05000482/LER-2010-014

02-04-2011

On December 6, 2010, at 0948 Central Standard Time (CST), Wolf Creek Generating Station (WCGS) entered Mode 3 in accordance with Required Action H.1 of Technical Specification (TS) 3.8.1, "AC Sources - Operating." The TS required shutdown was due to inoperability of the Train 'A' emergency diesel generator (EDG), which was removed from service on November 29, 2010, for planned maintenance.

The cause of the TS required shutdown of WCGS was the inability to return the EDG to operable status within the seven-day completion time of Required Action 8.4.2.2 of TS 3.8.1.

The extended out-of-service time was due to excessive emergent work activities, including a drop in peak firing pressure in one cylinder during the surveillance run of the EDG.

The Command and Control structure used for seven-day TSEOs was changed to improve management of work delays and effectively control emergent work.

LER-2010-004, Technical Specification Required Shutdown Due to Inadequate Planning Resulting in Extended Emergency Diesel Generator Inoperability
Docket Number
Event date:	12-06-2010
Report date:	02-04-2011
Reporting criterion:	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
4822010004R00 - NRC Website
v • d • e

This event is of low safety significance. The Train 'B' EDG, the off-site diesel gensets used for peak loading located at the Sharpe Station, and offsite power were available during the inoperability of the Train 'A' EDG.

OPERATING EXPERIENCE/PREVIOUS EVENTS

due to water leakage from a buried portion of the Train 'A' Essential Service Water (ESW) system [EllS Code: BI]. Subsequent Engineering evaluation of the through-wall leak concluded that the ESW system was capable of performing its design safety function.

