ML12101A280
From kanterella
Revision as of 00:36, 3 March 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
| ML12101A280 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/09/2012 |
| From: | Lynch T A Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-12-0557 LER 12-001-00 | |
| Download: ML12101A280 (7) | |
Similar Documents at Farley | |
|---|---|
Category:Letter
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024
[Table view]Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 2024-09-05 Category:Licensee Event Report (LER) MONTHYEAR05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024
[Table view]Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel 05000364/LER-2024-001, Manual Reactor Trip Due to Rising Steam Generator Levels2024-01-11011 January 2024 Manual Reactor Trip Due to Rising Steam Generator Levels 05000348/LER-2023-003, Emergency Diesel Generator (Eog) Lube Oil Pwnp Outlet Coupling Leak2023-12-0707 December 2023 Emergency Diesel Generator (Eog) Lube Oil Pwnp Outlet Coupling Leak 05000364/LER-2023-003, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits2023-12-0707 December 2023 Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2023-002, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift2023-11-30030 November 2023 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift 05000348/LER-2023-002, Residual Heat Removal Pump Inoperable for Longer than Allowed by Technical Specifications2023-11-29029 November 2023 Residual Heat Removal Pump Inoperable for Longer than Allowed by Technical Specifications 05000364/LER-2023-001, Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits2023-09-28028 September 2023 Pressurizer Code Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000348/LER-2023-001, Automatic Reactor Trip Due to DC Ground on Turbine Trip Solenoid2023-03-30030 March 2023 Automatic Reactor Trip Due to DC Ground on Turbine Trip Solenoid 05000348/LER-2022-001, Outdated Relay Settings Resulted in an Automatic Reactor Trip After a Floor Tile Was Dropped in High Voltage Switch House2022-09-30030 September 2022 Outdated Relay Settings Resulted in an Automatic Reactor Trip After a Floor Tile Was Dropped in High Voltage Switch House 05000364/LER-2017-0052018-01-11011 January 2018 Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector, LER 17-005-00 for Joseph M. Farley Nuclear Plant, Unit 2, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector 05000364/LER-2017-0042017-12-22022 December 2017 I OF 3, LER 17-004-00 for Joseph M. Farley Nuclear Plant, Unit 2 Regarding Turbine-Driven Auxiliary Feedwater Pump Steam Admission Valve Air Leak Resulted in a Condition Prohibited by Technical Specifications 05000364/LER-2017-0032017-12-20020 December 2017 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits, LER 17-003-00 for Joseph M. Farley, Unit 2, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2017-0022017-12-19019 December 2017 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits, LER 17-002-00 for Joseph M. Farley, Unit 2, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits 05000364/LER-2017-0012017-08-21021 August 2017 2B Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability, LER 17-001-00 for Farley, Unit 2, Regarding 28 Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability 05000348/LER-2016-0072017-06-0707 June 2017 Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters, LER 16-007-01 for Joseph M. Farley, Unit 1, Regarding Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters 05000348/LER-2016-0092017-02-0202 February 2017 Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications, LER 16-009-00 for Joseph M. Farley Nuclear Plant, Units 1 and 2 Regarding Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications 05000348/LER-2016-0082017-01-23023 January 2017 Manual Reactor Trip Due to Generator Voltage Swings, LER 16-008-00 for Farley, Unit 1, Regarding Manual Reactor Trip Due to Generator Voltage Swings 05000348/LER-2016-0052016-12-28028 December 2016 Toxic Gas Event, LER 16-005-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Toxic Gas Event 05000348/LER-2016-0042016-12-19019 December 2016 Unapproved Environmental Qualification Material Caused Inoperability of One Containment Cooling Train, LER 16-004-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Unapproved Environmental Qualification Material Caused lnoperability of One Containment Cooling Train 05000348/LER-2016-0062016-12-19019 December 2016 Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump, LER 16-006-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump 05000348/LER-2016-0032016-12-12012 December 2016 Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band, LER 16-003-00 for Farley, Unit 1, Regarding Pressurizer Safety Valve Setpoint Pressure Outside of Technical Specification Tolerance Band 05000348/LER-2016-0022016-11-30030 November 2016 Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve, LER 16-002-00 for Joseph M. Farley Nuclear Plant, Unit 1 Regarding Automatic Reactor Trip and Safety Injection Due to Closure of Main Steam Isolation Valve 05000348/LER-2016-0012016-06-0909 June 2016 Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications, LER 16-001-00 for Farley, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to 600V Load Center Inoperable Longer than Allowed by Technical Specifications 05000364/LER-2015-0012016-01-13013 January 2016 Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications due ,to a Design Issue, LER 15-001-01 for Farley, Unit 2, Regarding Turbine Driven Auxiliary Feedwater Pump in a Condition Prohibited by Technical Specifications Due to a Design Issue NL-13-1525, Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B2013-07-26026 July 2013 Special Report 13-001-00 for Joseph M. Farley, Unit 2, Regarding Nonfunctional Radiation Monitor R-60B NL-11-2445, LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems2012-01-0909 January 2012 LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems NL-08-0756, Special Report 2008-002-00, Inoperable Radiation Monitor R-60B2008-05-0909 May 2008 Special Report 2008-002-00, Inoperable Radiation Monitor R-60B NL-08-0659, Special Report 2008-001-00, Inoperable Radiation Monitor R-29B2008-04-25025 April 2008 Special Report 2008-001-00, Inoperable Radiation Monitor R-29B NL-05-2234, Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B2005-12-0606 December 2005 Special Report No. 2005-001-00 for Joseph M. Farley Nuclear Plant - Unit 1 Re Inoperable Radiation Monitor R-60B 2024-06-19 |
Retrieved from "https://kanterella.com/w/index.php?title=ML12101A280&oldid=455184"