NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.
NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.
NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency
NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit
NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions
NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023
NL-24-0188, Cycle 33 Core Operating Limits Report
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 5.5
NL-24-0191, Annual Radiological Environmental Operating Reports for 2023
NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations
NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal
NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information
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)
NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in
NL-24-0234, 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-360
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)
NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions
NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023
NL-24-0315, – ISFSI, Registration of Spent Fuel Cask Use
NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information
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 Changes
NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32
NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency
NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided
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,.
NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves
NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing
NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002
NL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34
NL-24-0406, Response to Request for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-003
NL-24-0397, Response to Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement
NL-25-0014, Withdrawal of Request for Exemption from Physical Barrier Requirements
NL-25-0433, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2 - DC Electrical Rewrite - Update to TSTF-360 - Response to Request for Additional Information
NL-24-0117, Change to Quality Assurance Program to Adopt Regulatory Guide 1.8 Revision 4 and License Amendment Request to Relocate Control of the Unit/Facility/Plant Staff Qualification Requirements from Technical Specifications to the Quality Assura
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205. 992.7872 Fax 205.992.7601 April 26, 2013 SOUIHERN'\\
COMPANY Docket No.:
50-348 NL-13-0849 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Post Accident Monitoring Report Ladies and Gentlemen:
Joseph M. Farley Nuclear Plant - Unit 1 Post Accident Monitoring Report Enclosure Post Accident Monitoring Report This Report is being submitted due to Unit 1 Condensate Storage Tank Transmitter 6 not being restored to operable status within the time required by Technical Specification (TS)
TS 3.3.3 requires that instrument be restored to operable status within 30 days. If restored within the 30 day period then a Post Accident Monitoring Report is required to be submitted within following 14 per On March 13, pm, with Unit 1 in Mode 1 at 100 percent power, the Unit 1 Condensate Storage Tank Transmitter LT-516 was declared inoperable due to control room operators observing erratic indication.
Repair work commenced on April 8, 2013 work order SNC 472925. Initial attempts at by replacement of the transmitter and power supply card were not successful. Engineering personnel were then engaged to develop and implement a troubleshooting process which determined that the erratic indication was an intermittent open or ground in the field cabling the control room and the Condensate Storage Tank. The of the field cabling could not be completed within the 30 day Condition Report 622666 generated to document the untimely scheduling of repair and Technical Evaluation 623278 has assigned to establish expectations for scheduling the repair of Technical Specification equipment.
Continued troubleshooting on April 22, 2013 identified a 1"I"'.....*<>t1"'1"t located inside a splice box in Unit 1 Service Water Valve Box 4B. On April 23, 2013 the degraded splice was repaired work SNC 479291. Level Transmitter 6 was returned to service and the Technical Specification Required Action Statement was cleared at 0500 on April 24,
3.
While L T -516 was out of service, alternate indication of Condensate Storage level was provided by a redundant safety related level transmitter (L T-515) an related (L T -501).