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| | issue date = 06/04/2014 | | | issue date = 06/04/2014 |
| | title = 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 29 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) | | | title = 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 29 (TAC Nos. MF1879, MF1880, MF1881, and MF1882) |
| | author name = Robinson L R | | | author name = Robinson L |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| | addressee name = Gallagher M P | | | addressee name = Gallagher M |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000454, 05000455, 05000456, 05000457 | | | docket = 05000454, 05000455, 05000456, 05000457 |
| | license number = NPF-037, NPF-066, NPF-072, NPF-077 | | | license number = NPF-037, NPF-066, NPF-072, NPF-077 |
| | contact person = Robinson L R, 415-4115 | | | contact person = Robinson L, 415-4115 |
| | case reference number = TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 | | | case reference number = TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 5 | | | page count = 5 |
| | project = TAC:MF1879, TAC:MF1880, TAC:MF1881, TAC:MF1882 | | | project = TAC:MF1879, TAC:MF1880, TAC:MF1881, TAC:MF1882 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 4, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 SUBJECT: 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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) Dear Mr. Gallagher: By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4115 or e-mail Lindsay.Robinson@nrc.gov. Sincerely, /RA/ Lindsay R. 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 Enclosure: Request for Additional Information cc w/encl: Listserv June 4, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 SUBJECT: 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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 4, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 |
| | |
| | ==SUBJECT:== |
| | 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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) |
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| |
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| ==Dear Mr. Gallagher:== | | ==Dear Mr. Gallagher:== |
|
| |
|
| By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4115 or e-mail Lindsay.Robinson@nrc.gov. Sincerely, /RA/ Lindsay R. 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 Enclosure: Request for Additional Information cc w/encl: Listserv DISTRIBUTION: See following pages ADAMS Accession No.: ML14149A260 *concurred via email OFFICE LA:DLR PM: RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME IKing LRobinson YDiazSanabria LRobinson DATE 6/2/14 6/3/14 6/3/14 6/4/14 OFFICIAL RECORD COPY Letter to M.P. Gallagher from Lindsay R. Robinson dated June 4, 2014 SUBJECT: 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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) DISTRIBUTION EMAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource ---------------------------------- LRobinson DMcIntyre, OPA JMcGhee, RIII EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII ENCLOSURE BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION, SET 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) RAI B.2.1.5-1a Applicability: | | By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. |
| Byron Station (Byron) and Braidwood Station (Braidwood), all units Background: By letter dated January 13, 2014, the applicant responded to request for additional information (RAI) B.2.1.5-1, which addressed loss of material due to wear of control rod drive mechanism (CRDM) nozzles resulting from interactions with CRDM nozzle thermal sleeves. The applicant stated that it is planning to demonstrate, using analysis, that the CRDM nozzle wear will not exceed a minimum safe value such that examinations will not be required during the period of extended operation (PEO). The applicant further stated that when completed, the analyses will include a detailed ASME Code evaluation of the CRDM housing with a reduced wall thickness using the bounding CRDM loads and transients. In addition, all ASME Code stress categories will be evaluated utilizing a finite element analysis and will explicitly consider all conditions to which the CRDM housing is subjected during normal and upset conditions. Issue: | | These requests for additional information were discussed with John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4115 or e-mail Lindsay.Robinson@nrc.gov. |
| The staff cannot determine the adequacy of the applicant's analysis since this analysis has yet to be completed. Additional information is necessary to confirm that the applicant's analysis has an adequate technical basis and that analytical results are acceptable for managing CRDM nozzle wear. Request: | | Sincerely, |
| : 1. Describe the technical basis of the analysis and specific references for the acceptance criteria of the analysis (e.g., ASME Code Section III Edition and paragraphs and current license basis document sections). As part of the response, confirm whether the acceptance criteria adequately address the design, normal, upset, emergency, faulted, testing, and cyclic (i.e., fatigue analysis) conditions in updated final safety analysis report (UFSAR) Section 3.9 and its subsections. 2. Upon completion of the CRDM nozzle wear analysis, provide the results confirming that the wear indications meet the acceptance criteria discussed in Request Part 1. If the analysis finds that the acceptance criteria cannot be met for the maximum possible wear depth of 0.1075 inches, clarify whether volumetric examinations will be performed to monitor the wear depths for adequate aging management. 3. Provide any necessary updates to the license renewal application (LRA), consistent with the applicant's response to Request Parts 1 and 2 (e.g., revisions to the time-limited aging analyses and UFSAR supplements in the LRA). | | /RA/ |
| - 2 - RAI B.2.1.5-2a Applicability: Byron and Braidwood Background: By letter dated January 13, 2014, the applicant responded to RAI B.2.1.5-2, which addressed loss of material due to wear of CRDM nozzle thermal sleeves. The applicant indicated that based on the current examination results at Byron and Braidwood, none of the evaluated thermal sleeve indications approach the minimum wall thickness. The applicant also stated that as a result of the initial visual examinations at each unit, the five thermal sleeves with the worst wear were selected to be examined with ultrasonic testing (UT) in order to obtain measurements of the wear indications. In addition, the applicant indicated the applicant's ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, program will monitor the depths of these worst wear indications for aging management. Issue: It is not clear to staff that the initial examinations detected the worst wear locations because the applicant's response did not specifically state where on the thermal sleeves the worst wear was located. In addition, the applicant's response does not include revisions to the UFSAR supplement (LRA Section A.2.1.1) for the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, program to specify the inspections of the thermal sleeves, as described in the applicant's response to RAI B.2.1.5-2. Request: 1. Describe the locations of the thermal sleeve wear to confirm that the initial visual examinations were capable of detecting the worst wear indications. 2. Justify why the applicant's response does not include revisions to the UFSAR supplement (LRA Section A.2.1.1) to identify the additional inspections of the thermal sleeves.
