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| {{Adams | | {{Adams |
| | number = ML100610223 | | | number = ML090630284 |
| | issue date = 03/03/2010 | | | issue date = 03/04/2009 |
| | title = 03/03/2010, Braidwood Power Plant EOC Annual Assessment Letter (05000456-10-001; 05000457-10-001) | | | title = Annual Assessment Letter - Braidwood (05000456/2010-001; 05000457/2010-001) |
| | author name = West S K | | | author name = Skokowski R A |
| | author affiliation = NRC/RGN-III/DRP | | | author affiliation = NRC/RGN-III/DRP/B3 |
| | addressee name = Pardee C G | | | addressee name = Pardee C G |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter: |
| [[Issue date::March 3, 2010]] | | [[Issue date::March 4, 2009]] |
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| Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear | | Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555 |
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| 4300 Winfield Road Warrenville IL 60555
| | SUBJECT: ANNUAL ASSESSMENT LETTER - BRAIDWOOD STATION, UNITS 1 AND 2 (05000456/2010001; 05000457/2010001) |
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| SUBJECT: ANNUAL ASSESSMENT LETTER - BRAIDWOOD STATION, UNITS 1 AND 2, (05000456/2010001; 05000457/2010001) | |
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| ==Dear Mr. Pardee:== | | ==Dear Mr. Pardee:== |
| On February 10, 2010, the NRC staff completed its performance review of Braidwood Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2009. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility. | | On February 11, 2009, the Nuclear Regulatory Commission (NRC) staff completed its performance review of Braidwood Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2008. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility. |
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| This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only - Security Information" will include the Security Cornerstone review and resultant inspection plan. | | This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only--Security Information" will include the security cornerstone review and resultant inspection plan. |
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| Overall, Braidwood Station operated in a manner that preserved public health and safety and fully met all cornerstone objectives. | | Overall, Braidwood Station, Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter at Braidwood Units 1 and 2 was within the Licensee Response column of the NRC's 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 |
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| Plant performance for the most recent quarter at Braidwood Station Unit 1 was within the Regulatory Response Cornerstone column of the NRC's Action Matrix, based on one inspection finding being classified as having low-to-moderate safety significance (White) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). The White finding involved the failure of the containment sump suction isolation valve to fully open.
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| When you notify us of your readiness, we will conduct a supplemental inspection for Braidwood Unit 1 using Inspection Procedure 95001, "Inspection for One or Two White Inputs in a Strategic Performance Area." In addition, we plan to conduct reactor oversight program (ROP) baseline inspections at Braidwood Unit 1.
| | Although plant performance was within the Licensee Response column, the significance of the Bryozoa infestation at the Lake Screen House circulating water forebays is still under review which, when finalized, may change our assessment of your plant |
| | =s safety performance. Therefore, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility. We also plan on conducting two infrequently performed inspection procedures (IPs), which include: IP 60856.1, "Review of 10 CFR 72.212(b) Evaluations at Operating Plants," and IP 60853, "OnSite Fabrication of Components and Construction of an ISFSI." The enclosed inspection plan details the inspections, less those related to physical protection scheduled through June 30, 2010. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. |
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| Plant performance for the most recent quarter, as well as the first three quarters of the assessment periods at Braidwood Station Unit 2, was within the Licensee Response column of the NRC's 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, we plan to conduct reactor oversight program (ROP)
| | The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle review. |
| baseline inspections at Braidwood Station Unit 2. The NRC also plans to conduct several special and infrequently performed inspection procedures (IPs), which include inspections related to the pre-operational testing and operation of the Independent Spent Fuel Storage Installation.
