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MONTHYEARML0417002862004-06-16016 June 2004 Request for Additional Information Exelon Generation Company and Amergen Energy Company Physical Security Plans Sections 10-19 (TAC Nos. MC2890, MC2891, MC2897, MC2898, MC2904, MC2915, MC2916, MC2932, MC2933, MC2934, MC2935, MC2948, MC2953. Project stage: RAI ML0418101252004-06-25025 June 2004 Request for Additional Information Exelon Generation Company and Amergen Energy Company Physical Security Plans Sections 1-9 (TAC Nos. MC2890, MC2891, MC2897, MC2898, MC2904, MC2915, MC2916, MC2932, MC2933, MC2934, MC2935, MC2948, MC2953, M Project stage: RAI ML0420200232004-07-0909 July 2004 Request for Additional Information Exelon Generation Company and Amergen Energy Company Training and Qualification Plans Project stage: RAI ML0421003482004-07-23023 July 2004 Request for Additional Information Safeguards Contingency Plan and Section 9.4.1 of the Physical Security Plan (TAC Nos. MC2890, MC2891, MC2897, MC2898, MC2904, MC2932, MC2933, MC2934, MC2935, MC2948, MC2953, MC2954, MC2961, MC2962, MC2981, Project stage: RAI RS-04-119, (Exelon) and Amergen Energy Co, LLC (Amergen), Response to Request for Additional Information Related to the Safeguards Contingency Plans and Section 9.4.1 of the Physical Security Plans2004-08-12012 August 2004 (Exelon) and Amergen Energy Co, LLC (Amergen), Response to Request for Additional Information Related to the Safeguards Contingency Plans and Section 9.4.1 of the Physical Security Plans Project stage: Response to RAI ML0431200312004-10-28028 October 2004 Administrative Change to Facility Operating Licenses in Conjunction with the Commission Order EA-03-086 Regarding Revised Design Basis Threat (Dbt); and Revisions to Physical Security Plan, Training and Qualification Plan.. Project stage: Other ML0431704272004-10-29029 October 2004 Administrative Change to Facility Operating License in Conjunction with the Commission Order EA-03-086 Regarding Revised Design Basis Threat... Project stage: Other 2004-06-25
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Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML22210A0312022-08-30030 August 2022 Issuance of Amendments Nos. 230, 230, 230, and 230, Respectively, Regarding Adoption of Technical Specifications Task Force Traveler (TSTF) 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22173A1812022-08-11011 August 2022 Issuance of Amendment No. 229 to Remove License Condition ML22173A2142022-08-10010 August 2022 Issuance of Amendments Nos. 228 and 228 Revision of Technical Specifications for the Ultimate Heat Sink ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21090A0152021-04-0707 April 2021 Correction to Amendment Nos. 219 and 219 Regarding Revision of Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21054A0082021-03-10010 March 2021 Issuance of Amendment Nos. 220 and 220 One-Time Deferral of Steam Generator Tube Inspections ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML20245E4192020-09-24024 September 2020 Issuance of Amendments Nos. 218 and 218 Revision of Technical Specifications for the Ultimate Heat Sink ML20163A0462020-09-18018 September 2020 Issuance of Amendments Nos. 217, 217, 221, and 221, Revise Technical Specification 5.6.6 to Allow Use of Areva Np Topical Report BAW-2308 ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20149K6982020-09-10010 September 2020 Issuance of Amendment Nos. 215, 215, 219, and 219 Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20111A0002020-05-0101 May 2020 Issuance of Amendment No. 209, Revision Technical Specification 5.5.9, Steam Generator (SG) Program, for One-Time Revision to Frequency of SG Tube Inspections (Exigent Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers ML19170A3112019-06-19019 June 2019 Redacted Braidwood Station, Units 1 & 2, and Byron Station, Units 1 & 2, Amendment 28 to Fire Protection Report, Appendix 5.1 (Public Version Pages 1-76 and 129-287) ML19168A1192019-06-17017 June 2019 Redacted Braidwood Station, Units 1 & 2, Amendment 28 to Fire Protection Report, Chapter 2.4, Safe Shutdown Analysis. (Public Version Pages 1-19 and 1726-1742) RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML18302A2272018-12-12012 December 2018 Issuance of Amendments No. 200 and 205 Regarding Axial Flux