|
|
Line 3: |
Line 3: |
| | issue date = 03/05/2012 | | | issue date = 03/05/2012 |
| | title = Annual Assessment Letter for Braidwood Station, Units 1 & 2 (Report 05000456-11-007 and 05000457-11-007) | | | title = Annual Assessment Letter for Braidwood Station, Units 1 & 2 (Report 05000456-11-007 and 05000457-11-007) |
| | author name = Duncan E R | | | author name = Duncan E |
| | author affiliation = NRC/RGN-III/DRP/B3 | | | author affiliation = NRC/RGN-III/DRP/B3 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000456, 05000457 | | | docket = 05000456, 05000457 |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532 | | {{#Wiki_filter:March 5, 2012 |
| -4352 March 5, 2012 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
| |
|
| |
|
| SUBJECT: ANNUAL ASSESSMENT LETTER FOR BRAIDWOOD STATION, UNITS 1 AND 2 (REPORT 05000456/20 1 1 00 7 AND 05000457/20 1 1 00 7) | | ==SUBJECT:== |
| | ANNUAL ASSESSMENT LETTER FOR BRAIDWOOD STATION, UNITS 1 AND 2 (REPORT 05000456/20 1 1 00 7 AND 05000457/20 1 1 00 7) |
|
| |
|
| ==Dear Mr. Paci l i o:== | | ==Dear Mr. Paci l i o:== |
| On February 1 4, 20 1 2 , the Nuclear Regulatory Commission (N RC) staff completed its end-of-cycle performance review of Braidwood Station, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 201 1 , through December 31, 201 1. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security | | On February 1 4, 20 1 2 , the Nuclear Regulatory Commission (N RC) staff completed its end-of-cycle performance review of Braidwood Station, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 201 1 , through December 31, 201 1. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security-related inspection plan. |
| -related inspection plan. | |
|
| |
|
| The NRC determined that overall, Braidwood Station, Units 1 and 2, operated in a manner that preserved public health and safety and met all cornerstone objectives. Plant performance for the most recent quarter, as well as the first three quarters of the assessment period, at Braidwood Station | | The NRC determined that overall, Braidwood Station, Units 1 and 2, operated in a manner that preserved public health and safety and met all cornerstone objectives. Plant performance for the most recent quarter, as well as the first three quarters of the assessment period, at Braidwood Station |
Line 32: |
Line 31: |
| Therefore, the NRC plans to conduct ROP baseline inspections at Braidwood Station. | | Therefore, the NRC plans to conduct ROP baseline inspections at Braidwood Station. |
|
| |
|
| We also plan to conduct infrequently performed and temporary instruction inspections at your facility. These inspections include a follow-up inspection using IP 92723, "Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12 Month Period ," to evaluate your corrective actions and extent of condition review related to a Steam Generator Margi n-to-Overfill Backfit [ML 110320508] that was issued. | | We also plan to conduct infrequently performed and temporary instruction inspections at your facility. These inspections include a follow-up inspection using IP 92723, "Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12 Month Period ," to evaluate your corrective actions and extent of condition review related to a Steam Generator Margi n-to-Overfill Backfit [ML110320508] that was issued. |
|
| |
|
| Temporary Instruction 182, "Review of the Implementation of an Industry Initiative to Control the Degradation of Underground Piping and Tanks," | | Temporary Instruction 182, "Review of the Implementation of an Industry Initiative to Control the Degradation of Underground Piping and Tanks," |
| will also be conducted at Braidwood Station | | will also be conducted at Braidwood Station |
| . | | . |
| M. Pacilio | | M. Pacilio-2-The enclosed inspection plan lists the inspections scheduled through June 30, 20 1 3. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. |
| -2-
| |
| The enclosed inspection plan lists the inspections scheduled through June 30, 20 1 3. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid | |
| -cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. | |
|
| |
|
| In accordance with 10 CFR 2.390 of the NRC | | In accordance with 10 CFR 2.390 of the NRC |
| =s ARules of Practice,@ a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading | | =s ARules of Practice,@ a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| -rm/adams.html (the Public Electronic Reading Room). | |
|
| |
|
| Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan. | | Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan. |
|
| |
|
| Sincerely,/RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50 | | Sincerely, |
| -456 and 50-457 License Nos. NPF | | /RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-456 and 50-457 License Nos. NPF-72 and NPF-77 Enclosure: Braidwood Station Inspection/Activity Plan |
| -72 and NPF-77 | |
| | |
| ===Enclosure:===
| |
| Braidwood Station Inspection/Activity Plan | |
|
| |
|
| cc w/encl: Distribution via LIstServ | | cc w/encl: Distribution via LIstServ |
|
---|
Category:Inspection Plan
