Braidwood, Byron, Clinton, Dresden, and Peach Bottom - 10 CFR 50, Appendix E - Evacuation Time Estimate Analysis InformationML14141A047 |
Person / Time |
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Site: |
Dresden, Peach Bottom, Byron, Braidwood, Clinton |
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Issue date: |
05/02/2014 |
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From: |
Jim Barstow Exelon Generation Co |
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To: |
Document Control Desk, NRC/FSME, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
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Shared Package |
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ML14141A046 |
List: |
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References |
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RS-14-151 |
Download: ML14141A047 (3) |
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Category:Letter
MONTHYEARIR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 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 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) 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 IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan 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 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 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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 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 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 BYRON 2023-0065, Unit 2 - 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 Guideline2023-11-17017 November 2023 Unit 2 - 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 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 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 BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, 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 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 RS-23-119, 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 2024-02-02
[Table view] |
Text
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 § 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