Licensee Event Report

Docket Number

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		Reporting criterion
05000220/LER-2010-001	Reactor Scram Due to Inadequate Post Maintenance Testing	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000410/LER-2010-001	Reactor Scram Due to Inadvertent Actuation of the Redundant Reactivity Control System During Maintenance	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000395/LER-2010-001	Reactor Building Cooling Units Reduced Air Flow Rate Below Technical Specification Limits	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000382/LER-2010-001	Spent Fuel Pool Cooling Single Failure	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000374/LER-2010-001	High Pressure Core Spray System Declared Inoperable Due to Failed Room Ventilation Control Relay	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000373/LER-2010-001	Unauthorized Individual Gained Access to the Protected Area.
05000370/LER-2010-001	Loose connection in a panel board serving a Solid State Protection System Train concurrent with redundant train maintenance could have prevented fulfillment of a safety function.	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000261/LER-2010-001	Emergency Diesel Generator Inoperable in Excess of Technical Specifications Allowed Completion Time	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2010-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-2010-001	Potential Loss of Safety Function Due to a Service Water Pump Shaft Coupling Failure	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
05000266/LER-2010-001	Engineered Safety Features Steam Line Pressure Dynamics Modules Discovered Outside of Technical Specification Values	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000306/LER-2010-001	Unit 2 Turbine Trip during Reactor Shutdown Resulting in a Reactor Scram	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000305/LER-2010-001	Safety Injection Pump Recirculation Line Isolation Results in Violation of Technical Specifications
05000298/LER-2010-001	Cooper Nuclear Station 05000298 1 of 4	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000269/LER-2010-001	Standby Shutdown Facility Letdown Line Orifice Strainer Blocked by Valve Gasket Material	10 CFR 50.73(a)(2)(i)(b)
05000282/LER-2010-001	Unanalyzed Condition Due to Postulated High Energy Line Break On Cooling Water System	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000277/LER-2010-001	Multiple Slow Control Rods Results in Condition Prohibited by Technical Specifications	10 CFR 50.73(a)(2)(i)
05000361/LER-2010-001	Broken Manual Valve Prevents Timely Condensate Storage Tank Isolation	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000483/LER-2010-001	Emergency Core Cooling System MODE 4 Operating Practices Prohibited by current Technical Specification 3.5.3	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000498/LER-2010-001	Unit Shutdown Required by Technical Specifications	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000316/LER-2010-001	Valid Actuation of Auxiliary Feedwater System in Response to Valid Steam Generator Low-Low Levels	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000321/LER-2010-001	Corrosion Induced Bonding Results in Safety Relief Valve Lift Setpoint Drift	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-2010-001	Millstone Power Station Unit 2 Reactor Trip	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000413/LER-2010-001	Technical Specification Violation Associated with Failure to Perform Offsite Circuit Verification	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000440/LER-2010-001	Invalid Isolation Signal Results in Shutdown Cooling Interruption	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000424/LER-2010-001	Breaker Failure Results in I B Train Containment Cooling System Being Declared Inoperable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000416/LER-2010-001	Automatic Reactor Scram On Decreasing Reactor Water Level Due To Inadvertent Reactor Feed Pump Trip	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000249/LER-2010-001	OPRM Power Supply Failure during Maintenance Results in Unit 3 Automatic Reactor Scram	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000251/LER-2010-001	Two Shutdown Bank Rods Were Dropped from Fully Withdrawn Position	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation
05000261/LER-2010-002	Plant Trip due to Electrical Fault	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000255/LER-2010-002	Condition that Could Have Prevented the Fulfillment of a Safety Function	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000335/LER-2010-002	Opened ECCS Boundary Door in Violation of Identified Compensatory Measures	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000334/LER-2010-002	270 Degree Circumferential Flaw Found on Residual Heat Removal System Drain Valve Socket Weld	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
05000316/LER-2010-002	Containment Divider Barrier Seal Mounting Bolts Not Properly Installed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000250/LER-2010-002	Fuel Transfer Pump Failure Renders 3B Emergency Diesel Generator Inoperable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000269/LER-2010-002	Manual Reactor Trip due to 1A1 and 1A2 Reactor Coolant PumDHigh Vibration Indication	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000315/LER-2010-002	Manual Auxiliary Feedwater Actuation in Response to Main Feedpump Failure	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000271/LER-2010-002	Inoperability of Main Steam Safety Relief Valves due to Degraded Thread Seals	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000277/LER-2010-002	Improperly Fastened Rod Hanger Results in Inoperable Subsystem of Emergency Service Water	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000413/LER-2010-002	Discovery of Reactor Coolant System Pressure Boundary Leak at Thermowell 1NCTW5850 Seal Weld.
05000282/LER-2010-002	Postulated Flooding of Unit 1 Fuel Oil Transfer Pump Motor Starters Could Have Resulted In Reduced Fuel Oil Inventory
