Letter Sequence RAI |
---|
|
Results
Other: ML13212A367, ML14050A304, ML14071A620, ML14072A369, ML14092A346, ML14177A430, ML14238A691, ML15098A181, ML15106A736, RS-14-183, Updated Responses to NRC Set 14 Requests for Additional Information, Related License Renewal Application, RS-14-249, Results of Detailed Review Performed in Response to Request 1 of NRC RAI B.2.1.7-7 from Set 17, Related to License Renewal Application
|
MONTHYEARML13212A3672013-08-12012 August 2013 Plan for the Aging Management Program Regulatory Audits Regarding the Byron and Braidwood Nuclear Stations License Renewal Application Review (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: Other ML13281A5742013-11-25025 November 2013 Requests for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Aging Management, Set 3 (TAC Nos. MF1879, MF1880, MF1881, and MF1882 Project stage: RAI ML13303B4632013-11-25025 November 2013 Summary of Telephone Conference Call Held on October 22, 2013, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning RAI Set 3 for the Byron-Braidwood LRA Project stage: RAI ML13281A5692013-12-12012 December 2013 Request for Additional Information for the Review of the Byron Nuclear Station Units 1 and 2, and the Braidwood Nuclear Station Units 1 and 2, LRA - Aging Management, Set 4 Project stage: RAI ML13282A3692013-12-13013 December 2013 Requests for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Aging Management, Set 2 (TAC Nos. MF1879, MF1880, MF1881, and MF1882 Project stage: RAI RS-13-273, Responses to NRC Requests for Additional Information, Set 3, Dated November 25, 2013, Related to the License Renewal Application2013-12-17017 December 2013 Responses to NRC Requests for Additional Information, Set 3, Dated November 25, 2013, Related to the License Renewal Application Project stage: Response to RAI RS-13-274, Response to NRC Requests for Additional Information, Set 5, Dated November 22, 2013, Related to License Renewal Application2013-12-19019 December 2013 Response to NRC Requests for Additional Information, Set 5, Dated November 22, 2013, Related to License Renewal Application Project stage: Response to RAI ML13317A0752014-01-13013 January 2014 Requests for Additional Information for Review of Byron, Units 1 & 2, and Braidwood, Units 1 & 2, License Renewal Applications, Set 6 Project stage: RAI RS-14-003, Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application2014-01-13013 January 2014 Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application Project stage: Response to RAI ML14007A6582014-01-22022 January 2014 Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 9 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML13309A9322014-01-23023 January 2014 Summary of Telephone Conference Call Held on October 31, 2013, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Byron Station and Braid Project stage: Draft RAI RS-14-030, Response to NRC Requests for Additional Information, Set 6, Dated January 13, 2014, Related to License Renewal Application2014-02-0404 February 2014 Response to NRC Requests for Additional Information, Set 6, Dated January 13, 2014, Related to License Renewal Application Project stage: Response to RAI ML14006A0212014-02-0606 February 2014 Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application- Aging Management, Set 8 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14023A5642014-02-0707 February 2014 RAI for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 13 (TAC MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14030A5962014-02-10010 February 2014 Requests for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 12 (TAC MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14007A6032014-02-18018 February 2014 Request for Additional Information for the Review of the Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, LRA - Aging Management - Set 17 Project stage: RAI ML14035A1892014-02-20020 February 2014 Summary of Telephone Conference Call Held on January 30, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Byron Station and Braidw Project stage: Draft RAI ML14035A5342014-02-20020 February 2014 January 22, 2014, Summary of Telephone Conference Call Held Between NRC and Exelon Generation Company, Llc., Concerning Draft Requests for Additional Information Pertaining to the Byron Station and Braidwood Station, License Renewal Applica Project stage: Draft RAI RS-14-051, Response to NRC Requests for Additional Information, Set 8, Dated February 6, 2014 Related to the License Renewal Application2014-02-27027 February 2014 Response to NRC Requests for Additional Information, Set 8, Dated February 6, 2014 Related to the License Renewal Application Project stage: Response to RAI ML14063A4952014-03-0404 March 2014 Units 1 & 2, Response to NRC Requests for Additional Information, Set 13, Dated February 7, 2014 Re License Renewal Application Project stage: Response to RAI ML14050A1672014-03-0404 March 2014 Summary of Telephone Conference Call on January 23, 2014, Between U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning RAI Set 11, for Byron-Braidwood License Renewal Application (TAC Nos. MF1879, MF1880, MF1881 Project stage: RAI ML14036A3102014-03-0404 March 2014 Summary of Telephone Conference Call Held on January 28, 2014, Between NRC and Exelon, Concerning RAI Set 10, for the Byron and Braidwood Station, LRA Project stage: RAI ML14051A4312014-03-0404 March 2014 Summary of Telephone Conferene Call Held on January 29, 2014, Between the NRC and Exelon Generating Company, Llc., Concerning RAI Set 10, for the Byron and Braidwood Station License Renewal Application (TAC Nos. MF1879, MF1880, MF1881, and Project stage: RAI ML14051A4282014-03-0606 March 2014 January 13, 2014, Summary of Telephone Conference Call Held Between the NRC and Exelon RAI Set 8, for the Byron and Braidwood Station LRA Project stage: RAI ML14050A0812014-03-0707 March 2014 Correction to Request for Additional Information B.2.1.10-1, Letter Dated February 7, 2014, for the Review of the Byron Station and Braidwood Station, Units 1 and 2, LRA Set 13 Project stage: RAI ML14058B1802014-03-11011 March 2014 Summary of Telephone Conference Call on February 18, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Regarding Byron & Braidwood Stations, License Renewal Project stage: Draft RAI ML14064A4032014-03-11011 March 2014 Summary of Telephone Conference Call on February 27, 2014, Between U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information Re Byron Station & Braidwood Station License Renewal Project stage: Draft RAI ML14064A3912014-03-11011 March 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 15 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14071A6202014-03-13013 March 2014 Aging Management Programs Audit Report Regarding the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (Tac Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: Other ML14072A3692014-03-13013 March 2014 AMP Audit Enclosure (3) Project stage: Other ML14050A3042014-03-14014 March 2014 Scoping and Screening Methodology Audit Report Regarding the Byron Station, and Braidwood Station, Units 1 and 2, LRA Project stage: Other ML14058B1822014-03-18018 March 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 14 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14051A5032014-03-20020 March 2014 Request for Additional Information for the Review of the Byron Nuclear Station Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2, License Renewal Application - Set 17 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI RS-14-084, Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application2014-03-28028 March 2014 Responses to NRC Requests for Additional Information, Set 10, Dated February 26, 2014 Related to the License Renewal Application Project stage: Response to RAI ML14084A3352014-04-0303 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 16 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14073A7052014-04-0303 April 2014 Summary of Telephone Conference Call Held on February 12, 2014, Between