Letter Sequence Response to RAI |
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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
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September 25,201 2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 NRC 2012-0076 TS 5.6.8 Point Beach Nuclear Plant, Units 1 Docket 50-266 Renewed License No. DPR-24 Response to Request for Additional Information Fall 201 1 Unit I (U1 R33) Steam Generator Tube lnspection Report
References:
(1) NextEra Energy Point Beach, LLC letter to NRC, dated May 29, 2012, Fall 201 1 Unit 1 (U1 R33) Steam Generator Tube lnspection Report (MLI 21 50A287) (2) NRC letter to NextEra Energy Point Beach, LLC, dated August 28,2012, Point Beach Nuclear Plant, Unit 1 - Request for Additional lnformation Regarding the Fall 201 1 Steam Generator Tube Inservice lnspection Report (TAC No. ME8780) (MLl2234A460)
NextEra Energy Point Beach, LLC (NextEra) submitted the Fall 201 1 Unit 1 (U1 R33) Steam Generator Tube lnspection Report via Reference (1) documenting the scope and results of the inspection per prescribed Technical Specification Reporting Requirements. The NRC Staff has determined additional information (Reference
- 2) is required to enable continued review of the Reference (1) report. Enclosure 1 provides the NextEra response to the NRC Staff's request for additional information.
This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.
Very truly yours, NextEra Energy Point Beach, LLC James Costedio + V Licensing Manager Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REACTOR VESSEL INTERNALS INSPECTION PLAN RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The NRC Staff determined that additional information is required (Reference
- 1) to enable the continued review of the Point Beach Nuclear Plant (PBNP) Fall 201 1 Unit 1 (Ul R33) Steam Generator Tube Inspection Report (Reference 2). The following information is provided by NextEra Energy Point Beach, LLC (NextEra) in response to the NRC Staff's request.
RAI I - It was indicated that the secondary-side inspections showed "no significant degradation. " Please discuss the results of the secondary-side inspections, including clarifying whether any degradation was observed.
NextEra Response The general area of the steam drum was inspected following the modifications made in support of an extended power uprate (EPU). The mid and lower decks of the steam drums were inspected for a baseline. The internal feedring, J-nozzles, and thermal sleeve were inspected.
The secondary moisture separators, primary moisture separators (PMSs), mid-deck extension, hatch, hinges, riser barrels, top hats, and externals of feedring and J-nozzles were inspected in the general area inspections. Burn-through on the interface of the J-nozzle and feedring was observed at J-nozzle 28 in Steam Generator (SG)
A, and at J-nozzles 7, I1 and 14 in SG B. Burn-through indications are from construction of the SGs and not a service induced condition. The interior of the feedring was clear of any foreign material. The 112 PMSs were visual inspected.
All PMSs were covered in a light coating of magnetite. Baseline ultrasonic testing (UT) measurements were taken in various locations on the secondary side to allow future trending of post-EPU secondary side wear. There were 56 UT measurements taken on the SG A PMSs, 64 UT measurements taken on the SG A feedring, 55 UT measurements taken on the SG B PMSs, and 64 UT measurements taken on the SG B feedring.
No abnormal measurements were identified.
RAI 2 - Please discuss the results of the tube plug inspections.
NextEra Response A video inspection of five installed plugs in SG A (hot and cold legs) and six installed plugs in SG B (hot and cold legs) showed that all plugs are dry. Page 1 of 3 RAI 3 - Please clarify whether 50 or I00 percent of the tube ends in steam generator A were inspected with a rotating probe (since Sections 2.l.b and 2.l.e both indicate that 50 percent of the tubes were inspected).
NextEra Response In the SG A hot leg, 50% of all tubes were inspected for the full depth of the tubesheet with a rotating probe. An expansion to 100% inspection of the tubes in SG A was not required since crack indications were not found in that SG. In the SG B hot leg, the inspection of the tubes within the tubesheet was expanded from 50% to 100% based on the discovery of crack indications in that SG. 100% of the peripheral tubes in the cold leg of both SGs were inspected with a rotating probe for the full depth of the tubesheet.
RAI 4 - In Section 5.2.6, it was indicated that 74 indications of wear at the anti-vibration bars were observed and that 72 of these indications were sized with the bobbin coil. Please discuss how the remaining two indications were sized.
If not sized, how were they dispositioned and how was it determined that condition monitoring criteria were satisfied.
NextEra Response The wording in Section 5.2.b is inconsistent with Table 5-2, which shows the Anti-Vibration Bar (AVB) Wear History for SG B. There are 73 AVB wear indications in 51 tubes that were sized by the bobbin coil in the U1 R33 inspection.
Tube R16 C77 in Table 5-2 is Indication Not Reportable (INR), and therefore, no sizing was performed on that particular tube. Table 5-2 includes Tube R16 C77, which makes the total 74 indications of wear in 52 tubes. Therefore, all 73 indications that had a percent wear call were sized by the bobbin coil. RAI 5 ' - The number of indications of wear above the top of the tubesheet which were attributed to sludge lancing equipment in Table 5-6 does not appear to match the corresponding text. According to the text, there were 17 indications of wear; however, Table 5-6 only lists 10 indications with wear (and 7 "indications not reporfable'j).
Please clarify. NextEra Response A review of the Eddy Current Database was performed.
The 21 SG A tubes with 22 indications reported in Section 5.6 of Reference (2) are comprised of both volumetric (percentage wear) and geometric (GEO) anomalies. Table 5-6 of Reference (2) provides a historical view of the volumetric indications from the current inspection as well as previous inspections for a total of 17 indications. There were 10 indications of wear and 7 previous wear indications which did not show wear and are classified as INR. There is no wear associated with the indications classified as INR, and therefore, those indications are not counted as wear in U1 R33, but are still included in Table 5-6 of Reference (2). Page 2 of 3 Additional reviews of the Eddy Current Database identified additional GEO indications. Table 5-6 of Reference (2) did not include GEO indications because they are geometric distortions without wear and are tracked for additional analysis in future inspections. Based on additional review of the Eddy Current Database, the original report should have stated there were 13 tubes with 14 GEO indications, 10 tubes with wear indications, and 7 tubes with 7 INR as part of monitoring from previous outages for a total of 30 tubes with 31 indications.
In future reports, GEO indications will not be counted as mechanical wear. RAI 6 - Several foreign objects were left in steam generator A. Please confirm that an engineering analysis was performed to assess the acceptability of leaving these objects in the steam generator until the next inspection.
NextEra Response Three sludge rocks and two wire bristles were not retrieved from SG A. The wire bristles were 0.005 inches in diameter and a length of 0.125 inches. There is no reported history of tube damage from a sludge rock and the sludge rocks not retrieved from SG A were determined to be harmless. The wire bristles have essentially no mass associated with them and would not affect tube integrity. Longer wire bristles have previously been reported in the Unit 1 SGs and those evaluations provide a bounding analysis for the smaller wire bristles identified in U1 R33. A foreign object search and retrieval (FOSAR) is scheduled following sludge lancing for both SGs in U1 R34. References (1) NRC letter to NextEra Energy Point Beach, LLC, dated August 28, 2012, Point Beach Nuclear Plant, Unit 1 - Request for Additional Information Regarding the Fall 201 1 Steam Generator Tube Inservice lnspection Report (TAC No.
ME8780) (ML12234A460)
(2) NextEra Energy Point Beach, LLC letter to NRC, dated May 29, 2012, Fall 201 1 Unit 1 (U1 R33) Steam Generator Tube lnspection Report (MLI 21 50A287) Page 3 of 3