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Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 IR 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 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 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 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)) ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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 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)) 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)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days 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 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 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)) RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 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 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 ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 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 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 2024-02-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 May 28, 2015 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, BYRON STATION, CLINTON POWER STATION, DRESDEN NUCLEAR POWER STATION, LASALLE COUNTY STATION, AND QUAD CITIES NUCLEAR POWER STATION - INFORMATION REQUEST TO SUPPORT THE NRC ANNUAL BASELINE EMERGENCY ACTION LEVEL AND EMERGENCY PLAN CHANGES INSPECTION
Dear Mr. Hanson:
This letter is to request information to support the Emergency Action Level and Emergency Plan change inspection that will be conducted during the third quarter of 2015. This inspection will be performed as an in-office review and in accordance with the U.S. Nuclear Regulatory Commission (NRC) baseline inspection procedure IP 71114.04.
In the past, this inspection was conducted at the end of the calendar year, and all requests were made informally to your staff. However, in order to increase efficiency and timeliness of the review, and promote consistency of document requests across the sites, this request is being sent to all operating reactor licensees in Region III.
The list of requested documents needed for this inspection from each site is enclosed. We are requesting that these documents are for the time period specified in the list, as applicable.
The point of contact for this request is Ms. Michelle Garza, Region III Emergency Preparedness Inspector, and can be reached at (630) 829-9719. We will keep in close communications with the Emergency Preparedness staff at your site regarding this request and the inspection when performed.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
B. Hanson In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Docket No. 50-461 License No. NPF-62 Docket Nos. 50-237; 50-249;72-037 License Nos. DPR-19; DPR-25 Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18 Docket Nos. 50-254; 50-265;72-053 License Nos. DPR-29; DPR-30
Enclosure:
Emergency Action Level and Emergency Plan Changes Inspection Document Request cc w/encl: Distribution via LISTSERV
EMERGENCY ACTION LEVEL AND EMERGENCY PLAN CHANGES INSPECTION DOCUMENT REQUEST We request that all information listed below be received no later than July 17, 2015. The information is preferred electronically on a CD-ROM. Send the information requested to the NRC Region III office:
U.S. NRC Region III Attn: Michelle Garza, DRS 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Documents Requested:
- 1. Current revision of the Emergency Plan
- 2. Current Emergency Action Level (EAL) scheme
- 3. Most recent NRC-approved Emergency Plan and EAL
- 4. On Shift Staffing Analysis baseline
- 5. Most recent Evacuation Time Estimate
- 6. Governing site document for Title 10, Code of Federal Regulations (CFR) Part 50.54(q) evaluation process
- 7. Title 10 CFR 50.54(q) evaluator training program and qualification records
- 8. Title 10 CFR 50.54(q) evaluations that were completed between October 31, 2014 and June 30, 2015
- 9. For each change evaluation, the previous documents and proposed documents, and the associated 50.54(q) screen and evaluation (if performed)
- 10. Corrective Action Program entries related to EAL and Emergency Plan changes dated between October 31, 2014 and June 30, 2015.
B. Hanson In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Docket No. 50-461 License No. NPF-62 Docket Nos. 50-237; 50-249;72-037 License Nos. DPR-19; DPR-25 Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18 Docket Nos. 50-254; 50-265;72-053 License Nos. DPR-29; DPR-30
Enclosure:
Emergency Action Level and Emergency Plan Changes Inspection Document Request cc w/encl: Distribution via LISTSERV DISTRIBUTION w/encl:
See next page.
ADAMS Accession Number ML15149A292 Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME MGarza:cl SOrth DATE 05/13/15 05/28/15 OFFICIAL RECORD COPY
Letter to Bryan C. Hanson from Steven K. Orth dated May 28, 2015.
SUBJECT:
BRAIDWOOD STATION, BYRON STATION, CLINTON POWER STATION, DRESDEN NUCLEAR POWER STATION, LASALLE COUNTY STATION, AND QUAD CITIES NUCLEAR POWER STATION - INFORMATION REQUEST TO SUPPORT THE NRC ANNUAL BASELINE EMERGENCY ACTION LEVEL AND EMERGENCY PLAN CHANGES INSPECTION cc w/encl: Distribution via LISTSERV DISTRIBUTION w/encl:
Kimyata MorganButler RidsNrrDorlLpl3-2 Resource RidsNrrPMBraidwood Resource RidsNrrPMByron Resource RidsNrrPMClinton Resource RidsNrrPMDresden Resource RidsNrrPMLaSalle RidsNrrPMQuadCities Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Richard Skokowski Allan Barker DRPIII DRSIII Carole Ariano Linda Linn Jim Clay Carmen Olteanu