the NRC and Exelon, Concerning Drais Pertaining to the Byron and Braidwood Station, LRA Project stage: RAI ML14092A3462014-04-0707 April 2014 Project Manager Change for the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: Other ML14092A2612014-04-0707 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 20 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14084A4882014-04-0707 April 2014 03/04/2014 Summary of Telephone Conference Call Held Between NRC and Exelon Generation Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Byron and Braidwood License Renewal Application Set 16 Project stage: Draft RAI ML14094A3662014-04-0808 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 19 Project stage: RAI ML14093B2472014-04-10010 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 18 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14099A4852014-04-17017 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 & 2, and Braidwood Station, Units 1 & 2, License Renewal Application, Set 21, (TAC Nos. MF1879, MF1880, MF1881, and MF1882) Project stage: RAI ML14099A4932014-04-22022 April 2014 April 03, 2014 Summary of Telephone Conference Call Held Between NRC and Exelon Generation Co., LLC, Concerning Draft Request for Additional Information, Set 21, Pertaining to Byron, Units 1 & 2, Braidwood, Units 1 & 2, License Renewal Appl Project stage: Draft RAI ML14111A1182014-04-24024 April 2014 Request for Additional Information for the Review of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, License Renewal Application, Set 22 Project stage: RAI ML14107A0772014-04-25025 April 2014 Summary of Telephone Conference Call Held on April 9, 2014, Between the U.S. Nuclear Regulatory Commission & Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 23, Pertaining to the Byron Station & Braid Project stage: Draft RAI ML14107A2262014-05-14014 May 2014 Summary of Telephone Conference Call Held on March 26, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 21, Pertaining to the Byron Station and Project stage: Draft RAI ML14092A4402014-05-14014 May 2014 Summary of Telephone Conference Call Held on March 19, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 18, Pertaining to the Byron Station and Project stage: Draft RAI ML14112A4182014-05-14014 May 2014 Summary of Telephone Conference Call Held on April 10, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 22, Pertaining to the Byron Station and Project stage: Draft RAI ML14094A4252014-05-14014 May 2014 Summary of Telephone Conference Call Held on April 1, 2014, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Concerning Draft Request for Additional Information, Set 19, Pertaining to the Byron Station and B Project stage: Draft RAI ML14129A3392014-05-14014 May 2014 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2014-03-11
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 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 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 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 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (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 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 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 BYRON 2023-0065, Unit 2 - 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 Guideline2023-11-17017 November 2023 Unit 2 - 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 BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, 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-23-118, 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 ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments 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 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 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-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 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. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals 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) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) 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 IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 2024-02-02
[Table view] Category:Meeting Summary
MONTHYEARML24009A0552024-01-24024 January 2024 Summary of January 8, 2024, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Removal of the Power Distribution Monitoring System from Technical Specifications ML24018A1772024-01-19019 January 2024 Summary of August 30, 2023, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Relaxation of Inspection Requirements for the Head Penetration P-75 Flaw ML23363A0942024-01-0303 January 2024 Summary of October 4, 2023, Pre Submittal Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding Revising Technical Specification 3.7.9. Ultimate Heat Sink (UHS) ML23362A0042024-01-0202 January 2024 Documentation of Cancelled September 1, 2023, Presubmittal Meeting Between the NRC and Constellation Energy Generation, LLC, Regarding 6-Month Extension of Certain Reactor Pressure Vessel Weld Inspections ML23352A3822023-12-19019 December 2023 Summary of December 11, 2023, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Deletion of Technical Specification 5.6.5.b.5 ML23320A2472023-11-17017 November 2023 Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591 ML23263B1062023-09-22022 September 2023 R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary ML23164A2112023-06-14014 June 2023 Summary of the June 1, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2; and Byron Station, Units 1 and 2 ML23129A0202023-05-30030 May 2023 Summary of March 22, 2023, Closed Meeting with Constellation Energy Generation, LLC, to Discuss a Future License Amendment Request That Allows Byron Station and Braidwood Station to Utilize a New Citicality Analysis for the Spent Fuel Pools ML23055A0352023-03-24024 March 2023 Summary of February 23, 2023, with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans to Revise Emergency Action Levels ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML22264A1992022-11-14014 November 2022 Summary of August 22, 2022, Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Steam Generator Welds (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and ML22305A5992022-11-10010 November 2022 Summary of Closed Presubmittal Meeting Between the U. S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Transition to Framatome Fuel ML22159A2232022-06-0909 June 2022 Summary of the June 2, 2022, Public Outreach to Discuss the NRC 2021 End of Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 ML22115A2122022-05-12012 May 2022 Summary of April 11, 2022, Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding a Future Amendment to Place One High Burnup Lead Test Assembly Into the Byron, Unit 2, Reactor ML22111A2852022-05-0909 May 2022 Summary of April 4, 2022, Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Pressurizer Welds (EPIDs L-2022-LLR-0035/36) ML22111A3362022-05-0909 May 2022 Summary of April 7, 2022, Meeting Between the NRC and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Pressurizer Welds (Epids L-2022-LRR-0035 and 0036) ML21330A0722021-12-0303 December 2021 Summary of November 17, 2021, Meeting with Exelon Generation Company, LLC, Related to a Future License Amendment to Remove License Condition 2.C.