05000301/LER-1998-001, Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics

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Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics
Person / Time
ML20217P818
Site:	Point Beach
Issue date:	03/04/1998
From:	Dante Johnson WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217P823	List: 05000301/LER-1998-001, Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics 05000301/LER-1998-001-01, :on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 980202
References
NPL-98-0156, NPL-98-156, NUDOCS 9803110116
Download: ML20217P818 (1)
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LER-1998-001, Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function
3011998001R00 - NRC Website
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text

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Electnc POWER COMPANY p

l Point Bectch Nucleu Plant (920)755-2321 6610 Nuclear Rd., Two Rivers, WI 54241 NPL 98-0156 March 4,1998 I

Document Control Desk i

U.S. NUC. LEAR REGULATORY COMMISSION Mail Station PI-137

' Washington, D. C. 20555 Ladies / Gentlemen:

DOCKET 50-301 LICENSEE EVENT REPORT 98-001-00 STEAM GENERATOR VENT MISPOSITIONED DURING PLANT HEATUP '

POINT BEACH NUCI' EAR PLANT. UNIT 2 Enclosed is Licensee Event Report 98-001-00 for Point Beach Nuclear Plant, Unit 2. This report is provided in accordance with 10 CFR 50.73(a)(2)(v), "any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to i

mitigate the consequences of an accident." This report describes a valve mispositioning event which resulted in a steam generator venting steam outside the containment during a plant heatup.

New commitments within the report are indicated in italics.

If you require additional information, please contact us.

Sincerely, I

Tp.

1 Douglas F. Johnson I

Manager,

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Regulatory Services & Licensing

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Enclosure cc:

NRC Resident inspector NRC Regional Administrator NRC Project Manager INPO Support Services llllllllll]lllg[lllg'l 9803110116 900304 PDR ADOCK 05000301 S

