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| Title | Reporting criterion | |
|---|---|---|
| 05000369/LER-2010-003 | Dropped Control Rods Resulting in Completion of a Technical Specification Required Shutdown and Actuation of the Reactor Protection System and Auxiliary Feedwater System. | |
| 05000261/LER-2010-003 | Potential Loss of Residual Heat Removal System Safety Function In Modes 3 and 4 Due To Void Formation | 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)(i)(B), Prohibited by Technical Specifications |
| 05000346/LER-2010-003 | Auxiliary Feedwater Control Valve Inoperable Due to Inadequate Prioritization of DC System Ground | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000335/LER-2010-003 | Unanalyzed Condition Resulting from Alignment of Non-Essential CCW Header Under Certain Accident Scenari s | 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(ix) |
| 05000334/LER-2010-003 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| 05000263/LER-2010-003 | Secondary Containment Briefly Dearaded | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000316/LER-2010-003 | Changed Modes from Mode 5 to Mode 4 with Divider Barrier Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000482/LER-2010-003 | Post Fire Safe Shutdown Issue with the B Emergency Diesel Generator Voltage Control Circuitry | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000315/LER-2010-003 | MICHIGAN One Cook Place
Bridgman, MI 49106 PIOWER® AE P.c om A unit of American Electric Power February 9, 2011 AEP-NRC-2011-7 10 CFR 50.73 Docket No. 50-315 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 LICENSEE EVENT REPORT 315/2010-003-00 MANUAL AFW ACTUATION IN RESPONSE TO MANUAL MFP TRIP In accordance with the criteria established by 10 CFR 50.73, Licensee Event Report System, the following report is being submitted: LER 315/2010-003-00: "Manual AFW Actuation in response to manual MFP trip" There are no commitments contained in this submittal. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649. Sincerely, Joel P. Gebbie Site Vice President JEN/jmr Attachment c: INPO Records Center J. T. King — MPSC, w/o attachment S. M. Krawec — AEP Ft. Wayne, w/o attachment MDNRE — WHMD/RPS, w/o attachment NRC Resident Inspector M. A. Satorius — NRC Region III P. S. Tam — NRC Washington DC 12 NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: 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 comments regarding burden estimate to the Records and FOIA/PrivacyLICENSEE EVENT REPORT (LER) Service Branch (T-5 F52), U.S.0Nuclear 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(See reverse for required number of 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, anddigits/characters for each block) a person is not required to respond to, the information collection. 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Donald C. Cook Nuclear Plant, Unit 1 05000315 1 of 3 4. TITLE Manual Auxiliary Feedwater Actuation in Response to Manual Main Feedpump Trip 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000277/LER-2010-003 | Laboratory Analysis Identifies Safety Relief Valves and Safety Valve Set Point Deficiencies | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000456/LER-2010-004 | Reactor Trip Due to Performance of a Channel Calibration With a Coincident Bistable in a Half-Trip Condition | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000346/LER-2010-004 | Spent Fuel Pool Rack Patterns Did Not Comply With Technical Specification 3.7.16 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000461/LER-2010-004 | OPDRV Requirements Not Met During Control Rod Drive Mechanism Replacements | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000482/LER-2010-014 | Technical Specification Required Shutdown Due to Inadequate Planning Resulting in Extended Emergency Diesel Generator Inoperability | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 05000272/LER-2010-004 | Technical Specification 3.0.4.b Non-Compliance | |
| 05000266/LER-2010-004 | Improper Controls for Breach of HELB Barrier | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(ii) |
| 05000369/LER-2010-004 | McGuire Nuclear StationCI Energy® Duke Energy MG01VP / 12700 Hagers Ferry Rd. Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis. repko@duke-energy. corn November 23, 2010 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555 Subject:D Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Licensee Event Report 369/2010-04, Revision 0 Problem Investigation Process No.: M-10-05299 Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report (LER) 369/2010-04, Revision 0, regarding operation of the diesel generator starting air system not in accordance with Technical' Specifications. This report is being submitted in accordance with 10 CFR 50.73 (a)(2)(i)(B), an operation prohibited by Technical Specifications. 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, please contact P.T. Vu at (980) 875-4302. Very truly yours, Regis T. Repko Attachment www. duke-energy. corn U.S. Nuclear Regulatory Commission November 23, 2010 Page 2 cc:LL. A. Reyes Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. H. Thompson Project Manager (McGuire) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station W. L. Cox III 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: 08/31/2010 (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 comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52),LICENSEE EVENT REPORT (LER) U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to infocollects@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 (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 3. PAGE 0369 McGuire Nuclear Station, Unit 1 _ 0500- 1O OF 8 4. TITLE Improper Technical Specification Application when Diesel Generator Starting Air_ Receivers Cross-Tied. | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000261/LER-2010-004 | Clearance Error Results in the 'A' Emergency Diesel Generator Becoming Inoperable | 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 |
| 05000413/LER-2010-004 | Technical Specification Violation Involving Notice of Enforcement Discretion Due to Failure of Diesel Generator Engine-Mounted Thermocouple | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000263/LER-2010-004 | Secondary Containment Briefly Inoperable Due to Simultaneous Opening of Airlock Doors | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000282/LER-2010-005 | Surveillance Required by Technical Specifications for the Emergency Diesel Generator Not Completed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000261/LER-2010-005 | Emergency Diesel Generator Inoperable Due To Inverter Failure | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| 05000263/LER-2010-005 | Average Power Range Monitor Indication Outside Allowable Range | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000456/LER-2010-005 | Incorrect Methodology Used in Calculations in 1999 Resulted in Non-Conservative Control Room Outside Air Intake Monitor Alarm Setpoints | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000263/LER-2010-006 | Mode Change Made with PCIVs Inoperable | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000261/LER-2010-006 | Pressurizer Heaters Inoperable Longer Than Allowed Due to Inadequate Procedure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000456/LER-2010-006 | Technical Specifications Allowed Outage Time Extension Request for Component Cooling System Contained Inaccurate Design Information That Significantly Impacted the Technical Justification | 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 |
| 05000261/LER-2010-007 | Reactor Trip Due to a Degraded Connection on a Circuit Board in the Electro-Hydraulic Control Cabinet | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000251/LER-2010-007 | Unplanned entry into TS 3.0.3 due to misalignment of Unit 3 HHSI pump discharge valves | 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)(vii), Common Cause Inoperability |
| 05000251/LER-2010-008 | Turkey Point Unit 4 05000251 1 of 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000247/LER-2010-008 | Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Low- Low Level Alarms | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| 05000261/LER-2010-009 | Reactor Trip due to Motor Fault on the 'C' Reactor Coolant Pump, and Actuation of Auxiliary Feedwater Signal and Override of Feedwater Isolation Function due to Inadequate Post-trip Procedure Guidance | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 |