Letter Sequence Draft RAI |
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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
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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
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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
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Text
May 14, 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 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 BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, AND 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 April 10, 2014, to discuss and clarify the staff's draft request for additional information (DRAI), Set 22, 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 DRAIs.
Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/ Lindsay 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
May 14, 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 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 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 April 10, 2014, to discuss and clarify the staff's draft request for additional information (DRAI),
Set 22, 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 DRAIs.
Enclosure 1 provides a listing of the participants, and Enclosure 2 contains a listing of the DRAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary. /RA/ Lindsay 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 DISTRIBUTION: See next page ADAMS Accession No.: ML14112A418 *concurred via email OFFICE LA:DLR* PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME IKing LRobinson YDiazSanabria LRobinson DATE 4/29/14 5/7/14 5/13/14 5/14/14 OFFICIAL RECORD COPY SUBJECT: 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 BRAIDWOOD STATION, LICENSE RENEWAL APPLICATION (TAC NOS. MF1879, MF1880, MF1881, MF1882)
DISTRIBUTION EMAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource
LRobinson DMcIntyre, OPA EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JMcGhee, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII ENCLOSURE 1 TELEPHONE CONFERENCE CALL BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS April 10, 2014 PARTICIPANTS AFFILIATIONS Lindsay Robinson U.S. Nuclear Regulatory Commission (NRC) Matthew Homiack NRC James Medoff NRC Seung Min NRC Carolyn Fairbanks NRC John Hufnagel Exelon Generating Company, LLC (Exelon)
Don Warfel Exelon Al Fulvio Exelon Albert Piha Exelon Gary Becknell Exelon Pete Tamburro Exelon Phil O'Donnell Exelon Paul Thimmesch Exelon Don Brindle Exelon Ralph Wolen Exelon ENCLOSURE 2 DRAFT REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION April 10, 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 April 10, 2014, to discuss and clarify the following draft request for additional information (DRAI), Set 22, concerning the Byron Station, Units 1 and 2, and the Braidwood Station, Units 1 and 2, license renewal application (LRA). DRAI B.2.1.19-1a Applicability:
Byron Station (Byron) and Braidwood (Station), all units
Background: By letter dated December 12, 2013, the staff issued a request for additional information (RAI)titled, "RAI B.2.1.19-1," requesting an updated surveillance capsule withdrawal schedule for each unit "including, but not limited to: identification of the capsule and associated neutron fluence value which will provide test results consistent with the [Generic Aging Lessons Learned] GALL Report recommendation of a neutron fluence exposure of between one and two times the peak reactor vessel wall neutron fluence at the end of the period of extended operation, and identification of a date for the submittal of each summary technical report." In its response dated January 13, 2014, the applicant stated that each technical summary report for the next surveillance capsule testing "will be submitted to the NRC prior to entering the associated period of extended operation." Currently, each unit of Byron and Braidwood stores the untested surveillance capsules in the spent fuel pool for future use.
Per Appendix H of 10 CFR Part 50, "Each capsule withdrawal and the test results must be the subject of a summary technical report to be submitted-within one year of the date of capsule withdrawal, unless an extension is granted by the Director, Office of Nuclear Reactor Regulation." The Byron and Braidwood Pressure-Temperature Limits Reports (PTLRs) include Tables for surveillance capsule withdrawal schedules and state that "surveillance capsule testing has been completed for the original operating period. Other capsules will be removed to avoid excessive fluence accumulation should they be needed to support life extension." These surveillance capsule withdrawal schedules are no longer applicable beyond the original operating period. Issue:
In its response, the applicant did not clearly address the withdrawal dates and summary technical report submittal dates. The surveillance capsules have already received neutron fluence exposures of 1-2 times the projected neutron fluence values at the end of the period of extended operation and have been withdrawn from the reactor vessel and moved to the spent fuel pool. Since the current surveillance capsule withdrawal schedule is valid for the current operating period, the staff considers the initiation of a new surveillance capsule withdrawal schedule to be necessary for the period of extended operation. Upon receiving a renewed
- 2 - operating license, the surveillance capsules, identified in Table 1 of the applicant's response dated January 13, 2014, would no longer be considered standby capsules; instead, they would be considered part of the program to meet the GALL Report and 10 CFR Part 50, Appendix H, requirements. Capsules should be tested and summary reports submitted within 1 year of receiving the renewed license, unless Byron and Braidwood submits a request for extension for approval by the Director, Office of Nuclear Reactor Regulation, within this period.
