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MONTHYEARNRC 2011-0106, License Renewal Commitment Reactor Vessel Lnternals Program Submittal2011-12-19019 December 2011 License Renewal Commitment Reactor Vessel Lnternals Program Submittal Project stage: Other ML12159A1132012-06-0707 June 2012 Draft RAI on Reactor Vessel Internals Inspection Plan Project stage: Draft RAI ML12198A0502012-07-10010 July 2012 E-mail Point Beach Nuclear Plant Units 1 and 2 - Draft Request for Additional Information Re Reactor Vessel Internals Inspection Plan Project stage: Draft RAI NRC 2012-0052, Reactor Vessel Internals Inspection Plan, Response to Request for Additional Information2012-08-16016 August 2012 Reactor Vessel Internals Inspection Plan, Response to Request for Additional Information Project stage: Response to RAI ML13036A3002013-01-31031 January 2013 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information (Second Round) Reactor Vessel Internals Inspection Plan Review (TAC Nos. ME8235 & ME8236) Project stage: Draft RAI NRC 2013-0029, Reactor Vessel Lnternals Inspection Plan, Response to Request for Additional Lnformation2013-03-15015 March 2013 Reactor Vessel Lnternals Inspection Plan, Response to Request for Additional Lnformation Project stage: Request NRC 2014-0021, Reactor Vessel Internals Inspection Plan Response to Request for Addtional Information2014-04-21021 April 2014 Reactor Vessel Internals Inspection Plan Response to Request for Addtional Information Project stage: Request NRC 2015-0003, Reactor Vessel Internals Inspection Plan Response to Request for Additional Information2015-01-13013 January 2015 Reactor Vessel Internals Inspection Plan Response to Request for Additional Information Project stage: Response to RAI ML15334A2642015-03-30030 March 2015 Official Exhibit - ENT000649-00-BD01 - Letter from D. Pelton, NRC, to E. Mccartney, NextEra Energy Point Beach, Point Beach Np, Units 1 and 2 - Staff Assessment of Reactor Vessel Internals Inspection Plan Based on MRP-227-A Project stage: Other ML15079A0872015-03-30030 March 2015 Staff Assessment of Reactor Vessel Internals Inspection Plan Based on MRP 227 a Project stage: Other ML15222A9172015-03-30030 March 2015 ENT000649 - Letter from D. Pelton, NRC, to E. Mccartney, NextEra Energy Point Beach, Point Beach Nuclear Plant, Units 1 and 2 - Staff Assessment of Reactor Vessel Internals Inspection Plan Based on MRP-227-A (TAC Nos. ME8235 and ME8236)(Mar Project stage: Other 2013-01-31
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Category:Letter type:NRC
MONTHYEARNRC 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 NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
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January 13, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed license Nos. DPR-24 and DPR-27 Reactor Vessel Internals Inspection Plan Response to Request for Additional Information
References:
( 1) NextEra Energy Point Beach, LLC letter to NRC, dated NRC 2015-0003 10 CFR 54 December 19, 2011, License Renewal Commitment, Reactor Vessel Internals Program Submittal (ML 113540301)
(2) NRC electronic mail to NextEra Energy Point Beach, LLC, dated November 21, 2014, Point Beach Nuclear Plant, Units 1 and 2 -Request for Additional Information re: Aging Management Program for Reactor Vessel Internals (TAC ME8235 and ME8236) NextEra Energy Point Beach, LLC (NextEra) submitted the Point Beach Nuclear Plant (PBNP) program NP 7.7.30, Reactor Vessel Internals Program, via Reference (1 ). The PBNP Reactor Vessel Internals Program is based on Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) Technical Report MRP-227, Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines, Revision 0. The NRC determined additional information was required to enable the staff's continued review of the PBNP Reactor Vessel Internals Program (Reference 2). The Enclosure to this letter contains NextEra's response to this request. NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 Document Control Desk Page 2 This letter contains no new or revised Regulatory Commitments.