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| In the mid-cycle performance review letter dated September 1, 2009, [ML092440402], we advised you of a substantive cross-cutting issue in the area of human performance. The substantive cross-cutting issue was the result of several findings that involved deficiencies in human performance throughout the station. In response to the identified cross-cutting issues, you had provided us your Human Performance Improvement Plan and specific actions that you planned to take to correct the cross-cutting issue performance deficiencies. | | In accordance with 10 CFR 2.390 of the NRC |
| | | =s A Rules 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). |
| Nevertheless, the staff has continued to have concerns with your human performance. During this assessment period, you have had three of these findings in the human performance area that shared the common cross-cutting aspect of failure to make conservative assumptions and demonstrating the proposed action is safe (H.1(b)). These findings were from more than one cornerstone (Mitigating Systems and Initiating Ev ents). Moreover, your Human Performance Improvement Plan actions have not yet proven effective in substantially mitigating the cross-cutting theme even though a reasonable duration of time has passed. Therefore, this substantive cross-cutting issue remains open until your corrective actions have resulted in a positive sustainable improvement in the area and the number of findings in the theme is reduced or maintained. Please provide a status update of the progress that was made to improve the human performance during the annual end-of-cycle public meeting to be scheduled at a later date. We will also access the human performance related issues as a Problem Identification and Resolution follow-up inspection item in accordance with IP 71152,
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| "Identification and Resolution of Problems," Section 03.02, "Selected Issue Follow-up Inspection."
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| The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through June 30, 2011. Please note that we plan on conducting two infrequently performed IPs: IP 60854.1, "Preoperational Testing of an Independent Spent Fuel Storage Facility Installation at Operating Plants," and IP 60855.1, "Operation of an Independent Spent Fuel Storage Installation at Operating Plants," this year at your Braidwood Station. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle review.
| | If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at 630-829-9620 with any questions you may have regarding this letter or the inspection plan. |
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| In accordance with 10 CFR 2.390 of the NRC
| | Sincerely,/RA/ Richard A. Skokowski, Chief |
| =s A Rules 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). If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Richard A. Skokowski at 630-829-9620 with any questions you may have regarding this letter or the inspection plan.
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| Sincerely,/RA/
| | Branch 3 Division of Reactor Projects |
| Steven West, Director Division of Reactor Projects
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| Docket Nos. 50-456, 50-457 | | Docket Nos. 50-456, 50-457 |
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| Braidwood Station Inspection/Activity Plan | | Braidwood Station Inspection/Activity Plan |
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| cc w/encl: Distribution via ListServ
| | DISTRIBUTION See next page |
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| Inspection / Activity Plan Page 1 of 2 02/24/2010 Report 22 03/01/2010
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| -06/30/2011 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Braidwood BI ENG-COMPONENT DESIGN BASIS INSPECTION 8 1 IP Component Design Bases Inspection 7111121 03/01/2010 04/02/2010 BI EP-EP EXERCISE INSPECTION / PI VERIFICATION 3 1 IP Exercise Evaluation 7111401 03/22/2010 03/26/2010 1 IP Drill/Exercise Performance 71151-EP01 03/22/2010 03/26/2010 1 IP ERO Drill Participation 71151-EP02 03/22/2010 03/26/2010 1 IP A lert & Notification System 71151-EP03 03/22/2010 03/26/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTI 1 1 IP Radiation Monitoring Instrumentation 71124.05 06/14/2010 06/18/2010 1 IP Reactor Coolant System Activity 71151-BI01 06/14/2010 06/18/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTI 1 1 IP Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124.08 07/12/2010 07/16/2010 1 IP RETS/ODCM Radiological Effluent 71151-PR01 07/12/2010 07/16/2010 BI PI&R-BIENNIAL PI&R INSPECTION 4 1 IP Identification and Resolution of Problems 71152B 08/30/2010 09/17/2010 BI ENG-ENGINEERING INSERVICE INSPECTION 1 1 IP Inservice Inspection Activities - PWR 7111108P 10/04/2010 10/29/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Verification of Licensee Responses to NRC Requirement for Inventories of Materials Tracked in NSTS 2515/179 10/18/2010 10/22/2010 1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 10/18/2010 10/22/2010 1 IP Occupational ALARA Planning and Controls 71124.02 10/18/2010 10/22/2010 1 IP Occupational Exposure Control Effectiveness 71151-OR01 10/18/2010 10/22/2010 BI ENG-POLAR CRANE SINGLE FAILURE PROOF UPGRADE 1 1 IP Refueling and Other Outage Activities 7111120 11/15/2010 12/03/2010 BI EP-EP ROUTINE INSPECTION / PI VERIFICATION 2 1 IP Radiological Environmental Monitoring Program 7111402 01/31/2011 02/04/2011 1 IP Emergency Response Organization Augmentation Testing 7111403 01/31/2011 02/04/2011 1 IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 01/31/2011 02/04/2011 1 IP Drill/Exercise Performance 71151-EP01 01/31/2011 02/04/2011 1 IP ERO Drill Participation 71151-EP02 01/31/2011 02/04/2011 1 IP A lert & Notification System 71151-EP03 01/31/2011 02/04/2011 ISFSI-ISFSI INSPECTION. - SCHEDULE DEPENDENT 2 1 IP Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants 60854.1 03/01/2011 06/30/2011 1 IP Operation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.1 06/01/2011 08/31/2011 This report does not include INPO and OUTAGE activities.
