| | Reporting criterion |
---|
05000413/LER-2008-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
05000334/LER-2008-001 | Control Room Envelope Air Intake During Normal Operation Higher Than Assumed In Design Basis Accident Dose Calculations | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000315/LER-2008-001 | Unit 1 Manual Reactor Trip due to Main Turbine Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000272/LER-2008-001 | Inadvertent Start of an Emergency Diesel Generator During Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000251/LER-2008-001 | Manual Reactor Trip due to High Level in the 4A Steam Generator | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000247/LER-2008-001 | Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of Feedwater Pump Speed Control Malfunction | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000530/LER-2008-001 | Manual Reactor Trip when Removing a Degraded CEDM MG Set from Service | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000457/LER-2008-001 | 2A Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and Growth | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000454/LER-2008-001 | Technical Specification Non-Compliance of Containment Sump Monitor Due to Improper Installation During Oriainal construction | |
05000440/LER-2008-001 | ' Condition Prohibited by Technical Specifications Due to Unrecognized Reactor Core Isolation Cooling Inoperability | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000483/LER-2008-001 | Containment Cooler Inoperability | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000412/LER-2008-001 | Unplanned Actuation of the Auxiliary Feedwater System During Plant Startup | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000374/LER-2008-001 | High Pressure Core Spray System Declared Inoperable Due to Failed Room Ventilation Supply Fan | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
05000323/LER-2008-001 | Reactor Trip Due to Main Electrical Transformer Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000305/LER-2008-001 | Pressurizer PORV and Reactor Coolant System Vent Valves Appendix R Spurious Operation Concern | |
05000271/LER-2008-001 | Crane Travel Limit Stops not Installed as Required by Technical Specifications due to an Inadequate Procedure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000269/LER-2008-001 | Gas Void Found in High Pressure Injection System Suction Piping | |
05000263/LER-2008-001 | | |
05000261/LER-2008-001 | Appendix R Pathway Impassable due to Lock Configuration | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor |
05000361/LER-2008-001 | Valid actuation of Emergency Feedwater system following Main Feedwater pump trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000335/LER-2008-001 | Unattended Ammunition Discovered Inside Protected Area | |
05000456/LER-2008-001 | Technical Specification Non-Compliance Due to Inadequate Design of Auxiliary Feedwater (AF) Tunnel Access Covers Causing AF Valves Within the Tunnel to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000423/LER-2008-001 | Postulated Fire Scenario Results in Unanalyzed Condition - Pressurizer Overfill | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
05000369/LER-2008-001 | Potential Failure of Containment Isolation Valves (CIV) to Remain Fully Closed and Ino erable loner than allowed bCTechnical S ecification 3.6.3. | |
05000220/LER-2008-002 | Manual Reactor Scram Due to Loss of Reactor Pressure Control | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000261/LER-2008-002 | Manual Reactor Trip due to High Turbine Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000270/LER-2008-002 | Main Steam Relief Valves Exceeded Lift Setpoint Acceptance Band 050002 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000305/LER-2008-002 | 5 . Blocked Open Steam Exclusion Door Results in Postulated Inoperability of Safety Systems | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
05000336/LER-2008-002 | Unplanned LCO Entry - Three Charging Pumps Aligned for Injection With the Reactor Coolant System Temperature Less than 300 Degrees F. | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000354/LER-2008-002 | BLOWN lE INVERTER MAIN FUSE WITH ONE EMERGENCY DIESEL GENERATOR INOPERABLE CAUSES LOSS OF CONTROL ROOM EMERGENCY FILTRATION LOSS OF SAFETY FUNCTION | |
05000395/LER-2008-002 | Control Room Normal and Emergency Air Handling Systems Inoperable Due to Pressure Boundary Breach | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000382/LER-2008-002 | Inoperable Steam Generator Narrow Range Level Channels | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000369/LER-2008-002 | 'Energy® BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MGOIVP 112700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.corn August 21, 2008
U.S. Nuclear Regulatory Commission
ATTENTION: Document Control Desk
Washington, D.C. 20555
Subject: Duke Energy Carolinas, LLC
McGuire Nuclear Station, Unit 1
Docket No. 50-369
Licensee Event Report 369/2008-02, Revision 0
Problem Investigation Process No.: M-08-03862
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached
is Licensee Event Report (LER) 369/2008-02, Revision 0,
regarding the Unit 1 Reactor trip on June 26, 2008 due to
the 1B Reactor Coolant Pump Motor trip which was caused by
a failed surge capacitor.