I declare under penalty of perjury that the foregoing is true and correct. Executed on January 13, 2015. Very truly yours, NextEra Energy Point Beach, LLC Eric McCartney Site Vice President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW ENCLOSURE NEXTERA ENERGY POINT BEACH, POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REACTOR VESSEL INTERNALS INSPECTION PLAN RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By letter dated April 18, 2014 (ML 14111 A050), NextEra Energy Point Beach, LLC (NextEra) provided a response to the U.S. Nuclear Regulatory Commission (NRC) staff's requests for additional information (RAis) regarding the Point Beach Nuclear Plant (PBNP), Units 1 and 2, Reactor Vessel Internals Aging Management Program Plan, which credits the implementation of Materials Reliability Program (MRP)-227-A, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines." The NRC staff in the Vessels and Internals Integrity Branch of the Office of Nuclear Reactor Regulation reviewed the April18, 2014, response and, based on its review, requires additional clarification to NextEra's response to RAI-1 a, as detailed below. RAI-1 a (Follow-up)
Since the NRC staff's submittal of RAI-1a, industry guidance MRP 2013-025 (Reference
- 1) has been approved to answer the issued raised in RA/-1 a. NextEra's response in the April 18, 2014, letter, includes information that answers part of the checklist of issues in MRP 2013-025, but does not clearly address all of the points. As such, in order to demonstrate that PBNP is bounded by MRP-227-A, the staff requests NextEra answer the following questions listed below from MRP 2013-025:
Question 2 Fuel Design or Fuel Management Does the plant have atypical fuel design or fuel management that could render the assumptions of MRP-227-A, regarding core loading/core design, non-representative for the plant?" and, Question 3 Extended Power Uprate (EPU) "If the plant implemented an Extended Power Uprate (EPU), are the peak internal metal temperatures within the assumptions made in developing MRP-227-A
?" Reference
- 1. Electric Power Research Institute letter to MRP, MRP 2013-025, "MRP-227-A Applicability Template Guideline," dated October 14, 2013 (ADAMS Accession No. ML 13322A454).
Page 1 of 3 NextEra Response to Question 2 As stated in the Conclusion Section from MRP 2013-025, "To demonstrate plant-specific applicability of the MRP-227 -A sampling inspection strategy for managing aging in reactor internals, licensees must demonstrate that the criteria of MRP-227 -A, Section 2.4 are met, and that the neutron fluence and heat generation rates are within the range of the following variables summarized.
The limiting threshold values for Westinghouse plants are:
- active fuel-upper core plate distance>
12.2 inches,
- average core power density< 124 Watts/cm3,
- heat generation figure of merit, F :::;;68 Watts/cm3." Both Point Beach Units comply with the MRP-227 -A assumptions regarding core loading/core design. Neutron fluence and heat generation rates are concluded to be acceptable based on the following assessment to the limiting MRP guidance threshold values.
- Distance from top of active fuel to the upper core plate The distance from the top of the active fuel to the upper core plate is 13.2 inches for both Point Beach Units. This meets the requirement of> 12.2 inches.
- Average core power density The average core power density for all cycles evaluated is less than 103 W/cc. This meets the requirement of< 124 W/cc.
- Heat generation figure of merit The highest calculated figure of merit (W/cc) is 63.6 W/cc. This meets the requirement of< 68 W/cc. NextEra Response to Question 3 Point Beach Nuclear Plant Units 1 and 2 reactor thermal power was increased by 17% to 1800 MWt by an extended power uprate (EPU) license amendment.
All EPU fuel cycles for both Units were evaluated.
- Average core power density The average core power density for all cycles evaluated is less than 103 W/cc. This meets the requirement of< 124 W/cc. Page 2 of 3
- Heat generation figure of merit The heat generation figure of merit was determined for each unique corner (assuming eighth-core symmetry) using cycle average assembly powers. The results for each cycle evaluated are provided in the tables below. Unit 1 F (W/cc) Cycle Corner 1 Corner 2 34 56.7 54.5 35 62.4 56.8 36 63.6 54.3 Unit 2 F (W/cc) Cycle Corner 1 Corner 2 32 56.0 59.0 33 55.9 53.1 34 62.7 57.7 As stated in the response to Question 2, the highest calculated figure of merit (W/cc) is 63.6 W/cc which meets the requirement of< 68 W/cc. Given the margin to the requirement in the cycles evaluated, it is expected to be met in future cycles with typical cycle-to-cycle variations.
Note that pre-EPU cycles are bounded by the evaluation above since the pre-EPU average core power density was significantly lower. References
- 1. NextEra Energy Point Beach, LLC letter to NRC, dated December 19, 2011, License Renewal Commitment, Reactor Vessel Internals Program Submittal (ML 113540301)
- 2. NRC electronic mail to NextEra Energy Point Beach, LLC, dated November 21, 2014, Point Beach Nuclear Plant, Units 1 and 2-Request for Additional Information re: Aging Management Program for Reactor Vessel Internals (TAC ME8235 and ME8236) 3. Electric Power Research Institute letter to MRP, MRP 2013-025, "MRP-227 -A Applicability Template Guideline," dated October 14, 2013 (ML 13322A454).
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