NMP1L3481, Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates

From kanterella
Jump to navigation Jump to search
Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates
ML22269A417
Person / Time
Site: Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, 07201036  Constellation icon.png
Issue date: 09/15/2022
From: David Helker
Constellation Energy Generation
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML22269A403 List:
References
NMP1L3481, RS-22-105
Download: ML22269A417 (5)
v • d • e


Text

200 Exelon Way Kennett Square, PA 19348 www.ConstellationEnergy.com 10 CFR 50, Appendix E 10 CFR 50.4 RS-22-105 NMP1L3481 September 15, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456, 50-457, and 72-73 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454, 50-455, and 72-68 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Calvert Cliffs Independent Spent Fuel Storage Installation Materials License No. SNM-2505 NRC Docket No. 72-8 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237, 50-249, and 72-37 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant Independent Spent Fuel Storage Installation General License SFGL-12 Docket No.72-012

U.S. Nuclear Regulatory Commission Development of Evacuation Time Estimates September 15, 2022 Page2 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373, 50-374, and 72-70 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352, 50-353, and 72-65 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220, 50-410, and 72-1036 Peach Bottom Atomic Power Station, Units 1, 2, and 3 Facility Operating [Possession Only] License No. DPR-12 Subsequent Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-171, 50-277, 50-278 and 72-79 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, and 72-53 R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket Nos. 50-244 and 72-67

Subject:

10 CFR 50, Appendix E - Development of Evacuation Time Estimates In accordance with the requirements of 10 CFR 50 Appendix E, Section IV, "Content of Emergency Plans," Constellation Energy Generation, LLC (CEG) is submitting Evacuation Time Estimates (ETE) analysis information and supporting checklists for the plants noted above. 10 CFR 50 Appendix E, Section IV, paragraph 4, specifies the following:

Within 365 days of the later of the date of the availability of the most recent decennial census data from the U.S. Census Bureau or December 23, 2011, nuclear power reactor

  • licensees shall develop an ETE analysis using this decennial data and submit it under

§ 50.4 to-the NRG. These licensees shall submit this ETE analysis to the NRG at least 180 days before using it to form protective action recommendations and providing it to State and local governmental authorities for use in developing offsite protective action strategies.

Due to the COVID-19 pandemic public health emergency of 2020-2021, the data from the 2020 Census was not immediately available. The NRC issued Emergency Preparedness Frequently Asked Question (EPFAQ) 2021-002, "Clarification of NUREG-7002, 'Criteria for Development of Evacuation Time Estimate Studies,"' regarding the availability date for the census data. For the 2020 Census, the NRC considers the "date of the availability of the

U.S. Nuclear Regulatory Commission Development of Evacuation Time Estimates September 15, 2022 Page3 most recent decennial census data" to be September 16, 2021, because that was the date that census data from the U.S. Census Bureau was first made publicly available.

The attached ETE analysis information for the CEG plants cited used 2020 decennial census data from the U.S. Census Bureau and was prepared by KLD Engineering in accordance with the Federal guidance established in NUREG/CR-7002, Revision 1, "Criteria for Development of Evacuation Time Estimate Studies," published February 2021.

As noted in 10 CFR 50, Appendix E, Section IV, licensees shall use NRG-approved ETEs in the formulation of protective action recommendations and provide the ETEs and ETE updates to State and local governmental authorities for use in developing offsite protective action strategies. The requirements further stipulate that licensees shall submit the ETE analysis to the NRC at least 180 days before using it to form protective action recommendations and providing it to State and local governmental authorities for use in developing offsite protective action strategies.

There are no commitments contained in this submittal.

If you have any questions concerning this letter, please contact Marino Kaminski at (610) 765-5869.

Respectfully, David P. Helker Sr. Manager, Licensing Constellation Energy Generation, LLC Attachments {DVD}: - Braidwood Station - Development of Evacuation Time Estimates - Byron Station - Development of Evacuation Time Estimates - Calvert Cliffs Nuclear Power Plant - Development of Evacuation Time Estimates - Clinton Power Station - Development of Evacuation Time Estimates - Dresden Nuclear Station - Development of Evacuation Time Estimates - James A. FitzPatrick Nuclear Power Plant and Nine Mile Point Nuclear Station - Development of Evacuation Time Estimates - LaSalle County Station - Development of Evacuation Time Estimates - Limerick Generating Station - Development of Evacuation Time Estimates - Peach Bottom Atomic Power Station - Development of Evacuation Time Estimates 0 - Quad Cities Nuclear Power Station - Development of Evacuation Time Estimates 1 - R. E. Ginna Nuclear Power Plant - Development of Evacuation Time Estimates

U.S. Nuclear Regulatory Commission Development of Evacuation Time Estimates September 15, 2022 Page4 cc: w/o Attachments (DVD}

Regional Administrator - NRC Region Ill Regional Administrator-. NRC Region I NRC Fleet Project Manager, NRR NRC Senior Resident Inspector - Braidwood NRC Project* Manager, NRR - Braidwood

  • NRC Senior Resident Inspector - Byron NRC Project Manager, NRR - Byro!'!

NRC Senior Resident Inspector - Calvert Cliffs NRC Project Manager, NRR - Calvert Cliffs NRC Senior Resident Inspector - Clinton NRC Project Manager, NRR - Clinton NRC Senior Resident Inspector - Dresden NRC Project Manager, NRR - Dresden NRC Senior Resident Inspector - FitzPatrick NRC Project Manager, NRR - 'FitzPatrick NRC Senior Resident Inspector - Ginna NRC Project Manager, NRR - Ginna NRC Senior Resident Inspector - LaSalle NRC Project Manager, NRR - LaSalle NRC Senior Resident Inspector - Limerick NRC Project Manager, NRR - Limerick NRC Senior Resident Inspector - Nine Mile Point NRC Project Manager, NRR - Nine Mile Point NRC Senior Resident Inspector - Peach Bottom NRC Project Manager, NRR - Peach Bottom NRC Senior Resident Inspector - Quad Cities NRC Project Manager, NRR - Quad Cities Illinois Emergency Management Agency Division of. Nuclear Safety W. DeHaas, PA DEP, Bureau of Radiation Protection S. Seaman, State of Maryland

DVD-ROM Contents 10 CFR 50, Appendix E - Development of Evacuation Time Estimates Attachment 1 - Braidwood Station Attachment 2 - Byron Station

, Attachment 3 - Calvert Cliffs Nuclear Power Plant Attachment 4 - Clinton Power Station Attachment 5 ~ Dresden Nuclear Station Attachment 6 - James A FitzPatrick Nuclear Power Plant &

Nine Mile Point Nuclear Station Attachment 7 - LaSalle County Station Attachment 8 - Limerick Generating Station

\Attachment 9 - ~each Bottom Atomic Power Station Attachment 1O - Quad Cities Nuclear Power Attachment 11 - R E. Ginna Nuclear Power Plant

Retrieved from "https://kanterella.com/w/index.php?title=NMP1L3481,_Constellation_Energy_Generation,_LLC,_10_CFR_50,_Appendix_E_-_Development_of_Evacuation_Time_Estimates&oldid=3516880"