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MONTHYEARML0724102492007-09-10010 September 2007 Environmental Assessment, Issuance of Environment Assessment Exemption Request Related to the Use of Areva Np Inc. Advanced Mark-BW(A) Project stage: Approval ML0726102132007-09-27027 September 2007 Exemption from the Requirements of 10 CFR Part 50, Section 46, and Appendix K to Part 50 Project stage: Approval 2007-09-10
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Category:Environmental Assessment
MONTHYEARML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) ML21165A0412021-06-30030 June 2021 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature ML20155K6912020-11-23023 November 2020 Encl. Environmental Assessment Memo to File: Environmental Assessment and Finding of No Significant Impact for Exelon Corporation, LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30 (B) and (C) for Braidwood ISFSI ML20231A4692020-09-0303 September 2020 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature ML18135A1882018-06-13013 June 2018 Environmental Assessment: Exelon Generation Company, LLC - Braidwood, Units 1 and 2; Byron, Unit Nos. 1 and 2; Clinton, Unit No. 1; Dresden, Units 1, 2, and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 2 NRC-2018-0122, Environmental Assessment: Exelon Generation Company, LLC - Braidwood, Units 1 and 2; Byron, Unit Nos. 1 and 2; Clinton, Unit No. 1; Dresden, Units 1, 2, and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 22018-06-13013 June 2018 Environmental Assessment: Exelon Generation Company, LLC - Braidwood, Units 1 and 2; Byron, Unit Nos. 1 and 2; Clinton, Unit No. 1; Dresden, Units 1, 2, and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 2 ML0724102492007-09-10010 September 2007 Environmental Assessment, Issuance of Environment Assessment Exemption Request Related to the Use of Areva Np Inc. Advanced Mark-BW(A) ML0614602842006-09-22022 September 2006 Unit Nos. 1 and 2 - Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of 10 CFR 50.60(a) and 10 CFR Part 50, Appendix G ML0609606242006-05-15015 May 2006 Quad Cities, TMI and Zion Environmental Assessment for Schedular Exemption from 10 CFR 50.54(a)(3) ML0209507042002-04-0505 April 2002 Environmental Assessment and Finding of No Significant Impact of Revising the Fuel Centerline Temperature Safety Limit (TAC MB3013, MB3014, MB3011, and MB3012) 2023-06-12
[Table view] Category:Finding of No Significant Impact
MONTHYEARML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) ML20155K6912020-11-23023 November 2020 Encl. Environmental Assessment Memo to File: Environmental Assessment and Finding of No Significant Impact for Exelon Corporation, LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30 (B) and (C) for Braidwood ISFSI ML18135A1882018-06-13013 June 2018 Environmental Assessment: Exelon Generation Company, LLC - Braidwood, Units 1 and 2; Byron, Unit Nos. 1 and 2; Clinton, Unit No. 1; Dresden, Units 1, 2, and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 2 NRC-2018-0122, Environmental Assessment: Exelon Generation Company, LLC - Braidwood, Units 1 and 2; Byron, Unit Nos. 1 and 2; Clinton, Unit No. 1; Dresden, Units 1, 2, and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 22018-06-13013 June 2018 Environmental Assessment: Exelon Generation Company, LLC - Braidwood, Units 1 and 2; Byron, Unit Nos. 1 and 2; Clinton, Unit No. 1; Dresden, Units 1, 2, and 3; LaSalle, Units 1 and 2; Quad Cities, Units 1 and 2 ML0724102492007-09-10010 September 2007 Environmental Assessment, Issuance of Environment Assessment Exemption Request Related to the Use of Areva Np Inc. Advanced Mark-BW(A) 2023-06-12
[Table view] Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 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 RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
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September 10, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - ISSUANCE OF ENVIRONMENTAL ASSESSMENT RE: EXEMPTION REQUEST RELATED TO THE USE OF AREVA NP INC. ADVANCED MARK-BW(A) FUEL ASSEMBLIES (TAC NOS. MD3083 AND MD3084)
Dear Mr. Crane:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for an exemption dated September 26, 2006, as supplemented on August 8, 2007. The proposed exemption would allow the use of AREVA NP Inc. modified Advanced Mark-BW fuel assemblies.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN 50-457
Enclosure:
Environmental Assessment cc w/encl: See next page
ML072410249 OFFICE LPL3-2/PM LPL3-2/LA DLR/REBA OGC LPL3-2/BC NAME RKuntz EWhitt EBenner RGibbs DATE 8/31/07 8/31/07 8/31/07 9/4/07 9/10/07 Braidwood Station, Units 1 and 2 Chairman, Ogle County Board Post Office Box 357 cc: Oregon, IL 61061 Document Control Desk - Licensing via e-mail Manager Regulatory Assurance -
Braidwood Mr. Dwain W. Alexander, Project Manager via e-mail Westinghouse Electric Corporation via e-mail Director - Licensing and Regulatory Affairs via e-mail Ms. Bridget Little Rorem Appleseed Coordinator Associate General Counsel via e-mail via e-mail Howard A. Learner Senior Vice President - Midwest Operations Environmental Law and Policy via e-mail Center of the Midwest 35 East Wacker Dr., Suite 1300 Vice President - Regulatory Affairs Chicago, IL 60601-2110 via e-mail Braidwood Senior Resident Inspector Manager Licensing - Braidwood, Byron U.S. Nuclear Regulatory Commission and LaSalle via e-mail via e-mail Ms. Lorraine Creek RR 1, Box 182 Manteno, IL 60950 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness via e-mail County Executive via e-mail Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Braidwood Station via e-mail Site Vice President - Braidwood via e-mail Senior Vice President - Operations Support via e-mail
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION EXELON GENERATION COMPANY, LLC DOCKET NOS. STN 50-456 AND STN 50-457 BRAIDWOOD STATION, UNITS 1 AND 2 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 46, and Appendix K to Section 50, for Facility Operating License Nos. NPF-72 and NPF-77, issued to Exelon Generation Company, LLC (the licensee), for operation of the Braidwood Station (Braidwood), Units 1 and 2 located in Will County, Illinois. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would allow the use of AREVA NP Inc. (AREVA) modified Advanced Mark-BW fuel assemblies.
The proposed action is in accordance with the licensees application dated September 26, 2006, as supplemented by letter dated August 8, 2007.
The Need for the Proposed Action:
The proposed action would allow up to eight AREVA modified Advanced Mark-BW fuel assemblies to be placed in nonlimiting Braidwood, Unit 1 core locations. Pursuant to 10 CFR 50.12, Specific Exemptions, the licensee has requested an exemption to 10 CFR 50.46,
acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, that requires, among other items, that each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding, must be provided with an emergency core cooling system (ECCS) that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents conforms to the criteria set forth in paragraph (b) of this section. Appendix K to 10 CFR Part 50, ECCS Evaluation Models, requires, among other items, that the rate of energy release, hydrogen generation, and cladding oxidation from the metal/water reaction shall be calculated using the Baker-Just equation. The regulation at 10 CFR 50.46 and 10 CFR Part 50, Appendix K, make no provisions for use of fuel rods clad in a material other than zircaloy or ZIRLO. The licensee will irradiate eight assemblies using fuel rods clad with AREVAs M5 alloy in Braidwood, Unit 1.
Since the material specifications of the M5 alloy differ from the specification for zircaloy or ZIRLO, a plant-specific exemption is required to support the use of the eight assemblies.
Environmental Impacts of the Proposed Action:
The NRC has completed its safety evaluation of the proposed action and concludes that application of 10 CFR 50.46, and Appendix K to 10 CFR 50, is not necessary for the licensee to achieve its underlying purposes.
The details of the NRC staffs safety evaluation will be provided in the exemption that will be issued as part of the letter to the licensee approving the exemption to the regulation.
The proposed action will not significantly increase the probability or consequences of accidents.
No changes are being made in the types of effluents that may be released off site. There is no significant increase in the amount of any effluent released off site. There is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential non-radiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the no-action alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for Braidwoood NUREG-1026, dated June 1984.
Agencies and Persons Consulted:
In accordance with its stated policy, on August 29, 2007, the NRC staff consulted with the Illinois State official, Mr. Frank Niziolek of the Illinois Emergency Management Agency, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated September 26, 2006, as supplemented by letter dated August 8, 2007. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, Public File Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 10th day of September.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation