Revision to Registration of Exelon Generation Company, LLC as an Authorized User of NRG-Licensed Transport PackageML14189A470 |
Person / Time |
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Site: |
Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Ginna, Diablo Canyon, Clinton, Quad Cities, LaSalle, 07201036, 07100019, 07100383, 07100008, 07100045, 07100053 ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
07/08/2014 |
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From: |
Simpson P Exelon Generation Co |
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To: |
Document Control Desk, NRC/NMSS/SFST |
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References |
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RS-14-190 |
Download: ML14189A470 (4) |
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Similar Documents at Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Ginna, Diablo Canyon, Clinton, Quad Cities, LaSalle, 07201036, 07100019, 07100383, 07100008, 07100045, 07100053 |
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Category:Letter type:RS
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RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges 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 2024-01-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Nine Mile Point]] OR [[:Oyster Creek]] OR [[:Byron]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:LaSalle]] OR [[:07201036]] OR [[:07100019]] OR [[:07100383]] OR [[:07100008]] OR [[:07100045]] OR [[:07100053]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Nine Mile Point]] OR [[:Oyster Creek]] OR [[:Byron]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:LaSalle]] OR [[:07201036]] OR [[:07100019]] OR [[:07100383]] OR [[:07100008]] OR [[:07100045]] OR [[:07100053]] </code>. |
Text
10 CFR 71.17(c)(3) 10 CFR 71.101(f)
RS-14-190 July 8, 2014 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRG Docket Nos. STN 50-456, 50-457, 71-0008, and 72-73 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRG Docket Nos. 50-454. 50-455. 71-0008. and 72-68 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 Independent Spent Fuel Storage Installation License No. SNM-2505 NRG Docket Nos. 50-317. 50-318. 71-0383. and 72-08 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRG Docket Nos. 50-461 and 71-0008 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRG Docket Nos.50-010. 50-237, 50-249. 71-0008, and 72-37 R.E. Ginna Nuclear Power Plant Facility Operating License No. DPR-18 NRG Docket Nos. 50-244. 71-0019, and 72-67 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRG Docket Nos. 50-373. 50-374, 71-0008, and 72-70 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRG Docket Nos. 50-352, 50-353, 71-0008, and 72-65
July 8, 2014 U.S. Nuclear Regulatory Commission Page 2 Nine Mile Point Nuclear Station, Units 1 and 2 Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220, 50-410, 71-0045, and 72-1036 Oyster Creek Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket Nos. 50-219, 71-0008, and 72-15 Peach Bottom Atomic Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-12 Renewed Facility Operating License Nos. DPR-44, and DPR-56 NRC Docket Nos. 50-171, 50-277, 50-278, 71-0008, and 72-29 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254, 50-265, 71-0008, and 72-53 Three Mile Island Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket Nos. 50-289 and 71-0008
Subject:
Revision to Registration of Exelon Generation Company, LLC as an Authorized User of NRG-Licensed Transport Package
Reference:
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Registration of Exelon Generation Company, LLC as an Authorized User of NRG-Licensed Transport Package," dated May 7, 2014 In the referenced letter, Exelon Generation Company, LLC (EGC) registered each of the EGC nuclear stations as a user of the Model No. RT-100 radioactive material transport package (i.e.,
Package Identification Number USA/9365/B(U)-96), in accordance with 10 CFR 71.17, "General License: NRG-approved package," paragraph (c)(3).
The purpose of this letter is to revise the original registration to remove Three Mile Island Station, Unit 2 from the list of applicable EGC nuclear stations. The revised list above provides the licensee names and license numbers for the applicable EGC nuclear stations. As such, this letter supersedes the referenced letter in its entirety.
In addition, the referenced letter included, as required by 10 CFR 71.101, "Quality assurance requirements," paragraph (f), notification that EGC intended to apply previously approved 10 CFR Part 50, Appendix B quality assurance programs to 10 CFR Part 71 transportation activities for the EGC nuclear stations. The attachment to this letter identifies, for each applicable EGC nuclear station, the quality assurance program by date of submittal to the NRC, 10 CFR Part 71 Docket Number, and the date of NRC approval.
July 8, 2014 U. S. Nuclear Regulatory Commission Page 3 There are no regulatory commitments in this submittal.
If you have any questions or require additional information, please contact John Schrage at (630) 657-2821.
Patrick R. Simpson Manager - Licensing
Attachment:
NRG-Approved Quality Assurance Programs, Exelon Generation Company, LLC
Attachment NRG-Approved Quality Assurance Programs Exelon Generation Company, LLC NRC Docket No. 71-0008 Braidwood Station, Units 1 and 2 Byron Station, Units 1 and 2 Clinton Power Station, Unit 1 Dresden Nuclear Power Station, Units 1, 2, and 3 LaSalle County Station, Units 1 and 2 Limerick Generating Station, Units 1 and 2 Oyster Creek Generating Station Peach Bottom Atomic Power Station, Units 1, 2, and 3 Quad Cities Nuclear Power Station, Units 1 and 2 Three Mile Island Station, Unit 1 Quality Assurance Program Approval for Radioactive Material Packages 71-0008, Revision 12 Application Dates: February 19, 2004, April 24, 2006, September 20, 2006, January 22, 2007 Approval Date: May 23, 2007 NRC Docket No. 71-0383 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Quality Assurance Program Approval for Radioactive Material Packages 71-0383, Revision 07 Application Dates: February 29, 2000, September 28, 2000, January 8, 2001, November 11, 2004 Approval Date: December 15, 2004 NRC Docket No. 71-0019 R.E. Ginna Nuclear Power Plant Quality Assurance Program Approval for Radioactive Material Packages 71-0019, Revision 09 Application Dates: May 10, 2004, June 10, 2004, June 15, 2004, May 14, 2009 Approval Date: July 16, 2009 NRC Docket No. 71-0045 Nine Mile Point Nuclear Station, Units 1 and 2 Quality Assurance Program Approval for Radioactive Material Packages 71-0045, Revision 08 Application Dates: June 19, 1978, May 25, 1994, May 25 1999, March 22, 2004, April 28, 2009 Approval Date: May 14, 2009