(12)(d) for Braidwood Station, Unit 2 ML21333A1532021-11-30030 November 2021 Summary of November 16, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Extend the Inservice Inspection Interval ML21237A0412021-08-30030 August 2021 Summary of the July 27, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use Case OMN-28, ML21176A0822021-07-0606 July 2021 June 15, 2021, Summary of Meeting with Exelon Generation Company, LLC Vessel Nozzle Repair Related to a Planned Request for an Alternative Related to Reactor Pressure ML21139A1852021-06-22022 June 2021 Summary of Meeting with Exelon Generation Company, LLC Regarding Its Requested Alternative to Eliminate Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting ML21167A2152021-06-16016 June 2021 June 8, 2021, Summary of the Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2; and Byron Station, Units 1 and 2 ML21147A4262021-06-0303 June 2021 Summary of May 12, 2021, Meeting with Exelon Generation Company, Llc, Related to a Planned License Amendment to Modify the Ultimate Heat Sink Technical Specifications ML21033A6582021-02-0404 February 2021 Summary of October 13, 2020, Presubmittal Meeting Between the U. S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding Post Shutdown Emergency Plan Staffing to Support the Planned Early Closures ML21011A2822021-01-21021 January 2021 Summary of January 6, 2021, Presubmittal Meeting Between the NRC and Exelon Generation Company, LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Unit Nos. 1 and 2 and Dresden, Units 2 and 3 ML20351A2832020-12-18018 December 2020 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Exemption to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs ML20342A3522020-12-10010 December 2020 Summary of November 13, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alterantive to Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting (EPID-L-2020-LRM-0102) ML20323A0332020-12-0101 December 2020 Summary of November 4, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs ML20280A2482020-10-0707 October 2020 Summary of September 22, 2020, Presubmittal Meeting Between the NRC and Exelon Generation Company LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Units 1 and 2 and Dresden, Units 2 and 3 ML20171A3812020-08-12012 August 2020 (COVID-19) Presubmittal Meeting Summary - Byron Unit 2 LAR - One-Time Extension of Steam Generator Tube Inspections ML20218A5302020-08-0505 August 2020 July 14, 2020, Summary of the Public Webinar to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of Braidwood Station, Units 1 and 2; and Byron Station, Units 1 and 2 ML20181A0002020-06-29029 June 2020 Summary of 6/24/20 Meeting with Exelon Generation Company, LLC Regarding Planned Request for Alternative to Supplemental Valve Position Indication Testing Requirements for Braidwood, Calvert Cliffs, Clinton, Limerick, Nine Mile, Peach Botto ML19326A3152019-12-0303 December 2019 Summary of November 18, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Supplemental Valve Position Indication Testing Requirements ML19326C3582019-12-0303 December 2019 Summary of November 20, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Revise the Quality Assurance Program ML19162A0272019-06-21021 June 2019 Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves ML20108F0902019-04-20020 April 2019 April 15, 2020, Meeting Summary with Exelon Generation Company, LLC Regarding Planned Request to Defer Submittal of Owner'S Activity Report (Braidwood 2,Byron 2,Calvert Cliffs 1, LaSalle 1, Limerick 1, Nine Mile Point 2, Quad 2, R. E. Ginna ML19036A8832019-02-0707 February 2019 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879 ML18354B1712019-01-0202 January 2019 Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines ML18325A1712018-11-28028 November 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned Fleet License Amendment Request to Revise Technical Specifications for High Radiation Areas ML18297A1722018-10-26026 October 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Adopt TSTF-427 ML18225A3042018-08-16016 August 2018 Summary of August 8, 2018, Meeting with Exelon Generation Company, LLC, on a Future Relief Request to Extend the Post Peening Follow-Up Inspections for Certain Reactor Pressure Vessel Head Penetrations ML18135A0222018-05-14014 May 2018 Summary of the May 10th, 2018, Public Open House Regarding Braidwood Nuclear Power Station ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing ML18113A7052018-04-23023 April 2018 Summary of Open House to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Byron Station ML18113A6592018-04-23023 April 2018 Summary of Open House to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML18065A8362018-03-0707 March 2018 Summary of February 27, 2018, Meeting with Exelon Generation Company, LLC Planned Fleet License Amendment Request to Relocate Staff Qualification Requirements from TSs to the Quality Assurance Topical Report ML18058A5232018-03-0101 March 2018 Summary of February 26, 2018, Meeting with Exelon Generation Company, LLC Regarding Proposed Alternative to the Main Steam Isolation Valve Testing Requirements ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 ML17347B1022017-12-14014 December 2017 Summary of Meeting with Exelon Generation Company, LLC on Its Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response 2024-01-03
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML23018A1632023-01-18018 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22241A0522022-08-29029 August 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004 ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 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 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21228A2352021-08-17017 August 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004 ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information ML20294A5492020-10-21021 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20104C1452020-04-10010 April 2020 NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request ML20023A0812020-01-23023 January 2020 NRR E-mail Capture - RAIs for L-2019-LLA-0201 - Braidwood, Units 1 and 2, LAR to Revise TS 3.7.9, Ultimate Heat Sink ML20008D3992020-01-0808 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2020001 ML19350B2952019-12-16016 December 2019 NRR E-mail Capture - Draft Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Impractical Inservice Inspection Requirements (L-2019-LLA-0081) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application 2023-07-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 3, 2014 LICENSEE Exelon Generation Company, LLC FACILITY: Byron Station, Units 1 and 2 Braidwood Station, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on February 12, 2014, to discuss and clarify the staff's draft request for additional information (ORAl), Set 14, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's ORAls. provides a listing of the participants, and Enclosure 2 contains a listing of the ORAls discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
l..-tindsay Robinson, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-454, 50-455, 50*456, and 50-457
Enclosures:
- 1. List of Participants
- 2. List of Draft Request for Additional Information cc w/encls: Listserv
- ML14073A705 *concurred via email OFFICE LA:DLR PM: RPB1 :DLR BCRPB1:DLR PM:RPB1 :DLR NAME IKing LRobinson YDiazSanabria LRobinson DATE 3/24/14 4/1/14 4/3/14 4/314
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 12, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE BYRON STATION AND BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
DISTRIBUTION EMAIL:
PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsOgcMaiiCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource LRobinson JDaily DMclntyre, OPA EDuncan, Rill JBenjamin, Rill AGarmoe, Rill JMcGhee, Rill JRobbins, Rill VMitlyng, Rill PChandrathil. Rill
TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS February 12, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC)
Angie Buford NRC Alice Erickson NRC Sam Cuadrado De Jesus NRC John Hufnagel Exelon Generating Company, LLC (Exelon)
AI Fulvia Exelon Don Warfel Exelon Jim Annett Exelon Dylan Cimock Exelon Paul Cervenka Exelon John Hilditch Exelon Albert Piha Exelon Don Brindle Exelon Ralph Wolen Exelon ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION February 12, 2014 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Exelon Generation Company, LLC (Exelon or the applicant), held a telephone conference call on February 12, 2014, to discuss and clarify the following draft request for additional information (ORAl) concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA).
