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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-01-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 28, 2017 Mr. James J. Hutto Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P.O. Box 1295 /Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO JUNE 2, 2017, STAFF EVALUATION OF THE REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM
Dear Mr. Hutto:
By letter dated June 2, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17135A252), the U.S. Nuclear Regulatory Commission (NRG) issued a staff evaluation of the reactor vessel internals ageing management program for the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 The purpose of this letter is to correct an error regarding the outage dates for the inspections of the baffle-former bolts that was identified on page 5 of the Safety Evaluation in Section 3.2.2, "Baffle Bolts."
The following is the statement located in the June 2, 2017, letter, with the incorrect outage dates highlighted in bold font With respect to baffle bolts at FNP Unit 1, the licensee stated that it will perform initial inspections (ultrasonic testing-UT) of these bolts during the spring 2018 outage.
Similarly, for FNP Unit 2, the licensee stated that it will perform initial inspections of these bolts during the spring 2022 outage.
The following is the corrected statement that replaces the above incorrect statement with the correct outage dates highlighted in bold font:
With respect to baffle bolts at FNP Unit 1, the licensee stated that it will perform initial inspections (ultrasonic testing-UT) of these bolts during the fall 2025 outage. Similarly, for FNP Unit 2, the licensee stated that it will perform initial inspections of these bolts during the fall 2026 outage.
Enclosed is the corrected page 5 of the Safety Evaluation that contain marginal lines indicating the areas of change.
J. Hutto If you have any questions concerning this matter, please contact the Project Manager, Shawn Williams, at 301-415-1009 or by e-mail at Shawn.Williams@nrc.gov.
Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
Staff Evaluation cc w/enclosure: Distribution via Listserv
J Hutto
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO JUNE 2, 2017, STAFF EVALUATION OF THE REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM DATED JUNE 28, 2017 DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsRgn2MailCenter Resource RidsNrrDorllpl2-1 Resource RidsACRS_MailCTR Resource RidsNrrDeEvib Resource RidsNrrKGoldstein Resource RidsNrrPMFarley Resource GCheruvenki, NRR ADAMS Accession No ML17171A351 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/BC NAME SWilliams KGoldstein MMarklev DATE 06/20/17 06/26/17 06/28/17 OFFICE NRR/DORL/LPL2-1/PM NAME SWilliams DATE 06/28/17 OFFICIAL RECORO COPY
addition, it reduces the pressure difference across the baffle, which reduces the loading on the bolt. With respect to baffle bolts at FNP Unit 1, the licensee stated that it will perform initial inspections (ultrasonic testing-UT) of these bolts during the fall 2025 outage. Similarly, for FNP Unit 2, the licensee stated that it will perform initial inspections of these bolts during the fall 2026 outage.
NRG Staff Evaluation The NRC staff noted that baffle bolt replacement in the FNP units with Type 316 materials in conjunction with modified bolt design and upflow conversion, which reduces loads on the baffle bolts, provides reasonable assurance that the licensee is adequately managing the aging degradation in these bolts. In order to maintain the adequacy of the AMP for these bolts, the licensee will be inspecting the baffle bolts at the FNP units during the PEO. The staff noted that the inspection frequency and the inspection techniques that would be used for these bolts are consistent with l&E guidelines addressed in MRP-227-A. Therefore, the staff concludes that the licensee's proposed plan provides reasonable assurance that the aging degradation in this component is being monitored adequately by the licensee during the PEO at the FNP units.
Based on the emerging OE associated with IASCC on these bolts, on August 1, 2016, Westinghouse issued Nuclear Safety Advisory Letter (NSAL)-16-1, Revision 1, "Baffle-Former Bolts," which provides recommendations to manage the aging degradation in baffle-former bolts (ADAMS Accession No. ML16225A729). Recommendations addressed in NSAL-16-t were developed based on the OE of the baffle-former bolt failures. Each plant that experienced bolt failures was binned under a tier based on the extent of aging degradation of the bolts. The FNP units were binned under "Tier 3" category, and the NRC staff expects that the licensee will follow the guidelines recommended in Nuclear Energy Institute (NEI) NEI 03-08, "Guidelines for the Management of Materials Issues," and NSAL-16-1.
3.2.3 Control Rod Guide Cards Licensee Evaluation In Table 7-1 of the licensee's submittal dated August 12, 2015, the licensee indicated that the control rod guide cards at the FNP units are to be inspected no later than two refueling outages from the beginning of the PEO for each unit. The licensee further stated that it will inspect control rod guide cards in accordance with MRP-227-A and WCAP-17451-P, "Reactor Internals Guide Tube Wear." To date, the licensee did not identify any active aging degradation in guide cards at FNP units.
NRG Staff Evaluation The NRG staff reviewed the licensee's evaluation of the guide cards and determined that the licensee's plan to follow the guidelines addressed in MRP-227-A and WGAP-17451-P provides reasonable assurance that the AMP for the guide cards would be effectively implemented at the FNP units. The staff's basis for this conclusion is addressed below. The staff's assessment of WCAP-17451-P was included in the staff"s SE for the WCAP-17096-NP. Revision 2, "Reactor Internals Acceptance Criteria Methodology and Data Requirements," December 2009 (ADAMS Accession No. ML 101460t 57). In the SE for the WCAP-17096-NP. Revision 2 (ADAMS Accession No. ML16061A243), the staff stated that the evaluation methodology and acceptance criteria for the guide cards is acceptable because it provides a methodology for measuring wear that ls based on ensuring functionality of the rod cluster control assemblies, and the acceptance