05000263/LER-1992-012-01, Forwards LER 92-012-01 Initially Re Failure to Include Manual Valves in Section XI Testing.Results of Review & Other ASME Section XI Program Discrepancies,Noted in Insp Rept 50-263/92-10 Warranted Rev to LER

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Forwards LER 92-012-01 Initially Re Failure to Include Manual Valves in Section XI Testing.Results of Review & Other ASME Section XI Program Discrepancies,Noted in Insp Rept 50-263/92-10 Warranted Rev to LER
Person / Time
ML20127L376
Site:	Monticello
Issue date:	11/19/1992
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20127L381	List: 05000263/LER-1992-012, :on 920824,six RHR Svc Water Valves,Two ESW Valves & Two EDG Emergency Svc Water Valves,Noted During NRC Insp,Not Included in ASME Section XI Program.Caused by Code Misinterpretation.All Components Will Be Tested 05000263/LER-1992-012-01, Forwards LER 92-012-01 Initially Re Failure to Include Manual Valves in Section XI Testing.Results of Review & Other ASME Section XI Program Discrepancies,Noted in Insp Rept 50-263/92-10 Warranted Rev to LER
References
NUDOCS 9211240070
Download: ML20127L376 (1)
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LER-1992-012, Forwards LER 92-012-01 Initially Re Failure to Include Manual Valves in Section XI Testing.Results of Review & Other ASME Section XI Program Discrepancies,Noted in Insp Rept 50-263/92-10 Warranted Rev to LER

Event date:
Report date:
2631992012R01 - NRC Website
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Northem States Power Company 414 Wicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330 550G November 19, 1992 Report Required by 10 CFR Part 50, Section 50,73 U.S. Nuclear Regulatory Cammission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Failure to Include Manual Valves in Section XI Testinr. Caused by Interpretation of ASME ReautremenLg c

The supplemental Licensee Ev nt Report for this occurrence is attached.

The original report for this event (Monticello Licensee Event Report 92-012 00, dated September 23, 1992) identified an action to be completed that involved a review of our ASME Section XI Inservice Testing Program to determine if thers were other components that should have been included in the program but were not.

The results of this review, as well as other ASME Section XI prograr discrepancies identified in NRC Inspection Report 50-263/92010, dat4:d September 30,199', were significant enough to warrant revision of the original event reporu.

Please contact us if you require further information.

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Thomas Parker Manager Nuc1 car Support Services c:

Regional Administrator - III NRC Sr Resident Inspector, NRC NRR Project Manager, NRC State of Minnesota, Attu: Kris Sanda Attachment 9211240070 921119

