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 Start dateReporting criterionEvent description
05000369/LER-2016-00122 March 2016
23 May 2016
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

On March 22, 2016, while Unit 1 was in end of cycle (EOC) refueling outage 1E0C24 (Mode 5), a manual ultrasonic (UT) examination of the Chemical and Volume Control System (NV), Charging Line to the 1A Reactor Coolant System (NC) cold leg confirmed a previously identified circumferential indication associated with weld 1NC1F-1374. The current examination results had shown that the indication had changed since the previous examination during 1E0C23 and concluded that the indication no longer met American Society of Mechanical Engineers (ASME) Section XI Code requirements. This condition is reportable under 10CFR50.73(a)(2)(ii)(A) as a degraded condition.

A specific cause for the condition could not be determined. A metallurgical examination concluded that the cause of the UT result could have been influenced by pre-existing welds associated with a legacy modification.

The affected NV piping on Unit 1 was replaced during refueling outage 1E0C24.

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 Reported lessons learned are incorporated into the licensing process and fed back to industry.

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

05000369/LER-1999-001, Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence16 April 1999
05000369/LER-1998-006, Forwards LER 98-006-00 Re Noncompliance with TS SR 4.6.5.1b.3 Re Flow Passage Insp of Ice Condensers.Item 2 in Planned Corrective Action Subsection Is Only Regulatory Commitment Associated with Rept11 September 1998
05000369/LER-1998-004, Forwards LER 98-004-00 Re Missed Auxiliary Hoist Surveillance Prior to Drive Rod Latching.Event Is Considered to Be of No Significance W/Respect to Health & Safety of Public.Planned C/As in LER Are Regulatory Commitments16 July 1998
05000369/LER-1998-003, Forwards LER 98-003-00,re Inoperability of 1CF-30 During Unit 1 Cycle 12.Hydraulic Actuators for All of the Unit 1 Feedwater Isolation Valves Are Being Replaced W/Pneumatic Actuators During Current Refueling Outage26 June 1998
05000369/LER-1998-002, Forwards LER 98-002-00,concerning Reactor Trip at McGuire Unit 1,per 10CFR50.73(a)(2)(iv)(A)11 March 1998
05000369/LER-1998-001, Forwards LER 98-001-00,re Inadvertent Removal of Inoperable Fwst Level Channel from Tripped Condition & Inadvertent Removal of Cpcs Channel from Start Permissive Condition27 February 1998
05000369/LER-1997-011, Forwards LER 97-011-00,re Inadequate Solid State Protection System Surveillance Testing,Per 10CFR50.73(a)(1) & (D)8 December 1997
05000369/LER-1997-010, Forwards LER 97-010-00,which Describes Potential for Inadequate Margin to Be Maintained W/Regard to RCS Flow Rate Due to Inadequate Analytical Basis for Associated TS21 November 1997
05000369/LER-1997-009, Forwards LER 97-009-00 Re Reactor Trips on Both Units Caused by Loss of non-vital Electrical Bus.Meeting Requested W/ Staff of Nuclear Reactor Regulation to Discuss Event6 October 1997
05000369/LER-1997-008, Forwards LER 97-008-01 Re Inoperability of Auxiliary Feedwater Sys Due to Potential Air Entrapment.Revised LER Documents Ongoing Analysis & Expected Submission of Supplemental Info on 97101111 September 1997
05000369/LER-1997-007, Forwards LER 97-007-00 Re Unit 1 Rt from Zero % Power During Power Range Instrument Testing on 97051411 June 1997
05000369/LER-1996-005, Forwards Suppl Info Re LER 96-005,rev 1 Re TS Required Shutdown of Both Units Due to Failed Surveillance Test of Vital Battery Bank Evcc.Rev Changes Commitment Re Vital Battery Vank Evcc7 May 1997
05000369/LER-1996-003, Forwards LER 96-003-01 Re Concurrent Inoperability of Edgs. Rev Submitted to Provide Addl Info Re Troubleshooting of Components Removed from EDG 1A7 November 1996
05000369/LER-1996-001, Forwards LER 96-001-01 Re Manual Reactor Trip.Rev Due to Determination That Event Not NPRDS Reportable & Not Considered Significant Re Public Health & Safety19 April 1996
05000369/LER-1995-003, Forwards LER 95-003,Rev 1 Re Failure of Turbochargers Associated W/Edgs31 August 1995
05000369/LER-1995-001, Forwards LER 95-001-01 Concerning Manual Trip Initiated as Result of Equipment Failure7 June 1995
05000369/LER-1994-010, Forwards LER 94-010-01 Re Failure to Perform TS Required Surveillance Because Testing Not Specified.Event Considered to Be of No Significance W/Respect to Health & Safety of Public11 May 1995
