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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 August 6, 2012 Mr. Michael J. Pacilio Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
| -4352 August 6, 2012 Mr. Michael J. Pacil i o Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ASSESSMENT FOLLOW-UP LETTER FOR BRAIDWOOD STATION UNIT 2 | | ASSESSMENT FOLLOW-UP LETTER FOR BRAIDWOOD STATION UNIT 2 |
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| ==Dear Mr. Paci l i o:== | | ==Dear Mr. Pacilio:== |
| As a result of our quarterly review of plant performance, which was completed on July 31, 2012 , the NRC updated its assessment of Braidwood Station Unit 2. The NRC's evaluation consisted of a review of performance indicators and inspection results. This letter informs you of the NRC's assessment of Braidwood Station Unit 2 and its plans for a future inspection at your facility. This letter supplements, but does not supersede, the annual assessment letter issued on March 5, 2012 (ADAMS A ccession No. ML12065A102
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| ).
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| The NRC's review of Braidwood Unit 2 identified that the Mitigating System Performance Index for the Cooling Water Support System has crossed th e Green-to-White threshold. This was due to probabilistic risk assessment model change errors, operating restrictions on the cooling water support system, and equipment failures.
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| The NRC determined the performance at Braidwood Station Unit 2 to be in the Regulatory Response Column of the Reactor Oversight Process Action Matrix beginning in the second quarter of 2012 based on the PI data report ed to the NRC.
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| Therefore, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 9500 1 , "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," to provide assurance that the root causes and contributing causes of risk-significant performance issues are understood, that the extent of condition and cause is identified, and to ensure the licensee's corrective actions for risk
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| -significant performance issues are sufficient to address the root and contributing causes and prevent recurrence.
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| The NRC requests that your staff provide notification of your readiness for the NRC to conduct this supplemental inspection.
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| M. Pacilio In accordance with 10 CFR 2.390 of the NRC
| | As a result of our quarterly review of plant performance, which was completed on July 31, 2012, the NRC updated its assessment of Braidwood Station Unit 2. The NRCs evaluation consisted of a review of performance indicators and inspection results. This letter informs you of the NRCs assessment of Braidwood Station Unit 2 and its plans for a future inspection at your facility. This letter supplements, but does not supersede, the annual assessment letter issued on March 5, 2012 (ADAMS Accession No. ML12065A102). |
| =s ARules of Practice,@ a copy of this letter 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
| | The NRCs review of Braidwood Unit 2 identified that the Mitigating System Performance Index for the Cooling Water Support System has crossed the Green-to-White threshold. This was due to probabilistic risk assessment model change errors, operating restrictions on the cooling water support system, and equipment failures. |
| -rm/adams.html (the Public Electronic Reading Room).
| | The NRC determined the performance at Braidwood Station Unit 2 to be in the Regulatory Response Column of the Reactor Oversight Process Action Matrix beginning in the second quarter of 2012 based on the PI data reported to the NRC. Therefore, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, to provide assurance that the root causes and contributing causes of risk-significant performance issues are understood, that the extent of condition and cause is identified, and to ensure the licensees corrective actions for risk-significant performance issues are sufficient to address the root and contributing causes and prevent recurrence. The NRC requests that your staff provide notification of your readiness for the NRC to conduct this supplemental inspection. |
| Please contact Eric Duncan a t 6 30-829-9620 with any questions you may have regarding this letter. Sincerely, /RA/ Gary L. Shear , Acting Director Division of Reactor Projects
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| Docket No. | | M. Pacilio In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter 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). |
| 50-45 7 License No. | | ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| NPF-77 cc: Distribution via ListServ TM M. Pacilio In accordance with 10 CFR 2.390 of the NRC | | Please contact Eric Duncan at 630-829-9620 with any questions you may have regarding this letter. |
| =s ARules of Practice,@ a copy of this letter 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 | | Sincerely, |
| -rm/adams.html (the Public Electronic Reading Room). | | /RA/ |
| Please contact Eric Duncan at 630-829-9620 with any questions you may have regarding this letter. Sincerely, | | Gary L. Shear, Acting Director Division of Reactor Projects Docket No. 50-457 License No. NPF-77 cc: Distribution via ListServ TM |
| /RA/ Gary L. Shear, Acting Director Division of Reactor Projects Docket No. | | |