This report is being submitted in accordance with 10 CFR
50.73 (a)(2)(iv)(A). This event is considered to be of no
significance with respect to the health and safety of the
public. There are no regulatory commitments contained in
this LER.
If questions arise regarding this LER, contact Lee A. Hentz
at 704-875-4187.
Very truly yours,
Bruce H. Hamilton
Attachment
www. duke-energy. corn U.S. Nuclear Regulatory Commission
August 21, 2008
Page 2
cc: L. A. Reyes, Regional Administrator
U.S. Nuclear Regulatory Commission, Region II
Sam Nunn Atlanta Federal Center
61 Forsyth Street, SW, Suite 23T85
Atlanta, GA 30303
J. F. Stang, Jr. (Addressee Only)
Senior Project Manager (McGuire)
U.S. Nuclear Regulatory Commission
Mail Stop O-8G9A
Washington, DC 20555
J. B. Brady
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
McGuire Nuclear Station
B. 0. Hall, Section Chief
Radiation Protection Section
1645 Mail Service Center
Raleigh, NC 27699
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVEDBYOMB:NO.3150-0104 EXPIRES: 08/31/2010 (9-2007) Estimated burden per response to comply with this mandatory collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send ' LICENSEE EVENT REPORT (LER) comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@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 (See reverse for required number of means used to impose an information collection does not display a currently valid OMB control digits/characters for each block) number, the NRC may not conduct or sponsor, and a person is not required to respond to,' the information collection. 1, FACILITY NAME 2. DOCKET NUMBER I 3. PAGE 05000- ' 1 8McGuire Nuclear Station, Unit 1 _ 0369' OF .4, TITLE . . Unit 1 Reactor Trip due to the 1B Reactor Coolant Pump Motor Trip which was caused by a
failed Surge Capacitor | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000440/LER-2008-002 | Inoperable Emergency Closed Cooling System Results In Condition Prohibited By Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000454/LER-2008-002 | Technical Specification Non-Compliance Due to Inadequate Design of Auxiliary Feedwater (AF) Tunnel Access Covers Causing AF Valves Within the Tunnel to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000298/LER-2008-002 | Technical Specification Prohibited Condition Due to Safety Relief Valve Test Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000237/LER-2008-002 | Unit 2 High Pressure Coolant Injection System Declared Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
05000272/LER-2008-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000361/LER-2008-002 | Disturbance on the Pacific DC Intertie cause offsite power frequency to dip below operability limits | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
05000362/LER-2008-003 | Missed TS completion time results in TS Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000220/LER-2008-003 | Power Supplies for Drywell Pressure Indication not Qualified for Required Post-Accident Operating Duration | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000529/LER-2008-003 | Technical Specification - Limiting Condition for Operation 3.0.3 for Greater Than 1 Hour | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000293/LER-2008-003 | | |
05000263/LER-2008-003 | | |
05000423/LER-2008-003 | Automatic Reactor Trip During Shutdown for Refueling Outage 3R12 ., | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
05000251/LER-2008-003 | . Class 1 Weld Leak Due to Fatigue and Completion of Technical Specification Required Shutdown | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
05000282/LER-2008-003 | Loss of AFW Safety Function and Condition Prohibited by Technical Specifications Due to Mispositioned Isolation Valve | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
05000286/LER-2008-003 | Automatic Actuation of Emergency Diesel Generator 33 During Surveillance Testing Caused by .Inadvertent Actuation of the Undervoltage Sensing Circuit on 480 Volt AC Safeguards Bus 5A | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
05000361/LER-2008-003 | Disturbance on the Pacific DC Intertie cause offsite power frequency to dip below operability limits | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
05000305/LER-2008-003 | Door Bottom Seal Failure Results in Inoperability of Control Room Ventilation System | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |