Blocked.Pump Disassembled & Foam Rubber Plug Removed.Pump Reassembled & Declared Operable
05000266/LER-1992-003-01, :on 920428,EDG G01 Automatically Started When Potential Transformer for Supplied Bus Deenergized.Caused by Personnel Error.Addl Loads on Bus 1B04 Secured & Isolated & Buses 1B03 & 1B04 Reenergized	on 920428,EDG G01 Automatically Started When Potential Transformer for Supplied Bus Deenergized.Caused by Personnel Error.Addl Loads on Bus 1B04 Secured & Isolated & Buses 1B03 & 1B04 Reenergized	10 CFR 50.73(a)(2)(iv), System Actuation
05000266/LER-1992-004, :on 920515,improper Sequencing of Emergency Safety Features Occurred.Caused by Faulty Relay for 1-W1B1.Time Delay Relay Replaced & Adjusted to within Acceptance Criteria	on 920515,improper Sequencing of Emergency Safety Features Occurred.Caused by Faulty Relay for 1-W1B1.Time Delay Relay Replaced & Adjusted to within Acceptance Criteria	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1992-004-01, :on 920515,discovered Improper Sequencing of Esf.Caused by Failure to Identify Need for Acceptance Criteria for Shared Components.Test Procedure ORT-3 Revised	on 920515,discovered Improper Sequencing of Esf.Caused by Failure to Identify Need for Acceptance Criteria for Shared Components.Test Procedure ORT-3 Revised	10 CFR 50.73(a)(2)(i)
05000301/LER-1992-004-02, :on 920926,reactor Manually Tripped During Hot CR Drop Testing Due to Unexpected CR Buttom Indications. Caused by Lack of Communication.Cr Testing Terminated. Procedure Resp 1.1 Will Be Revised	on 920926,reactor Manually Tripped During Hot CR Drop Testing Due to Unexpected CR Buttom Indications. Caused by Lack of Communication.Cr Testing Terminated. Procedure Resp 1.1 Will Be Revised	10 CFR 50.73(a)(2)(iv), System Actuation
05000266/LER-1992-005, :on 920527,during Performance of Refueling Procedure Temp cool-down Limit Was Exeeded Per Ts.Caused by Personnel Error.Need to Perform SG Crevice Flushing in Future Will Be Assessed	on 920527,during Performance of Refueling Procedure Temp cool-down Limit Was Exeeded Per Ts.Caused by Personnel Error.Need to Perform SG Crevice Flushing in Future Will Be Assessed	10 CFR 50.73(a)(2)(1)
05000301/LER-1992-005-01, :on 921022,SG Tube Degradation Revealed.Tubes Plugged	on 921022,SG Tube Degradation Revealed.Tubes Plugged
05000301/LER-1992-005, Forwards LER 92-005-00,per TS 15.4.2.A.7(a) After Each ISI, Number of Tube Plugged or Repaired in Each SG Shall Be Reported to Commission as Soon as Practical. Rept Also Reported Per TS Table 15.4.2-1 & TS 15.4.2.A.7(b)	Forwards LER 92-005-00,per TS 15.4.2.A.7(a) After Each ISI, Number of Tube Plugged or Repaired in Each SG Shall Be Reported to Commission as Soon as Practical. Rept Also Reported Per TS Table 15.4.2-1 & TS 15.4.2.A.7(b)	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1992-006, :on 920531,SG a MSIV IMS-2018 Failed to Fully Close During Initial Test.Caused by Galling on Both Ends of Valve Shaft Due to Mispositioning of Gaskets.Msiv Instructions Will Be Updated & Revised	on 920531,SG a MSIV IMS-2018 Failed to Fully Close During Initial Test.Caused by Galling on Both Ends of Valve Shaft Due to Mispositioning of Gaskets.Msiv Instructions Will Be Updated & Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000301/LER-1992-006, Forwards LER 92-006-00 for Point Beach Nuclear Plant,Unit 2, Re Inadvertent Actuation of non-safeguards Equipment Lockout	Forwards LER 92-006-00 for Point Beach Nuclear Plant,Unit 2, Re Inadvertent Actuation of non-safeguards Equipment Lockout