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| This report shows only on-site and announced inspection procedures.
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| Inspection / Activity Plan Page 2 of 2 02/24/2010 Report 22 03/01/2010
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| -06/30/2011 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Braidwood BI RP-RADIATION PROTECTION BASELINE INSPECTI 1 1 IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 03/28/2011 04/01/2011 1 IP Occupational Dose Assessment 71124.04 03/28/2011 04/01/2011 1 IP Reactor Coolant System Activity 71151-BI01 03/28/2011 04/01/2011 BI ENG-ENGINEERING INSERVICE INSPECTION - U2 1 2 IP Inservice Inspection Activities - PWR 7111108P 04/18/2011 05/05/2011 BI RP-RADIATION PROTECTION BASELINE INSPECTI 1 1 IP Radioactive Gaseous and Liquid Effluent Treatment 71124.06 05/23/2011 05/27/2011 1 IP Performance Indicator Verification 71151 05/23/2011 05/27/2011 OL PREP-BRAIDWOOD INIT PREP - 05/2011 2 1 OL - INITIAL EXAM - JUN 2011 - BRAI W90226 05/30/2011 06/03/2011 OL EXAM-BRAIDWOOD INIT EXAM - 06/2011 2 1 OL - INITIAL EXAM - JUN 2011 - BRAI W90226 06/20/2011 07/01/2011 This report does not include INPO and OUTAGE activities.
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Category:Inspection Plan
MONTHYEARIR 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) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML23339A0452023-12-0505 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) 2024-08-29
[Table view] Category:Letter
MONTHYEARIR 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) 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) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open 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 ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 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) 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 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 IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 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)) 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 2024-08-09
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March 4, 2009
Mr. Charles 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 - BRAIDWOOD STATION, UNITS 1 AND 2 (05000456/2010001; 05000457/2010001)
Dear Mr. Pardee:
On February 11, 2009, the Nuclear Regulatory Commission (NRC) staff completed its performance review of Braidwood Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2008. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only--Security Information" will include the security cornerstone review and resultant inspection plan.
Overall, Braidwood Station, Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter at Braidwood Units 1 and 2 was within the Licensee Response column of the NRC's 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).
Although plant performance was within the Licensee Response column, the significance of the Bryozoa infestation at the Lake Screen House circulating water forebays is still under review which, when finalized, may change our assessment of your plant
=s safety performance. Therefore, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility. We also plan on conducting two infrequently performed inspection procedures (IPs), which include: IP 60856.1, "Review of 10 CFR 72.212(b) Evaluations at Operating Plants," and IP 60853, "OnSite Fabrication of Components and Construction of an ISFSI." The enclosed inspection plan details the inspections, less those related to physical protection scheduled through June 30, 2010. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature.
The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle review.
In accordance with 10 CFR 2.390 of the NRC
=s A Rules 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).
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at 630-829-9620 with any questions you may have regarding this letter or the inspection plan.
Sincerely,/RA/ Richard A. Skokowski, Chief
Branch 3 Division of Reactor Projects
Docket Nos. 50-456, 50-457
License Nos. NPF-72, NPF-77
Enclosure:
Braidwood Station Inspection/Activity Plan
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