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
MONTHYEARML24036A2652024-02-0505 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,
L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023
Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule
IR 05000266/20234022023-11-14014 November 2023
Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402
ML23279A0672023-11-0909 November 2023
Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval
IR 05000266/20230032023-10-16016 October 2023
Integrated Inspection Report 05000266/2023003 and 05000301/2023003
ML23346A1322023-10-0606 October 2023
Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published
L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023
License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program
ML23243A9102023-09-0606 September 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
IR 05000266/20235012023-08-29029 August 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501
ML23208A2262023-08-28028 August 2023
Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter
ML23208A0952023-08-28028 August 2023
Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach
IR 05000266/20230052023-08-24024 August 2023
Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005)
ML23160A0642023-08-21021 August 2023
Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System
L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023
Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update
ML23221A0522023-08-0909 August 2023
Confirmation of Initial License Examination, March 2024
L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
ML23201A0872023-08-0303 August 2023
Audit Plan in Support of Review of License Amendment
L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023
Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections
IR 05000266/20230022023-07-18018 July 2023
Integrated Inspection Report 05000266/2023002 and 05000301/2023002
IR 05000266/20234012023-07-13013 July 2023
Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401
L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023
Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023
10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval
ML23171B1062023-06-21021 June 2023
Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2
ML23163A2422023-06-13013 June 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023
Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023
Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response
ML23103A1332023-06-0101 June 2023
Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023
NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
ML23118A1762023-05-0404 May 2023
Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191
IR 05000266/20230012023-05-0101 May 2023
Integrated Inspection Report 05000266/2023001 and 05000301/2023001
ML23114A1222023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023
2022 Annual Monitoring Report
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-028, 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 Applications2023-03-27027 March 2023
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
2024-02-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 8, 2017 Mr. Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 1 - REVIEW OF THE SPRING 2016 STEAM GENERATOR 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. ML16264A202), and supplemented by letter dated February 23, 2017 (ADAMS Accession No. ML17054C310), 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 e-mail at Mahesh.Chawla@nrc.gov.
Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosure:
Staff Assessment cc w/encl: Distribution via ListServ
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. ML16264A202), and supplemented by letter dated February 23, 2017 (ADAMS Accession No. ML17054C310), 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
ML17159A499
- 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