Difference Technical Specifications ML18291A9802018-11-0808 November 2018 Issuance of Amendment Nos. 199 Regarding Use of TORMIS for Assessing Tornado Missile Protection ML18264A0922018-10-22022 October 2018 Issuance of Amendment Nos. 198, 198, 204, and 204, Respectively, Regarding Adoption of Title 10 of the Code of Federal Regulations Section 50.69 CAC Nos. MG0201, MG0202, MG0203, and MG0204; EPID-L 2017-LLA-0285) ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18065A5292018-06-27027 June 2018 Issuance of Amendments Regarding Clarification of Rod Position Requirements (CAC Nos. MF9951-9954; EPID L-2017-LLA-0249) ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML18054B4362018-04-30030 April 2018 Issuance of Amendments Regarding Control Room Ventilation Temperature Control System (CAC Nos. MF9932, MF9933, MF9934, and MF9935; EPID L-2017-LLA-0247) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17088A7032017-07-0505 July 2017 Issuance of Amendments to Regarding Request to Delete Obsolete License Conditions and Make Administrative Changes to Technical Specifications (CAC Nos. MF9338-MF9341) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) 2024-09-10
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SAFEGUARDS INFORMATION October 28, 2004 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - ADMINISTRATIVE CHANGE TO FACILITY OPERATING LICENSES IN CONJUNCTION WITH THE COMMISSION ORDER EA-03-086 REGARDING REVISED DESIGN BASIS THREAT (DBT); AND REVISIONS TO PHYSICAL SECURITY PLAN, TRAINING AND QUALIFICATION PLAN, AND SAFEGUARDS CONTINGENCY PLAN (TAC NOS. MC2890 AND MC2891)
Dear Mr. Crane:
By letter dated April 28, 2004, the Exelon Generation Company and AmerGen Energy Company submitted a supplemental response in accordance with Order EA-03-086, the Order requiring compliance with the revised design basis threat, dated April 29, 2003 (DBT Order), for Braidwood Station, Units 1 and 2 (Braidwood).Section III.A of the DBT Order required licensees to revise physical security plans (PSPs), training and qualification plans (T&Q Plans),
and safeguards contingency plans (SCPs) in order to provide protection against the revised DBT set forth in Attachment 2 to the DBT Order. These revised plans, along with an implementation schedule, were required to be submitted to the Nuclear Regulatory Commission (NRC or the Commission) for review and approval no later than April 29, 2004.
The NRC staffs review of the Braidwood PSP, SCP, and T&Q Plan submitted in your letter dated April 28, 2004, as supplemented on July 6, July 9, July 23, August 4, August 12, September 9, October 14, and October 21, 2004, has focused on ensuring that the necessary programmatic elements are contained in these plans in order to provide high assurance that activities involving special nuclear material are not inimical to the common defense and security and do not constitute an unreasonable risk to the public health and safety.
NOTICE: Enclosure 2 contains Safeguards Information. Upon separation from Enclosure 2, this letter and Enclosure 1 are DECONTROLLED.
SAFEGUARDS INFORMATION
C. Crane The NRC staff has determined that these plans, subject to subsequent inspection and evaluation, contain the necessary programmatic elements that, when effectively implemented, will provide the high assurance that Braidwood will be protected against the revised DBT. The NRC staff, therefore, approves the PSP, SCP, and T&Q Plan for Braidwood. However, ultimately the effectiveness of these plans will be judged on your ability to meet regulatory requirements through facility implementing procedures and site practices. As such, your facility implementing procedures and practices will continue to be subject to future NRC review and inspection, including NRC-conducted force-on-force exercises.
In addition, the NRC staff noted that your PSP included alternatives to certain requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 73.55. In each case, the NRC staff found that the alternative measures provide an equivalent level of protection to that of the associated requirements and meets the high assurance objective of 10 CFR 73.55(a). The NRC staff, therefore, approves the alternatives shown in the table below. The NRC staffs evaluation is discussed further in the enclosed Safety Evaluation (SE).
Approved Alternatives to the Requirements of 10 CFR Part 73 SE Section PSP Section Alternative to 10 CFR Description 3.6.2 6.2 73.55(c)(3) Isolation Zones 3.9.4.3 9.4.3 73.55(d)(4) Protected Areas (PA) vehicle search requirements 3.9.4.4 9.4.4 73.55(d)(1) PA personnel search requirements 3.9.5.2 9.5 73.55(d)(1) PA access control requirements 73.55(d)(4) 3.10.1 10.1 73.55(c)(5) PA illumination requirements 3.13.1 14.1 73.55(c)(1) Temporary reclassification of Vital Areas 73.55(d)(7)(i)(B) to PA status (devitalization)
Finally, consistent with the DBT Order, conforming administrative changes to Facility Operating Licenses (FOLs) are required to ensure implementation of DBT Order requirements.
Therefore, administrative license changes to FOL Nos. NPF-72 and NPF-77 are being made to incorporate the reference to the revised PSP, SCP, and T&Q Plan required by the DBT Order.
These changes comply with the standards and requirements of the Atomic Energy Act of 1954, as amended, and the Commission's rules and regulations set forth in 10 CFR Chapter I.
Please replace the enclosed pages to your FOLs as indicated in the enclosure.
C. Crane A copy of our SE with regard to your security plans (designated as Safeguards Information) is provided in Enclosure 2.
Sincerely,
/RA/
John A. Nakoski, Chief Security Plan Review Team Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-456 and 50-457
Enclosures:
- 1. Administrative Change to FOL Nos. NPF-72 and NPF-77
- 2. SE Regarding the Security Plans (Safeguards Information) cc w/encl 1 only: See Mailing List 1 cc w/encls 1 and 2: Greg Baker, Station Security Manager
C. Crane A copy of our SE with regard to your security plans (designated as Safeguards Information) is provided in Enclosure 2.
Sincerely,
/RA/
John A. Nakoski, Chief Security Plan Review Team Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-456 and 50-457
Enclosures:
- 1. Administrative Change to FOL Nos. NPF-72 and NPF-77
- 2. SE Regarding the Security Plans (Safeguards Information) cc w/encl 1 only: See Mailing List 1 cc w/encls 1 and 2: Greg Baker, Station Security Manager DISTRIBUTION:
PUBLIC SPRT R/F OGC ACRS PCoates GDick AMendiola WRuland GHill (4) DLPM DPR TBoyce SReynolds, RIII Accession No.: ML043120031 *See previous concurrence OFFICE SPRT/TL* SPRT/PM* SPRT/LA SPRT/PL* OGC* NSIR/SC NRR/SC NAME DHuyck RFretz CRaynor JPeralta JHeck NLO SMorris JNakoski DATE 10/8/04 10/8/04 10/18/04 10/16/04 10/18/04 10/28/04 10/28/04 OFFICIAL RECORD COPY
Braidwood Station Units 1 and 2 cc:
Regional Administrator, Region III Illinois Emergency Management U.S. Nuclear Regulatory Commission Agency 801 Warrenville Road Division of Disaster Assistance &
Lisle, IL 60532-4351 Preparedness 110 East Adams Street Document Control Desk - Licensing Springfield, IL 62701-1109 Exelon Generation Company, LLC 4300 Winfield Road Chairman Warrenville, IL 60555 Will County Board of Supervisors Will County Board Courthouse Mr. Dwain W. Alexander, Project Manager Joliet, IL 60434 Westinghouse Electric Corporation Energy Systems Business Unit Attorney General Post Office Box 355 500 S. Second Street Pittsburgh, PA 15230 Springfield, IL 62701 Joseph Gallo George L. Edgar Gallo & Ross Morgan, Lewis and Bockius 1025 Connecticut Ave., NW, Suite 1014 1111 Pennsylvania Ave, NW Washington, DC 20036 Washington, DC 20004 Ms. Bridget Little Rorem Braidwood Station Plant Manager Appleseed Coordinator Exelon Generation Company, LLC 117 N. Linden Street 35100 S. Rt. 53, Suite 84 Essex, IL 60935 Braceville, IL 60407-9619 Howard A. Learner Site Vice President - Braidwood Environmental Law and Policy Exelon Generation Company, LLC Center of the Midwest 35100 S. Rt. 53, Suite 84 35 East Wacker Dr., Suite 1300 Braceville, IL 60407-9619 Chicago, IL 60601-2110 Senior Vice President, Nuclear Services U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC Braidwood Resident Inspectors Office 4300 Winfield Road 35100 S. Rt. 53, Suite 79 Warrenville, IL 60555 Braceville, IL 60407 Vice President of Operations - Mid-West Ms. Lorraine Creek Pressurized Water Reactors RR 1, Box 182 Exelon Generation Company, LLC Manteno, IL 60950 4300 Winfield Road Warrenville, IL 60555 Chairman, Ogle County Board Post Office Box 357 Oregon, IL 61061
Braidwood Station Units 1 and 2 Regulatory Assurance Manager - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood, Byron and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-456 BRAIDWOOD STATION, UNIT 1 ADMINISTRATIVE LICENSE CHANGE TO FACILITY OPERATING LICENSE License No. NPF-72