| 50-45 7 License No. | | M. Pacilio In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter 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). |
| NPF-77 cc: Distribution via ListServ TM DOCUMENT NAME: | | ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| G:\DRPIII\BRAI\Braidwood Assessment Follow | | Please contact Eric Duncan at 630-829-9620 with any questions you may have regarding this letter. |
| -up Letter | | Sincerely, |
| - White PI.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII RIII NAME RNg:dtp EDuncan DPassehl JLara GShear DATE 08/03/12 08/03/12 08/06/12 08/06/12 08/06/12 OFFICIAL RECORD COPY | | /RA/ |
| | Gary L. Shear, Acting Director Division of Reactor Projects Docket No. 50-457 License No. NPF-77 cc: Distribution via ListServ TM DOCUMENT NAME: G:\DRPIII\BRAI\Braidwood Assessment Follow-up Letter - White PI.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = |
| | Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII RIII NAME RNg:dtp EDuncan DPassehl JLara GShear DATE 08/03/12 08/03/12 08/06/12 08/06/12 08/06/12 OFFICIAL RECORD COPY |
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| Letter to M. Pacilio from G. Shear dated August 6, 2012. | | Letter to M. Pacilio from G. Shear dated August 6, 2012. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ASSESSMENT FOLLOW | | ASSESSMENT FOLLOW-UP LETTER FOR BRAIDWOOD STATION UNIT 2 DISTRIBUTION: |
| -UP LETTER FOR BRAIDWOOD STATION UNIT 2 DISTRIBUTION | | Silas Kennedy RidsNrrDorlLpl3-2 Resource RidsNrrPMBraidwood Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Steven Orth Jared Heck Allan Barker DRPIII DRSIII Carole Ariano Linda Linn Patricia Buckley Tammy Tomczak ROPreports.Resource@nrc.gov}} |
| : Silas Kennedy RidsNrrDorlLpl3
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| -2 Resource RidsNrrPMBraidwood Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Steven Orth Jared Heck Allan Barker DRPIII DRSIII Carole Ariano Linda Linn Patricia Buckley Tammy Tomczak ROPreports.Resource@nrc.gov}} | |
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Category:Letter
MONTHYEARML24263A1272024-09-23023 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) 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 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 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 2024-09-23
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 August 6, 2012 Mr. Michael J. Pacilio Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
ASSESSMENT FOLLOW-UP LETTER FOR BRAIDWOOD STATION UNIT 2
Dear Mr. Pacilio:
As a result of our quarterly review of plant performance, which was completed on July 31, 2012, the NRC updated its assessment of Braidwood Station Unit 2. The NRCs evaluation consisted of a review of performance indicators and inspection results. This letter informs you of the NRCs assessment of Braidwood Station Unit 2 and its plans for a future inspection at your facility. This letter supplements, but does not supersede, the annual assessment letter issued on March 5, 2012 (ADAMS Accession No. ML12065A102).
The NRCs review of Braidwood Unit 2 identified that the Mitigating System Performance Index for the Cooling Water Support System has crossed the Green-to-White threshold. This was due to probabilistic risk assessment model change errors, operating restrictions on the cooling water support system, and equipment failures.
The NRC determined the performance at Braidwood Station Unit 2 to be in the Regulatory Response Column of the Reactor Oversight Process Action Matrix beginning in the second quarter of 2012 based on the PI data reported to the NRC. Therefore, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, to provide assurance that the root causes and contributing causes of risk-significant performance issues are understood, that the extent of condition and cause is identified, and to ensure the licensees corrective actions for risk-significant performance issues are sufficient to address the root and contributing causes and prevent recurrence. The NRC requests that your staff provide notification of your readiness for the NRC to conduct this supplemental inspection.
M. Pacilio In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter 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 Eric Duncan at 630-829-9620 with any questions you may have regarding this letter.
Sincerely,
/RA/
Gary L. Shear, Acting Director Division of Reactor Projects Docket No. 50-457 License No. NPF-77 cc: Distribution via ListServ TM
M. Pacilio In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter 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 Eric Duncan at 630-829-9620 with any questions you may have regarding this letter.
Sincerely,
/RA/
Gary L. Shear, Acting Director Division of Reactor Projects Docket No. 50-457 License No. NPF-77 cc: Distribution via ListServ TM DOCUMENT NAME: G:\DRPIII\BRAI\Braidwood Assessment Follow-up Letter - White PI.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" =
Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII RIII NAME RNg:dtp EDuncan DPassehl JLara GShear DATE 08/03/12 08/03/12 08/06/12 08/06/12 08/06/12 OFFICIAL RECORD COPY
Letter to M. Pacilio from G. Shear dated August 6, 2012.
SUBJECT:
ASSESSMENT FOLLOW-UP LETTER FOR BRAIDWOOD STATION UNIT 2 DISTRIBUTION:
Silas Kennedy RidsNrrDorlLpl3-2 Resource RidsNrrPMBraidwood Resource RidsNrrDirsIrib Resource Chuck Casto Cynthia Pederson Steven Orth Jared Heck Allan Barker DRPIII DRSIII Carole Ariano Linda Linn Patricia Buckley Tammy Tomczak ROPreports.Resource@nrc.gov