ORAl B.3.1.2*1 Applicability:
Byron Station (Byron) and Braidwood Station (Braidwood), all units
Background:
License renewal application (LRA) Section 8.3.1.2 states that the "Concrete Containment Tendon Prestress" aging management program (AMP) is consistent with an enhancement with the Generic Aging Lessons Learned (GALL) Report, Revision 2, AMP X.S1, "Concrete Containment Tendon Prestress." The "monitoring and trending" program element of the GALL Report AMP X.S1 states that "the trend line represents the trend of prestressing forces based on the actual measured forces" and that NRC Information Notice (IN) 99-10, "Degradation of Prestressing Tendon Systems in Prestressed Concrete Containments," provides guidance for constructing the trend line.
LRA Section 8.3.1.2 also states that the "[t]rend line regression analysis is consistent with NRC Information Notice (IN) 99-10." The LRA further states that the "[t]rend lines, one for each tendon group, are constructed using the measured tendon forces and represent the changes in mean vertical, hoop and dome prestressing forces with time" and that "the analysis evaluates force trends by group (dome, hoop, vertical) and shows that group mean forces will not fall below applicable [minimum required values] MRV's prior to the end of the period of extended operation."
Issue:
Table IWL-2521-1 in Subsection IWL of the ASME Code,Section XI, states that for each tendon group the number of tendons to be examined varies between 2 to 5 percent of the tendon population. IN 99-10 discusses that for a small sample size, using the average of the tendon force (TF) for each surveillance test masks the true variation between TF and time (T) (i.e., the tendency of the TF to vary systematically with T, where the scattering of points about the "curve" represents the true relationship between TF and T). The staff noted that LRA Figures 4.5-1 through 4.5-12 show that multiple tendon values are plotted for past lSI years. It is not clear whether the applicant uses average/mean TF or individual lift-off values when developing the trend lines.
ENCLOSURE 2
Request Clarify the methodology used for the construction of the regression analysis. Specifically, state whether the Byron and Braidwood regression analyses use the individual lift-off forces for the development of statistically validated trend lines.
Discussion: The applicant requested clarity on the staff's request. No edits were made to the DRAI. This question will be sent as a formal RAI titled RAI 8.3.1.2-1."
DRAI B.3. 1.2-2 Applicability:
Byron and Braidwood
Background:
LRA Section 8.3.1.2 states that the "Concrete Containment Tendon Prestress" AMP is consistent with an enhancement with the GALL Report, Revision 2, AMP X.S1, "Concrete Containment Tendon Prestress." The GALL Report AMP X.S1, in its program description, states that "[t]he program consists of an assessment of inspections performed in accordance with the requirements of Subsection IWL of the ASME Code,Section XI, as supplemented by the requirements of 10 CFR 50.55a(b)(2)(viii)" and that the parameters monitored are the prestressing tendon forces (TF) in prestressed concrete containments.
LRA Section B.3.1.2 states that "[t]he program requires measurement of prestressing forces on an initial 2% sample of each tendon group (dome, hoop, vertical) every five years, as specified in IWL-2400." The LRA also states in the "operating experience" program element:
In 2009 and 2011, Byron and Braidwood, respectively, performed the 251h year interval ASME Section XI, Subsection IWL, examinations of the concrete containment tendons. These examinations included testing to assess the loss of prestressing forces in select containment tendons, consistent with lWL requirements.
Issue:
The audited procedure ER-AA-330-006, "lSI and Testing of the Prestressed Concrete Containment Post Tensioning System, Rev. 6," indicates that Byron and Braidwood alternate every ten years between visual and full examinations which include testing and measurements of TF. Subsection IWL-2421 of Section XI of the ASME Code allows the examination frequency to be modified if the containments are essentially identical in design, utilize the same prestressing systems, and post tensioning operations were completed within 2 years apart. If all criteria are met, then full examinations as required by IWL-2500 shall be performed at 1, 3, and 10 years and every 10 years thereafter for the first containment unit; and for each subsequent containment constructed at the site, examinations shall be performed at 1, 5, and 15 years and every 10 years thereafter. It is not clear whether Byron and Braidwood follow the modified lSI intervals as stated in IWL-2421 and procedure ER-AA-330-006 to perform measurement of TF at alternating time frames for each unit (e.g., one unit fully examined per IWL-2500 on year 20 while the other on year 25} or examines, tests, and measures TF for both units at each site every five years, as stated in the LRA.
Request Clarify the frequency of measuring the prestressing tendon forces for each selected tendon group {dome, hoop, vertical) sample examined during ISis for Byron and Braidwood, all units.
