|
---|
Category:Letter
MONTHYEARNL-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 IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 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 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 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 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 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 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 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 NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 2024-09-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 October 25, 2016
Mrs. Cheryl A. Gayheart
VP Nuclear Plant Site
Southern Nuclear Operating Co., Inc.
Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia, AL 36319
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mrs. Gayheart:
From January 9 - 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) will perform a Post-Approval Inspection for License Renewal at the Farley Nuclear Plant, Units 1 and 2, in accordance with NRC inspection procedure (IP) 71003, "Post-Approval Site Inspection for License Renewal." Previous inspections confirm that this inspection is resource-intensive for both the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for information.
The enclosed request identifies the documents that the inspectors will need upon arrival at the site, to successfully meet the inspection objectives. Requested documents should be current and complete to maximize efficiency during onsite portions of the inspection.
We have discussed the schedule for these inspection activities with your staff, and understand that our regulatory contact for this inspection will be Julie Collier of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Robert E. Williams Jr., at 404-997-4664.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public inspections, exemptions, requests for withholding," of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter, its Enclosure, and your response (if any), will be available electronically for public inspection in the NRC's Public Document Room, or from the Publicly C. Gayheart 2 Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/ Shakur A. Walker, Chief Engineering Branch 3 Division of Reactor Safety
Docket No. 50-348, 50-364 License No. NPF-2, NPF-8
Enclosure:
Request for Information Post-Approval Inspection for License Renewal
cc: Distribution via Listserv
_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE REW1 SAW4 NAME RWILLIAMS SWALKER DATE 10/25/2016 10/25/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO Enclosure REQUEST FOR INFORMATION POST-APPROVAL INSPECTION FOR LICENSE RENEWAL Site: Joseph M. Farley Nuclear Plant, Units 1 and 2
Inspection Dates: January 9 - 13, 2017 (onsite week 1)
January 16 - 20, 2017 (in-office review week)
January 23 - 27, 2017 (onsite week 2)
Inspection Procedure: IP 71003, "Post-Approval Site Inspection for License Renewal" dated July 08, 2016
Inspectors: Alexander Butcavage, Reactor Inspector Robert Carrion, Senior Reactor Inspector Brendan Collins, Reactor Inspector Paula Cooper, Reactor Inspector Abhijit Sengupta, Reactor Inspector Robert Williams, Senior Reactor Inspector (Lead)
The following information should be made available to the inspection team in hard copy or electronic format upon arrival to the site. Due to differences in license conditions and regulatory commitments among operating reactor sites associated with the license renewal process, the information requested below may not be entirely applicable to Farley Nuclear Plant.
The information listed in Section 'A' of this enc losure is not aimed to a particular regulatory commitment, license condition, aging managemen t program (AMP), or time-limited aging analysis (TLAA). Section 'A' requests general information that will help the inspectors to understand the applicable administrative procedures and overall completion status of license renewal activities. Prior to the inspection, the lead inspector will select a sample of regulatory commitments, license conditions, and AMPs for review, including TLAAs. The information listed in Section 'B' of this enclosure should be provided for each item selected for review. If there are any questions regarding this information request, please contact the lead inspector as soon as
possible.
A. General Information Request (As Applicable)
(1) Sections of the quality assurance program manual applicable to license renewal activities (2) Corrective Action Program (CAP) procedures (3) Regulatory Commitment Change Process procedures (4) Operating Experience (OE) Program procedures (5) Latest version of the updated final safety analysis report (UFSAR) supplement for license renewal submitted with the license renewal application (LRA).
(6) Last version of the UFSAR supplement for license renewal submitted to the NRC per 10 CFR 50.71.
2 (7) Living version of the UFSAR supplement for license renewal (8) Post-approval evaluations or assessments performed to verify that in-scope structures, systems, or components (SSCs) were not excluded from the LRA and appropriate aging management has been considered in accordance with 10CFR 54.37(b)
(9) List of plant modifications with a brief description of the modification scope that were approved and/or implemented from the date the LRA was submitted to the date the
renewed license was issued (10) Self-assessments performed after the renewed license was issued associated with the implementation of license renewal commitments, including AMPs and TLAAs (11) "Gap analyses" performed to assess the differences between the current AMPs and the recommendations in the latest revision of NUREG-1801, "Generic Aging Lessons Learned (GALL)," and subsequent Interim Staff Guidance (12) Site-specific responses and/or evaluations for NRC generic communications associated with license renewal that were issued after the renewed license was granted
(13) Description of the overall completion status of action items associated with license renewal commitments, including AMPs and TLAAs (14) Description of administrative controls that will be used to ensure that all activities due prior to (and during) the period of extended operation (PEO) will be satisfactorily completed as described in the license renewal documents
(15) Description of plans or processes that would be used during the PEO to continuously incorporate operating experience into license renewal activities B. Specific Requests for each License Renewal Commitment Selected for Review, including AMPs and TLAAs (As Applicable)
(1) Program basis documents and administrative procedures describing key program attributes such as program objectives, scope, detection and monitoring methods, administrative controls, acceptance criteria, corrective actions, and scope expansion requirements
(2) Implementing procedures for program activities (e.g. visual examination procedures, ultrasonic examination procedures, maintenance procedures, system walkdowns, etc)
(3) Updated license renewal scoping drawings showing the SSCs within the scope of the AMP
(4) Applicable sections of the LRA
(5) Applicable requests for additional information (RAIs) issued by NRC's technical reviewers during the review of the LRA and corresponding responses
(6) Applicable sections of the NRC's safety evaluation report
3 (7) Copy or ready access to the key industry standards that will be followed during the PEO for the implementation of the program (e.g. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Electric Power Research Institute Guidelines, Nuclear Energy Institute Guidelines, etc.
(8) Description of changes made to the license renewal commitment, including the associated technical and regulatory evaluations supporting the change.
(9) Description of activities completed to meet license conditions, license renewal commitments, and the UFSAR. For example, this should include completed Work Orders (WOs) with associated inspection reports describing the work done and the results of the inspection.
(10) Description of instances where examination scope expansion was required based on the initial examination of a SSC for license renewal. Please describe the logic to select the scope expansion, and any resulting changes to the AMP.
(11) Description of instances where examination scope changes were required based on limitations encountered during the initial examination of a SSC for license renewal. Please describe the actions taken, and any resulting changes to the AMP.
(12) Description of pending activities due prior to the PEO, which are necessary to meet license conditions, license renewal commitments, and the activities described in the UFSAR. For example, this may include a list of pending WOs with a brief description of the work to be performed.
(13) Copy of any correspondence between the licensee and the NRC, after the license was issued, associated with regulatory issues affecting the license renewal commitment. For example, this may include notifications of commitment changes, or license amendment requests, affecting a license condition or a license renewal commitment.
(14) List of CAP documents (e.g., Condition Reports) associated with the implementation of the AMP. This includes unacceptable aging effects identified during the implementation of license renewal activities, and programmatic deficiencies requiring resolution.
(15) Copy of evaluations performed for applicable external and internal OE issues associated with license renewal. This request is limited to OE items issued after the renewed operating license was granted.
Inspector Contact Information: Mailing Address: Robert Williams USNRC Region 2 Senior Reactor Inspector Attn: Robert Williams 404-997-4664 Marquis One Tower Robert.Williams@nrc.gov 245 Peachtree Center Avenue NE Suite 1200 Atlanta, GA 30303