PDR A subsWayafMinasm Exm Canwho

Licensee Event Report

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		Reporting criterion
05000266/LER-1998-001, :on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements	on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000301/LER-1998-001, Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics	Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000301/LER-1998-001-01, :on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 980202	on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 980202	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation
05000266/LER-1998-002, :on 980108,failure of High Voltage Station Auxiliary Transformer Occurred Due to Ground in Low Voltage Side Bus Duct.Operability of 1X03 Was Restored & Verified to Be in Operation by Infrared Scan	on 980108,failure of High Voltage Station Auxiliary Transformer Occurred Due to Ground in Low Voltage Side Bus Duct.Operability of 1X03 Was Restored & Verified to Be in Operation by Infrared Scan	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000301/LER-1998-002, Forwards LER 98-002-00 Re Serious Degradation of Reactor Coolant Pump Component Cooling Water Return Line Check Valve Which May Prevent Closure	Forwards LER 98-002-00 Re Serious Degradation of Reactor Coolant Pump Component Cooling Water Return Line Check Valve Which May Prevent Closure
05000301/LER-1998-002-01, :on 980313,discovered Serious Degradation of Reactor Coolant Cooling Water Return Line Check Valve.Caused by Service Related Wear.Valve Was Opened,Repaired & Returned to Service	on 980313,discovered Serious Degradation of Reactor Coolant Cooling Water Return Line Check Valve.Caused by Service Related Wear.Valve Was Opened,Repaired & Returned to Service	10 CFR 50.73(a)(2)(x)
05000266/LER-1998-003-01, Forwards LER 98-003-01 Re Discovery That Flow Rates Were Outside Design Basis of Plant.Rept Revises Corrective Action Commitment Re Replacement of SW Piping to Unit 2 Fan Cooler Motor Heat Exchangers	Forwards LER 98-003-01 Re Discovery That Flow Rates Were Outside Design Basis of Plant.Rept Revises Corrective Action Commitment Re Replacement of SW Piping to Unit 2 Fan Cooler Motor Heat Exchangers	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000301/LER-1998-003-01, :on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement	on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement	10 CFR 50.73(a)(2)(1)
05000301/LER-1998-003, Forwards LER 98-003-00,describing Discovery That Vent Valve from Reactor Coolant Drain Tank Which Had Been Placed on Increased Frequency Surveillance for Stroke Time Was Not Tested in Time Frame Required.New Commitments in Ital	Forwards LER 98-003-00,describing Discovery That Vent Valve from Reactor Coolant Drain Tank Which Had Been Placed on Increased Frequency Surveillance for Stroke Time Was Not Tested in Time Frame Required.New Commitments in Italics
05000301/LER-1998-004, Forwards LER 98-004-00,which Describes Operation of Unit W/Eight Hour Average Reactor Thermal Output in Excess of Licensed Limit.Commitments Made within Ltr Encl	Forwards LER 98-004-00,which Describes Operation of Unit W/Eight Hour Average Reactor Thermal Output in Excess of Licensed Limit.Commitments Made within Ltr Encl	10 CFR 50.73(a)(2)(i)
05000266/LER-1998-004, :on 980114,RCP LO Collection Sys Design Did Not Comply W/App R Section III.0.Caused by Design Mod Conducted in 1981-82 Did Not Rigorously Document Design Basis of Locs. Minor Maint & Matl Repairs Were Initiated & Are Complete	on 980114,RCP LO Collection Sys Design Did Not Comply W/App R Section III.0.Caused by Design Mod Conducted in 1981-82 Did Not Rigorously Document Design Basis of Locs. Minor Maint & Matl Repairs Were Initiated & Are Complete	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000301/LER-1998-004-01, :on 980424,operations W/Reactor Core Power Level Was in Excess of 1518.5 Mwt.Caused by Failure to Return FT-466V Input Parameter to Off Scan.Input FT-446V Was Removed from on Scan at Approx 1452	on 980424,operations W/Reactor Core Power Level Was in Excess of 1518.5 Mwt.Caused by Failure to Return FT-466V Input Parameter to Off Scan.Input FT-446V Was Removed from on Scan at Approx 1452	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(1)
05000266/LER-1998-005, :on 980121,discovered That Control Rod Exercise Test Required Tech Specs Had Not Been Performed as Required. Caused Data Entry Error Into Computerized Maint Planning. Maint Planning Sys Revised	on 980121,discovered That Control Rod Exercise Test Required Tech Specs Had Not Been Performed as Required. Caused Data Entry Error Into Computerized Maint Planning. Maint Planning Sys Revised	10 CFR 50.73(a)(2)(1)
05000266/LER-1998-006, :on 980122,unanticipated Partial Svc Water Sys Isolation During Special Test Occurred.Caused by Inadequate Test Procedure.Procedure PBTP-77 Will Be Archived W/ Documentation of Deficiencies	on 980122,unanticipated Partial Svc Water Sys Isolation During Special Test Occurred.Caused by Inadequate Test Procedure.Procedure PBTP-77 Will Be Archived W/ Documentation of Deficiencies	10 CFR 50.73(a)(2)(iv), System Actuation
