Letter Sequence Response to RAI |
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MONTHYEARL-08-106, License Renewal Application Amendment No. 3 Related to Appendix E-Applicant's Environmental Report, Severe Accident Mitigation Alternatives (SAMA) Information2008-03-28028 March 2008 License Renewal Application Amendment No. 3 Related to Appendix E-Applicant's Environmental Report, Severe Accident Mitigation Alternatives (SAMA) Information Project stage: Other NRC 2008-0044, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control2008-07-24024 July 2008 License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control Project stage: Request ML0825301712008-09-10010 September 2008 Acceptance Review for License Amendment Request Number 247 Spent Fuel Pool Criticality Control-Supplemental Information Required TAC Nos. MD9321 and MD9322) Project stage: Acceptance Review NRC 2008-0071, Supplement to License Amendment Request Number 247, Spent Fuel Pool Storage Criticality Control2008-09-19019 September 2008 Supplement to License Amendment Request Number 247, Spent Fuel Pool Storage Criticality Control Project stage: Supplement ML0826711132008-09-25025 September 2008 Acceptance Review for License Amendment Request Numbers 247 Spent Fuel Pool Criticality Control Project stage: Acceptance Review ML0831108992008-11-18018 November 2008 FPL Energy Point Beach, LLC - Request for Withholding of Proprietary Information from Public Disclosure for Point Beach Nuclear Plant, Units 1 and 2 Project stage: Withholding Request Acceptance NRC 2009-0037, Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control2009-04-14014 April 2009 Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control Project stage: Response to RAI NRC 2009-0057, Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control2009-05-22022 May 2009 Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control Project stage: Response to RAI NRC 2009-0073, Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control2009-08-0707 August 2009 Response to Request for Additional Information License Amendment Request 247 Spent Fuel Pool Storage Criticality Control Project stage: Response to RAI 2008-09-19
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Category:Letter
MONTHYEARML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, 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 Applications2024-03-13013 March 2024 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 IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24036A2652024-02-0505 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 2024-09-09
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Point Beach Nuclear Plant April 14, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Units 1 and 2 Docket No. 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Response to Request for Additional lnformation License Amendment Reauest 247 Spent Fuel Pool Storarre Criticalitv Control NRC 2009-0037 10 CFR 50.90 (1) FPL Energy Point Beach Letter to NRC, License Amendment Request 247, Transmittal of Changes to Technical Specifications re: Spent Fuel Pool Storage Criticality Control, dated July 24, 2008 (ML082240685) (2) FPL Energy Point Beach Letter to NRC, Supplement to License Amendment Request Number 247, Spent Fuel Pool Storage Criticality Control, dated September 19, 2008 (ML082630114) (3) NRC letter to FPL Energy Point Beach, Point Beach Nuclear Plant, Units I and 2 - Request for Additional lnformation from CSGB Branch Related to License Amendment Request No. 247 Spent Fuel Pool Storage Criticality Control, dated March 16, 2009 (TAC Nos. MD9321 and MD9322) (ML 090650276) FPL Energy Point Beach, LLC submitted a proposed license amendment request for Commission review and approval pursuant to 10 CFR 50.90 for the Point Beach Nuclear Plant (PBNP), Units I and 2 (Reference I). The proposed amendment revises the licensing basis to reflect a revision to the spent fuel pool (SFP) criticality analysis methodology. The revised criticality analysis for the SFP storage racks credits burnup, integral fuel burnable absorber (IFBA), Plutonium-241 decay, and soluble boron, where applicable. FPL Energy Point Beach provided a supplemental response (Reference 2) containing additional quantitative information to support the fidelity of key methodology aspects described in Reference (1). On March 6,2009, a teleconference was held between NRC and FPL Energy Point Beach personnel to discuss additional information that was requested by the Commission to enable further review of the application. During the teleconference, FPL Energy Point Beach stated that the response to the request for additional information would be submitted within 30 days of receipt. Enclosure 1 of this letter provides the FPL Energy Point Beach response to the request for additional information in Reference (3). Enclosure 2 provides a drawing of the poison insert assembly and details. An FPL Group company Document Control Desk Page 2 This supplement does not affect the no significant hazards conclusion, as defined in 10 CFR 50.92, provided in Reference (I). This letter contains no new commitments and no revisions to existing commitments. 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 and enclosed information is true and correct. Executed on April 14, 2009. Very truly yours, FPL Energy Point Beach, LLC Larry Meyer Site Vice President
Enclosures:
cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW ENCLOSURE I FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 247 SPENT FUEL POOL STORAGE CRITICALITY CONTROL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The following information is provided by FPL Energy Point Beach, LLC in response to the NRC staff's request for additional information dated March 16, 2009. Question I In the application, the licensee is proposing to no longer credit Boraflex for criticality in Point Beach's Boraflex storage racks. Currently, the licensee is committed to periodic sampling of the Boraflex in the spent fuel pool as stated in their October 23, 1996, response to Generic Letter 96-04, "Boraflex Degradation in the Spent Fuel Pool Storage Racks. " However, it is not clear in the submittal whether the licensee is intending to continue the Boraflex Monitoring Program. Please clarify whether the existing Boraflex Monitoring Program will continue to be implemented. FPL Enernv Point Beach Response The Boraflex Surveillance Program described in the letter dated October 23, 1996, was discontinued on December 21, 2006. Commitments to implement a Boraflex monitoring program for the period of extended operation remain in place. The Boraflex monitoring program commitments made for the period of extended operation will be discontinued when the proposed license amendment is approved. Question 2 If the Boraflex monitoring program will be discontinued as a result of this proposed license amendment request, please explain how Point Beach will be able to identify and mitigate any degradation of the Boraflex that may impede other plant operations. Examples may include excessive silica levels impacting the spent fuel pool chemistry or an unforeseen damage mechanism to the Boraflex cladding that may impact safe fuel handling, The spent fuel pool water is sampled for silica monthly. Periodic sampling of silica levels in the spent fuel pool will continue. The PBNP operating experience program provides sharing of industry lessons learned. This program will provide industry information for new Boraflex problems that may impede plant operations. The Boraflex poison panels at PBNP are designed with openings at the top of each panel. These openings allow gas to vent, precluding warping of the poison panels that could impact safe fuel handling. A drawing of the poison panel construction is included in Enclosure 2.
ENCLOSURE 2 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 PBNP DRAWING OF POISON INSERT ASSEMBLY AND DETAILS 1 page follows