View source for RS-14-151, Braidwood, Byron, Clinton, Dresden, and Peach Bottom - 10 CFR 50, Appendix E - Evacuation Time Estimate Analysis Information

{{Adams
| number = ML14141A047
| issue date = 05/02/2014
| title = Braidwood, Byron, Clinton, Dresden, and Peach Bottom - 10 CFR 50, Appendix E - Evacuation Time Estimate Analysis Information
| author name = Barstow J
| author affiliation = Exelon Generation Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/FSME, NRC/NMSS, NRC/NRR
| docket = 05000171, 05000237, 05000249, 05000277, 05000278, 05000454, 05000455, 05000456, 05000457, 05000461, 07200029, 07200037, 07200068, 07200073
| license number = DPR-019, DPR-025, DPR-044, DPR-056, NPF-037, NPF-062, NPF-066, NPF-072, NPF-077
| contact person = 
| case reference number = RS-14-151
| package number = ML14141A046
| document type = Letter
| page count = 3
}}

=Text=
{{#Wiki_filter:Exeton Generation.
Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50, Appendix E 10 CFR 50.4 RS-14-151 May 2, 2014 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 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 Peach Bottom Atomic Power Station, Units 1, 2 and 3 Facility Operating License DPR-12 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-171, 50-277, 50-278 and 72-29 

==Subject:==
10 CFR 50, Appendix E -Evacuation Time Estimate Analysis Information

==References:==
: 1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S.Nuclear Regulatory Commission, "10 CFR 50 Appendix E Evacuation Time Estimate Analysis for Braidwood Station," dated December 12, 2012 2) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S.Nuclear Regulatory Commission, "10 CFR 50 Appendix E Evacuation Time Estimate Analysis for Byron Station," dated December 12, 2012 f S HE,-D U.S. Nuclear Regulatory Commission Evacuation Time Estimate Analysis Information May 2, 2014 Page 2 3) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S.Nuclear Regulatory Commission, "10 CFR 50 Appendix E Evacuation Time Estimate Analysis for Clinton Power Station," dated December 12, 2012 4) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S.Nuclear Regulatory Commission, "10 CFR 50 Appendix E Evacuation Time Estimate Analysis for Dresden Nuclear Power Station," dated December 12, 2012 5) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S.Nuclear Regulatory Commission, "10 CFR 50 Appendix E Evacuation Time Estimate Analysis for Peach Bottom Atomic Power Station," dated December 12, 2012 In accordance with the requirements of 10 CFR 50 Appendix E, Section IV, "Content of Emergency Plans," paragraph 4, Exelon Generation Company, LLC (Exelon) is resubmitting Evacuation Time Estimates (ETE) analysis information and supporting checklists for Braidwood Station, Byron Station, Clinton Power Station, Dresden Nuclear Power Station, and Peach Bottom Atomic Power Station. 10 CFR 50, Appendix E, Section IV, paragraph 4 stipulates 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 December23, 2011, nuclear power reactor licensees shall develop an ETE analysis using this decennial data and submit it under &sect; 50.4 to the NRC. These licensees shall submit this 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.
The attached ETE analysis information for the Exelon plants cited was developed using the decennial census data from the U.S. Census Bureau and in accordance with the Federal guidance established in NUREG/CR-7002 (SAND2010-0016P), "Criteria for Development of Evacuation Time Estimate Studies," published November 2011. The subject information is being resubmitted following re-performance of the ETEs to address comments received from the U.S. Nuclear Regulatory Commission (NRC) pertaining to the submittals listed in the References above.There are no commitments contained in this submittal.
U.S. Nuclear Regulatory Commission Evacuation Time Estimate Analysis Information May 2, 2014 Page 3 If you have any questions concerning this letter, please contact Richard Gropp at (610) 765-5557.Respectfully, James Barstow Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments:
Attachment 1 -Braidwood Generating Station -Development of Evacuation Time Estimates Attachment 2 -Byron Generating Station -Development of Evacuation Time Estimates Attachment 3 -Clinton Power Station -Development of Evacuation Time Estimates Attachment 4 -Dresden Generating Station -Development of Evacuation Time Estimates Attachment 5 -Peach Bottom Atomic Power Station -Development of Evacuation Time Estimates cc: w/ Attachments (CD)Regional Administrator 
-NRC Region III Regional Administrator 
-NRC Region I NRC Senior Resident Inspector 
-Braidwood NRC Project Manager, NRR -Braidwood NRC Senior Resident Inspector 
-Byron NRC Project Manager, NRR -Byron NRC Senior Resident Inspector 
-Clinton NRC Project Manager, NRR -Clinton NRC Senior Resident Inspector 
-Dresden NRC Project Manager, NRR -Dresden NRC Senior Resident Inspector 
-Peach Bottom NRC Project Manager, NRR -Peach Bottom Illinois Emergency Management Agency Division of Nuclear Safety R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland w/ Attachments 1-4 only w/ Attachment 5 only w/ Attachment 1 w/ Attachment 1 w/ Attachment 2 w/ Attachment 2 w/ Attachment 3 w/ Attachment 3 w/ Attachment 4 w/ Attachment 4 w/ Attachment 5 w/ Attachment 5 w/o Attachments w/o Attachments w/o Attachments}}