05000369/LER-1993-003, Forwards LER 93-003-00 Re Problem Investigation Process 0-M93-0198 Covering Past Inoperability of Train B of CR Ventilation Sys Due to Possible Fabrication/Installation Deficiency3 May 1993
05000369/LER-1991-014, Requests Delay for Submitting LER 91-014-00 Re Mispositioning of Valves,Causing Containment Spray & RHR Sys Inoperability from 911111 to 91121111 November 1991
05000369/LER-1989-004, Informs That LER 89-004 Re Steam Generator Tube Rupture on 890307 Will Be Delayed & Submitted No Later than 890420.Addl Calculations Re Leak Rate & Total Steam Leakage Required to Complete Rept6 April 1989
05000369/LER-1987-033, Informs That LER 87-33 Due on 880108 Delayed Due to Unresolved Concerns & Will Be Submitted on 88012930 December 1987
05000369/LER-1987-020, Forwards Revised LER 87-020-01 Re 8-day Inoperability of RHR Pump 1B Due to Addl Analysis of Event & to Correct Wording in Abstract,Provide Expanded Safety Analysis & Discuss Addl Corrective Action16 February 1988
05000369/LER-1987-016, Informs That Unit 1 Did Not Exceed Indicated Rated Thermal Power & That LER 87-016 Will Not Be Submitted or Used in Future22 September 1987
05000369/LER-1987-003, Forwards Rev 1 to LER 87-003 Re Inoperable Containment Air Return Fans Due to Missing Water Curbs.Event Was Subject of Temporary Waiver of Tech Spec Requirements Obtained from NRC on 870130,per15 April 1987
05000369/LER-1986-001, Forwards LER 86-001-00 Re Chemical & Vol Control Sys Pump Inoperable for More than 72 H.Decision to Repair Pump to Stop Leakage Resulted in Pump Being Declared Inoperable4 February 1986
05000369/LER-1985-021, Forwards LER 85-021-01 Re Personnel Exposure,Initially Determined to Be Overexposure.Revised Calculation Indicates No Overexposure Occurred2 August 1985
05000369/LER-1985-003, Advises of Delay of Commitment in LER 85-003 to Reroute Instrument Impulse Lines & to Heat Trace & Insulate by Dec 1985,due to Design & Matl Lead Times.Implementation of Mods Delayed Until 1986 Outage20 August 1985
05000369/LER-1984-030, Suppl to LER 84-030:review Revealed Installation Error That Would Result in Failure of Upper Head Injection Accumulator Discharge Valves to Isolate on Low Level.Analysis of Safety Significance & Encl19 December 1984
05000369/LER-1984-029, Forwards LER 84-029-00 Re High Concentration of Nitrogen in Upper Head Injection (Uhi).Rept Re Improperly Installed Uhi Level Instrumentation Scheduled to Be Submitted by 84120729 November 1984
05000369/LER-1984-025, Forwards LER 84-025-00 Re Open Vent Valve in Containment Spray Sys.Event Initially Determined to Be Not Reportable Due to Minimal Impact on Design Function.Event Determined Reportable Per Insp Rept 50-369/84-299 November 1984
05000369/LER-1984-024, Revised Page 6 to LER 84-024-01,providing Corrective Actions.Relay House Emergency Lighting Improved,Operating & Maint Activities Reviewed for Potential Impact on Offsite Power & Switchyard Computer Will Be Replaced by Mar 19889 November 1984
05000369/LER-1984-022, Discusses LER 84-22 Describing Design Deficiency in Area of Seismic Qualification of Certain Fire Protection & Drain Piping Serving Control Room.Design Mod to Rectify Situation Will Be Completed by 85110110 October 1984
05000369/LER-1983-117, Forwards Rev 1 to LER 83-117/03L-1.Rev Submitted in Same Format as Original,Per NUREG-1022,Suppl 1,Section 14.8. Incident Attributed to Design Oversight.Procedure Revised to Prevent Further Violation of Tech Spec 3.1.3.69 June 1986
05000369/LER-1983-043, Forwards LER 83-043/01T-0 & 83-029/01T-014 July 1983
05000369/LER-1983-016, Forwards LER 83-016/03L-026 April 1983
05000369/LER-1983-015, Forwards LER 83-015/03L-0 & 83-003/03L-022 April 1983
05000369/LER-1983-014, Forwards LER 83-014/03L-015 April 1983
05000369/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl29 April 1983
05000369/LER-1983-012, Forwards LER 83-012/03L-01 April 1983
05000369/LER-1983-011, Forwards LER 83-011/01T-0.Detailed Event Analysis Encl24 March 1983
05000369/LER-1983-010, Forwards LER 83-010/03L-021 March 1983
05000369/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl16 March 1983
05000369/LER-1983-008, Forwards LER 83-008/03L-016 March 1983
05000369/LER-1983-007, Forwards LER 83-007/03L-02 March 1983
05000369/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl2 March 1983
05000369/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl25 February 1983
05000369/LER-1983-004, Forwards LER 83-004/03L-018 February 1983
05000369/LER-1983-003, Forwards LER 83-003/03L-015 February 1983
05000369/LER-1983-002, Forwards LER 83-002/03L-09 February 1983