| | Lindsay R. 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 |
| Alternatively, revise the UFSAR supplement to identify the additional inspections of the thermal sleeves. | | |
| }} | | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Listserv |
| | |
| | ML14149A260 *concurred via email OFFICE LA:DLR PM: RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME IKing LRobinson YDiazSanabria LRobinson DATE 6/2/14 6/3/14 6/3/14 6/4/14 |
| | |
| | Letter to M.P. Gallagher from Lindsay R. Robinson dated June 4, 2014 |
| | |
| | ==SUBJECT:== |
| | 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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) |
| | DISTRIBUTION EMAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource |
| | ---------------------------------- |
| | LRobinson DMcIntyre, OPA JMcGhee, RIII EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII |
| | |
| | BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION, SET 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882) |
| | RAI B.2.1.5-1a Applicability: |
| | Byron Station (Byron) and Braidwood Station (Braidwood), all units |
| | |
| | ==Background:== |
| | |
| | By letter dated January 13, 2014, the applicant responded to request for additional information (RAI) B.2.1.5-1, which addressed loss of material due to wear of control rod drive mechanism (CRDM) nozzles resulting from interactions with CRDM nozzle thermal sleeves. The applicant stated that it is planning to demonstrate, using analysis, that the CRDM nozzle wear will not exceed a minimum safe value such that examinations will not be required during the period of extended operation (PEO). The applicant further stated that when completed, the analyses will include a detailed ASME Code evaluation of the CRDM housing with a reduced wall thickness using the bounding CRDM loads and transients. In addition, all ASME Code stress categories will be evaluated utilizing a finite element analysis and will explicitly consider all conditions to which the CRDM housing is subjected during normal and upset conditions. |
| | Issue: |
| | The staff cannot determine the adequacy of the applicants analysis since this analysis has yet to be completed. Additional information is necessary to confirm that the applicants analysis has an adequate technical basis and that analytical results are acceptable for managing CRDM nozzle wear. |
| | Request: |
| | : 1. Describe the technical basis of the analysis and specific references for the acceptance criteria of the analysis (e.g., ASME Code Section III Edition and paragraphs and current license basis document sections). As part of the response, confirm whether the acceptance criteria adequately address the design, normal, upset, emergency, faulted, testing, and cyclic (i.e., fatigue analysis) conditions in updated final safety analysis report (UFSAR) |
| | Section 3.9 and its subsections. |
| | : 2. Upon completion of the CRDM nozzle wear analysis, provide the results confirming that the wear indications meet the acceptance criteria discussed in Request Part 1. |
| | If the analysis finds that the acceptance criteria cannot be met for the maximum possible wear depth of 0.1075 inches, clarify whether volumetric examinations will be performed to monitor the wear depths for adequate aging management. |
| | : 3. Provide any necessary updates to the license renewal application (LRA), consistent with the applicants response to Request Parts 1 and 2 (e.g., revisions to the time-limited aging analyses and UFSAR supplements in the LRA). |
| | ENCLOSURE |
| | |
| | RAI B.2.1.5-2a Applicability: |
| | Byron and Braidwood |
| | |
| | ==Background:== |
| | |
| | By letter dated January 13, 2014, the applicant responded to RAI B.2.1.5-2, which addressed loss of material due to wear of CRDM nozzle thermal sleeves. The applicant indicated that based on the current examination results at Byron and Braidwood, none of the evaluated thermal sleeve indications approach the minimum wall thickness. The applicant also stated that as a result of the initial visual examinations at each unit, the five thermal sleeves with the worst wear were selected to be examined with ultrasonic testing (UT) in order to obtain measurements of the wear indications. In addition, the applicant indicated the applicants ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, program will monitor the depths of these worst wear indications for aging management. |
| | Issue: |
| | It is not clear to staff that the initial examinations detected the worst wear locations because the applicants response did not specifically state where on the thermal sleeves the worst wear was located. In addition, the applicants response does not include revisions to the UFSAR supplement (LRA Section A.2.1.1) for the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, program to specify the inspections of the thermal sleeves, as described in the applicants response to RAI B.2.1.5-2. |
| | Request: |
| | : 1. Describe the locations of the thermal sleeve wear to confirm that the initial visual examinations were capable of detecting the worst wear indications. |
| | : 2. Justify why the applicants response does not include revisions to the UFSAR supplement (LRA Section A.2.1.1) to identify the additional inspections of the thermal sleeves. |
| | Alternatively, revise the UFSAR supplement to identify the additional inspections of the thermal sleeves.}} |
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] |
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 29 (TAC Nos. MF1879, MF1880, MF1881, and MF1882)| ML14149A260 |
| Person / Time |
|---|
| Site: |
Byron, Braidwood  |
|---|
| Issue date: |
06/04/2014 |
|---|
| From: |
