|
|---|
Category:Inspection Report Correspondence
MONTHYEARIR 05000456/20224012022-07-13013 July 2022
Security Baseline Inspection Report 05000456/2022401 and 05000457/2022401
IR 05000456/20225012022-03-21021 March 2022
Emergency Preparedness Biennial Exercise Inspection Report 05000456/2022501 and 05000457/2022501
IR 05000456/20155012016-02-0303 February 2016
NRC Emergency Preparedness Annual Inspection Report No. 05000456/2015501; 05000457/2015501
IR 05000456/20105012011-01-14014 January 2011
IR 05000456-10-501, 05000457-10-501 on 12/31/10, Braidwood, Units 1 & 2, NRC Emergency Preparedness Annual Inspection
IR 05000456/20085012009-02-13013 February 2009
Emergency Preparedness Annual Inspection Report No. 05000456-08-501, 05000457-08-501, Security Annual Inspection Report No. 05000456-08-401, 05000457-08-401
IR 05000456/20075012008-02-14014 February 2008
IR 05000456-07-501, IR 05000457-07-501, IR 05000456-07-403, and IR 05000457-07-403, on 12/31/2007, for Braidwood, Emergency Preparedness Annual Inspection Report and Security Annual Inspection Report
ML0718304902007-06-29029 June 2007
MC&A Cover Letter Only
ML0707300272007-03-0707 March 2007
Oak Ridge Institute for Science and Education - Letter Report for 18 Water Samples from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2007-003) (Rfta No. 06-001)
IR 05000456/20060042006-11-16016 November 2006
Errata to IR 05000456-06-004, 05000457-06-004, on 07/01/2006 - 09/30/2006, Braidwood, Units 1 & 2; Fire Protection
ML0631206012006-11-0808 November 2006
IR 05000456-06-004, 05000457-06-004, on 07/01/2006 - 09/30/2006, Braidwood, Units 1 & 2; Fire Protection
IR 05000456/20060112006-09-22022 September 2006
IR 05000456-06-011, IR 05000457-06-011, - Cover Letter
ML0621602722006-07-28028 July 2006
Analytical Results for Fourteen Water Samples, Batch Eight, from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2006-004)(RFTA No. 06-001)
IR 05000456/20060082006-05-25025 May 2006
IR 05000456-06-008; IR 05000457-06-008; on 02/13/2006 - 05/25/2006; Braidwood, Units 1 and 2
ML0514502322005-05-23023 May 2005
Re Information Request for an NRC Biennial Ssdpc Baseline Inspection
ML0506000252005-02-28028 February 2005
Notification of NRC Inspection and Request for Information
IR 05000456/20020052002-04-26026 April 2002
IR 05000456/2002-005(DRP), IR 05000457/2002-005(DRP); on 2/19-3/31/02, Exelon Generation Company, LLC; Braidwood Station; Units 1 & 2. Post Maintenance Testing, and Surveillance Testing. Non-Cited Violations Issued
IR 05000456/20020022002-03-18018 March 2002
IR 05000456/2002-002, 05000457/2002-002; on 12/30/01-02/18/02, Exelon Generation Co, LLC; Braidwood Station, Units 1 and 2. Fire Protection and Maintenance Risk Assessment and Emergent Work Control
IR 05000456/20010132002-01-28028 January 2002
IR 05000456/2001-013(DRP), IR 05000457/2001-013(DRP), Exelon Generation Company, LLC, Braidwood Station, Units 1 & 2, Inspection on 11/20-12/29/2001 Re Post Maintenance Testing. One Noncited Violation Noted
2022-07-13
[Table view]
Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024
Integrated Inspection Report 05000456/2023004 and 05000457/2023004
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
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
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
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
ML23313A1552023-12-0101 December 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report
ML23331A8922023-11-22022 November 2023
Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference
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
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
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023
Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
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-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles
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
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
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
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.