05000301/LER-1992-006-01, :on 921020,inadvertent ESF Actuation Occurred as Result of as-built Wire Tracing & Disconnected Output from 2B04 Lockout Relay.Cabling Reconnected on 921020	on 921020,inadvertent ESF Actuation Occurred as Result of as-built Wire Tracing & Disconnected Output from 2B04 Lockout Relay.Cabling Reconnected on 921020
05000301/LER-1992-007, Forwards LER 92-007-00 for Point Beach Nuclear Plant Re Automatic Starting of Emergency DG G02 Following de-energization of 4,160 Volt Safeguards Bus	Forwards LER 92-007-00 for Point Beach Nuclear Plant Re Automatic Starting of Emergency DG G02 Following de-energization of 4,160 Volt Safeguards Bus
05000266/LER-1992-007, :on 920818,RPS Engineered Safeguards Sys & Process Instrumentation within Cabinets Declared Inoperable. Caused by Friction Clip Assemblies Loaded Beyond Yield Point.Cabinet Bolting Upgraded	on 920818,RPS Engineered Safeguards Sys & Process Instrumentation within Cabinets Declared Inoperable. Caused by Friction Clip Assemblies Loaded Beyond Yield Point.Cabinet Bolting Upgraded	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000301/LER-1992-007-01, :on 921026,inadvertent ESF Actuation Occurred as Result of Improper Surveillance Testing.Caution Label Installed in Vicinity of Undervoltage Relay Test Button	on 921026,inadvertent ESF Actuation Occurred as Result of Improper Surveillance Testing.Caution Label Installed in Vicinity of Undervoltage Relay Test Button
05000266/LER-1992-008-01, :on 921005,automatic Turbine Trip & Reactor Trip Occurred.Caused by B Train Solenoid Vent Valve Being Open.Thorough Review of PC-11,Part 2 Performed.Vent Valve Replaced & Retested Satisfactorily	on 921005,automatic Turbine Trip & Reactor Trip Occurred.Caused by B Train Solenoid Vent Valve Being Open.Thorough Review of PC-11,Part 2 Performed.Vent Valve Replaced & Retested Satisfactorily	10 CFR 50.73(a)(2)(iv), System Actuation
05000266/LER-1992-009-01, Forwards Suppl LER-92-009-01 Re Ccws Surge Tank Vent Valves Being Outside Design Basis.Rept Provided to Rept Final Corrective Actions to Resolve Condition	Forwards Suppl LER-92-009-01 Re Ccws Surge Tank Vent Valves Being Outside Design Basis.Rept Provided to Rept Final Corrective Actions to Resolve Condition
05000266/LER-1992-009, :on 921012,identified That CCW Sys Surge Tank Vent Valves 1&2cc-00017 Did Not Meet Design Basis.Caused by Oversight During Original Design of CCW Sys.Design Will Be Evaluated & Modified If Necessary	on 921012,identified That CCW Sys Surge Tank Vent Valves 1&2cc-00017 Did Not Meet Design Basis.Caused by Oversight During Original Design of CCW Sys.Design Will Be Evaluated & Modified If Necessary	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1992-010, :on 921208,discovered That Inservice Tests IT-40 & IT-45 Re SI Valves (Quarterly) Could Lead to Isolation of All Available Flow Paths for SI Pumps.Pra Performed.Issue Also Reported Per Part 21	on 921208,discovered That Inservice Tests IT-40 & IT-45 Re SI Valves (Quarterly) Could Lead to Isolation of All Available Flow Paths for SI Pumps.Pra Performed.Issue Also Reported Per Part 21	10 CFR 50.73(a)(2)(v), Loss of Safety Function

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