Robinson L
License Renewal Projects Branch 1 |
|---|
| To: |
Gallagher M
Exelon Generation Co |
|---|
| Robinson L, 415-4115 |
| References |
|---|
| TAC MF1879, TAC MF1880, TAC MF1881, TAC MF1882 |
| Download: ML14149A260 (5) |
|
|
|---|
Category:Letter
MONTHYEARML24291A0012024-10-17017 October 2024
Submittal of Core Operating Limits Report, Cycle 25
RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024
Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
ML24281A1502024-10-0707 October 2024
Request for Information for NRC Commercial Grade Dedication Inspection Report 05000454/2025010 and 05000455/2025010
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024
Cycle 27 Core Operating Limits Report
RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024
Relief Requests Associated with the Fifth Inservice Inspection Interval
IR 05000456/20240112024-09-12012 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011
ML24164A0032024-09-10010 September 2024
Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink
ML24250A1182024-09-0606 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024
Both Trains of Control Room Ventilation Temperature Control System Inoperable
ML24227A0522024-08-29029 August 2024
Audit Plan for LAR to Remove ATWS Mtc Limit
IR 05000456/20240052024-08-29029 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005)
IR 05000454/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005)
ML24225A1112024-08-13013 August 2024
Notification of NRC Fire Protection Team Inspection Request for Information
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000454/20240112024-08-0808 August 2024
Phase 2 Post- Approval License Renewal Report 05000454/2024011
IR 05000456/20240022024-08-0808 August 2024
Integrated Inspection Report 05000456/2024002 and 05000457/2024002
ML24172A1252024-07-26026 July 2024
Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter
IR 05000454/20240022024-07-26026 July 2024
Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion
ML24179A3262024-07-23023 July 2024
LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056)
05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024
Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
Nuclear Radiological Emergency Plan Document Revisions
RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024
Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller
ML24163A3922024-06-25025 June 2024
Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter
ML24170A7652024-06-19019 June 2024
Confirmation of Initial License Examination
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
ML24164A2132024-06-13013 June 2024
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant
RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024
License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink
IR 05000456/20240102024-05-31031 May 2024
License Renewal Phase 1 Report 05000456/2024010
RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024
License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed
RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024
Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024
Completion of License Renewal Activities Prior to Entering the Period of Extended Operation
ML24136A0132024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
ML24136A2452024-05-15015 May 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004
IR 05000454/20240012024-05-10010 May 2024
Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001
BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024
Annual Radiological Environmental Operating Report (AREOR)
ML24128A1212024-05-0707 May 2024
Response to Braidwood and Dresden FOF Dates Change Request (2025)
BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024
2023 Regulatory Commitment Change Summary Report
ML24122A6522024-05-0101 May 2024
Submittal of 2023 Annual Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
IR 05000456/20243012024-04-29029 April 2024
NRC Initial License Examination Report 05000456/2024301; 05000457/2024301
ML24116A0052024-04-25025 April 2024
Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25
RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
ML24116A1192024-04-25025 April 2024
2023 Annual Radioactive Effluent Release Report (ARERR)
IR 05000456/20240012024-04-24024 April 2024
Integrated Inspection Report 05000456/2024001 and 05000457/2024001
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24263A1272024-09-23023 September 2024
– Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary
ML24250A1182024-09-0606 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
ML24113A2892024-04-22022 April 2024
Notification of NRC Baseline Inspection and Request for Information
ML24053A3382024-02-22022 February 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062)
ML24039A0412024-01-30030 January 2024
NRR E-mail Capture - Request for Additional Information Regarding Braidwood Request for Alternative (I4R-18)
ML23339A0452023-12-0505 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
ML22129A0132022-05-0606 May 2022
NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10
ML22271A0772022-05-0606 May 2022
NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request
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
2024-09-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 4, 2014 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
Dear Mr. Gallagher:
By letter dated May 29, 2013, Exelon Generation Company, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-37, NPF-66, NPF-72, and NPF-77 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, respectively, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4115 or e-mail Lindsay.Robinson@nrc.gov.
Sincerely,
/RA/
Lindsay R. 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
Enclosure:
Request for Additional Information cc w/encl: Listserv
ML14149A260 *concurred via email OFFICE LA:DLR PM: RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME IKing LRobinson YDiazSanabria LRobinson DATE 6/2/14 6/3/14 6/3/14 6/4/14
Letter to M.P. Gallagher from Lindsay R. Robinson dated June 4, 2014
SUBJECT:
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 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
DISTRIBUTION EMAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsOgcMailCenter RidsNrrPMByron Resource RidsNrrPMBraidwood Resource
LRobinson DMcIntyre, OPA JMcGhee, RIII EDuncan, RIII JBenjamin, RIII AGarmoe, RIII JRobbins, RIII VMitlyng, RIII PChandrathil, RIII
BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION, SET 29 (TAC NOS. MF1879, MF1880, MF1881, AND MF1882)
RAI B.2.1.5-1a Applicability:
Byron Station (Byron) and Braidwood Station (Braidwood), all units
Background:
By letter dated January 13, 2014, the applicant responded to request for additional information (RAI) B.2.1.5-1, which addressed loss of material due to wear of control rod drive mechanism (CRDM) nozzles resulting from interactions with CRDM nozzle thermal sleeves. The applicant stated that it is planning to demonstrate, using analysis, that the CRDM nozzle wear will not exceed a minimum safe value such that examinations will not be required during the period of extended operation (PEO). The applicant further stated that when completed, the analyses will include a detailed ASME Code evaluation of the CRDM housing with a reduced wall thickness using the bounding CRDM loads and transients. In addition, all ASME Code stress categories will be evaluated utilizing a finite element analysis and will explicitly consider all conditions to which the CRDM housing is subjected during normal and upset conditions.
Issue:
The staff cannot determine the adequacy of the applicants analysis since this analysis has yet to be completed. Additional information is necessary to confirm that the applicants analysis has an adequate technical basis and that analytical results are acceptable for managing CRDM nozzle wear.
Request:
- 1. Describe the technical basis of the analysis and specific references for the acceptance criteria of the analysis (e.g., ASME Code Section III Edition and paragraphs and current license basis document sections). As part of the response, confirm whether the acceptance criteria adequately address the design, normal, upset, emergency, faulted, testing, and cyclic (i.e., fatigue analysis) conditions in updated final safety analysis report (UFSAR)
Section 3.9 and its subsections.
- 2. Upon completion of the CRDM nozzle wear analysis, provide the results confirming that the wear indications meet the acceptance criteria discussed in Request Part 1.
If the analysis finds that the acceptance criteria cannot be met for the maximum possible wear depth of 0.1075 inches, clarify whether volumetric examinations will be performed to monitor the wear depths for adequate aging management.
- 3. Provide any necessary updates to the license renewal application (LRA), consistent with the applicants response to Request Parts 1 and 2 (e.g., revisions to the time-limited aging analyses and UFSAR supplements in the LRA).
ENCLOSURE
RAI B.2.1.5-2a Applicability:
Byron and Braidwood
Background:
By letter dated January 13, 2014, the applicant responded to RAI B.2.1.5-2, which addressed loss of material due to wear of CRDM nozzle thermal sleeves. The applicant indicated that based on the current examination results at Byron and Braidwood, none of the evaluated thermal sleeve indications approach the minimum wall thickness. The applicant also stated that as a result of the initial visual examinations at each unit, the five thermal sleeves with the worst wear were selected to be examined with ultrasonic testing (UT) in order to obtain measurements of the wear indications. In addition, the applicant indicated the applicants ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, program will monitor the depths of these worst wear indications for aging management.
Issue:
It is not clear to staff that the initial examinations detected the worst wear locations because the applicants response did not specifically state where on the thermal sleeves the worst wear was located. In addition, the applicants response does not include revisions to the UFSAR supplement (LRA Section A.2.1.1) for the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, program to specify the inspections of the thermal sleeves, as described in the applicants response to RAI B.2.1.5-2.
Request:
- 1. Describe the locations of the thermal sleeve wear to confirm that the initial visual examinations were capable of detecting the worst wear indications.
- 2. Justify why the applicants response does not include revisions to the UFSAR supplement (LRA Section A.2.1.1) to identify the additional inspections of the thermal sleeves.
Alternatively, revise the UFSAR supplement to identify the additional inspections of the thermal sleeves.