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Category:Letter type:NRC
MONTHYEARNRC 2024-0007, Ile Post-Exam Submittal Letter2024-03-18018 March 2024 Ile Post-Exam Submittal Letter NRC-2024-0026, Ile Proposed Exam Submittal Letter2023-12-20020 December 2023 Ile Proposed Exam Submittal Letter NRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary 2024-03-18
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October 16,2009 POINT BEACH NRC 2009-0096 TS 5.6.8 U.S. Nuclear Regulatory Commission AlTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit I Docket 50-266 Renewed License No. DPR-24 Res~onse to Request for Additional Information Fall 2008 Unit 1 (U1 R31) Steam Generator Tube lns~ection Re~ort
Reference:
(1 NextEra Energy Point Beach, LLC letter to NRC, dated May 7, 2009, Fall 2008 Unit 1 (Ul R31) Steam Generator Tube lnspection Report (ML091280187) (2) NRC letter to NextEra Energy Point Beach, LLC dated September 25, 2009, Point Beach Nuclear Plant, Unit I - Request for Additional lnformation Regarding the 2008 Steam Generator Tube Inservice lnspection Reports for Refueling Outage 31 (TAC No. ME1 247) (ML092650639) NextEra Energy Point Beach, LLC (NextEra) submitted the Fall 2008 Unit I Steam Generator Tube lnspection Report via Reference (I), documenting the scope and results of the inspection in accordance with Technical Specification 5.6.8 reporting requirements. Reference (2) transmitted the NRC staff's request for additional information. Enclosure I provides the NextEra response to Reference (2). This letter contains no new commitments and no revisions to existing commitments. Very truly yours, NextEra Energy Point Beach, LLC James Costedio Licensing Manager Point Beach Nuclear Plant 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, UNIT I RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FALL 2008 (UlR31) STEAM GENERATOR TUBE INSPECTION REPORT The following information is provided by NextEra Energy Point Beach, LLC in response to the NRC staff's request for additional information (Reference I) regarding the Fall 2008 Unit 1 (Ul R31) Steam Generator Tube lnspection Report. Question 1 It was indicated that a visual foreign object search and retrieval was performed at various locations on the secondary side of the steam generators (SGs). Please discuss the scope and results of any other secondary side inspections performed. Response During Ul R31, the scope of the secondary side visual inspections included the following for both SG A and SG B: e Steam drum (upper shell and upper internals including primary and secondary moisture separator assemblies), feedwater ring and J-nozzles a Top (sixth) support plate quatrefoil inspection e Flow distribution baffle (FDB) e Post-chemical cleaning and sludge lance cleanliness visual inspection and foreign object search and retrieval (FOSAR) SG A and B Inspection Results A visual inspection of the steam drum and upper internals was conducted. Residual dry chemical residue and rust coloring was noted on much of the components post-chemical cleaning. Flow impingement patterns were seen on the feedwater ring, on the outside of some primary moisture separator riser barrels as well as under and around several J-nozzles, as previously reported. Erosion of the feedwater ring and riser barrel areas was not discernable by touch. Inside the feedwater ring, possible wear marks were noted in SG B nearing the tee at the bottom concaved portion of the distribution ring with no discernable pattern. These will be monitored as part of the secondary side integrity program. Thin wafers of rust colored debris were noted in-bundle of the primary separator riser barrels. The consistency was brittle, breaking apart easily in hand, and is likely magnetite or scale pieces fallen from the riser tubes. Page 1 of 3 An inspection of the top (sixth) support plate was conducted. No anomalies on the lower U-bends or foreign objects on the support plate were observed. Quatrefoils were inspected as well. The degree of blockage within observed individual foils was 0%. Based on these visual inspections, overall aggregate blockage is estimated to be 0%. Scale was visible in crevices, but no pattern was discernable as to extent or location. The flow distribution baffle was noted as clean with no discernable scale on the tubes or in crevice regions. Tubesheet cleanliness and FOSAR visual inspections included the annulus, no-tube lane and select in-bundle columns during U1 R31 following chemical cleaning and sludge lancing. FOSAR results are as previously reported in Reference (2). Cleanliness visuals showed the annulus free of debris or sludge. The no-tube lane contained diminished remnants of sludge debris ranging from 114 to 112" high and confined to the center stay rod area. In-bundle visual examinations revealed remnant skeletal bridging and collars within the previous sludge pile region limited to a few columns near the center. Question 2 In prior SG reports it was indicated that the sludge height could have exceeded 3 inches. It was indicated that for outer diameter stress corrosion cracking in the sludge pile, an examination for 3 inches above and below the top of the tubesheet was performed. Please discuss why the entire sludge pile height was not inspected with a rotating probe. Please discuss whether the chemical cleaning reduced the sludge pile height. Response The sludge height estimated in Reference (3) was based upon eddy current test results. Based on industry experience and guidance, the highest likelihood of outer diameter stress corrosion cracking within the sludge pile is on the hot leg, near the transition zone, given the stress region and possible chemical concentration point. A 100% +pointTM examination of the hot leg top of tubesheet was conducted following chemical cleaning. In addition to the +pointTM examination, a 100% examination of tubing in this region was conducted using a bobbin coil. Visual examinations showed the sludge pile was essentially eliminated except for remnant skeletal bridging and collaring. No explicit measuring of the collars were made, however visual inspection supports a highest estimated collar of approximately 1 ". Question 3 It was indicated that 34 indications of wear were identified in 27 tubes near the top of the tubesheet in SG A. Please discuss why table 3 does not list all 34 indications. If the indications were not sized, please discuss the basis for keeping these tubes in service. As described in Reference (2), there were 27 tubes with 34 bobbin probe indications in SG A attributed to mechanical wear above the top of tubesheet. Based on subsequent examination using +pointTM probes, Table 3 represents those indications which were confirmed as mechanical wear degradation. The remaining indications that did not confirm as wear based on subsequent +pointTM probe examination remained in service and were assigned a tracking code for monitoring in future inspections. Page 2 of 3 References (1) NRC letter to NextEra Energy Point Beach, LLC dated September 25, 2009, Point Beach Nuclear Plant, Unit I - Request for Additional Information Regarding the 2008 Steam Generator Tube Inservice lnspection Reports for Refueling Outage 31 (TAC No. ME1247) (ML092650639) (2) NextEra Energy Point Beach, LLC letter to NRC, dated May 7, 2009, Fall 2008 Unit I (Ul R31) Steam Generator Tube lnspection Report (ML091280187) (3) FPL Energy Point Beach, LLC letter to NRC, dated March 14, 2008, Spring 2007 Unit 1 (U1 R30) Steam Generator Tube lnspection Report (ML080770187) Page 3 of 3