Letter Sequence Other |
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TAC:ME0206, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME0207, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME0208, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME0209, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
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Category:Letter
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Review of the Fall 2022 Steam Generator Tube Inspection Report
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IR 05000454/20233012023-11-27027 November 2023
NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301
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Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference
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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
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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
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Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
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Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments
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Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection
IR 05000456/20234012023-10-18018 October 2023
Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401
IR 05000456/20230102023-10-18018 October 2023
Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010
RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
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RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
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RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
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Operator Licensing Examination Approval - Byron Station, October 2023
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023
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RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023
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ML23251A1622023-09-29029 September 2023
Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements
RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023
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IR 05000454/20235012023-08-31031 August 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501
IR 05000454/20230052023-08-30030 August 2023
Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005)
IR 05000456/20230052023-08-30030 August 2023
Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005
ML23234A2462023-08-25025 August 2023
Confirmation of Initial License Examination
IR 05000456/20230022023-08-0303 August 2023
Integrated Inspection Report 05000456/2023002 and 05000457/2023002
IR 05000454/20230022023-08-0303 August 2023
Integrated Inspection Report 05000454/2023002 and 05000455/2023002
2024-02-02
[Table view]
Category:License-Materials Byproduct Amendment DKT 30
MONTHYEARML1010501552010-04-15015 April 2010
Correction to Amendments Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification
2010-04-15
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 15, 2010 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - CORRECTION TO AMENDMENTS RE: DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION (TAC NOS. IVIE0206, ME0207, ME0208, AND ME0209)
Dear Mr. Pardee:
On March 23, 2010 (Agencywide Documents Access and Management System Accession No. ML100690386), the Nuclear Regulatory Commission (NRC) issued Amendment No. 162 to Facility Operating License No. NPF-72 and Amendment No. 162 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2 (Braidwood), and Amendment No. 167 to Facility Operating License No. NPF-37 and Amendment No. 167 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively.
The amendments revised Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS
[Reactor Coolant System] Specific Activity," and Surveillance Requirements 3.4.16.1, 3.4.16.2, and 3.4.16.3. The revisions replaced the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity. The revisions adopted TS Task Force (TSTF)
Change Traveler, TSTF-490, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec [sic]," Revision O.
Subsequent to issuance, your staff noted that the amended license pages for Braidwood were not included in the package. Therefore, we are issuing the enclosed Amendment No. 162 pages for Facility Operating License Nos. NPF-72 and NPF-77 for the Braidwood Station, Units 1 and 2, respectively.
C. Pardee -2 The NRC staff regrets any inconvenience this may have caused.
Sincerely,
~~~1:(ff.anager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455
Enclosures:
- 1. Amendment No. 162 NPF-72 Page 3
- 2. Amendment No. 162 NPF-77 Page 3 cc w/encls: Distribution via Listserv
- 3 (3) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1 ) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified.
Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 162, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(sX2) will apply.
Amendment No. 162
-3 material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation Company, LLC pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts are required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified.
Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 162, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s){2) will apply.
Amendment No. 162
C. Pardee -2 The NRC staff regrets any inconvenience this may have caused.
Sincerely, IRA!
Marshall J. David, Senior Project Manager Plant licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455
Enclosures:
- 1. Amendment No. 162 NPF-72 Page 3
- 2. Amendment No. 162 NPF-77 Page 3 cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorlLpl3-2 Resource LPL3-2 RtF RidsNrrPMBraidwood Resource RidsNrrDraAadb Resource RidsOgcRp Resource RidsNrrLATHarris Resource RidsNrrDorlDpr Resource LBenton, NRR RidsNrrPMByron Resource RidsNrrDirsltsb Resource RGrover, NRR RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource ADAMS Accession No. ML101050155 NRR-106 OFFICE LPL3-2/PM -21LA LPL3-2/BC NAME MDavid ris SCampbell DATE 4/15/10 4/15/10 4/15/10 OFFICIAL RECORD COpy
