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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 3,201 0 NRC 2010-0141 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units I and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 241 Alternate Source Term Res~onse to Request for Additional lnformation
References:
(1) FPL Energy Point Beach, LLC letter to NRC, dated December 8, 2008, License Amendment Request 241, Alternate Source Term (ML083450683) (2) NRC letter to NextEra Energy Point Beach, LLC, dated January 5, 2010, Point Beach Nuclear Plant, Units 1 and 2 - Request for Additional lnformation Regarding Alternate Source Term (TAC Nos. ME0219 and ME0220) (ML093630246) (3) NextEra Energy Point Beach, LLC letter to NRC, dated February 4, 2010, License Amendment Request 241, Alternate Source Term, Response to Request for Additional lnformation (MLI 00360065) NextEra Energy Point Beach, LLC (NextEra) submitted License Amendment Request (LAR) 241 (Reference 1) to the NRC pursuant to 10 CFR 50.90. The proposed amendment would revise the current licensing basis to implement the alternative source term (AST) through reanalysis of the radiological consequences of the Point Beach Nuclear Plant (PBNP) final safety analysis report (FSAR) Chapter 14 accidents. Via Reference (2), the NRC staff determined that additional information was required to enable the staff's continued review of Reference (1). NextEra responded to the NRC request via Reference (3). During a telephone conference on August 25, 201 0, the NRC requested additional information to complete the review of the response provided in Reference (3). The NextEra response to the request for additional information is provided in Enclosure 1. This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments. NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 Document Control Desk Page 2 The information contained in this letter does not alter the no significant hazards consideration contained in Reference (I) and continues to satisfy the criteria of 10 CFR 51.22 for categorical exclusion from the requirements of an environmental assessment. In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Wisconsin Official. I declare under penalty of perjury that the foregoing is true and correct. Executed on September 3,201 0. Very truly yours, NextEra Energy Point Beach, LLC se President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW ENCLOSURE l NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS l AND 2 LICENSE AMENDMENT REQUEST 241 EXTENDED POWER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION During a telephone conference conducted on August 25, 2010, the NRC determined that additional information was required to enable the staff's continued review of License Amendment Request (LAR) 241, Alternative Source Term (Reference I). The following information is provided by NextEra Energy Point Beach, LLC (NextEra) in response to the NRC staff's request. Question I Provide a summary of the LOCA control room dose analysis performed without credit for the VNPAB that was referenced in the response to Question 4 of the NRC's request for additional information dated January 5, 2010. NextEra Response As stated in the response to Question 4 of Reference 2, to address the common plenum condition, NextEra performed dose analyses, without credit for the primary auxiliary building ventilation WNPAB) system for large-break loss-of-coolant accident. The analysis used was the same that was used for the alternative source term methodology that was submitted to the NRC in Reference I. The assumptions are the same used in Reference I except that the control room X/Q values for the run considering emergency core cooling system (ECCS) leakage to the PAB were revised to reflect no credit for VNPAB, and flashing fractions for ECCS leakage were revised based on the time dependent sump temperature. The values appropriate for releases without the VNPAB in service are listed below and compared to the values modeled in Reference 1. Page 1 of 3 Time Period 0-2 hours 2-8 hours 8-24 hours 24-96 hours96-720 hours Control Room X/Q Assuming VNPAB In Service (sec/m3) I .80E-3 1.31 E-3 5.15E-4 4.03E-4 3.03E-4 Control Room X/Q Assuming VNPAB Out of Service (sec/m3) 6.78E-3 5.03E-3 I .72E-3 I .60E-3 1.34E-3 With regard to flashing fractions for ECCS leakage based on sump temperature, the assumptions in Reference I were revised as follows: This model assumes that the airborne fraction is approximately 0.01 above the calculated flashing fraction and that when the value calculated in this manner drops below 0.02 a value of 0.02 is assumed. This minimum airborne fraction is maintained for the 30-day duration of the event. The flashing fraction is determined based on Regulatory Guide (RG) I .I 83 Appendix A, Position 5.4. The flashing fraction is calculated by: FF = ha -ha hfg where: hfl is the enthalpy of the sump fluid. This is evaluated using the time dependant sump temperature and the system design pressure he is the enthalpy of liquid at saturation conditions (14.7 psia, 212°F) = 180.16 Btullbm hfg is the heat of vaporization at 212°F = 970.3 Btullbm Table I below presents the points selected from the sump temperature data to develop the airborne fractions assumed in this case. The value in each time period is based on the maximum temperature in that period. The calculated time-dependant flashing fraction is presented in the figure below compared to the assumed airborne fraction. Table 1: Airborne Fractions Page 2 of 3 Assumed Airborne Fraction 0.07 0.06 0.05 Time Period (Seconds) 0 - 1800 1800 - 2700 2700 - 3600 Sump Temperature (OF) 265.8 258.5 243.8 Calculated Flashing Fraction 0.056 0.049 0.033 The flashing fraction methodology was developed consistent with that applied for the R.E. Ginna Nuclear Power Plant AST Analysis submitted via Reference 3 (ML042020571), and subsequently approved by the NRC in Reference 4 (ML050320491). Flashing Fraction Airborne Fraction Utilizing the AST methodology provided in Reference I, and applying the same Reference I inputs with the exception of the ones noted above, the revised LOCA Control Room dose analysis results in the following total effective dose equivalent (TEDE) values: 0.1EtOO 0.8E 0.6E Control Room - All Pathways (excludes shine) 4.23 REM Control Room - Shine 0.28 REM Control Room - Total Dose 4.51 REM - - - - - - - I---, Considering operation of VNPAB has no influence on offsite doses for LOCA, the exclusion area boundary and low population zone doses presented in Reference I remain valid. .- + 0 e L" 0.4E 0.2E ---------- 01"1'1'"1 I I I 0 2000 4000 6000 8000 Time (sec) References (1) FPL Energy Point Beach, LLC letter to NRC, dated December 8, 2008, License Amendment Request 241, Alternative Source Term (ML083450683) (2) NextEra Energy Point Beach, LLC letter to NRC, dated February 4, 2010, License Amendment Request 241, Alternate Source Term, Response to Request for Additional Information (MLI 00360065) (3) Constellation Energy letter to NRC, dated July 14, 2004, R.E. Ginna Nuclear Power Plant, Revised Atmospheric Dispersion Factors (x/Q) and Dose Analysis (ML042020571) (4) NRC letter to Constellation Energy, dated February 25, 2005, R.E. Ginna Nuclear Power Plant -Amendment Re: Modification of the Control Room Emergency Air Treatment System and Change to Dose Calculation Methodology to Alternate Source Term (TAC No. MB9123) (ML050320491) Page 3 of 3