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. Consistent with Order EA-03-086, the Order requiring compliance with the revised design basis threat, (DBT Order) issued on April 29, 2003, conforming administrative changes to Facility Operating Licenses (FOLs) are required to ensure implementation of DBT Order requirements. Therefore, an administrative license change to FOL No. NPF-72 is being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan required by the DBT Order. These changes comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this administrative license change can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this administrative license change will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this administrative license change is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the FOL is changed, as indicated in the attachment.
- 3. This administrative license change is effective as of its date of issuance and shall be implemented on or before October 29, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
John A. Nakoski, Chief Security Plan Review Team Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the FOL Date of Issuance: October 28, 2004
CHANGES TO FACILITY OPERATING LICENSE NO. NPF-72 DOCKET NO. 50-456 Replace the following page of Facility Operating License NPF-72 with the attached revised page as indicated. The revised page is identified by revision date and contains marginal lines indicating the area of change.
Remove Page Insert Page 5 5
F. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled:
"Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 0," submitted by letter dated October 21, 2004.
G. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
H. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic.Energy Act of 1954, as amended, to cover public liability claims.
I. This license is effective as of the date of issuance and shall expire at midnight on October 17, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by:
Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:
- 1. Work Items to be completed
- 2. Appendix A - Technical Specifications (NUREG-1276)
- 3. Appendix B - Environmental Protection Plan
- 4. Appendix C - Additional Conditions Date of Issuance: July 2, 1987 1
The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Amendment No. 109 Revised by letter dated October 28, 2004
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-457 BRAIDWOOD STATION, UNIT 2 ADMINISTRATIVE LICENSE CHANGE TO FACILITY OPERATING LICENSE License No. NPF-77
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. Consistent with Order EA-03-086, the Order requiring compliance with the revised design basis threat, (DBT Order) issued on April 29, 2003, conforming administrative changes to Facility Operating Licenses (FOLs) are required to ensure implementation of DBT Order requirements. Therefore, an administrative license change to FOL No. NPF-77 is being made to incorporate the reference to the revised Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan required by the DBT Order. These changes comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this administrative license change can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this administrative license change will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this administrative license change is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the FOL is changed, as indicated in the attachment.
- 3. This administrative license change is effective as of its date of issuance and shall be implemented on or before October 29, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
John A. Nakoski, Chief Security Plan Review Team Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the FOL Date of Issuance: October 28, 2004
CHANGES TO FACILITY OPERATING LICENSE NO. NPF-77 DOCKET NO. 50-457 Replace the following page of Facility Operating License NPF-77 with the attached revised page as indicated. The revised page is identified by revision date and contains marginal lines indicating the area of change.
Remove Page Insert Page 6 6
F. Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled:
"Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 0," submitted by letter dated October 21, 2004.
G. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
H. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
I. This license is effective as of the date of issuance and shall expire at midnight on December 18, 2027.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by:
James H. Sniezek, Deputy Director Office of Nuclear Reactor Regulation Attachments:
- 1. Work Items to be completed
- 2. Appendix A -Technical Specifications
- 3. Appendix B - Environmental Protection Plan
- 4. Appendix C - Additional Conditions Date of Issuance: May 20, 1988 1
The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Amendment No. 109 Revised by letter dated October 28, 2004