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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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September 12, 2013 NRC 2013-0076 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 NextEra Energy Point Beach. LLC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites
References:
(1) NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 [ML12073A348]
(2) NRC Letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2013 [ML12319A074]
(3) EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic
[ML12333A170]
(4) NEI Letter to NRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April9, 2013 [ML13107B386]
(5) NRC Letter, EPRI Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Near-Term Task Force Recommendation 2.1 : Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 [ML13106A331]
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee in the Central and Eastern United States (CEUS) to submit a written response consistent with the requested seismic hazard evaluation information (items 1 through 7) by September 12, 2013. On February 15, 2013, NRC issued Reference 2, endorsing the Reference 3 industry guidance for responding to Reference 1. Section 4 of Reference 3 identifies the detailed information to be included in the seismic hazard evaluation submittals.
NextEra Energy Point Beach, LLC, 6610 Nuclear Road , Two Rivers, WI 54241
Document Control Desk Page 2 On April 9, 2013, NEI submitted Reference 4 to NRC, requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the EPRI (2004, 2006) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 5, NRC agreed with this recommendation.
The enclosure to this letter contains the requested descriptions of subsurface materials and properties and base case velocity profiles for Point Beach Nuclear Plant, Units 1 and 2. The information provided in the enclosure to this letter is considered an interim product of seismic hazard development efforts being performed for the industry by EPRI. The complete and final seismic hazard report for Point Beach will be provided to the NRC by March 31 , 2014 in accordance with Reference 5.
This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.
If you have any questions please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845.
I declare under penalty of perjury that the foregoing is true and correct. Executed on September 12, 2013.
Very truly yours ,
NextEra Energy Point Beach , LLC
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/ . rr {Meyer U te Vice President Enclosure cc: Director, Office of Nuclear Reactor Regulation Administrator, Region Ill, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Ms. Sue Perkins-Grew, NEI
ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT SEISMIC HAZARD EVALUATION INFORMATION 1.0 Point Beach Site Description The basic information used to create the site geologic profile at the Point Beach Nuclear Power Plant is shown in Table 1. This profile was developed using information documented in References 1, 5, 6 and 7. The profiles were developed up to elevation- 22 feet, the elevation of the deepest foundation at the Point Beach site. The use of this elevation for the Ground Motion Response Spectra (GMRS) comparison to the Safe Shutdown Earthquake (SSE) will be verified as part of the final report.
For dynamic properties of lake deposits and glacial till layers, modulus and damping curves were represented with two models. The first model used soil curves taken from Reference 2, the second model used soil curves taken from References 3 and 4. These dynamic property models were weighted equally.
The three base-case shear-wave velocity profiles used to model amplification at the site are shown in Figure 1. The profiles are a generalization of the *data in Table 1, appropriate for glacial till and glacial outwash. Profiles 1, 2, and 3 are weighted 0.4, 0.3, and 0.3, respectively.
Thicknesses, depths, and shear-wave velocities (Vs) corresponding to each profile are shown in Table 2.
Table 1 Shear 5 4 Modulus of Shear 1 Soil/ Rock Density Poisson's Dampinp Wave Elevation 5 Elasticity 5 Modulus 5
4 Description (pcf) Ratio Percent ' 5 Velocity (psf} (psf)
(fps) 7 7
+26' to +10' Glacial till 130 0.45 3.0x10 1.0 X 10 20 900
+1 0' to -5' Lake deposits 1.5x 10 6
1.5 X 106 4 125 0.49 30 900
-5' to -25' Lacustrine Footnote 3 Footnote 3
-25' to -35' 960 Glacial till and 7 7
-35' to -50' 130 0.45 3.0x10 1.0x10 20 1,000 glacial outwash
-50' to -75' 1,030 Bedrock (Niagara 8 below -75' 175 0.25 1.8 X 109 7.5x10 -- 12,000 Dolomite)
Footnotes:
- 1. Reference elevation 0' is the City of Milwaukee Datum.