ML23226A0062023-09-19019 September 2023
Review of License Renewal Commitment Number 10 Submittal
ML23180A1692023-09-11011 September 2023
Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
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
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
ML23191A8442023-07-10010 July 2023
05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023
Withdrawal - Proposed Alternatives Related to the Steam Generators
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
ML23110A1152023-06-12012 June 2023
Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter)
RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023
Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023
Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process
RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
ML23138A1342023-05-18018 May 2023
Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station
ML23132A0472023-05-12012 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
ML23130A0072023-05-10010 May 2023
Submittal of Core Operating Limits Report Cycle 24, Rev. 16
IR 05000456/20230012023-05-0808 May 2023
Integrated Inspection Report 05000456/2023001 and 05000457/2023001
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
ML23118A0202023-04-28028 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023
Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10
RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML23095A1292023-04-0505 April 2023
Steam Generator Tube Inspection Report for Refueling Outage 23
ML23094A1352023-04-0404 April 2023
Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010
RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023
License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
2024-02-02
[Table view] |
Text
July 13, 2022
SUBJECT:
BRAIDWOOD STATION - SECURITY BASELINE INSPECTION REPORT 05000456/2022401 AND 05000457/2022401
Dear Mr. Rhoades:
On June 24, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station and discussed the results of this inspection with Mr. J. Petty, Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Signed by Orth, Steven on 07/13/22 Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000456 and 05000457 License Numbers: NPF-72 and NPF-77 Report Numbers: 05000456/2022401 and 05000457/2022401 Enterprise Identifier: I-2022-401-0029 Licensee: Constellation Energy Generation, LLC Facility: Braidwood Station Location: Braceville, IL Inspection Dates: April 11, 2022 to June 24, 2022 Inspectors: J. Kutlesa, Physical Security Inspector A. Nguyen, Senior Resident Inspector Approved By: Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a security baseline inspection at Braidwood Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2201, Security Inspection Program for Commercial Nuclear Power Reactors. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
SAFEGUARDS
71130.02 - Access Control
The inspectors evaluated the access control program through completion of the following
inspection elements: Access Control
Main article: IP 71130.02
- (1) Tier I: All Tier II: All Tier III: All
71130.04 - Equipment Performance, Testing, and Maintenance
The inspectors evaluated the security equipment testing and maintenance program.
The following elements were evaluated: Equipment Performance, Testing, and Maintenance
Main article: IP 71130.04
- (1) Tier I: All Tier II: All Tier III: All
71130.09 - Security Plan Changes
The inspectors evaluated the security plan changes through completion of the following procedure elements:
Security Plan Changes (1 Partial)
(1) (Partial)
The opportunity to apply this procedure was not available in accordance with IMC 0306. This sample was not available because the licensee did not conduct the activity covered by this inspection procedure. Specifically, the licensee has not initiated a physical security plan change in accordance with Title 10 of the Code of Federal Regulations 50.54(p)(2) since the last performance of this inspection procedure.
71130.14 - Review of Power Reactor Target Sets
The inspectors evaluated the Security Target Set Program. The following elements were evaluated:
Review of Power Reactor Target Sets
Main article: IP 71130.14
- (1) 02.02 a-d, f, 02.03, 02.04 a-b,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
PP01: Protected Area Security Equipment Performance Index Sample (IP Section 02.17)
=
- (1) January 01, 2021 through April 30,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On June 24, 2022, the inspectors presented the security baseline inspection results to Mr. J. Petty, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71130.02 Corrective Action AR 04395545 Security PA/VA Key Core Change 01/12/2021
Documents AR 04456795 Individuals Granted UA 10/29/2021
AR 04471653 Unattended Vehicle 01/13/2022
AR04488423 30 Day BOP 03/30/2022
Corrective Action AR 04502211 Refresher of BOP Requirements 05/26/2022
Documents
Resulting from
Inspection
Procedures SY-AA-101-102 Compensating for Security System Failures 19
SY-AA-101-106 Control and Classification of Safeguards Information (SGI) 22
and Sensitive Unclassified Non-Safeguards Information
(SUNSI)
SY-AA-101-112 Exelon Security Search Processes 38
SY-AA-101-117 Processing and Escorting of Personnel and Vehicles 33
SY-AA-101-120 Control of Security Access Control Devices 9
SY-AA-101-132 Security Assessment and Response to Unusual Activities 35
SY-AA-101-155- Safeguards Event Report 07/2021
F-01 through
05/2022
71130.04 Engineering 6300960 X-Ray Machines Replacement 0
Changes
Miscellaneous SY-AA-150-103- Weapon Maintenance Log 01/2020
F-01 through
06/2022
Procedures SY-AA-101-122 Testing Security Equipment 23
SY-AA-150-103 Firearms Maintenance, Testing, And Accountability 2
SY-AA-500-127 Safety/Security Interface 7
Self-Assessments NOSA-BEW-2101 Security Programs Audit Report 02/26/2021
(AR 4394272)
71130.09 Miscellaneous N/A Braidwood Station Security Plan 18
71130.14 Corrective Action 4492929 NRC Inspection on Target Sets 04/13/2022
Documents 4496341 NRC ID: Inspection on Target Sets 04/28/2022
Inspection Type Designation Description or Title Revision or
Procedure Date
Resulting from
Inspection
Engineering BB-PRA-012 Byron/Braidwood PRA Update: Internal Flood Evaluation 09
Evaluations Summary Notebook
Procedures 0Bw0A Security-1 Security Threat 18
SY-BR-101-502 Braidwood Nuclear Generation Station Target Sets 06, 07, 08,
Procedure and 09
71151 Miscellaneous LS-AA-2160 Monthly Data Elements for NRC ROP Indicator 01/2021
through
04/2022
6