Discussion: The applicant requested clarity on the staff's request. No edits were made to the DRAI. This question will be sent as a formal RAI titled RAI 8.3.1.2-2."
ORAl 8.2.1.34-1 Applicability:
Byron and Braidwood
Background:
LRA Section 8.2.1.34 states that the "Structures Monitoring" AMP is consistent with enhancements with the GALL Report, Revision 2, AMP XI.S6, "Structures Monitoring." During a walkdown of Byron and Braidwood's main steam and tendon gallery tunnels, the staff observed white material deposits, or efflorescence, on some below-grade reinforced concrete walls. The conditions at Byron are far more evident than at Braidwood. A review of operating experience revealed similar conditions in the auxiliary feedwater tunnel concrete walls. Through discussions with the applicant, the staff learned that the cracks through which the material appears to be leaching have existed since initial plant construction, and the material deposits are considered to be the result of the limestone backfill migrating through these cracks. The staff noted that the groundwater at both Byron and Braidwood is considered to be an aggressive environment due to high chloride levels (i.e., >500 ppm}.
Issue:
10 CFR 54.21 (a)(3) requires that the applicant demonstrate that the effects of aging will be adequately managed so that the intended function will be maintained consistent with the current licensing basis for the period of extended operation. However, without knowing the source of the material deposits in the main steam, auxiliary feedwater, and tendon gallery tunnels (i.e.,
whether the material deposits are a result of the limestone backfill migrating through the cracks or material leaching from the concrete structures}, the staff does not have sufficient information to conclude that the proposed LRA AMP, "Structures Monitoring," will be adequate to manage the effects of aging during the period of extended operation.
Requests:
- 1. State what actions, if any, have been taken to determine the composition of the material (white deposits}. State whether an evaluation has been performed to determine the source of the material deposits. If so, provide the technical basis for that conclusion.
- 2. Considering that the groundwater at Byron and Braidwood is aggressive, state what actions, if any, have been taken to evaluate the condition of the concrete in these below-grade structures.
Discussion: The applicant requested clarification on the staff's requests. No edits were made to the ORAl. This question will be sent as a formal RAI titled "RAI 8.2.1.34-1."
DRAI 8.2.1.30-1 Applicability:
Byron and Braidwood
Background:
LRA Section 8.2. 1.30 states that the ASME Section XI, Subsection IWL AMP is an existing program that, following enhancements, will be consistent with the GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL." During Byron and Braidwood onsite AMP audits, the staff reviewed operating experience regarding a crack found on the Braidwood Unit 1 primary containment. The crack was found in 2006 during the 251h ASME Section XI, Subsection IWL visual inspection of the containment concrete. Based on the description in the applicant's action request, the crack is diagonal and located on the upper right corner of the concrete patch placed after the Unit 1 containment concrete was cut out for the steam generator (SG) replacement in 1998. Grease leakage was also observed through the crack. During the Braidwood onsite audit, the staff performed a walkdown to look at the condition of the concrete where the crack was located and noted that there was also a similar crack on the upper left corner of the SG replacement patch in Unit 1's primary containment. Also during the audit, the applicant stated that a similar condition exists for the Byron Unit 1 primary containment concrete at the SG replacement patch.
Issue:
The GALL Report states that "[o}perating experience involving the AMP, including past corrective actions resulting in program enhancements or additional programs, should provide objective evidence to support a determination that the effects of aging will be adequately managed so that the structure and component intended functions will be maintained during the period of extended operation." GALL Report AMP XI.S2 states that the frequency and scope of examinations specified in 10 CFR 50.55a and ASME Section XI, Subsection IWL, should ensure that aging effects would be detected before they would compromise the design-basis requirements. The GALL Report also states that areas that indicate suspect conditions receive a more rigorous detailed visual examination (as defined by the ASME Code). The staff requires additional information on whether the applicant has made a determination as to (1) whether more rigorous detailed visual examinations are needed per the IWL acceptance criteria for crack width; (2) whether the cracking indicates an adverse condition has occurred with the prestressed tendons in that location; and (3) if grease leakage from the cracks has been evaluated against IWL limits.
Request:
Describe the actions taken to assess the condition of the cracks, type and frequency of inspections performed (if any), and corrective actions (if any) in accordance with the ASME Section XI, Subsection IWL Program. Also state whether there has been an evaluation per the IWL Code to assess the amount of grease leakage coming through the cracks and to determine if the leakage has any adverse effect on the ability of the affected tendons to perform their intended function.
Discussion: The applicant stated that it had responded on the docket to a similar request from a previously issued RAJ. The reviewers agreed to review the docketed information.
After review of the docketed information, the staff determined that this question needed to be reevaluated and was resubmitted as part of ORAl Set 20. Therefore, this ORAl has been removed and will not be issued as a formal RAI in Set 14.
ORAl 8.2.1.30-2 Applicability:
Byron and Braidwood
Background:
LRA Section 8.2. 1.30 states that the ASME Section XI, Subsection IWL AMP is an existing program that, following enhancements, will be consistent with the GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL." During its onsite audit at both Byron and Braidwood, the staff reviewed operating experience regarding suspected areas of degradation in the primary containment tendon access gallery tunnel ceilings. The staff noted that, in June 2006, while performing visual examinations of Braidwood's tunnel ceilings concrete surfaces, 11 locations in Unit 1 and 141ocations in Unit 2 were identified as suspect areas with degradation. The suspected areas were covered in white deposits and rust. In addition, during the 2006 201h ASME Section XI, Subsection IWL, concrete examinations at Braidwood Units 1 and 2, degradation was found in the tendon tunnel ceilings near seven vertical tendon anchorage cans.
The degradation was within a previously placed patch that extended from the outer wall to the inner wall in the tendon tunnel and consisted of a combination of the following: wet stalactites, surface concrete cracks exceeding .04", heavy accumulation of minerals, corrosion staining, moisture "wetting," accumulation of efflorescence in localized areas, "minor" cracking, and "hollow" sound emitted from the area when tapped with a hammer. In 2012, while performing augmented examinations of suspect areas identified during the 2011 25 1h year ASME IWL examinations, the following conditions were found at Braidwood Unit 2 tendon tunnel ceilings near six additional vertical tendon anchorage cans: buildup of minerals, efflorescence with evidence of moisture, 8" and 5" long stalactites, and surface corrosion on embedded plates.
