|
---|
Category:Letter
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 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
[Table view] |
Text
August 31, 2007 Southern Nuclear Operating Company, Inc.
ATTN: Mr. J. Randy Johnson Vice President Joseph M. Farley Nuclear Plant 7388 N. State Highway 95 Columbia, AL 36319
SUBJECT:
MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN - JOSEPH M.
FARLEY NUCLEAR PLANT
Dear Mr. Johnson:
On August 15, 2007, the NRC staff completed its performance review of the Joseph M. Farley Nuclear Plant for the first half of the calendar year 2007 assessment cycle. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results over the previous twelve months. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
This performance review and the enclosed inspection plan do not include physical protection information. A separate letter, designated and marked as Exempt from Public Disclosure in Accordance with 10 CFR 2.390, will include the physical protection review and a resultant inspection plan.
Overall, both Farley Unit 1 and Unit 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for Unit 1 for the most recent quarter as well as the previous three quarters was within the Licensee Response Column of the NRCs Action Matrix. Therefore, the NRC plans to conduct only baseline inspections at Unit 1 through March 31, 2009. In addition, we plan to conduct non-ROP activities involving initial reactor operator examinations at both Unit 1 and Unit 2.
Plant performance for Unit 2 for the previous three quarters was within the Licensee Response Column of the NRCs Action Matrix. However, the Mitigating Systems Performance Index (MSPI), Residual Heat Removal (RHR) System PI crossed the threshold from Green to White in the second quarter of calendar year 2007. This White PI resulted in Unit 2 moving into the Regulatory Response Column of the NRCs Action Matrix which reflected performance at a level requiring increased regulatory response. Therefore, in addition to conducting baseline inspections at Unit 2, the NRC plans to conduct Supplemental Inspection Procedure 95001, Inspection for One or Two White Inputs In a Strategic Performance Area when you have notified us of your readiness.
The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through March 31, 2009. The inspection plan is provided to minimize the resource impact on your staff and to allow for the resolution of any scheduling conflicts and personnel
SNC 2 availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature.
During the calendar year 2006 assessment cycle, the MSPI, Cooling Water Systems PI for both Unit 1 and Unit 2 crossed the threshold from Green to White in the second quarter. In March 2007, we conducted Supplemental Inspection Procedure 95001 for this White PI.
Supplemental Inspection Report 05000348/2007008 and 05000364/2007008 documented a parallel PI White finding due to continuing problems with evaluating safety-related breaker failures. This parallel White finding was not considered during this performance review because the final determination was made after the review had been completed. However, this parallel White finding will be applied to the NRCs Action Matrix beginning with the third quarter of calendar year 2007.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
The NRC is currently evaluating the scope and frequency of all baseline inspection procedures.
If the results of this evaluation, or any other circumstances, cause us to change the inspection plan, we will contact you to discuss the changes as soon as possible. Please contact Scott Shaeffer to (404) 562-4521 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Charles A. Casto, Director Division of Reactor Projects Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8
Enclosure:
Farley Inspection/Activity Plan cc w/encl: (See page 3)
OFFICE RII:DRP RII:DRP RII:DRP RII:DRP SIGNATURE SMS /RA/ CWR /RA/ CAC /RA/
NAME SShaeffer CRapp HChristensen CCasto DATE 08/30/2007 08/30/2007 08/30/2007 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO SNC 3 cc w/encls:
B. D. McKinney, Licensing Services Manager, B-031 Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution L. M. Stinson, Vice President, Fleet Operations Support Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution J. T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution David H. Jones Vice President - Engineering Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Moanica Caston Southern Nuclear Operating Company, Inc.
Bin B-022 P. O. Box 1295 Birmingham, AL 35201-1295 State Health Officer Alabama Department of Public Health RSA Tower - Administration 201 Monroe St., Suite 700 P. O. Box 303017 Montgomery, AL 36130-3017 M. Stanford Blanton Balch and Bingham Law Firm P. O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 William D. Oldfield Quality Assurance Supervisor Southern Nuclear Operating Company Electronic Mail Distribution
SNC 4 Letter to J. Randy Johnson from Charles A. Casto dated August 31, 2007
SUBJECT:
MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN - JOSEPH M.
FARLEY NUCLEAR PLANT Distribution w/encl:
R. Martin, NRR C. Evans, RII EICS L. Slack, RII EICS RIDSNRRDIRS OE Mail PUBLIC