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| Title | Reporting criterion | |
|---|---|---|
| 05000461/LER-2006-003 | High Reactor Water Level Scram Result of Bad Inverter Circuit Board Solder Joint | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000389/LER-2006-003 | Missed Eddy Current Indication from SL2 - 1 5 Inspection | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000362/LER-2006-003 | Reactor Coolant System Pressure Boundary Leak Caused by Incomplete Compression of a Mechanical Nozzle Seal Assembly Grafoil Seal. | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-2006-003 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | |
| 05000315/LER-2006-003 | Failure to Comply with Technical Specification 3.3.6, Containment Purge Supply and Exhaust System Isolation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000298/LER-2006-003 | Both Diesel Generators Inoperable Due to Voltage Regulator Design Results in Loss of Safety Function | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
| 05000289/LER-2006-003 | ||
| 05000247/LER-2006-003 | Manual Reactor Trip Due to a Mismatch Between Reactor Power and Turbine Load Caused by Cycling of Steam Dump Valves After a Power Reduction for Loss of Heater Drain Tank Pumps | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000237/LER-2006-003 | Unit 2 Reactor Steam Dome Pressure-Low Permissive Switch Determined To Have Been Historically Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000413/LER-2006-003 | Technical Specification Violations Associated with H drogen Ignition System | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000346/LER-2006-003 | Degraded Condenser Pressure Due to Failed Drain Line Results in Manual Reactor Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000335/LER-2006-003 | Unanalyzed Condition for Diesel Generators and Degraded Voltage Relaying | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| 05000305/LER-2006-003 | 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 | |
| 05000255/LER-2006-003 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | |
| 05000528/LER-2006-004 | TS Required Reactor Shutdown on failure of the class pressurizer heaters to be able to meet their mission time. | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 05000443/LER-2006-004 | Technical Specification Violation Due to Inoperable Battery Charger | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000395/LER-2006-004 | Turbine Trip Due To High Steam Generator Level P-14 05000 | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000389/LER-2006-004 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000362/LER-2006-004 | Station ManagerEDISON® San Onofre An EDISON INTERNATIONAL@ Company November 22, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Subject:DDocket No. 50-362 Licensee Event Report No. 2006-004 San Onofre Nuclear Generating Station, Unit 3 Dear Sir or Madam: This submittal provides Licensee Event Report (LER) 2006-604, which describes an occurrence of an inoperable breaker causing a charging pump to be inoperable longer than allowed by Technical Specifications. This event did not affect the health and safety of either plant personnel or the public. If you require any additional information, please contact me. Sincerely, Unit 3 LER No. 2006-004 cc:DB. S. Mallett, NRC Regional Administrator, Region IV C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3 P.O. Box 128 San Clemente, CA 92674-0128 949-368-9263/PAX 89263 Fax 949-368-6183 breigdp@songs.sce.com ) ARC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (7-2001) COMMISSION Estimated burden per response to comply with this mandatory information 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 Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to bjs@nrc.gov, andLICENSEE EVENT REPORT (LER) to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of (See reverse for required number of Management and Budget, Washington, DC 20503. If a means used to impose 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. digits/characters for each block) 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE San Onofre Nuclear Generating Station (SONGS) Unit 3 05000362 1 OF 4 4. TITLE Inoperable breaker causes train "A" charging pump to be inoperable for longer than allowed by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-2006-004 | Failure to Enter the Technical Specification Action Statement for Inoperable Reactor Protection System Trips | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000316/LER-2006-004 | Failure to comply with Technical Specification 3.8.2, AC Sources - Shutdown, LCO 3.8.2.b | 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 |
| 05000298/LER-2006-004 | 10 CFR 50.73(a)(2)(iv), System Actuation | |
| 05000440/LER-2006-004 | OSCILLATION POWER RANGE MONITORS (OPRMs) INOPERABLE | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000305/LER-2006-004 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000269/LER-2006-004 | Design Oversight Results in Appendix R Deficiencies | |