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PDR ADOCK 05000263

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Licensee Event Report

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		Reporting criterion
05000263/LER-1992-008, :on 920624,1-inch Conduit Fire Barrier Declared Inoperable & on 920831,4-inch Conduit Fire Barrier Declared Inoperable Based on Review of NRC Bulletin 92-001 & Suppl 1. Continuous Fire Watch Established	on 920624,1-inch Conduit Fire Barrier Declared Inoperable & on 920831,4-inch Conduit Fire Barrier Declared Inoperable Based on Review of NRC Bulletin 92-001 & Suppl 1. Continuous Fire Watch Established	10 CFR 50.73(a)(2)(1)
05000263/LER-1992-009, :on 920728,HPCI Declared Inoperable Due to Concerns That Sys Would Not Perform as Described in FSAR During Atws.Caused by Inadequate Consendate Storage Tank Inventory.Updated FSAR Will Be Revised	on 920728,HPCI Declared Inoperable Due to Concerns That Sys Would Not Perform as Described in FSAR During Atws.Caused by Inadequate Consendate Storage Tank Inventory.Updated FSAR Will Be Revised
05000263/LER-1992-010-01, Forwards LER 92-010-01,modifying Root Cause of First Event, Based on Investigation Delineated in LER 92-012-00	Forwards LER 92-010-01,modifying Root Cause of First Event, Based on Investigation Delineated in LER 92-012-00
05000263/LER-1992-010, :on 920725,discovered That Four Valves Used to Mitigate Consequences of HELB Not Included in ASME Section XI Testing Program.Caused by Failure to Include Emergency Svc Water Valves in Aop.Aops Revised	on 920725,discovered That Four Valves Used to Mitigate Consequences of HELB Not Included in ASME Section XI Testing Program.Caused by Failure to Include Emergency Svc Water Valves in Aop.Aops Revised
05000263/LER-1992-011-01, :on 920922,determined That Existing Elevator Could Have Damaged Safe Shutdown Equipment During Design Bases Seismic Event.Caused by Inadequate Original Design.New Elevator Will Be Installed	on 920922,determined That Existing Elevator Could Have Damaged Safe Shutdown Equipment During Design Bases Seismic Event.Caused by Inadequate Original Design.New Elevator Will Be Installed
05000263/LER-1992-012-01, Forwards LER 92-012-01 Initially Re Failure to Include Manual Valves in Section XI Testing.Results of Review & Other ASME Section XI Program Discrepancies,Noted in Insp Rept 50-263/92-10 Warranted Rev to LER	Forwards LER 92-012-01 Initially Re Failure to Include Manual Valves in Section XI Testing.Results of Review & Other ASME Section XI Program Discrepancies,Noted in Insp Rept 50-263/92-10 Warranted Rev to LER
05000263/LER-1992-012, :on 920824,six RHR Svc Water Valves,Two ESW Valves & Two EDG Emergency Svc Water Valves,Noted During NRC Insp,Not Included in ASME Section XI Program.Caused by Code Misinterpretation.All Components Will Be Tested	on 920824,six RHR Svc Water Valves,Two ESW Valves & Two EDG Emergency Svc Water Valves,Noted During NRC Insp,Not Included in ASME Section XI Program.Caused by Code Misinterpretation.All Components Will Be Tested	10 CFR 50.73(a)(2)(1)
05000263/LER-1992-013-02, :on 920930,identified That Fire Barrier Damper Had Not Been Inspected as Required by Ts.Caused by Failure to Include Damper in Surveillance Program.Fire Watch Established & Damper Inspected	on 920930,identified That Fire Barrier Damper Had Not Been Inspected as Required by Ts.Caused by Failure to Include Damper in Surveillance Program.Fire Watch Established & Damper Inspected	10 CFR 50.73(a)(2)(1)
05000263/LER-1992-013-01, :on 920930,identified That Fire Barrier Damper Had Not Been Inspected as Required by Ts.Caused by Failure to Perform Surveillance.Surveillance Procedure Revised to Include Damper for Insp Every 18 Months	on 920930,identified That Fire Barrier Damper Had Not Been Inspected as Required by Ts.Caused by Failure to Perform Surveillance.Surveillance Procedure Revised to Include Damper for Insp Every 18 Months	10 CFR 50.73(a)(2)(1)
05000263/LER-1992-014-01, :on 921003,automatic Transfer of High Pressure Coolant Injection Suction from Condensate Storage Tanks to Suppression Pool Occurred Due to Inadvertent Jarring of Level Switch.Hpci & RCIC Returned to Normal	on 921003,automatic Transfer of High Pressure Coolant Injection Suction from Condensate Storage Tanks to Suppression Pool Occurred Due to Inadvertent Jarring of Level Switch.Hpci & RCIC Returned to Normal	10 CFR 50.73(a)(2)(iv), System Actuation
05000263/LER-1992-014, :on 921003,automatic Transfer of HPCI Suction from Condensate Storage Tanks to Suppression Pool Occurred. Caused by Inadvertent Jarring of Level Switch.Hpci & Core Isolation Cooling Sys Returned to Normal	on 921003,automatic Transfer of HPCI Suction from Condensate Storage Tanks to Suppression Pool Occurred. Caused by Inadvertent Jarring of Level Switch.Hpci & Core Isolation Cooling Sys Returned to Normal
05000263/LER-1992-015, :on 921021,determined That CR Ventilation & Emergency Filtration Train Radiation Detectors Outside Design Basis.Caused by Design Deficiency During Initial CR Design.Mod to Initiate Transfer Installed	on 921021,determined That CR Ventilation & Emergency Filtration Train Radiation Detectors Outside Design Basis.Caused by Design Deficiency During Initial CR Design.Mod to Initiate Transfer Installed
05000263/LER-1992-016-01, Forwards LER 92-016-01 Re Failure of Emergency Svc Water Check Valves to Seat Due to Accumulation of Silt.Evaluation Will Be Performed to Determine Feasibility of Replacing Check Valves ESW-13 & ESW-14	Forwards LER 92-016-01 Re Failure of Emergency Svc Water Check Valves to Seat Due to Accumulation of Silt.Evaluation Will Be Performed to Determine Feasibility of Replacing Check Valves ESW-13 & ESW-14
05000263/LER-1992-016, :on 921107,two Check Valves in Esws Failed to Seat Properly.Cause Unknown.Check Valves Will Be Inspected, Replaced or Repaired & Supplemental Rept W/Results Will Be Submitted	on 921107,two Check Valves in Esws Failed to Seat Properly.Cause Unknown.Check Valves Will Be Inspected, Replaced or Repaired & Supplemental Rept W/Results Will Be Submitted	10 CFR 50.73(a)(2)(1)
05000263/LER-1992-017, :on 921109,non-safety Related Relays Could Prevent Both EDG from Performing Intended Function Due to Inadequate Design.Safety Evaluation Performed to Assess Operation of EDG W/Power Monitoring Relay	on 921109,non-safety Related Relays Could Prevent Both EDG from Performing Intended Function Due to Inadequate Design.Safety Evaluation Performed to Assess Operation of EDG W/Power Monitoring Relay
05000263/LER-1992-018, :on 921113,determined That APRM Scram Setpoint Set So Scram Could Occur Outside Analyzed Conditions.Caused by Failure to Implement Updated SAR Requirements.Gain Setting Adjusted	on 921113,determined That APRM Scram Setpoint Set So Scram Could Occur Outside Analyzed Conditions.Caused by Failure to Implement Updated SAR Requirements.Gain Setting Adjusted	10 CFR 50.73(a)(2)

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