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Revision as of 13:13, 1 April 2018
Letter Sequence Approval |
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CAC:MF8401, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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Category:Letter
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, 2024-09-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 June 8, 2017 SUBJECT: POINT BEACH NUCLEAR PLANT, UNIT 1 -REVIEW OF THE SPRING 2016 STEAM GENERA TOR TUBE INSPECTIONS DURING REFUELING OUTAGE 36 (CAC NO. MF8401) Dear Mr. Coffey: By letter dated September 20, 2016 (Agencywide Documents Access Management System (ADAMS) Accession No. ML 16264A202), and supplemented by letter dated February 23, 2017 (ADAMS Accession No. ML 17054C310), NextEra Energy Point Beach, LLC (the licensee), submitted information to U.S. Nuclear Regulatory Commission (NRC), summarizing the results of their steam generator tube inspections performed during the spring 2016 refueling outage at Point Beach Nuclear Plant, Unit 1. The NRC staff has completed its review of this report and concludes that the licensee provided the information required by their technical specifications. No additional follow up is required at this time. The staff's review is enclosed. If you have any questions concerning this matter, please contact me at (301) 415-8371 or via mail at Mahesh.Chawla@nrc.gov. Docket No. 50-266 Enclosure: Staff Assessment cc w/encl: Distribution via ListServ Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation STAFF ASSESSMENT BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE SPRING 2016 STEAM GENERATOR TUBE INSPECTION REPORT NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-266 By letter dated September 20, 2016 (Agencywide Documents Access Management System (ADAMS) Accession No. ML 16264A202), and supplemented by letter dated February 23, 2017 (ADAMS Accession No. ML 17054C310), NextEra Energy Point Beach, LLC (the licensee), submitted information summarizing the results of their steam generator (SG) tube inspections performed during the spring 2016 refueling outage (RFO) at Point Beach Nuclear Plant (Point Beach), Unit 1. Point Beach, Unit 1, has two Westinghouse 44F SGs each containing 3,214 thermally-treated Alloy 600 tubes. These SGs were installed during RFO 11 in 1983. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches. The tubes are supported by six stainless steel tube support plates and a baffle plate. The tube support plate holes are quatrefoil shaped. The U-bend region of the tubes in rows 1 through 8 was stress relieved after bending. The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. The tubes in both SGs A and B were inspected this outage. After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments/observations:
- Discoloration was observed inside the channel head near the primary manway during previous inspections in RFO 30 and RFO 34. The licensee stated that no rust coloration was observed during RFO 36.
- The licensee stated that the combined primary-to-secondary leak rate from both SGs is in the range of 0.0 to 0.4 gallons per day (compared with the 150 gallons per day operational leakage limit) and that the operational leakage remains at a constant low level and was evident prior to the spring 1991 outage. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 1 -REVIEW OF THE SPRING 2016 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 36 (CAC NO. MF8401) DATED JUNE 8, 2017 DISTRIBUTION: PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMPointBeach Resource RidsOgcRp Resource RidsNrrDeESGB Resource AHuynh, NRR RidsAcrs_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrLASRohrer Resource ADAMS Accession No.: ML 17159A499
- Via Memorandum OFFICE DORULPL3-1 /PM DORULPL3-1/LA DE/ESGB/BC(A)* DORULPL3-1 /BC NAME MChawla SRohrer AJohnson DWrona DATE 06/08/17 06/08/17 5/22/17 06/08/17 OFFICIAL RECORD COPY