During the onsite audits at both Byron and Braidwood, the staff performed walkdowns of the tendon access gallery tunnels to observe the overall condition of the area. The staff observed white deposits or efflorescence, stalactites, surface corrosion on embedded plates, and surface cracks in the tunnel ceilings near some of the vertical tendon anchorage cans.
The staff noted that the conditions of concrete degradation at the tendon gallery tunnel ceilings are present at both sites. In addition, based on its review of operating experience, the staff noted that the groundwater at both Byron and Braidwood is considered to be an aggressive environment due to high chloride levels (i.e.,> 500 ppm).
Per 10 CFR 54.21 (a)(3). the applicant is required to demonstrate that the effects of aging will be adequately managed so that the intended function will be maintained consistent with the current licensing basis for the period of extended operation. The staff is concerned that some below-grade areas of the concrete containment are exposed to aggressive groundwater, which may be causing chemical attack and leaching of the concrete. It is not clear whether an evaluation has been performed to assess this condition per the requirements of the IWL Code The staff needs additional information to determine whether the LRA ASME Section XI,
Subsection IWL, AMP will be adequate to manage the effects of aging during the period of extended operation {PEO).
Request:
State whether the concrete in the tunnel ceiling is subject to chemical attack or leaching and provide results of any evaluation conducted or planned to determine the composition of the material (e.g., mineral build-up, white efflorescence) and to evaluate the condition of the concrete at the tendon gallery tunnel ceilings.
Discussion: The applicant requested clarification on the staffs request. No edits were made to the ORAl. This question will be sent as a formal RAI titled "RAI 6.2.1.30-1."
ORAl 6.2.1.30-3 Applicability:
Braidwood
Background:
LRA Section 8.2.1.30 states that the ASME Section XI, Subsection IWL AMP is an existing program that, following enhancements, will be consistent with the GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL." During its review of Braidwood operating experience, the staff noted that ASME Section XI, Subsection IWL inspections have revealed that the sealant and cover are significantly degraded or missing at some of the drain assemblies in the dome area of the containment. Plant operating experience has documented that there is separation, chips, and loose concrete at some of the dome drains; accumulation of white deposits or efflorescence on concrete surfaces near all of the drains; and accumulation of water at the dome drains. The staff noted that the applicant performed a detailed visual examination of the suspected areas of concrete deterioration in accordance with Subsection IWL-231 0 of the ASME Code. During the detailed visual examinations, additional signs of deterioration were found on suspected areas of concrete in the form of "minor" spa lis near the drains and cracks extending from all six dome drain penetrations (one reported as being more than 6" long and .8" wide at the concrete surface), efflorescence within the cracks, and corrosion staining.
Issue:
Per 10 CFR 54.21(a)(3), the applicant is required to demonstrate that the effects of aging will be adequately managed so that the intended function will be maintained consistent with the current licensing basis for the period of extended operation. The staff noted that issues with degradation of the dome drainage system and suspected areas of concrete deterioration have been identified during previous ASME Section XI, Subsection IWL examinations at Braidwood.
The staff is concerned that the conditions observed by the applicant near the dome drains (accumulation of white deposits, water accumulation, spalling, cracks, and corrosion staining}
may be indicative of, or may result in, degradation. The water accumulated may leak through the cracks and reach the concrete rebar which can result in degradation of the rebar. The staff needs additional information regarding the condition of concrete suspected areas of degradation and methods of evaluation to conclude that the LRA ASME Section XI, Subsection IWL AMP will be adequate to manage the effects of aging during the period of extended operation.
Request Regarding the reported conditions of the containment concrete at the dome drainage system, state whether further actions have been taken or are needed per appropriate programs such that concrete degradation can be evaluated and appropriate mitigating actions are implemented to prevent loss of intended function during the period of extended operation. Also, provide a summary of actions that have been taken to date to correct the degraded condition of the dome drainage system such that water does not accumulate in the suspected areas of concrete degradation near the dome drains.
Discussion: The applicant noted an incorrect reference, which is underlined, in the Background section; the correct reference is "IWL-3210." This and other minor grammatical edits will be made prior to final issuance. The applicant also requested clarification on the staff's request.
This question will be sent as a formal RAI titled RAI B.2.1.30-2."
DRAI 8.2.1.30-4 Applicability:
Braidwood
Background:
LRA Section B.2.1.30 states that the ASME Section XI, Subsection IWL AMP is an existing program that, following enhancements, will be consistent with the GALL Report AMP XI.S2, "ASME Section XI, Subsection IWL." LRA Section 8.2.1.30 states that "free-water has been found in 3-8%of the tendon inspections at Braidwood Unit 2... the presence of free water has been consistently detected in specific horizontal, vertical, and dome tendons, and this type of condition has also been detected [at] Braidwood Unit 1." The LRA further states that, since Braidwood construction, free water has been found in a "few, specific horizontal and vertical tendon anchorages located below grade." The LRA also states that the water in the dome tendons is due to the degraded dome drainage system and that the water found at vertical tendons and below-grade horizontal tendons is due to the high water table, which is about 20 to 25 feet higher than the bottom of the containment.
LRA Section B.2.1.30 states that to address the presence of water in the tendon sheaths, the applicant has performed augmented inspections on additional tendons beyond those selected for the ASME Section XI, Subsection IWL Program. These augmented inspections are performed every 5 years in conjunction with the ASME Section XI, Subsection IWL examinations. The LRA also states that due to the history of water found in containment tendons, the applicant included Enhancements 2 and 3 to the ASME Section XI, Subsection IWLAMP.
