ML110820865: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(One intermediate revision by the same user not shown)
Line 3: Line 3:
| issue date = 03/31/2011
| issue date = 03/31/2011
| title = Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections
| title = Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections
| author name = Stang J F
| author name = Stang J
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
| addressee name = Gillespie P
| addressee name = Gillespie P
Line 9: Line 9:
| docket = 05000270
| docket = 05000270
| license number = DPR-047
| license number = DPR-047
| contact person = Stang J F, NRR/DORL, 415-1345
| contact person = Stang J, NRR/DORL, 415-1345
| case reference number = TAC ME4649
| case reference number = TAC ME4649
| document type = Letter, Report, Miscellaneous
| document type = Letter, Report, Miscellaneous
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 31,2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 OCONEE NUCLEAR STATION, UNIT 2, EVALUATION OF 2010 (CYCLE 24) STEAM GENERATOR (SG) TUBE INSPECTIONS (TAC NO. ME4649) Dear Mr. Gillespie By letter dated August 27,2010 (Agencywide Documents Access and Management System, Accession No. ML 102430530), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of the 2010 SG tube inspections at Oconee Nuclear Station, Unit 2 during the Cycle 24 refueling outage. The U.S Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staffs review of the reports is enclosed.
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 31,2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
Sincerely, senio4ect Manager Plant licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
 
Evaluation of SG Tube cc w/encl: Distribution via UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR EVALUATION OF THE 2010 STEAM GENERATOR TUBE PERFORMED DURING THE 2010 REFUELING OCONEE NUCLEAR STATION, UNIT DOCKET NO. By letter dated August 27,2010 (Agencywide Documents Access Management System, Accession No. ML 102430530), Duke Energy Carolinas, LLC (the licensee), submitted the results of their 2010 steam generator tube inspections performed during the Cycle 24 refueling outage at Oconee Nuclear Station, Unit 2 (Oconee 2). Oconee 2 is a two-loop pressurized-water reactor with once-through steam generators (OTSGs) manufactured by Babcock & Wilcox (B&W), Canada. The Oconee 2 OTSGs are replacement OTSGs that were installed during the 2004 refueling outage. The OTSGs consist of 15,631 thermally treated Alloy 690 tubes that have been hydraulically expanded into the tubesheets to a depth of 13 inches. There are 15 Type 410 stainless steel tube support plates (TSP) with trefoil shaped holes. However, there are some round drilled openings at the 14th TSP. Widespread wear degradation of the tubing at TSP locations has been observed at all three Oconee units. The licensee provided the scope, extent, methods, and results of their OTSG tube inspections in the document referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
==SUBJECT:==
OCONEE NUCLEAR STATION, UNIT 2, EVALUATION OF 2010 (CYCLE 24)
STEAM GENERATOR (SG) TUBE INSPECTIONS (TAC NO. ME4649)
Dear Mr. Gillespie By letter dated August 27,2010 (Agencywide Documents Access and Management System, Accession No. ML102430530), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of the 2010 SG tube inspections at Oconee Nuclear Station, Unit 2 during the Cycle 24 refueling outage.
The U.S Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staffs review of the reports is enclosed.
Sincerely, ~
                                                ~g,            senio4ect Manager Plant licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-270
 
==Enclosure:==
 
Evaluation of SG Tube Inspections cc w/encl: Distribution via Listserv
 
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION EVALUATION OF THE 2010 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING THE 2010 REFUELING OUTAGE OCONEE NUCLEAR STATION, UNIT 2 DOCKET NO. 50-270 By letter dated August 27,2010 (Agencywide Documents Access Management System, Accession No. ML102430530), Duke Energy Carolinas, LLC (the licensee), submitted the results of their 2010 steam generator tube inspections performed during the Cycle 24 refueling outage at Oconee Nuclear Station, Unit 2 (Oconee 2).
Oconee 2 is a two-loop pressurized-water reactor with once-through steam generators (OTSGs) manufactured by Babcock & Wilcox (B&W), Canada. The Oconee 2 OTSGs are replacement OTSGs that were installed during the 2004 refueling outage. The OTSGs consist of 15,631 thermally treated Alloy 690 tubes that have been hydraulically expanded into the tubesheets to a depth of 13 inches. There are 15 Type 410 stainless steel tube support plates (TSP) with trefoil shaped holes. However, there are some round drilled openings at the 14th TSP.
Widespread wear degradation of the tubing at TSP locations has been observed at all three Oconee units. The licensee provided the scope, extent, methods, and results of their OTSG tube inspections in the document referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
The licensee indicated that the following tubes were plugged:
The licensee indicated that the following tubes were plugged:
* OTSG A: 90-124,91-124,99-126, 112-102, 128-87, and 151-16
* OTSG A: 90-124,91-124,99-126, 112-102, 128-87, and 151-16
* OTSG B: 56-6,79-10,83-8,90-5, 136-11, and 144-50 In addition, the licensee stated that the array data obtained from the x-probe was only reviewed to characterize selected wear indications (i.e., array data was not reviewed at locations such as expansion transitions or dents/dings since only wear degradation is expected).
* OTSG B: 56-6,79-10,83-8,90-5, 136-11, and 144-50 In addition, the licensee stated that the array data obtained from the x-probe was only reviewed to characterize selected wear indications (i.e., array data was not reviewed at locations such as expansion transitions or dents/dings since only wear degradation is expected).
Based on a review of the information provided, the Nuclear Regulatory Commission staff concludes that the licensee provided the information required by the technical specifications.
Based on a review of the information provided, the Nuclear Regulatory Commission staff concludes that the licensee provided the information required by the 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 that inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
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 that inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Principal Contributor:
Principal Contributor: A. Obodoako, NRR/DCI Date:     March 31, 2011 Enclosure
A. Obodoako, NRR/DCI Date: March 31, 2011 Enclosure March 31, 2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 OCONEE NUCLEAR STATION, UNIT 2, EVALUATION OF 2010 (CYCLE 24) STEAM GENERATOR (SG) TUBE INSPECTIONS (TAC NO. ME4649) Dear Mr. Gillespie By letter dated August 27,2010 (Agencywide Documents Access and Management System, Accession No. ML 102430530), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of the 2010 SG tube inspections at Oconee Nuclear Station, Unit 2 during the Cycle 24 refueling outage. The U.S Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staff's review of the reports is enclosed.
 
Sincerely, IRA! John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
March 31, 2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
Evaluation of SG Tube cc w/encl: Distribution via DISTRIBUTION:
 
PUBLIC LPL2-1 r/f RidsNrrLAMO'Brien Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDciCsgb Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource KKarwoski, NRR/DCI RidsNrrPMOconee Resource AObodoako, NRR/DCI ADAMS A cceSSJon N 0.: ML 110820865
==SUBJECT:==
*M b 'tt d b T h St ff d t d erno su rnl e lY ec a ae OFFICE NAME DATE NRR/LPL2-1/PM JStang 03/30/11 NRR/LPL2-'liLA MO'Brien 03/30/11 NRR/DCI/CSGB/BC NRR/LPL2-1/BC RTaylor* GKulesa 03/16/11 03/31/11 NRRILPL2-1/PM JStang 03/31/11 OFFICIAL RECORD COpy}}
OCONEE NUCLEAR STATION, UNIT 2, EVALUATION OF 2010 (CYCLE 24)
STEAM GENERATOR (SG) TUBE INSPECTIONS (TAC NO. ME4649)
Dear Mr. Gillespie By letter dated August 27,2010 (Agencywide Documents Access and Management System, Accession No. ML102430530), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of the 2010 SG tube inspections at Oconee Nuclear Station, Unit 2 during the Cycle 24 refueling outage.
The U.S Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staff's review of the reports is enclosed.
Sincerely, IRA!
John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-270
 
==Enclosure:==
 
Evaluation of SG Tube Inspections cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC           LPL2-1 r/f                         RidsNrrLAMO'Brien Resource RidsAcrsAcnw_MailCTR Resource                       RidsOgcRp Resource RidsNrrDciCsgb Resource                             RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource                         KKarwoski, NRR/DCI RidsNrrPMOconee Resource                           AObodoako, NRR/DCI ADAMS A cceSSJon N0.: ML110820865                                  *M erno su brnl'tted blY Tech Staff dae t d OFFICE     NRR/LPL2-1/PM   NRR/LPL2-'liLA   NRR/DCI/CSGB/BC     NRR/LPL2-1/BC           NRRILPL2-1/PM NAME      JStang          MO'Brien          RTaylor*           GKulesa                 JStang DATE      03/30/11        03/30/11          03/16/11           03/31/11                 03/31/11 OFFICIAL RECORD COpy}}