- 2. Expressed as a percentage of critical damping.
- 3. The moduli for the Lake Deposits should be decreased by 10% for dynamic loads which will be acting on the soil for a large number of repetitions such as an SSE.
- 4. Reference Report, Point Beach Nuclear Plant IPEEE, Two Creeks, Wisconsin, dated June 1995.
Shear wave velocities are Recommended 'Best Estimate' Values.
- 5. From Dames & Moore Report of Foundation Investigation, Proposed Nuclear Power Plant, Point Beach Nuclear Power Station, Two Creeks, Wisconsin for the Wisconsin Michigan Power Company.
Page 1 of 3
Figure 1 Vs Profiles for Point Beach Site Vs profiles for Point Beach Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0
5 10 15 20 - Profile1
~ 25
- E. - Profile2
£D. 30 - Profile3 QJ 0 35 40 45 50 55 60 Table 2 Layer Thicknesses, Depths, and Vs for Three Profiles Point Beach Site Profile 1 Profile 2 Profile 3 Thickness Depth Vs Thickness Depth Vs Thickness Depth Vs (ft) (ft) (fUs) (ft) (ft) (fUs) (ft) (ft) (fUs) 0 1000 0 637 0 1570 5.0 5.0 1000 5.0 5.0 637 5.0 5.0 1570 5.0 10.0 1000 5.0 10.0 637 5.0 10.0 1570 5.0 15.0 1000 5.0 15.0 637 5.0 15.0 1570 5.0 20.0 1000 5.0 20.0 637 5.0 20.0 1570 5.0 25.0 1000 5.0 25.0 637 5.0 25.0 1570 5.0 30.0 1000 5.0 30.0 637 5.0 30.0 1570 5.0 35.0 1000 5.0 35.0 637 5.0 35.0 1570 5.0 40.0 1000 5.0 40.0 637 5.0 40.0 1570 5.0 45.0 1000 5.0 45.0 637 5.0 45.0 1570 5.0 50.0 1000 5.0 50 .0 637 5.0 50.0 1570 2.0 52.0 1000 2.0 52.0 637 2.0 52.0 1570 3280.8 3332.8 9285 3280.8 3332.8 9285 3280.8 3332.8 9285 Page 2 of 3
2.0 References (1) Point Beach Updated Final Safety Analysis Report, Sections 1.1 , "Site and Environment", 2.2, "Topography" and 2.8, "Geology" (2) EPRI (1993), Guidelines for Determining Design Basis Ground Motions, Electric Power Research Institute, Palo Alto, CA, Report TR-102293, Volumes 1-5 (3) Silva, W.J., N. A. Abrahamson, G.R. Toro, and C. Costantino (1996), Description and Validation of the Stochastic Ground Motion Model, Report submitted to Brookhaven National Laboratory, Assoc. Universities Inc., Upton NY 11973, Contract No. 770573 (4) Walling , M.A., W.J., Silva and N.A. Abrahamson (2008), "Nonlinear Site Amplification Factors for Constraining the NGA Models," Earthquake Spectra, 24 (1) 243-255 (5) "Report of Foundation Investigation, Proposed Nuclear Power Plant, Point Beach Nuclear Power Station, Two Creeks, Wisconsin for the Wisconsin Michigan Power Company", prepared by Dames & Moore; transmitted by letter from Dames & Moore to PBNP, dated December 2, 1966, Cimage Letter No. NPC99-02748 (6) PBNP Design Guideline DG-C03, Revision 1, "Seismic Design Criteria Guideline" (7) Point Beach Nuclear Plant IPEEE, Two Creeks, Wisconsin , dated June 1995, prepared by GEl Consultants, Inc., transmitted by Stevenson & Associates on 4/2/2002, Document Identity 93109, S&A title: "The Final GEl Soil Report Dated June 1995 Developed for the IPEEE Study" Page 3 of 3