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MONTHYEARML0510504842005-04-15015 April 2005 RAI, Licensing Basis for Control of Heavy Loads Project stage: RAI ML0602403642005-06-20020 June 2005 Westinghouse Report Plastic Analysis of Point Beach Reactor Coolant Piping for Reactor Vessel Head Drop, Revision 1 Dated June 20, 2005 Project stage: Request ML0517904092005-08-11011 August 2005 Errata to Safety Evaluation for Amendment No. 225, Dated June 24, 2005 Project stage: Approval NRC 2005-0079, Request for Withholding of Proprietary Information from Public Disclosure2005-09-0101 September 2005 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Request NRC 2005-0117, Request for Withholding of Proprietary Information from Public Disclosure2005-09-0707 September 2005 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Request ML0601200792006-01-23023 January 2006 Withholding Information from Public Disclosure, WEP-05-318-P - Attachment, Point Beach Unit 2 Reactor Vessel CMTRs Project stage: Other ML0602400292006-02-0909 February 2006 Document Reclassified as Non-Proprietary Project stage: Other ML0603000432006-02-13013 February 2006 Document Reclassified as Non-Proprietary Project stage: Other ML0605304542006-02-20020 February 2006 Fax from Licensee Regarding 2005 Steam Generator Tube Inspections at Salem, Unit 2 Project stage: Other 2005-09-07
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24215A2092024-08-0101 August 2024 NRR E-mail Capture - Final RAI - Point Beach 1 & 2 - License Amendment Request to Modify Containment Average Air Temperature Requirements ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 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 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 ML23136A2802023-05-0505 May 2023 SLRA Second Annual Update RAI Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22266A0872022-09-23023 September 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22172A1192022-06-27027 June 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-505 Provide Risk Informed Extended Complete Times - RITSTF Initiative 4B ML22130A5712022-05-12012 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21362A6812021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6702021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21273A0222021-09-29029 September 2021 SLRA Safety RAI Set 9 Final ML21287A0862021-09-29029 September 2021 SLRA Safety RAI Set 11 Final ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2472021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2202021-08-20020 August 2021 SLRA Safety RAI Set 7 Final ML21242A2142021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email ML21242A0152021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2392021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2032021-08-12012 August 2021 Srla Safety RAIs Set 5 Final ML21242A2382021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A2042021-08-12012 August 2021 SLRA Safety RAIs Set 5 Final Email ML21242A0122021-08-0909 August 2021 SLRA Draft Safety RAIs Set 6 ML21285A1212021-08-0505 August 2021 SLRA Public Meeting Discussion Questions August 5 2021 ML21242A2002021-08-0505 August 2021 SLRA Draft Safety RAIs Set 5 Email ML21242A1992021-08-0505 August 2021 Srla Draft Safety RAIs Set 5 ML21238A2322021-08-0404 August 2021 SLRA Safety RAI Set 4 Final Email ML21238A2332021-08-0404 August 2021 SLRA Safety RAI Set 4 Final ML21237A0062021-08-0202 August 2021 SLRA Draft Safety RAIs Set 4 ML21208A1892021-07-27027 July 2021 SLRA Safety RAIs Set 2 Final 2024-08-01
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Text
April 15, 2005 Mr. Dennis Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR POWER PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSING BASIS FOR CONTROL OF HEAVY LOADS (TAC NO. MC6729)
Dear Mr. Koehl:
During a planned inspection of your reactor vessel head replacement activities, the U.S.
Nuclear Regulatory Commission (NRC) regional inspectors asked to review the head-drop analysis for the replacement head. In response, by letter dated April 12, 2005, you provided clarification of your licensing basis for control of heavy loads associated with the containment polar cranes and reactor vessel head replacement activities. On April 12, 2005, we requested you to provide information regarding adequate protection of public health and safety during the reactor vessel head movement activities. Subsequently, the NRC staff has had several telephone discussions with you regarding this subject.
The NRC staff has identified in the enclosure specific information needed to ensure adequate protection of public health and safety during the reactor vessel head movement activities.
These questions were emailed to you on April 14, 2005. This letter documents these questions.
Aldo Capristo of your staff agreed to provide responses to these questions by April 15, 2005.
If you have any questions regarding this matter, please call me at (301) 415-2429 or your Project Manager at (301) 415-4018.
Sincerely,
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-301
Enclosure:
As stated cc w/encl: See next page
ML051050484 Pat Louden concurrence by phone 4/15/05 OFFICE PM:PDIII-1 PM:PDIII-1 LA:PDIII-1 SC:PDIII-1 NAME MPadovan HChernoff DClarke LRaghavan DATE 4/15/05 4/15/05 4/15/05 4/15/05 Point Beach Nuclear Plant, Unit 2 Clarification of Licensing Basis for Control of Heavy Loads Request for Additional Information Docket No. 50-301 Question 1 Is a reactor vessel head-drop analysis within the plant's current licensing basis? Please explain the basis for your position.
Question 2 Please explain how you have evaluated the potential for a head drop, and discuss your acceptance criteria.
Question 3 Provide a risk assessment based on the best information on initiating event frequency for a head-drop event. This assessment could be based on the WESTEC assessment, NUREG 1774, A Survey of Crane Operating Experience at U.S. Nuclear Power Plants from 1968 through 2002, or other sources with technically-justified and explained adjustments based on Point Beach-specific information.
Question 4 If Point Beach intends to rely on the WESTEC assessment, please submit it to the NRC to be placed on your plant docket.
Question 5 Discuss the mitigation strategies and measures that are in place, or will be put in place, prior to the proposed head lift. This should include a discussion of how these strategies and measures are implemented. This discussion does not need to be limited to just the "worst case" scenario, and could include any available additional information concerning consequences of the head-drop evaluation that the NRC may use to broaden its understanding of likely head-drop scenarios.
Enclosure
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Mr. Jeffery Kitsembel Vice President, Counsel & Secretary Electric Division Nuclear Management Company, LLC Public Service Commission of Wisconsin 700 First Street P.O. Box 7854 Hudson, WI 54016 Madison, WI 53707-7854 Mr. F. D. Kuester Nuclear Asset Manager President & Chief Executive Officer Wisconsin Electric Power Company WE Generation 231 West Michigan Street 231 West Michigan Street Milwaukee, WI 53201 Milwaukee, WI 53201 John Paul Cowan Regulatory Affairs Manager Executive Vice President & Chief Nuclear Point Beach Nuclear Plant Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 6610 Nuclear Road 700 First Street Two Rivers, WI 54241 Hudson, WI 54016 Mr. Ken Duveneck Douglas E. Cooper Town Chairman Senior Vice President - Group Operations Town of Two Creeks Palisades Nuclear Plant 13017 State Highway 42 Nuclear Management Company, LLC Mishicot, WI 54228 27780 Blue Star Memorial Highway Covert, MI 49043 Chairman Public Service Commission Site Director of Operations of Wisconsin Nuclear Management Company, LLC P.O. Box 7854 6610 Nuclear Road Madison, WI 53707-7854 Two Rivers, WI 54241 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241