Request: For each surveillance capsule identified in Table 1 of the applicant's response dated January 13, 2014, provide the withdrawal date and expected date of submittal of the summary technical report. A request for extension must be submitted for approval by the Director, Office of Nuclear Reactor Regulation, if the expected date for the submittal of the summary technical report exceeds 1 year from the date of capsule withdrawal. Discussion: The applicant requested clarity on the staff's concern. No edits were proposed. This question will be sent as part of the formal request titled: "RAI B.2.1.19-1a."
DRAI 4.7.1-1 Applicability:
Byron and Braidwood
Background: Per 10 CFR Part 50, Criterion 4 of Appendix A, "General Design Criteria for Nuclear Power Plants" (GDC-4), systems, structures, and components (SSCs) important to safety are required to be appropriately protected against dynamic effects associated with postulated pipe ruptures, unless analyses reviewed and approved by the Commission demonstrate that the probability of rupture is extremely low under conditions consistent with the design basis for the piping. An approved leak-before-break analysis permits a licensee to remove protective hardware such as pipe whip restraints and jet impingement barriers; redesign pipe connected components, their supports, and their internals; and other related changes. License renewal application (LRA)
Section 4.7.1 describes the applicant's time limited aging analyses (TLAA) evaluation for the Byron and Braidwood leak-before-break analyses. The LRA states that the applicant updated the existing leak-before-break analyses for the reactor coolant primary loop piping and the safety injection accumulator piping cold leg nozzles and concludes that the updated analyses meet the requirements of 10 CFR 54.21(c)(1)(ii).
Issue: To meet the requirements of 10 CFR 54.21(c)(1)(ii), the applicant must demonstrate that its updated leak-before-break analyses, which have been projected to the end of the period of extended operation, satisfy the requirements of GDC-4. The LRA provides a general description of how the applicant updated the leak-before-break analyses for the reactor coolant primary loop piping and the safety injection accumulator piping cold leg nozzles. However, the LRA does not clearly identify the methodology used to update these analyses, nor does it contain a sufficient level of technical detail for the NRC staff to confirm that the updated analyses comply with GDC-4.
- 3 - Request:
Provide the full updates to the leak-before-break analyses for the reactor coolant primary loop piping and the safety injection accumulator piping cold leg nozzles for NRC staff review and approval. The submitted analyses should contain a sufficient level of technical information to demonstrate compliance with the GDC-4 requirements for extremely low probability of rupture.
A sufficient level of technical information would address items 1 through 11 from NUREG-0800, "Standard Review Plan," Section 3.6.3, "Leak-Before-Break Evaluation Procedures,"
Subsection III, dated March 2007. Discussion: The applicant requested clarity on the staff's concern. The applicant did not agree with the staff's concern that full updates needed to be provided. The staff agreed to add the following statement as the last sentence in the Request to provide the applicant an opportunity to provide its rationale: "Otherwise, provide the rationale for not submitting the full updates to these leak-before-break analyses." Also, the applicant requested that "safety injection accumulator piping cold leg nozzles" be removed from this question and added to DRAI 4.7.1-4 since that question relates to this component. The staff agreed to make the edit as annotated by the strikethrough. Minor edits will also be made to the final issuance of this question and will be sent as part of the formal request titled: "RAI 4.7.1-1."
DRAI 4.7.1-2 Applicability:
Byron and Braidwood Background:
LRA Section 4.7.1 describes the applicant's TLAA evaluation for the Byron and Braidwood leak-before-break analyses. The LRA states that the applicant either updated the existing leak-before-break analyses or confirmed that they remain valid for the period of extended operation. Sargent and Lundy Report SL-4518, "Leak Before-Break Evaluation for Stainless Steel Piping, Byron and Braidwood Nuclear Power Stations Units 1 and 2," dated May 12, 1989, documents some of the existing analyses.
