05000361/LER-2008-001

LER-2008-001, Valid actuation of Emergency Feedwater system following Main Feedwater pump trip
Docket Number
Event date:	1-23-2008
Report date:	2-22-2008
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation
3612008001R00 - NRC Website
v • d • e

On 1/23/08, at about 1415 PST, with SONGS Unit 2 in Mode 1 at about 95 percent power, one of two main feedwater (MFW) [SJ] pumps tripped on low oil pressure. Control room operators manually actuated the emergency feedwater system (AFW) [BA] in accordance with plant procedures. The AFW system responded successfully. Control room operators reduced reactor power level to about 65 percent which can be sustained with one normal feedwater pump in operation.

The AFW manual actuation by plant operators was in response to the MFW pump trip. The MFW pump trip was due to overadjustment of the pump lubricating oil pressure regulator. Maintenance workers used the pump overhaul procedure that did not provide sufficient detail to adjust the oil pressure regulator while the pump is on-line.

The oil pressure regulator was correctly adjusted and the Unit was returned to power. SCE is completing a cause evaluation which may identify additional corrective actions.

All systems responded as designed and Control Room personnel acted timely and correctly. Neither the health nor the safety of plant personnel or the public were affected by this occurrence.

No valid actuation of the AFW due to inappropriate procedures has occurred over the last 3 years.

Licensee Event Report

Docket Number

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		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
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05000361/LER-2008-001

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