05000266/LER-1998-007, :on 980123,determined That Relay Installed in 1P-29 turbine-driven Auxiliary Fdw Pump Low Suction Pressure Trip Circuitry Possessed Incomplete Solder Connection.Caused by Incomplete Solder Connection.Circuitry Replaced	on 980123,determined That Relay Installed in 1P-29 turbine-driven Auxiliary Fdw Pump Low Suction Pressure Trip Circuitry Possessed Incomplete Solder Connection.Caused by Incomplete Solder Connection.Circuitry Replaced
05000266/LER-1998-008, :on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified	on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1998-009, :on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed	on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1)
05000266/LER-1998-010-01, Forwards LER 98-010-01,re Containment Spray Channel Functional Testing.Commitments Made within Ltr,Encl	Forwards LER 98-010-01,re Containment Spray Channel Functional Testing.Commitments Made within Ltr,Encl	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1998-010, :on 980213,inadequate TS Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Verify Switch Position.Bistable Switch Continuity Was Verified within 24 H of Determining Testing Was Inadequate	on 980213,inadequate TS Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Verify Switch Position.Bistable Switch Continuity Was Verified within 24 H of Determining Testing Was Inadequate	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1998-011, :on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed	on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed	10 CFR 50.73(a)(2)(1)
05000266/LER-1998-012, :on 980330,discovered That twenty-seven Containment Penetration Pressure Tests Had Not Been Performed.Caused by Inadequate Program Monitoring & Mgt. Submitted Relief Request & Initiated Root Cause Evaluation	on 980330,discovered That twenty-seven Containment Penetration Pressure Tests Had Not Been Performed.Caused by Inadequate Program Monitoring & Mgt. Submitted Relief Request & Initiated Root Cause Evaluation	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(1)
05000266/LER-1998-013, :on 980416,discovered That Discharge Pressure Indicator Root Valves for Containment Spray Pumps Were Not Shut as Required.Caused by Failure to Maintain Adequate Configuration Control.Shut Subject Root Valves	on 980416,discovered That Discharge Pressure Indicator Root Valves for Containment Spray Pumps Were Not Shut as Required.Caused by Failure to Maintain Adequate Configuration Control.Shut Subject Root Valves
05000266/LER-1998-014, :on 980417,ESF Actuation Automatic Start of Swp Occurred.Caused by Inadequate Procedure That Failed to Provide Info on Expected Start of Swps P32A & P32B.Revised Procedure Iwp 95-048-02 to Provide Necessary Info	on 980417,ESF Actuation Automatic Start of Swp Occurred.Caused by Inadequate Procedure That Failed to Provide Info on Expected Start of Swps P32A & P32B.Revised Procedure Iwp 95-048-02 to Provide Necessary Info
05000266/LER-1998-015, :on 980420,containments Fan Cooler Test Results Were Outside Acceptance Criteria.Cause Is Still Being Evaluated.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed	on 980420,containments Fan Cooler Test Results Were Outside Acceptance Criteria.Cause Is Still Being Evaluated.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000266/LER-1998-015-01, Forwards LER 98-015-01 Re Containment Fan Cooler Test Results Outside Acceptance Criteria.Addl Info Re Corrective Actions Taken,Provided.No New Commitments,Made	Forwards LER 98-015-01 Re Containment Fan Cooler Test Results Outside Acceptance Criteria.Addl Info Re Corrective Actions Taken,Provided.No New Commitments,Made	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1998-016, :on 980427,refueling Sys Interlock Testing Did Not Match That of FSAR Description.Caused by More Literal & Restrictive Interpretation of Description in Fsar.Revised ORT-15 to Include Items Discussed in FSAR Section 9.5	on 980427,refueling Sys Interlock Testing Did Not Match That of FSAR Description.Caused by More Literal & Restrictive Interpretation of Description in Fsar.Revised ORT-15 to Include Items Discussed in FSAR Section 9.5	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)
05000266/LER-1998-017, :on 980512,discovered Deficient Welds on B Loop Rrtd Piping Pipe Whip Restraint.Caused by Support Being Cut & Partially Removed During Plant Mod MR 84-284.Deficient Welds Were Repaired,Inspected & Confirmed to Perform	on 980512,discovered Deficient Welds on B Loop Rrtd Piping Pipe Whip Restraint.Caused by Support Being Cut & Partially Removed During Plant Mod MR 84-284.Deficient Welds Were Repaired,Inspected & Confirmed to Perform	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1998-018, :on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified	on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000266/LER-1998-019, :on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating	on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating
05000266/LER-1998-020, :on 980701,identified Group of Cables in Cable Spreading Room Which May Not Meet Licensee Fire Protection Commitments.Caused by Failure to Fully Implement Certain Requirements.Fire Watch Established Twice Per Shift	on 980701,identified Group of Cables in Cable Spreading Room Which May Not Meet Licensee Fire Protection Commitments.Caused by Failure to Fully Implement Certain Requirements.Fire Watch Established Twice Per Shift
05000266/LER-1998-021, :on 980702,discovered That ASME Section XI Inservice Stroke Tests Were Not Performed on Four Valves within Required Time Frame.Caused by Personnel Error.All 4 Valves Were Subsequently Tested & Found to Be Satisfactory	on 980702,discovered That ASME Section XI Inservice Stroke Tests Were Not Performed on Four Valves within Required Time Frame.Caused by Personnel Error.All 4 Valves Were Subsequently Tested & Found to Be Satisfactory	10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1998-022, :on 980714,TS LCOs for Safety Injection & RHR Operation Occurred.Caused by Unplanned Equipment Inoperability.Duty & Call Superintendent Handbook Procedure Has Been Approved to Provide Operators Guidance	on 980714,TS LCOs for Safety Injection & RHR Operation Occurred.Caused by Unplanned Equipment Inoperability.Duty & Call Superintendent Handbook Procedure Has Been Approved to Provide Operators Guidance	10 CFR 50.73(a)(2)(vi)
05000266/LER-1998-023, :on 980718,circulating Water Pumphouse Roof Was Not IAW Plant Design Basis.Caused by Inadequate Consideration of Structural Requirements.Operability Determination to Evaluate Effect of Condition Was Completed	on 980718,circulating Water Pumphouse Roof Was Not IAW Plant Design Basis.Caused by Inadequate Consideration of Structural Requirements.Operability Determination to Evaluate Effect of Condition Was Completed
05000266/LER-1998-024, :on 980721,inadvertent EDG Start Was Noted. Caused by Installation of Electrical Jumper Wire.Removed Temporary Jumper Wire & Revised Operating Procedure	on 980721,inadvertent EDG Start Was Noted. Caused by Installation of Electrical Jumper Wire.Removed Temporary Jumper Wire & Revised Operating Procedure
05000266/LER-1998-025, :on 980731,determined That Operation of CR Smoke Exhaust fan,W-13C,could Prevent Maintaining Positive Pressure in Cr.Caused by Oversight in Initial Mod Project. Administrative Controls Implemented for Operation of Fan	on 980731,determined That Operation of CR Smoke Exhaust fan,W-13C,could Prevent Maintaining Positive Pressure in Cr.Caused by Oversight in Initial Mod Project. Administrative Controls Implemented for Operation of Fan
05000266/LER-1998-026, :on 980914,determined That Operation of Potential Dilution in Progress Alarm Was Not Controlled IAW Ts.Caused by Failure to Address Plant Heatup Procedures. Revised Procedure OP-1A, Cold Shutdown to Hot Shutdown	on 980914,determined That Operation of Potential Dilution in Progress Alarm Was Not Controlled IAW Ts.Caused by Failure to Address Plant Heatup Procedures. Revised Procedure OP-1A, Cold Shutdown to Hot Shutdown	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000266/LER-1998-027, :on 981013,inadequate TS Surveillance Testing of non-essential Svc Water Isolation Logic,Was Identified. Caused by Failure of Existing Test Procedure to Adequately Consider All Postulated Failure Modes.Procedures Changed	on 981013,inadequate TS Surveillance Testing of non-essential Svc Water Isolation Logic,Was Identified. Caused by Failure of Existing Test Procedure to Adequately Consider All Postulated Failure Modes.Procedures Changed	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000266/LER-1998-028, :on 981113,surveillances Required by Section XI Pressure Test Program Were Missed.Caused by Failure to Take Timely Action on & Implement Corrective Actions for ASME Program Problems.Completed 40 Month Pressure Test	on 981113,surveillances Required by Section XI Pressure Test Program Were Missed.Caused by Failure to Take Timely Action on & Implement Corrective Actions for ASME Program Problems.Completed 40 Month Pressure Test	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000266/LER-1998-029, :on 981227,discovered That Automatic Start Feature for Train B Svc Water Pumps Was Not Functional. Caused by Failure to Recognize Full Significance of Deenergizing Safeguards Relay Racks.Equipment Reenergized	on 981227,discovered That Automatic Start Feature for Train B Svc Water Pumps Was Not Functional. Caused by Failure to Recognize Full Significance of Deenergizing Safeguards Relay Racks.Equipment Reenergized	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000266/LER-1998-030, :on 981124,determined That Safety Related Battery Charges Should Be Reclassified as Hot Shutdown Equipment.Caused by Incorrect Assumption.Mod Will Be Installed to Provide Manual Switches	on 981124,determined That Safety Related Battery Charges Should Be Reclassified as Hot Shutdown Equipment.Caused by Incorrect Assumption.Mod Will Be Installed to Provide Manual Switches	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition

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