Issue: In accordance with 10 CFR 54.21(c)(1), the LRA must contain an evaluation of TLAAs. As defined in 10 CFR 54.3, TLAAs are those calculations and analyses that are contained or incorporated by reference in the current licensing basis. Sargent and Lundy Report SL-4518 meets this definition because it is incorporated by reference into FSAR Section 3.6.2.1.1. The scope of this report covers leak-before-break analyses for three piping systems: (1) reactor coolant bypass system, (2) residual heat removal system, and (3) safety injection system. However, the LRA does not include a TLAA evaluation for the leak-before-break analysis for the residual heat removal system piping.
Request: Justify why the existing leak-before-break analysis for the residual heat removal system piping does not meet the definition of a TLAA in 10 CFR 54.3. Otherwise, provide a demonstration for this analysis in accordance with the requirements of 10 CFR 54.21(c)(1).
- 4 - Discussion: The applicant discussed with the staff that the leak-before-break analysis for the residual heat removal system piping had not been approved by the NRC (see NRC correspondence to applicant for additional information: ADAMS Accession Number 9104290046); therefore, there is no basis for this question. This question will be deleted from Set 22. DRAI 4.7.1-4 Applicability:
Byron and Braidwood
Background: GDC-4 requires SSCs important to safety to be appropriately protected against dynamic effects associated with postulated pipe ruptures, unless analyses reviewed and approved by the Commission demonstrate that the probability of rupture is extremely low under conditions consistent with the design basis for the piping. An approved leak-before-break analysis permits a licensee to remove protective hardware such as pipe whip restraints and jet impingement barriers, redesign pipe connected components, their supports and their internals, and other related changes. LRA Section 4.7.1 describes the applicant's TLAA evaluation for the Byron and Braidwood leak-before-break analysis for the safety injection accumulator piping cold leg nozzles, which are made of cast austenitic stainless steel (CASS). Because this material is susceptible to the effects of thermal aging, the LRA states that the applicant determined the fracture toughness properties for the materials at the fully aged condition applicable to the period of extended operation, and it used these properties to update the existing leak-before-break analysis. The LRA concludes that the updated analysis meets the requirements of 10 CFR 54.21(c)(1)(ii).
Issue:
To meet the requirements of 10 CFR 54.21(c)(1)(ii), the applicant must demonstrate that its updated leak-before-break analysis, which has been projected to the end of the period of extended operation, satisfies the requirements of GDC-4. The LRA does not clearly identify the methodology used for the updated leak-before-break analysis for the safety injection accumulator piping cold leg nozzles, nor does it contain a sufficient level of technical detail for the NRC staff to confirm that the updated analysis complies with GDC-4. To fulfill the requirements of 10 CFR 54.21(c)(1)(ii), the applicant must demonstrate the adequacy of its projected analysis. LRA Section 4.7.1 does not demonstrate that the projected analysis for the safety injection accumulator piping cold leg nozzles is adequate because the LRA does not identify and justify the specific methodology used to determine the CASS material properties at the end of the period of extended operation.
Request: 1. Provide for NRC staff review and approval the full update to the leak-before-break analysis for the safety injection accumulator piping cold leg nozzles. The submitted analysis should contain a sufficient level of technical information to demonstrate compliance with the GDC-4 requirements for extremely low probability of rupture. A sufficient level of technical information would address items 1 through 11 from
- 5 - NUREG-0800, "Standard Review Plan," Section 3.6.3, "Leak-Before-Break Evaluation Procedures," Subsection III, dated March 2007. Otherwise, provide the rationale for not submitting a full update to the leak-before-break analysis. 2. Identify and provide justification for the methodology used to determine the CASS fracture toughness properties at the end of the period of extended operation.
Identify the methodology that was used to determine the material properties of the CASS safety injection accumulator piping cold leg nozzle components at the end of the period of extended operation. Provide justification if this methodology has not been approved by the NRC.
Discussion: The applicant requested clarity on the staff's concern. Based on the applicant's request to remove "safety injection accumulator cold leg nozzles" from DRAI 4.7.1-1, the staff rewrote DRAI 4.7.1-4 to address both the methodology and updated leak-before-break analysis. The staff's additions to the original request are annotated by the underlined portions and the deletions are annotated by the strikethroughs. This question will be sent as part of the formal request titled: "RAI 4.7.1-3."