- ML13260A014 - Tennessee Valley Authority's Fleet Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year...
- ML13263A013 - LER 13-004-00 for Brown Ferry, Unit 1, Regarding High Pressure Coolant Injection System Declared Inoperable Due to Exceeding the Allotted Time Frame for Instrument Inoperability.
- ML13273A014 - Browns Ferry Nuclear Plant, Units 1, 2 and 3, 10 CFR Part 21 Interim Report - Engine Systems, Inc., Relay Contact A4X-A4Y.
- ML13268A421 - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Updated Reply to Notice of Violation; EA-1 1-252; and Follow-up to 10 CFR 50.9, "Completeness and Accuracy of Information," Notification.
- ML13241A461 - IR 05000259-13-201, 05000260-13-201, and 05000296-13-201, 8/16/2013, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - NRC Security Inspection Report (Cover Letter).
- ML13273A268 - LER 09-004-01 for Browns Ferry Nuclear Plant, Unit 1, Regarding High Pressure Core Injection Found Inoperable During Compensate Header Level Switch Calibration and Functional Test.
- ML13273A267 - LER 09-002-01 for Brown Ferry Nuclear Plant, Unit 1, Regarding Unexpected Logic Lockout of the Loop II Residual Heat Removal System Pumps.
- ML13280A276 - IR 05000259, -260, -296/2013-009; 08/05/2013 - 08/23/2013; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Post Approval Site Inspection for License Renewal.
- ML13274A340 - LER 09-006-001 for Brown Ferry, Unit 1 Regarding Inoperable High Pressure Coolant Injection Pump due to Emergency Core Cooling System Inverter Failure.
- ML13275A140 - LER 11-003-02 for Brown Ferry Plant Units 1, 2, and 3 Regarding Loss of Safety Function (SDC) Resulting from Emergency Diesel Generator Output Breaker Trip.
- ML13275A139 - LER 10-003-03 for Brown Ferry Nuclear Plant, Unit 1 Regarding Failure of a Low Pressure Coolant Injection Flow Control Valve.
- ML13275A141 - LER 10-004-02 for Browns Ferry Nuclear Plant, Unit 1, "Residual Heat Removal System Pump Motor Failure".
- ML13276A065 - ANP-3144(NP), Revision 0, "Nuclear Fuel Design Report BFE2-19 LAR ATRIUM 10XM," Enclosure 6.
- ML13276A066 - ANP-3153(NP), Revision 0, "Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM TM 1OXM Fuel," Enclosure 8.
- ML13276A063 - Browns Ferry, Units 1, 2 and 3 - Response to Request for Additional Information on Technical Specification Change TS-478.
- ML13276A064 - ANP-3248NP, Revision 1, "AREVA RAI Responses for Browns Ferry ATRIUM 10XM Fuel Transition," Enclosure 3.
'Tis the season...
I just finished my normal shopping trip prior to working the night shift. Lo and behold, it's baaaaack!!!
Post by Arthur Metcalf.
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