Latest revision as of 01:46, 13 November 2019

Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections
ML110820865
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 03/31/2011
From: Stang J
Plant Licensing Branch II
To: Gillespie P
Duke Energy Carolinas
Stang J, NRR/DORL, 415-1345
References
TAC ME4649
Download: ML110820865 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 31,2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 2, EVALUATION OF 2010 (CYCLE 24)

STEAM GENERATOR (SG) TUBE INSPECTIONS (TAC NO. ME4649)

Dear Mr. Gillespie By letter dated August 27,2010 (Agencywide Documents Access and Management System, Accession No. ML102430530), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of the 2010 SG tube inspections at Oconee Nuclear Station, Unit 2 during the Cycle 24 refueling outage.

The U.S Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staffs review of the reports is enclosed.

Sincerely, ~

~g, senio4ect Manager Plant licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-270

Enclosure:

Evaluation of SG Tube Inspections cc w/encl: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION EVALUATION OF THE 2010 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING THE 2010 REFUELING OUTAGE OCONEE NUCLEAR STATION, UNIT 2 DOCKET NO. 50-270 By letter dated August 27,2010 (Agencywide Documents Access Management System, Accession No. ML102430530), Duke Energy Carolinas, LLC (the licensee), submitted the results of their 2010 steam generator tube inspections performed during the Cycle 24 refueling outage at Oconee Nuclear Station, Unit 2 (Oconee 2).

Oconee 2 is a two-loop pressurized-water reactor with once-through steam generators (OTSGs) manufactured by Babcock & Wilcox (B&W), Canada. The Oconee 2 OTSGs are replacement OTSGs that were installed during the 2004 refueling outage. The OTSGs consist of 15,631 thermally treated Alloy 690 tubes that have been hydraulically expanded into the tubesheets to a depth of 13 inches. There are 15 Type 410 stainless steel tube support plates (TSP) with trefoil shaped holes. However, there are some round drilled openings at the 14th TSP.

Widespread wear degradation of the tubing at TSP locations has been observed at all three Oconee units. The licensee provided the scope, extent, methods, and results of their OTSG tube inspections in the document referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.

The licensee indicated that the following tubes were plugged:

  • OTSG A: 90-124,91-124,99-126, 112-102, 128-87, and 151-16
  • OTSG B: 56-6,79-10,83-8,90-5, 136-11, and 144-50 In addition, the licensee stated that the array data obtained from the x-probe was only reviewed to characterize selected wear indications (i.e., array data was not reviewed at locations such as expansion transitions or dents/dings since only wear degradation is expected).

Based on a review of the information provided, the Nuclear Regulatory Commission staff concludes that the licensee provided the information required by the 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 that inspection results appear to be consistent with industry operating experience at similarly designed and operated units.

Principal Contributor: A. Obodoako, NRR/DCI Date: March 31, 2011 Enclosure

March 31, 2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 2, EVALUATION OF 2010 (CYCLE 24)

STEAM GENERATOR (SG) TUBE INSPECTIONS (TAC NO. ME4649)

Dear Mr. Gillespie By letter dated August 27,2010 (Agencywide Documents Access and Management System, Accession No. ML102430530), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of the 2010 SG tube inspections at Oconee Nuclear Station, Unit 2 during the Cycle 24 refueling outage.

The U.S Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that the licensee provided the information required by their technical specifications and that no additional follow-up is required at this time. The NRC staff's review of the reports is enclosed.

Sincerely, IRA!

John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-270

Enclosure:

Evaluation of SG Tube Inspections cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL2-1 r/f RidsNrrLAMO'Brien Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDciCsgb Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource KKarwoski, NRR/DCI RidsNrrPMOconee Resource AObodoako, NRR/DCI ADAMS A cceSSJon N0.: ML110820865 *M erno su brnl'tted blY Tech Staff dae t d OFFICE NRR/LPL2-1/PM NRR/LPL2-'liLA NRR/DCI/CSGB/BC NRR/LPL2-1/BC NRRILPL2-1/PM NAME JStang MO'Brien RTaylor* GKulesa JStang DATE 03/30/11 03/30/11 03/16/11 03/31/11 03/31/11 OFFICIAL RECORD COpy

Retrieved from "https://kanterella.com/w/index.php?title=ML110820865&oldid=2119958"