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| | number = ML17324B358 | | | number = ML17324B358 |
| | issue date = 11/27/2017 | | | issue date = 11/27/2017 |
| | title = Braidwood Station, Unit 1 - Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 19 (CAC No. MF9343; EPID L-2017-LLL-0007) | | | title = Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 19 (CAC No. MF9343; EPID L-2017-LLL-0007) |
| | author name = Wiebe J S | | | author name = Wiebe J |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000456 | | | docket = 05000456 |
| | license number = NPF-072 | | | license number = NPF-072 |
| | contact person = Wiebe J S | | | contact person = Wiebe J |
| | case reference number = CAC MF9343, EPID L-2017-LLL-0007 | | | case reference number = CAC MF9343, EPID L-2017-LLL-0007 |
| | document type = Letter | | | document type = Letter |
| | page count = 3 | | | page count = 3 |
| | project = CAC:MF9343, EPID:L-2017-LLL-0007 | | | project = CAC:MF9343, EPID:L-2017-LLL-0007 |
| | stage = RAI | | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 November 27, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 November 27, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) |
| | Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BRAIDWOOD STATION, UNIT 1 -REVIEW OF THE FALL 2016 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 19 (CAC NO. MF9343; EPID L-2017-LLL-0007) | | BRAIDWOOD STATION, UNIT 1 - REVIEW OF THE FALL 2016 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 19 (CAC NO. MF9343; EPID L-2017-LLL-0007) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By letter dated February 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17058A085), Exelon Generation Company, LLC (the licensee), submitted information summarizing the results of its fall 2016 steam generator tube inspections performed during refueling outage 19 at Braidwood Station (Braidwood}, Unit 1. The U.S. Nuclear Regulatory Commission (NRG) staff has completed its review of the report and concludes that the licensee provided the information required by the Braidwood, Unit 1, technical specifications. No additional follow-up is required at this time. The NRG staff's review is enclosed. If you have questions regarding this review, please contact me at (301) 415-6606 or Joel.Wiebe@nrc.gov. Docket No. STN 50-456 | | |
| | By letter dated February 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17058A085), Exelon Generation Company, LLC (the licensee), submitted information summarizing the results of its fall 2016 steam generator tube inspections performed during refueling outage 19 at Braidwood Station (Braidwood}, Unit 1. |
| | The U.S. Nuclear Regulatory Commission (NRG) staff has completed its review of the report and concludes that the licensee provided the information required by the Braidwood, Unit 1, technical specifications. No additional follow-up is required at this time. The NRG staff's review is enclosed. |
| | If you have questions regarding this review, please contact me at (301) 415-6606 or Joel.Wiebe@nrc.gov. |
| | Sincerely, oel S. Wiebe, Senior Project Manager Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456 |
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| ==Enclosure:== | | ==Enclosure:== |
| Summary of the Review of Steam Generator Tube Inspections cc: Listserv Sincerely, oel S. Wiebe, Senior Project Manager Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUMMARY OF U.S. NUCLEAR REGULATORY COMMISSION STAFF'S REVIEW OF THE STEAM GENERATOR TUBE INSPECTIONS FOR REFUELING OUTAGE 19 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNIT 1 DOCKET NO. 50-456 By letter dated February 27, 2017 (Agencywide Documents Access and Management System Accession No. ML 17058A085), Exelon Generation Company, LLC (the licensee), submitted information summarizing the results of the fall 2016 steam generator (SG) tube inspections performed at Braidwood Station (Braidwood), Unit 1, during refueling outage (RFO) 19. Braidwood, Unit 1, has four recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 6,633 thermally treated Alloy 690 tubes that have an outside diameter of 0.6875 inches and a nominal wall thickness of 0.040 inches. The tubes are supported by Type 410 stainless steel, lattice-grid tube supports and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. The licensee provided the scope, extent, methods, and results of the SG tube inspections in its February 27, 2017, letter. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. After a review of the information provided by the licensee, the U.S. Nuclear Regulatory Commission staff has the following comments/observations: The licensee identified a total of 13 indications of secondary side foreign object (FO) wear in 12 tubes during RFO 19. In SG 1A, the licensee plugged and stabilized four tubes surrounding an FO that the licensee was unable to retrieve. The remaining tubes with FO wear were left in service since the FO presumed to have caused wear in these tubes was removed. The largest FO wear indication was measured to be 27 percent through-wall. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Braidwood, Unit 1, technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure
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| ML 173248358 OFFICE NRR/DORL/LPL3/PM NAME JWiebe DATE 11/27/2017 OFFICE NRR/DMLR/MCCB/BC* NAME SBloom DATE 11/16/2017 *via memo dated NRR/DORL/LSPB/LAiT N RR/DORL/LPL3/LA I Betts SRohrer (JBurkhardt for) 11/24/2017 11/27/2017 NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM DWrona JWiebe 11/27/2017 11/27/2017
| | Summary of the Review of Steam Generator Tube Inspections cc: Listserv |
| }} | | |
| | ==SUMMARY== |
| | OF U.S. NUCLEAR REGULATORY COMMISSION STAFF'S REVIEW OF THE STEAM GENERATOR TUBE INSPECTIONS FOR REFUELING OUTAGE 19 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNIT 1 DOCKET NO. 50-456 By letter dated February 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17058A085), Exelon Generation Company, LLC (the licensee), submitted information summarizing the results of the fall 2016 steam generator (SG) tube inspections performed at Braidwood Station (Braidwood), Unit 1, during refueling outage (RFO) 19. |
| | Braidwood, Unit 1, has four recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 6,633 thermally treated Alloy 690 tubes that have an outside diameter of 0.6875 inches and a nominal wall thickness of 0.040 inches. The tubes are supported by Type 410 stainless steel, lattice-grid tube supports and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. |
| | The licensee provided the scope, extent, methods, and results of the SG tube inspections in its February 27, 2017, letter. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. |
| | After a review of the information provided by the licensee, the U.S. Nuclear Regulatory Commission staff has the following comments/observations: |
| | The licensee identified a total of 13 indications of secondary side foreign object (FO) wear in 12 tubes during RFO 19. In SG 1A, the licensee plugged and stabilized four tubes surrounding an FO that the licensee was unable to retrieve. The remaining tubes with FO wear were left in service since the FO presumed to have caused wear in these tubes was removed. The largest FO wear indication was measured to be 27 percent through-wall. |
| | Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Braidwood, Unit 1, technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. |
| | Enclosure |
| | |
| | ML173248358 *via memo dated OFFICE NRR/DORL/LPL3/PM NRR/DORL/LSPB/LAiT NRR/DORL/LPL3/LA NAME JWiebe IBetts SRohrer (JBurkhardt for) |
| | DATE 11/27/2017 11/24/2017 11/27/2017 OFFICE NRR/DMLR/MCCB/BC* NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME SBloom DWrona JWiebe DATE 11/16/2017 11/27/2017 11/27/2017}} |
Letter Sequence Approval |
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MONTHYEARML17058A0852017-02-27027 February 2017
Steam Generator Tube Inspection Report for Refueling Outage 19
Project stage: Request
ML17324B3582017-11-27027 November 2017
Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 19 (CAC No. MF9343; EPID L-2017-LLL-0007)
Project stage: Approval
2017-11-27
[Table View] |
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Category:Letter
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Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002
IR 05000457/20230112024-01-25025 January 2024
2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation
ML24018A0362024-01-17017 January 2024
Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618
RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024
Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators
ML23348A2162023-12-15015 December 2023
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
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Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402
ML23277A0032023-12-11011 December 2023
Issuance of Amendments Regarding Adoption of TSTF-370
ML23339A0452023-12-0505 December 2023
Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010
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Review of the Fall 2022 Steam Generator Tube Inspection Report
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Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference
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Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline
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ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
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IR 05000456/20234012023-10-18018 October 2023
Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401
IR 05000456/20230102023-10-18018 October 2023
Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
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RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023
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RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023
Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023
License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.
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Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005
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Confirmation of Initial License Examination
IR 05000456/20230022023-08-0303 August 2023
Integrated Inspection Report 05000456/2023002 and 05000457/2023002
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Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
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Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink
ML23191A8442023-07-10010 July 2023
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Submittal of Core Operating Limits Report Cycle 24, Rev. 16
IR 05000456/20230012023-05-0808 May 2023
Integrated Inspection Report 05000456/2023001 and 05000457/2023001
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Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
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Submittal of 2022 Annual Radioactive Effluent Release Report
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Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
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[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 November 27, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNIT 1 - REVIEW OF THE FALL 2016 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 19 (CAC NO. MF9343; EPID L-2017-LLL-0007)
Dear Mr. Hanson:
By letter dated February 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17058A085), Exelon Generation Company, LLC (the licensee), submitted information summarizing the results of its fall 2016 steam generator tube inspections performed during refueling outage 19 at Braidwood Station (Braidwood}, Unit 1.
The U.S. Nuclear Regulatory Commission (NRG) staff has completed its review of the report and concludes that the licensee provided the information required by the Braidwood, Unit 1, technical specifications. No additional follow-up is required at this time. The NRG staff's review is enclosed.
If you have questions regarding this review, please contact me at (301) 415-6606 or Joel.Wiebe@nrc.gov.
Sincerely, oel S. Wiebe, Senior Project Manager Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456
Enclosure:
Summary of the Review of Steam Generator Tube Inspections cc: Listserv
SUMMARY
OF U.S. NUCLEAR REGULATORY COMMISSION STAFF'S REVIEW OF THE STEAM GENERATOR TUBE INSPECTIONS FOR REFUELING OUTAGE 19 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNIT 1 DOCKET NO. 50-456 By letter dated February 27, 2017 (Agencywide Documents Access and Management System Accession No. ML17058A085), Exelon Generation Company, LLC (the licensee), submitted information summarizing the results of the fall 2016 steam generator (SG) tube inspections performed at Braidwood Station (Braidwood), Unit 1, during refueling outage (RFO) 19.
Braidwood, Unit 1, has four recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 6,633 thermally treated Alloy 690 tubes that have an outside diameter of 0.6875 inches and a nominal wall thickness of 0.040 inches. The tubes are supported by Type 410 stainless steel, lattice-grid tube supports and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet.
The licensee provided the scope, extent, methods, and results of the SG tube inspections in its February 27, 2017, letter. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
After a review of the information provided by the licensee, the U.S. Nuclear Regulatory Commission staff has the following comments/observations:
The licensee identified a total of 13 indications of secondary side foreign object (FO) wear in 12 tubes during RFO 19. In SG 1A, the licensee plugged and stabilized four tubes surrounding an FO that the licensee was unable to retrieve. The remaining tubes with FO wear were left in service since the FO presumed to have caused wear in these tubes was removed. The largest FO wear indication was measured to be 27 percent through-wall.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Braidwood, Unit 1, technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
ML173248358 *via memo dated OFFICE NRR/DORL/LPL3/PM NRR/DORL/LSPB/LAiT NRR/DORL/LPL3/LA NAME JWiebe IBetts SRohrer (JBurkhardt for)
DATE 11/27/2017 11/24/2017 11/27/2017 OFFICE NRR/DMLR/MCCB/BC* NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME SBloom DWrona JWiebe DATE 11/16/2017 11/27/2017 11/27/2017