05000414/LER-2010-002	Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 803-701-3221 fax December 15, 2010 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Subject:�Duke Energy Carolinas, LLC (Duke Energy) Catawba Nuclear Station, Unit 2 Docket No. 50-414 Licensee Event Report 414/2010-002 Pursuant to 10 CFR 50.73(a)(1) and (d), attached is Licensee Event Report 414/2010-002, Revision 0 entitled, "Technical Specification Violation Involving Mode Change with Inoperable Auxiliary Feedwater System Train Due to Closed Pump Discharge Valves". This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B). There are no regulatory commitments contained in this letter or its attachment. This event is considered to be of no significance with respect to the health and safety of the public. If there are any questions on this report, please contact L.J. Rudy at (803) 701-3084. Sincerely, faius4- A James R. Morris LJR/s Attachment www.duke-energy.corn (14 Document Control Desk Page 2 December 15, 2010 xc (with attachment): L.A. Reyes Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J.H. Thompson (addressee only) NRC Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto, Ill NRC Senior Resident Inspector Catawba Nuclear Station INPO Records Center 700 Galleria Place Atlanta, GA 30339-5957 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010) Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send commentsLICENSEE EVENT REPORT (LER) regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to infocollectssesource@nre.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(See reverse for required number of to impose an information collection does not display a currently valid OMB control number, the NRCdigits/characters for each block) may not conduct or sponsor, and a person is not required to respond to, the info(mation collection. 1.. FACILITY NAME 2. DOCKET NUMBER I3. PAGE Catawba Nuclear Station, Unit 2 05000414 1 OF 7 4. TITLE Technical Specification Violation Involving Mode Change with Inoperable Auxiliary Feedwater System Train Due to Closed Pump Discharge ValvesD •	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000306/LER-2010-002	Unit 2 Turbine Shutdown Due To the Loss of a Main Feed Water Pump That Resulted in a Reactor Scram	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000440/LER-2010-002	Piping Leak Results in Condition Prohibited by Technical Specifications	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000382/LER-2010-002	Main Feedwater Isolation Valve B exceeded allowed outage time due to tubing connection failure	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000370/LER-2010-002	ref Energy® REGIS T. REPKO Vice President McGuire Nuclear Station Duke Energy MGO1VP / 12700 Hagers Ferry Rd. Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis.repko(Codu ke-energy.corn 10 CFR 50.73 May 10, 2011 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555 Subject: D Duke Energy Carolinas, LLC McGuire Nuclear Station, Unit 2 Docket Nos. 50-370 Licensee Event Report (LER) 370/2010-02, Supplement 1 Problem Investigation Process (PIP) M-10-05982 Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached is Supplement 1 to Licensee Event Report 370/2010-02, regarding past inoperability of the Unit 2 "A" Train Nuclear Service Water System and satisfies the commitment to supplement the LER following completion of the root cause analysis This supplement to LER 370/2010-02 supersedes the LER previously submitted December 20, 2010. Completion of the root cause analysis has not affected the original reporting criteria which was completed in accordance with 10 CFR 50.73 (a) (2) (i) (B), an Operation Prohibited by Technical Specifications, and 10 CFR 50.73 (a) (2) (v) (B), any Event or Condition That Could Have Prevented Fulfillment of the Safety Function needed to remove residual heat. Additionally, the supplement did not affect the significance of the event which was considered to be of no significance with respect to the health and safety of the public. There are no regulatory commitments contained in this report. If questions arise regarding this LER, contact Rick Abbott at 980-875-4685. Very truly yours, Zi1:77 Regis T. Repko Attachment www. duke-energy. corn U.S. Nuclear Regulatory Commission May 10, 2011 Page 2 cc:�V. M. McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NC, Suite 1200 Atlanta, Georgia 30303-1257 Jon H. Thompson (Addressee Only) Senior Project Manager (McGuire) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 J. B. Brady Senior Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear Station W. L. Cox Ill, Section Chief North Carolina Department of Environment and Natural Resources Division of Environmental Health Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB. NO 3150-0104 EXPIRES: 08/31/2013 (10-2010) Estimated burden per response to comply with this mandatory collection request: SO hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory Commission. Washington, DC 20555-0001, or by Internet e-mail to info (See reverse for required number of collects resmirceOnrc.gov, and to the Desk Officer, Office of Information and Regulatory digits/characters for each block) Affairs, NEOB-10202, (3150-01041, 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. LICENSEE EVENT REPORT (LER) 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE McGuire Nuclear Station,2Unit 2 05000-212 0370 OF-7 4. TITLE Unit 2 Nuclear Service Water System "A" Train Past Inoperable due to Failed Strainer Differential Pressure Instrument.	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000369/LER-2010-002
05000456/LER-2010-002	Limiting Condition for Operation Action Not Completed Within the Required Time	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000249/LER-2010-003	Steam Leak Results in HPCI Inoperability	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000251/LER-2010-003	Damaged Speed Sensor Caused the 4A Emergency Diesel Generator to be Inoperable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
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05000482/LER-2010-014

OPERATING EXPERIENCE/PREVIOUS EVENTS

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