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) ML22111A0752022-04-21021 April 2022 Information Request Letter for 2022 Problem Identification and Resolution Inspection at Braidwood Station IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) ML20183A3912020-07-0101 July 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) IR 05000456/20190052019-08-28028 August 2019 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2019005; 05000457/2019005) ML19154A6152019-06-0303 June 2019 Ltr. 06/03/19 Braidwood Station, Unit 1 - Notification of NRC Inspection and Request for Information; Inspection Report 05000456/2019004; 05000457/2019004 (DRS-J.Bozga) ML19136A1852019-05-15015 May 2019 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 IR 05000456/20180062019-03-0404 March 2019 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000457/2018006 and 05000456/2018006) ML18305A3542018-10-31031 October 2018 Ltr. 10/31/18 Braidwood Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000456/2019010; 05000457/2019010 (DRS-J.CorujoSandin) IR 05000456/20180052018-08-28028 August 2018 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2018005 and 05000457/2018005) IR 05000456/20170062018-03-0202 March 2018 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2017006 and 05000457/2017006) IR 05000456/20170052017-08-28028 August 2017 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2017005 and 05000457/2017005) IR 05000456/20160062017-03-0101 March 2017 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016006 and 05000457/2016006) ML16265A5772016-09-20020 September 2016 E-Mail; Braidwood Station, Unit 1 - Baseline Inservice Inspection Onsite Information Request (Msh) IR 05000456/20160052016-08-31031 August 2016 MID-CYCLE Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016005; 05000457/2016005) ML16174A0852016-06-21021 June 2016 Notification of NRC Inspection and Request for Information 05000456/2016004; 05000457/2016004 IR 05000456/20150062016-03-0202 March 2016 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Inspection Report 05000456/2015006 and 05000457/2015006) ML15328A5022015-11-24024 November 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection; Inspection Report 05000456/2016008; 05000457/2016008 (Bxj) IR 05000456/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Braidwood, Units 1 and 2 (Report 05000456/2015005; 05000457/2015005) ML15231A1492015-08-17017 August 2015 Ltr. 08/17/15 Braidwood Station, Unit 2 - Notification of NRC Inspection and Request for Information (Txb) IR 05000456/20140012015-03-0404 March 2015 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2014001; 05000457/2014001) ML15021A2322015-01-20020 January 2015 U1 ISI Request for Information ML14245A0692014-09-0202 September 2014 Mid-Cycle Assessment Letter for Braidwood Station, Units 1 and 2 ML14223B2132014-08-11011 August 2014 Heat Sink Request for Information IR 05000456/20130012014-03-0404 March 2014 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2013001; 05000457/2013001) IR 05000456/20130062013-09-0303 September 2013 Mid-Cycle Assessment Letter (IR 05000456-13-006 & 05000457-13-006) ML13120A5842013-04-29029 April 2013 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000456-13-007 05000457-13-007 IR 05000456/20120012013-03-0404 March 2013 Annual Assessment Letter - Braidwood Station, Units 1 and 2, 05000456/2012001 and 05000457/2012001 ML12248A3062012-09-0404 September 2012 Mid-Cycle Assessment Letter for Braidwood Station Units 1 and 2 IR 05000456/20110072012-03-0505 March 2012 Annual Assessment Letter for Braidwood Station, Units 1 & 2 (Report 05000456-11-007 and 05000457-11-007) IR 05000456/20110062011-09-0101 September 2011 Mid-Cycle Letter for Braidwood Station, Units 1 and 2, - 05000456/2011-006; 05000457/2011-006 ML1024401002010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Braidwood Nuclear Power Plant IR 05000456/20100012010-03-0303 March 2010 Braidwood Power Plant EOC Annual Assessment Letter (05000456-10-001; 05000457-10-001) ML0924404022009-09-0101 September 2009 Braidwood - Mid-Cycle Performance Review and Inspection Plan ML0906302842009-03-0404 March 2009 Annual Assessment Letter - Braidwood (05000456/2010-001; 05000457/2010-001) ML0824602282008-09-0202 September 2008 Braidwood, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000456/20080012008-03-0303 March 2008 Braidwood, EOC Annual Assessment Letter (Report 05000456-08-001; 05000457-08-001) ML0735402552007-12-19019 December 2007 Inspection Plan 1/1/08 - 12/31/08 ML0724303542007-08-31031 August 2007 8/31/07 Braidwood - Mid-Cycle Performance Review and Inspection Plan 2023-08-30
[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
March 5, 2012
SUBJECT:
ANNUAL ASSESSMENT LETTER FOR BRAIDWOOD STATION, UNITS 1 AND 2 (REPORT 05000456/20 1 1 00 7 AND 05000457/20 1 1 00 7)
Dear Mr. Paci l i o:
On February 1 4, 20 1 2 , the Nuclear Regulatory Commission (N RC) staff completed its end-of-cycle performance review of Braidwood Station, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 201 1 , through December 31, 201 1. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined that overall, Braidwood Station, Units 1 and 2, operated in a manner that preserved public health and safety and met all cornerstone objectives. Plant performance for the most recent quarter, as well as the first three quarters of the assessment period, at Braidwood Station
, Units 1 and 2 , was within the Licensee Response column of the NRC's Reactor Oversight Process (ROP) Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green).
Therefore, the NRC plans to conduct ROP baseline inspections at Braidwood Station.
We also plan to conduct infrequently performed and temporary instruction inspections at your facility. These inspections include a follow-up inspection using IP 92723, "Follow Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12 Month Period ," to evaluate your corrective actions and extent of condition review related to a Steam Generator Margi n-to-Overfill Backfit [ML110320508] that was issued.
Temporary Instruction 182, "Review of the Implementation of an Industry Initiative to Control the Degradation of Underground Piping and Tanks,"
will also be conducted at Braidwood Station
.
M. Pacilio-2-The enclosed inspection plan lists the inspections scheduled through June 30, 20 1 3. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
In accordance with 10 CFR 2.390 of the NRC
=s ARules of Practice,@ a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact me at (630) 829-9620 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-456 and 50-457 License Nos. NPF-72 and NPF-77 Enclosure: Braidwood Station Inspection/Activity Plan
cc w/encl: Distribution via LIstServ
Page 1 of 2 Planned Dates Start End Inspection Activity Title N