ML17324B358: Difference between revisions

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| issue date = 11/27/2017
| issue date = 11/27/2017
| title = 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
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==SUMMARY==
==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.
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.
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.
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.
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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)
DATED NOVEMBER 27, 2017. DISTRIBUTION:
DATED NOVEMBER 27, 2017. DISTRIBUTION:
PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDmlrMccb Resource RidsNrrDorlLpl3 Resource RidsNrrLAIBetts Resource RidsNrrLAJBurkhardt Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsRgn3MailCenter Resource SBloom, NRR AHuynh, NRR AJohnson, NRR ADAMS Accession No. ML 173248358 OFFICE NRR/DORL/LPL3/PM NAME JWiebe DATE 11/27/2017 OFFICE NRR/DMLR/MCCB/BC*
PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDmlrMccb Resource RidsNrrDorlLpl3 Resource RidsNrrLAIBetts Resource RidsNrrLAJBurkhardt Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsRgn3MailCenter Resource SBloom, NRR AHuynh, NRR AJohnson, NRR ADAMS Accession No. ML173248358 OFFICE NRR/DORL/LPL3/PM NAME JWiebe DATE 11/27/2017 OFFICE NRR/DMLR/MCCB/BC*
NAME SBloom DATE 11/16/2017  
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 OFFICIAL RECORD COPY}}
*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 OFFICIAL RECORD COPY}}

Revision as of 16:13, 18 June 2019

Review of Steam Generator Tube Report for the Fall 2016 Inspections During Refueling Outage 19 (CAC No. MF9343; EPID L-2017-LLL-0007)
ML17324B358
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 11/27/2017
From: Joel Wiebe
Plant Licensing Branch III
To: Bryan Hanson
Exelon Generation Co
Wiebe J
References
CAC MF9343, EPID L-2017-LLL-0007
Download: ML17324B358 (3)
v • d • e


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.

Docket No. STN 50-456

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. 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

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)

DATED NOVEMBER 27, 2017. DISTRIBUTION:

PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDmlrMccb Resource RidsNrrDorlLpl3 Resource RidsNrrLAIBetts Resource RidsNrrLAJBurkhardt Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsRgn3MailCenter Resource SBloom, NRR AHuynh, NRR AJohnson, NRR ADAMS Accession No. ML173248358 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 OFFICIAL RECORD COPY
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