Enhancement 2 states:
A one-time inspection of one (1) vertical and one (1) horizontal tendon on each unit will be performed prior to the period of extended operation. The inspection will consist of visually examining one (1) wire from each of the two (2) types of tendons at a worst-case location based on evidence of free water, grease discoloration, and grease chemistry results. This location will serve as a leading indicator for potential degradation or tendon surface corrosion (Braidwood only).
Enhancement 3 states:
In order to monitor for tendon exposure to free water and moisture and manage any potential adverse effects, a periodic tendon water monitoring and grease sampling program will be implemented (Braidwood only). The program will consist of:
(a) A baseline inspection of tendon grease caps at the bottom of all vertical and dome tendons, as well as all below-grade horizontal tendons, prior to the period of extended operation. The baseline inspection will check for evidence of free water and grease discoloration, with further actions taken based on the condition of the grease.
(b) A follow-up tendon grease cap inspection of all vertical and dome tendons, as well as all below-grade horizontal tendons, will be performed within 10 years of the initial inspection, using the same approach as the baseline inspection.
(c) For those tendons where free water, moisture, and grease did not meet acceptance criteria during the two (2) previous inspections, periodic monitoring of grease chemistry and moisture, free water, and grease discoloration will be performed on a frequency not to exceed 10 years.
Corrective actions will be taken as necessary to ensure that the tendon grease meets ASME Section XI, Subsection IWL requirements.
Issue:
The GALL Report states that "the conditions and operating experience at the plant must be bound by the conditions and operating experience for which the GALL program was evaluated, otherwise it is incumbent on the applicant to augment the GALL program as appropriate to address the additional aging effects." The GALL Report also states that "[o]perating experience involving the AMP, including past corrective actions resulting in program enhancements or additional programs, should provide objective evidence to support a determination that the effects of aging will be adequately managed so that the structure and component intended functions will be maintained during the period of extended operation." The staff noted that the applicant has augmented and will enhance (Enhancements 2 and 3) its IWL AMP to address its plant-specific operating experience regarding the historical exposure of tendons to free water at Braidwood. However, the staff needs additional information regarding how the augmented inspections and enhancements will adequately manage the effects of aging during the period of extended operation. The staff has the following concerns:
- For the augmented inspections of additional tendons, performed every 5 years in conjunction with the ASME Section XI, Subsection IWL examinations, it is unclear how the locations for additional tendon inspections will be identified.
- Enhancement 2 proposes a one-time inspection of one horizontal and vertical tendon prior to the period of extended operation. It is not clear what the acceptance criteria will be for the one-time inspection of the corrosion protection medium and tendon wires and what further actions will be taken if the acceptance criteria are not met. Additionally, the enhancement does not include inspection of dome tendons, and the basis for this exclusion is not clear.
- Enhancement 3 states that a follow-up inspection will be performed within 10 years after the first baseline inspection. The enhancement also states that tendons that do not meet the acceptance criteria during the two previous inspections will be subject to periodic monitoring
at a frequency not to exceed 10 years. The staff is concerned that tendons that meet the acceptance criteria during the baseline inspection but do not meet the acceptance criteria in the follow-up inspection will not be subject to periodic monitoring. For sites with multiple plants, IWL-2421 (b) states that when the conditions on IWL-2421 (a) are met, the examinations required by IWL-2500 can be performed at a 10-year frequency instead of every 5 years. A 10-year frequency is the maximum frequency (less conservative approach) allowed by the IWL Code for a site with multiple plants. It is unclear as to how a frequency of examinations not to exceed 10 years will be adequate to address the additional aging effects at Braidwood.
Request:
- 1. Describe how the locations for augmented inspections of additional tendons will be identified.
- 2. Regarding Enhancement 2, state (1) the acceptance criteria for the one-time inspections, (2) what actions will be taken if the acceptance criteria are not met, and (3) the justification for not performing a one-time inspection of the dome tendons.
- 3. Regarding Enhancement 3, state (1) what actions will be taken for those tendons where the corrosion protection medium meets the acceptance criteria during the baseline inspection but are found not acceptable during the follow-up inspection, and (2) how the proposed frequency of inspections (not to exceed 10 years) will ensure that possible age-related degradation due to water in leakage to the tendons will be detected in a timely manner and managed such that the tendons will continue to perform their intended functions during the PEO.
Discussion: The applicant requested clarification on the staff's requests. No edits were made to the ORAl. This question will be sent as a formal RAI titled "RAI 8.2.1.30-3."
DRAI 8.2.1.29-1 Applicability:
Byron
Background:
LRA Section 8.2.1.29 states that the ASME Section XI, Subsection IWE AMP is an existing program that, following enhancement, will be consistent with the GALL Report, Revision 2, AMP XI.S1. The "detection of aging effects" program element recommends, in accordance with IWE-1240, that augmented examinations should be performed for containment surface areas subject to degradation. In addition, the GALL Report states that operating experience involving the AMP should provide objective evidence to support a determination that the effects of aging will be adequately managed so that the structure and component intended functions will be maintained during the PEO.
During the audit, the staff performed walkdowns of the Byron main steam and tendon gallery tunnels and observed white material deposits on the concrete walls and tendon gallery tunnel ceilings, indicative of water leakage or seepage through the containment concrete. Through
discussions with the applicant, the staff learned that the cracks, through which the material appears to be leaching, have existed since initial plant construction_ The staff noted during its review that on the south side of Byron Unit 1 and north side of Unit 2, the below grade areas between the main steam tunnels and containment structures were in-filled with limestone during the original construction. According to plant operating experience, this area has allowed groundwater infiltration to the below-grade containment concrete. The staff noted that the groundwater at both Byron and Braidwood is considered to be an aggressive environment due to high chloride levels (i.e., >500 ppm).
IWE-1240 states that interior and exterior containment surface areas that are subject to accelerated corrosion, with no or minimal corrosion allowance, require augmented examinations.
