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Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
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February 16, 2011 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville IL 60555
SUBJECT:
INFORMATION REQUEST TO SUPPORT UPCOMING INSPECTION OF PREOPERATIONAL TESTING OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION AT THE BRAIDWOOD STATION
Dear Mr. Pacilio,
This letter is to request information to support our inspection of the Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) beginning February 28, 2011, at the Braidwood Station. This inspection will be performed in accordance with U.S. Nuclear Regulatory Commission (NRC) Inspection Procedures 60854.1 and 60856.1.
The inspection will take place in four parts: 1) an off-site review of your calculations used to support heavy loads movements throughout the site with on-site inspection of the structures;
- 2) an on-site review of your Title 10 of the Code of Federal Regulations (CFR) 72.212 Report;
- 3) an off-site review of procedures, evaluations, and programs to demonstrate site readiness to load spent fuel; and 4) on-site observations of dry run operations.
Experience has shown that these inspections are resource intensive both for the NRC inspectors and the utility staff. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection, we have enclosed a list of documents required for the inspection.
The document request is split into two sections. Section A requests documents associated with calculations used to support heavy loads movements throughout the site. Please provide this information to the NRC Region III office no later than February 28, 2011. Section B requests documents covering the balance of the inspection. Please provide this information to the NRC Region III office no later than the first NRC dry run demonstration. The documents requested are necessary to ensure the inspection team is adequately prepared for the inspection. The information may be provided either electronically or in hard copy.
If there are any questions about the material requested, or the inspection in general, please do not hesitate to call or e-mail Mr. Matthew Learn at 630-829-9603 or Matthew.Learn@nrc.gov.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the
M. Pacilio NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011.
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
Sincerely,
/RA/
Christine A. Lipa, Chief Materials Control, ISFSI, and Decommissioning Branch Division of Nuclear Materials Safety Docket Nos. 50-456; 50-457;72-073 License Nos. NPF-72; NPF-77
Enclosures:
- 1. Requested Information for NRC Inspection of Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) - Section A
- 2. Requested Information for NRC Inspection of Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) - Section B cc w/encl: Distribution via ListServe
M. Pacilio NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011.
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
Sincerely,
/RA/
Christine A. Lipa, Chief Materials Control, ISFSI, and Decommissioning Branch Division of Nuclear Materials Safety Docket Nos. 50-456; 50-457;72-073 License Nos. NPF-72; NPF-77
Enclosures:
- 1. Requested Information for NRC Inspection of Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) - Section A
- 2. Requested Information for NRC Inspection of Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) - Section B cc w/encl: Distribution via ListServe
- See previous concurrence DOCUMENT NAME: G:\DNMSIII\Work in progress\Braidwood Pre-Op RFI.doc Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl N" = No copy OFFICE RIII DNMS C RIII DNMS RIII RIII NAME MCLearn: jm MCL CALipa CAL DATE 02/15/11 02/16/11 OFFICIAL RECORD COPY
Requested Information for NRC Inspection of Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) - Section A
- 1. Design documentation, design calculations, safety evaluations (72.48 and 50.59), and resultant structural modifications that demonstrated the fuel cask could be safely placed into the spent fuel pool and loaded with spent fuel, lifted from the spent fuel pool and placed on the designated laydown areas, transferred to the transport vehicle, and transported to the ISFSI.
- 2. Current spent fuel cask drop analysis or single failure proof crane evaluation including the trolley, the bridge, and the support structure.
- 3. Other supporting documents that demonstrate equipment to maintain safe shutdown will be unaffected (i.e. calculations associated with the spent fuel cask drop analysis) and that potential off-site releases at the exclusion boundary will be within 10 CFR part 100 limits after a postulated spent fuel cask drop (if applicable).
- 4. Calculations for rigging and special lifting devices associated with lifting the spent fuel storage and transfer casks.
- 5. Documents that establish the total lift weights for loaded spent fuel storage and transfer casks.
- 6. Site procedures associated with Control of Heavy Loads, transport of loaded spent fuel storage and transfer casks during plant operations, and any contingency actions taken to mitigate the consequences of a spent fuel storage or transfer cask drop.
- 7. An electronic copy of the Braidwood Station UFSAR.
Enclosure 1
Requested Information for NRC Inspection of Pre-Operational Testing of an Independent Spent Fuel Storage Installation (ISFSI) - Section B
- 1. A copy of the 10 CFR 72.212 report.
- 2. A copy of all 72.48 Screenings performed to date.
- 3. A copy of the ISFSI ALARA plan.
- 4. A copy of calculations and / or drawings described below:
- a. Tornado missile analysis;
- b. Offsite ISFSI dose analysis;
- c. Cask spacing analysis;
- d. Pad cask layout; and
- e. Fire hazards analysis.
- 5. A list of condition reports since January 2009 related to:
- a. Dry cask storage program;
- b. Dry cask storage pad; and
- c. Fuel Handling Building crane.
- 6. A compliance matrix for fuel selected for this campaign indicating that it meets Technical Specifications.
- 7. A copy of the sites emergency plan that incorporates the ISFSI.
- 8. A copy of Fuel Handling Building crane:
- a. Trolley factory acceptance test;
- b. Trolley site acceptance test;
- c. Last periodic inspection;
- d. Last frequent inspection;
- e. Single failure proof compliance matrix; and
- f. Vendor recommendations, site procedures, and documentation of the crane preventive maintenance.
- 9. A copy of helium quality certificates used for helium backfilling of dry cask storage canisters.
- 10. A copy of the internal QA review associated with the ISFSI program if one has been performed.
- 11. A copy of ISFSI related training records for personnel.
- 12. A copy of an ISFSI organizational chart that identify roles and responsibilities of site and corporate personnel.
- 13. A copy of procedures used for ISFSI operations including:
- a. HI-TRAC, HI-STORM, and MPC receipt inspection;
- b. HI-TRAC, HI-STORM, and MPC preparation; Enclosure 2
- c. MPC loading;
- d. MPC processing;
- e. MPC welding;
- f. MPC non-destructive testing;
- g. MPC unloading;
- h. HI-TRAC movement;
- i. HI-STORM movement;
- j. HI-STORM processing;
- k. HI-STORM radiation surveys;
- l. HI-STORM technical specification monitoring;
- m. Fuel selection;
- n. 72.48 screening and evaluation process;
- o. Manual movement of the Fuel Handling Building crane;
- p. Rigging and lifting;
- q. Daily inspection of slings, yoke, and HI-TRAC trunnions; and
- r. ISFSI contingencies.
- 14. A copy of your QA program guidance document.
- 15. A copy of your readiness document including infrequent evolution briefings, if you have prepared one, based on lessons learned from audits at other sites.
- 16. A copy of the latest HI-TRAC trunnion annual testing report.
2 Enclosure 2