| 05000255/LER-2006-004 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000254/LER-2006-004 | Through-wall Leak in Standby Liquid Control Tank Due to the Original Construction Use of Grout with Leachable Halogens | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000528/LER-2006-005 | Technical Specification Prohibited Condition due to Check Valve Not Seated | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000458/LER-2006-005 | Automatic Start of Standby Service Water During Realignment of Reactor Plant Cooling Water | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000443/LER-2006-005 | Technical Specification Violation with Inoperable Main Steam Isolation Valve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000362/LER-2006-005 | Dilution error results in exceeding 20 percent power prior to completion of required surveillances | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-2006-005 | Inadvertent Actuation of 'A' Motor Driven Auxiliary Feedwater Pump | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000316/LER-2006-005 | Failure to Comply with Technical Specification Surveillance Requirement 3.6.1.1 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000298/LER-2006-005 | Cooper Nuclear Station 05000298 1 ofD4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000247/LER-2006-005 | Automatic Reactor Trip Due to a Turbine Trip as a Result of a Main Generator Exciter Protective Trip Caused by a Generrex Power Supply Loss of Electrical Ground | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000237/LER-2006-005 | Units 2 and 3 Control Room Emergency Ventilation Air Conditioning System Inoperable Due To Leaking Fittings | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| 05000440/LER-2006-005 | Decreasing Instrument Air Pressure Results in Manual Reactor Protection System Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000305/LER-2006-005 | 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 | |
| 05000269/LER-2006-005 | TS LCO Conditions Not Entered and Required Action Completion Times Not Met Due to Undetected Inoperable LTOP RCS Pressure Indication and Alarms | |
| 05000255/LER-2006-005 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000362/LER-2006-006 | One train of Component Cooling Water considered inoperable for longer than allowed by Technical Specification 3.7.7 due to gas entrainment. | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000247/LER-2006-006 | Licensee Event Report # 2006-006-00, "Automatic Actuation of Both Motor Driven Auxiliary Feedwater Pumps after Local Reset of the 21 Main Feedwater Pump During Corrective Maintenance and Troubleshooting of the Turbine Governor Valve" Dear Sir: The attached Licensee Event Report (LER) 2006-006-00 is the follow-up written report submitted in accordance with 10 CFR 50.73. This event is of the type defined in 10 CFR 50.73(a)(2)(iv)(A) for an event recorded in the Entergy corrective action process as Condition CR-IP2-2006-06885. There are no commitments contained in this letter. Should you or your staff have any questions regarding this matter, please contact Mr. Patric W. Conroy, Manager, Licensing, Indian Point Energy Center at (914) 734-6668. Fred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-247 NL-07-010 Page 2 of 2 Attachment: LER-2006-006-00 CC: Mr. Samuel J. Collins Regional Administrator — Region I U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspector's Office Resident Inspector Indian Point Unit 2 Mr. Paul Eddy State of New York Public Service Commission INPO Record Center NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104DEXPIRES: 06/30/2007 (6-2004) Estimated burden per response to comply with this mandatory collection request: 50 hours.DReported 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), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internetLICENSEE EVENT REPORT (LER) 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 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. 2. DOCKET NUMBER 3. PAGE1. FACILITY NAME: INDIAN POINT 2 05000-247 1DOF 5 4.TITLE: Automatic Actuation of Both Motor Driven Auxiliary Feedwater Pumps After Local Reset of the 21 Main Feedwater Pump During Corrective Maintenance and Troubleshooting of the Turbine Governor Valve | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000440/LER-2006-006 | Primary Containment Airlock Door Inoperability Results in Operation Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000305/LER-2006-006 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000255/LER-2006-006 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | |
| 05000244/LER-2006-007 | Main Steam Safety Valve Setpoint Exceedance | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000305/LER-2006-007 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000255/LER-2006-007 | 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000244/LER-2006-008 | Charcoal Filter Efficiency Test Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000305/LER-2006-008 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |