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Category:Letter
MONTHYEARIR 05000373/20243012024-10-31031 October 2024 Initial License Examination Report 05000373/2024301 05000374/2024301 IR 05000373/20244042024-10-23023 October 2024 County Station – Security Baseline Inspection Report 05000373/2024404 and 05000374/2024404 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 05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024 Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000373/20244012024-09-27027 September 2024 County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401 ML24263A2062024-09-19019 September 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS ML24260A0492024-09-16016 September 2024 Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000373/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005) IR 05000373/20244022024-08-28028 August 2024 County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer IR 05000373/20240022024-08-13013 August 2024 County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002 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 05000373/20244202024-08-0505 August 2024 County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420 05000373/LER-2024-003-01, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024 Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions ML24178A2522024-06-27027 June 2024 County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation 05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-19019 June 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer 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 05000373/LER-2024-003, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-06-0606 June 2024 Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded IR 05000373/20240102024-05-29029 May 2024 County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010 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 05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-17017 May 2024 Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24131A1512024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 IR 05000373/20240012024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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 05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded2024-04-26026 April 2024 Core Operating Limits Report Thermal Limits Exceeded ML24108A1562024-04-15015 April 2024 Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11 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-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24071A2122024-03-12012 March 2024 County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection IR 05000373/20230062024-02-28028 February 2024 Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006) RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces IR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 05000373/LER-2023-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation2023-12-0404 December 2023 Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation 2024-09-06
[Table view] Category:Environmental Assessment
MONTHYEARML21008A3282021-03-0909 March 2021 Environmental Assessment and Finding of No Significant Impact Related to Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink (EPID L-2020-LLA-0165) (FRN) ML21008A3272021-03-0909 March 2021 Environmental Assessment and Finding of No Significant Impact Related to Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink (EPID L-2020-LLA-0165) (Transmittal Letter) ML20150A2872020-11-23023 November 2020 Encl: Environmental Assessment (Memo to File: Envir. Assessment and Finding of No Significant Impact for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for LaSalle 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 ML1100410302011-02-10010 February 2011 Environmental Assessment and Finding of No Significant Impact - Cover Letter ML0609606242006-05-15015 May 2006 Quad Cities, TMI and Zion Environmental Assessment for Schedular Exemption from 10 CFR 50.54(a)(3) ML0232204442003-01-0202 January 2003 Environmental Assessment & Finding of No Significant Impact Related to License Amendment Request to Change Appendix B 2021-03-09
[Table view] Category:Finding of No Significant Impact
MONTHYEARML21008A3282021-03-0909 March 2021 Environmental Assessment and Finding of No Significant Impact Related to Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink (EPID L-2020-LLA-0165) (FRN) ML21008A3272021-03-0909 March 2021 Environmental Assessment and Finding of No Significant Impact Related to Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink (EPID L-2020-LLA-0165) (Transmittal Letter) ML20150A2872020-11-23023 November 2020 Encl: Environmental Assessment (Memo to File: Envir. Assessment and Finding of No Significant Impact for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for LaSalle 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 ML1100410442011-02-10010 February 2011 Environmental Assessment and Finding of No Significant Impact ML1100410302011-02-10010 February 2011 Environmental Assessment and Finding of No Significant Impact - Cover Letter NRC-2010-0254, LaSalle County Station, Units 1 and 2 - Environmental Assessment and Finding of No Significant Impact2011-02-10010 February 2011 LaSalle County Station, Units 1 and 2 - Environmental Assessment and Finding of No Significant Impact 2021-03-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 10, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT CONCERNING LOW-LEVEL RADIOACTIVE WASTE STORAGE(TAC NOS. ME3054 AND ME3055)(RS-10-007)
Dear Mr. Pacilio:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to the Exelon Generating Company, LLC (the licensee) application for amendment to the LaSalle County Station (LSCS) licenses dated January 6, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100070298), as supplemented by letters dated August 20, October 14, and December 2,2010 (ADAMS Accession Nos.