With the history of aggressive water infiltrating the containment concrete, as evidenced by signs of water intrusion at the tendon gallery ceilings, there is the potential that elevated moisture levels at the outside of the containment concrete could cause moisture to travel through the concrete and come in contact with the carbon steel containment liner. This condition could result in degradation of the containment liner plates caused by accelerated corrosion at exterior surfaces of the containment liner. The applicant has not provided information, based on examination or analysis, on a determination as to whether water has been in contact with the outer surface of the liner or whether there has been any loss of thickness in the carbon steel due to accelerated corrosion in order to ensure the requirements of IWE-1240 are met.
Request With regards to the operating experience indicating that water is infiltrating the containment concrete, state whether there has been (or will be) an evaluation in accordance with IWE to determine (1) if the moisture could come into contact with the liner plate and (2) any resulting loss of material thickness due to corrosion. Describe how the IWE AMP will be able to ensure that the liner is not degraded such that the leak-tight integrity of the carbon steel is maintained through the PEO.
Discussion: The applicant requested clarification on the staff's requests. No edits were made to the DRAI. This question will be sent as a formal RAI titled RAJ 8.2.1.29-1."
ORAl 8.2, 1.29-2 Applicability:
Braidwood
Background:
LRA Section 8.2.1.29 states that the ASME Section XI, Subsection IWE AMP is an existing program that, following enhancement, will be consistent with the GALL Report, Revision 2, AMP XI.S 1. The "detection of aging effects" program element recommends, in accordance with IWE-1240, that augmented examinations of containment surface areas should be performed for containment surface areas subject to degradation. The GALL Report states that operating experience involving the AMP, including past corrective actions resulting in program
enhancements or additional programs, should provide objective evidence to support a determination that the effects of aging will be adequately managed so that the structure and component intended functions will be maintained during the PEO.
During the audit, the staff reviewed action request (AR) 00105204, dated April24, 2002, and noted that during a Braidwood Station Unit 2 IWE visual examination the applicant observed several localized bulges or buckles in the liner. The staff also noted that AR 1433284, dated October 29, 2012, states that some of the bulges were corroded.
Issue:
IWE-1240 states that interior and exterior containment surface areas that are subject to accelerated corrosion, with no or minimal corrosion allowance, require augmented examinations. IWE-3511 states that the condition of an examined area is acceptable if the Responsible Individual determines that there is no evidence of damage or degradation sufficient to warrant further evaluation or performance of a repair/replacement activity. Suspect conditions shall be evaluated to the extent necessary to ensure that the component function is not impaired.
Continued loss of material coupled with the state of stress at the liner may warrant further evaluation during the PEO to ensure that the corrosion has not impacted the liner function. It is not clear whether an evaluation has been conducted, in accordance with ASME Section XI, Subsection IWE to assess the impact of corroded bulges in the containment liner. The staff needs additional information to determine whether the ASME Section XI, Subsection IWE AMP will provide reasonable assurance of the integrity and leak-tightness of the liner when monitoring aging and degradation due to corrosion (loss of material), bulging, and their combined effect during the PEO.
Request:
- 1. State whether evaluation or testing was performed in accordance with ASME Section XI, Subsection IWE. State the results of any evaluation or testing with regards to the observed bulging of the containment, including the impact of corrosion at the bulged areas.
- 2. If applicable, describe what monitoring and trending measures at the corroded and bulged areas of the liner will be taken to trend the condition and ensure that the ASME Section XI, Subsection IWE AMP will provide reasonable assurance of the liner integrity and leak-tightness during the PEO.
Discussion: The applicant noted errors in the DRAI Background section and requested the staff review AR1433284. After further review, the staff noted the errors and determined that the request was not necessary. Therefore, this DRAI has been removed and will not be issued as a formal RAI.
DRAI 6.2.1.29-3 Applicability:
Byron and Braidwood
Background:
LRA Section 8.2.1.29 states that the ASME Section XI, Subsection IWE AMP is an existing program that, following enhancement, will be consistent with the GALL Report, Revision 2, AMP Xl.S1. The "operating experience" program element recommends that the ASME Section XI, Subsection IWE program consider operating experience regarding liner plate and containment shell corrosion. The applicant should demonstrate that it utilizes industry operating experience in development of the AMP.
There is recent industry operating experience which has indicated that at some plants, the implementation of the IWE program has been ineffective in identifying moisture intrusion into the leak chase channel areas and potential leakage to the containment shell and liner seam welds.
This issue is discussed in NRC Integrated Inspection Report 05000348/2012003 and 05000364/2012003 (Joseph M. Farley Nuclear Plant); NRC Integrated Inspection Report 05000395/2011003 (Virgil C. Summer Nuclear Station); and NRC Integrated Inspection Report 05000327/2012005 and 05000328/2012005 (Sequoyah Nuclear Plant). Some licensees were not performing general visual examinations of 100 percent of the containment liner plate leak chase systems in accordance with ASME Code Section XI, Subsection IWE requirements; and upon inspection, moisture was discovered in the leak chase channel system. Moisture intrusion into the leak chase channel system could reach the containment seam welds. This has the potential to cause corrosion at the welds and affect leak-tightness at the containment or liner pressure boundary.
Issue:
Regarding the recent industry operating experience concerning implementation of the 100 percent visual inspection requirements of the ASME Code IWE and the GALL Report recommendation that the applicant consider industry operating experience in development of the ASME Section XI, Subsection IWE AMP, the staff needs additional information for applicability to Byron and Braidwood.
Request:
Considering the recent industry operating experience described above regarding implementation of the IWE visual examinations, inspections of the leak chase channel system, and concerns of standing water or moisture intrusion to the containment liner plate, state what actions have been or will be taken to (1) determine whether there is moisture in the leak chase channel area and (2) ensure the IWE program will be effective in ensuring moisture intrusion and corrosion do not affect the carbon steel containment liner through the PEO.
Discussion: The applicant requested clarification on the staff's requests. No edits were made to the DRAI. This question Will be sent as a formal RAI titled ""RAI 6.2.1.29-2.""