ML102320599, ML102880116, and ML103370375 respectively). The proposed change will enable LSCS to possess byproduct material from Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1. Specifically, the revised license paragraph would enable the licensee to store low-level radioactive waste from Braidwood, Byron, and Clinton in the LSCS Interim Radwaste Storage Facility.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-373 and 50-374
Enclosure:
Environmental Assessment cc w/encl: Distribution via Listserv
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment for Facility Operating License Nos. NPF-11 and NPF-18, issued to Exelon Generation Company, LLC (Exelon, the licensee) for operation of the LaSalle County Station, Units 1 and 2 (LSCS), located in Marseilles, Illinois. In accordance with Title 10 to the Code of Federal Regulations (10 CFR) Section 51.21, the NRC prepared an environmental assessment documenting its finding. The NRC concluded that the proposed actions will have no significant environmental impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would revise the Facility Operating Licenses for LSCS to possess, but not separate, byproduct material, specifically Class B and Class C low-level radioactive waste (LLRW), from the following Exelon owned nuclear power stations: Braidwood Station, Units 1 and 2 (Braidwood), Byron Station, Units 1 and 2 (Byron), and Clinton Power Station, Unit 1 (Clinton). The LLRW will be stored in LSCS's interim radwaste storage facility (IRSF).
The proposed action is in accordance with the licensee's application dated January 6, 2010, as supplemented by letters dated August 20, October 14, and December 2,2010.
-2 The Need for the Proposed Action:
The proposed action is needed to provide the licensee with adequate interim storage capacity for Class B and Class C LLRW, since it does not currently have access to a licensed disposal facility for this LLRW. This is due to the State of South Carolina's licensed LLRW disposal facility, located in Barnwell, which has limited access for radioactive waste generators located in states that are not part of the Atlantic Low-Level Waste Compact. Illinois is not a member of the Atlantic Low-Level Waste Compact. Therefore, Exelon facilities located in Illinois do not have access to the Barnwell disposal facility for their Class B and Class C LLRW. LSCS has a LLRW storage facility capable of safely storing a large amount of LLRW, on an interim basis. The other Exelon facilities in Illinois do not have the capability to store all of the LLRW they generate. The building at LSCS is designed to comply with NRC regulatory guidance, primarily Generic Letter 81-38, "Storage of Low-Level Radioactive Wastes at Power Reactor Sites" and to meet the radiation protection standards in 10 CFR Part 20, "Standards for Protection Against Radiation," and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations."
Environmental Impacts of the Proposed Action:
The proposed action involves the transportation of LLRW from Exelon's Braidwood, Byron, and Clinton nuclear power plants for interim storage at LSCS. The LLRW will be transported by truck in accordance with U.S. Department of Transportation and NRC regulations. The distance between the plant sites is less than the distance that was previously traveled to the Barnwell disposal facility in South Carolina. The licensee anticipates that there will be approximately five to eight shipments a year of LLRW to LSCS from the combination of the Braidwood, Byron, and Clinton stations. The projected number of shipments is consistent with the past annual average number of shipments to the Barnwell facility. The proposed action will reduce the total annual number of miles driven for the transport of LLRW. With less miles
-3 traveled, it is expected that there will be no change or possibly a corresponding reduction in the impacts associated with transportation such as lower radiation exposure to the truck driver and members of the public along the transportation route. The proposed action would not result in an increased risk of accidents and radiological hazards beyond those associated with the transport to the Barnwell facility. There will be no change to radioactive effluents from the power plants and the LLRW containers that affect radiation exposure to plant workers and members of the public. The interim storage building is designed to comply with NRC regulatory guidance, primarily Generic Letter 81-38, "Storage of Low-Level Radioactive Wastes at Power Reactor Sites" and to meet the radiation protection standards in 10 CFR Part 20, "Standards for Protection Against Radiation," and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations." The cumulative dose from handling the LLRW from LSCS and from the additional LLRW from Braidwood, Byron, and Clinton will be controlled by station procedures to ensure compliance with the radiation dose standards to workers and members of the public. Based on this information, the staff concludes that the radiological impacts associated with the transportation, handling, and storage of LLRW at LSCS will not result in a significant impact to plant workers and members of the public.
The proposed action does not involve a change to plant buildings or land areas on the LSCS site. The proposed action does not result in changes to land use or water use, or result in changes to the quality or quantity of non-radiological effluents. With less miles traveled, it is expected that there will be no change or possibly a corresponding reduction in the impacts associated with transportation such as reduced use of fossil fuel and reduced air emissions that would affect air quality. No changes to the National Pollutant Discharge Elimination System permit are needed. No effects on the aquatic or terrestrial habitat in the vicinity of the plant, or to threatened, endangered, or protected species under the Endangered Species Act, or impacts to essential fish habitat covered by the Magnuson-Stevens Act are expected. There are no
-4 impacts to historical and cultural resources. There would be no impact to socioeconomic resources. Therefore, no changes to or different types of non-radiological environmental impacts are expected as a result of the proposed exemption.
Accordingly, the NRC staff concludes that there are no significant environmental impacts associated with the proposed action.
The NRC staff's safety evaluation will be provided in the license amendment, if approved by the NRC, which will be issued as part of the letter to the licensee approving the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed actions, the NRC staff considered denial of the proposed actions (i.e .* the "no-action" alternative). Denial of the exemption request would result in no change in current environmental impacts. The environmental impacts of the proposed exemption and the "no action" alternative are similar.
Alternative Use of Resources:
The action does not involve the use of any different resources than those considered in the NUREG-0486. "Final Environmental Statement related to the Operation of the LaSalle County Station. Units 1 and 2 dated November 1978".
Agencies and Persons Consulted:
In accordance with its stated policy, on December 15.2010, the NRC staff consulted with the Illinois State official, Paul Smith, Nuclear System Analysis Section Chief, 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,
-5 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 licensee's letter dated January 6, 2010, as supplemented by letters dated August 20, October 14, and December 2, 2010. These documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, Public File Area 0-1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. 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 Website:
http://www.nrc.govlreading-rmladams.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.resource@nrc.gov.
Dated at Rockville, Maryland, this 10th day of February 2011.
FOR THE NUCLEAR REGULATORY COMMISSION IRA!
Eva A Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
February 10, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,lL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT CONCERNING LOW-LEVEL RADIOACTIVE WASTE STORAGE(TAC NOS. ME3054 AND ME3055)(RS-10-007)
Dear Mr. Pacilio:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to the Exelon Generating Company, LLC (the licensee) application for amendment to the LaSalle County Station (LSCS) licenses dated January 6,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100070298), as supplemented by letters dated August 20, October 14, and December 2,2010 (ADAMS Accession Nos.
ML102320599, ML102880116, and ML103370375 respectively). The proposed change will enable LSCS to possess byproduct material from Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1. Specifically, the revised license paragraph would enable the licensee to store low-level radioactive waste from Braidwood, Byron, and Clinton in the LSCS interim Radwaste Storage Facility.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos: 50-373 and 50-374
Enclosure:
Environmental Assessment cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2Branch Reading File RidsNrrDlrRerb Resource RidsNrrDorlLpl3-2 Resource RidsNrrLA[THarrisResource RidsNrrPMEBrownResource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource ADAMS Accession Nos. PKG ML110041068 Letter (NRR-1 06) ML110041030 EA FRN ADM-012 ML110041044 OFFICE LPL3-2/PM LPL3-2/LA RERB/BC OGC LPL3-2PM Almboden EBrown NAME EBrown THarris (ARivera for) LSubin (NLO) RCarlson DATE 02/08/11 01/05/11 01/06/11 02/08/11 02/10/11 02/10/11 OFFICIAL RECORD COpy