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| number = ML12249A193
| number = ML12249A193
| issue date = 09/11/2012
| issue date = 09/11/2012
| title = Review of the 2011 Refueling Outage Steam Generators Tube Inservice Inspection Report (TAC No. ME7764)
| title = Review of the 2011 Refueling Outage Steam Generators Tube Inservice Inspection Report
| author name = Martin R E
| author name = Martin R
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
| addressee name = Ajluni M J
| addressee name = Ajluni M
| addressee affiliation = Southern Nuclear Operating Co, Inc
| addressee affiliation = Southern Nuclear Operating Co, Inc
| docket = 05000424
| docket = 05000424
| license number = NPF-068
| license number = NPF-068
| contact person = MARTIN R E
| contact person = MARTIN R
| case reference number = TAC ME7764
| case reference number = TAC ME7764
| document type = Letter, Inservice/Preservice Inspection and Test Report
| document type = Letter, Inservice/Preservice Inspection and Test Report
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 11,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway P. O. Box 1295, Bin -038 Birmingham, AL 35201-1295 VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 -REVIEW OF THE 2011 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT (TAC NO. ME7764)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 11,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway P. O. Box 1295, Bin - 038 Birmingham, AL 35201-1295 SUB~IECT:      VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 - REVIEW OF THE 2011 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT (TAC NO. ME7764)


==Dear Mr. Ajluni:==
==Dear Mr. Ajluni:==
By letters dated June 30 and September 21, 2011 and July 30, 2012, (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML 111820361, ML 112650199 and ML 12212A335, respectively), Southern Nuclear Operating Company, Inc. submitted information summarizing the results of the Spring 2011 steam generator (SG) tube inspections performed during refueling outage 16 (V1 R16) at Vogtle Electric Generating Plant, Unit 1. The Nuclear Regulatory Commission (NRC) staff has completed its review of the report and concludes that the licensee provided the information required by the technical specifications, and that no additional follow-up is required at this time. The NRC staff's review of the report is enclosed.
Sincerely,
/Robert E.
Senior Project Manager Plant Licensing Branch 11-1 DiviSion of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No.
Inspection Summary cc w/encl: Distribution via UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE 2011 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT SOUTHERN NUCLEAR OPERATING COMPANY, INC. VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 DOCKET NO. 50-424 By letters dated June 30 and September 21, 2011 and July 30, 2012, (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML 111820361, ML 112650199 and ML 12212A335, respectively), Southern Nuclear Operating Company, the licensee, submitted information summarizing the results of the Spring 2011 steam generator (SG) tube inspections performed during refueling outage 16 at VogtJe Electric Generating Plant, Unit 1 (Vogtle 1). Vogtle Electric Generating Plant, Unit 1 has four Westinghouse Model F SGs. Each SG has 5,626 thermally treated Alloy 600 tubes with an outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes installed in rows 1 through 10 was thermally treated after bending in order to reduce stress. The licensee provided the scope, extent, methods and results of the SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging, taken in response to the inspection findings).
The tubes in SGs 1 and 4 were inspected during this outage. Regions susceptible to cracking (e.g., tubesheet, U-bend of row 1 and 2) were inspected in all four SGs. After reviewing the information provided by the licensee, the staff has the following comments/observations: The licensee identified a single axially oriented outside diameter stress corrosion crack (ODSCC) indication in SG 4 in row 8, column 57. It is located below the bottom of the expansion transition and is entirely within the tubesheet.
The tube was plugged. There was no evidence of change in the region of SG 4 affected by the tube pulling operation based on the eddy current bobbin probe data. Enclosure 
-Based on a review of the information provided, the staff concludes that the licensee provided the information required by the Vogtle 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. Principal Contributor:
A. Obodoako, NRR/DCI Date: September 11, 2012 


ML12249A 193
By letters dated June 30 and September 21, 2011 and July 30, 2012, (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111820361, ML112650199 and ML12212A335, respectively), Southern Nuclear Operating Company, Inc. submitted information summarizing the results of the Spring 2011 steam generator (SG) tube inspections performed during refueling outage 16 (V1 R16) at Vogtle Electric Generating Plant, Unit 1.
* Transmitted by memo dated 8/24/12 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/CSGB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME RMartin SFigueroa GKulesa* RPascarelli RMartin DATE 09/10/12 09/05/12 08/24/12 09/11/12 09/11/12}}
The Nuclear Regulatory Commission (NRC) staff has completed its review of the report and concludes that the licensee provided the information required by the technical specifications, and that no additional follow-up is required at this time. The NRC staff's review of the report is enclosed.
Sincerely, ae{kr(M~
                                                  /Robert E. Martrn~ Senior Project Manager Plant Licensing Branch 11-1 DiviSion of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No. 50-424
 
==Enclosure:==
 
Inspection Summary Report cc w/encl: Distribution via Listserv
 
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE 2011 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT SOUTHERN NUCLEAR OPERATING COMPANY, INC.
VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 DOCKET NO. 50-424 By letters dated June 30 and September 21, 2011 and July 30, 2012, (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111820361, ML112650199 and ML12212A335, respectively), Southern Nuclear Operating Company, the licensee, submitted information summarizing the results of the Spring 2011 steam generator (SG) tube inspections performed during refueling outage 16 at VogtJe Electric Generating Plant, Unit 1 (Vogtle 1).
Vogtle Electric Generating Plant, Unit 1 has four Westinghouse Model F SGs. Each SG has 5,626 thermally treated Alloy 600 tubes with an outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes installed in rows 1 through 10 was thermally treated after bending in order to reduce stress.
The licensee provided the scope, extent, methods and results of the SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging, taken in response to the inspection findings). The tubes in SGs 1 and 4 were inspected during this outage. Regions susceptible to cracking (e.g., tubesheet, U-bend of row 1 and 2) were inspected in all four SGs.
After reviewing the information provided by the licensee, the staff has the following comments/observations:
* The licensee identified a single axially oriented outside diameter stress corrosion crack (ODSCC) indication in SG 4 in row 8, column 57. It is located below the bottom of the expansion transition and is entirely within the tubesheet. The tube was plugged.
* There was no evidence of change in the region of SG 4 affected by the tube pulling operation based on the eddy current bobbin probe data.
Enclosure
 
                                                - 2 Based on a review of the information provided, the staff concludes that the licensee provided the information required by the Vogtle 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.
Principal Contributor: A. Obodoako, NRR/DCI Date: September 11, 2012
 
ML12249A193
* Transmitted by memo dated 8/24/12 OFFICE NRR/LPL2-1/PM       NRR/LPL2-1/LA       NRR/CSGB/BC         NRR/LPL2-1/BC       NRR/LPL2-1/PM NAME       RMartin         SFigueroa           GKulesa*           RPascarelli         RMartin DATE       09/10/12         09/05/12             08/24/12           09/11/12           09/11/12}}

Latest revision as of 22:59, 11 November 2019

Review of the 2011 Refueling Outage Steam Generators Tube Inservice Inspection Report
ML12249A193
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 09/11/2012
From: Martin R
Plant Licensing Branch II
To: Ajluni M
Southern Nuclear Operating Co
MARTIN R
References
TAC ME7764
Download: ML12249A193 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 11,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway P. O. Box 1295, Bin - 038 Birmingham, AL 35201-1295 SUB~IECT: VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 - REVIEW OF THE 2011 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT (TAC NO. ME7764)

Dear Mr. Ajluni:

By letters dated June 30 and September 21, 2011 and July 30, 2012, (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111820361, ML112650199 and ML12212A335, respectively), Southern Nuclear Operating Company, Inc. submitted information summarizing the results of the Spring 2011 steam generator (SG) tube inspections performed during refueling outage 16 (V1 R16) at Vogtle Electric Generating Plant, Unit 1.

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

Sincerely, ae{kr(M~

/Robert E. Martrn~ Senior Project Manager Plant Licensing Branch 11-1 DiviSion of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No. 50-424

Enclosure:

Inspection Summary Report cc w/encl: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE 2011 REFUELING OUTAGE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT SOUTHERN NUCLEAR OPERATING COMPANY, INC.

VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 DOCKET NO. 50-424 By letters dated June 30 and September 21, 2011 and July 30, 2012, (Agencywide Documents Access Management System (ADAMS) Accession Nos. ML111820361, ML112650199 and ML12212A335, respectively), Southern Nuclear Operating Company, the licensee, submitted information summarizing the results of the Spring 2011 steam generator (SG) tube inspections performed during refueling outage 16 at VogtJe Electric Generating Plant, Unit 1 (Vogtle 1).

Vogtle Electric Generating Plant, Unit 1 has four Westinghouse Model F SGs. Each SG has 5,626 thermally treated Alloy 600 tubes with an outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes installed in rows 1 through 10 was thermally treated after bending in order to reduce stress.

The licensee provided the scope, extent, methods and results of the SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging, taken in response to the inspection findings). The tubes in SGs 1 and 4 were inspected during this outage. Regions susceptible to cracking (e.g., tubesheet, U-bend of row 1 and 2) were inspected in all four SGs.

After reviewing the information provided by the licensee, the staff has the following comments/observations:

  • The licensee identified a single axially oriented outside diameter stress corrosion crack (ODSCC) indication in SG 4 in row 8, column 57. It is located below the bottom of the expansion transition and is entirely within the tubesheet. The tube was plugged.
  • There was no evidence of change in the region of SG 4 affected by the tube pulling operation based on the eddy current bobbin probe data.

Enclosure

- 2 Based on a review of the information provided, the staff concludes that the licensee provided the information required by the Vogtle 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.

Principal Contributor: A. Obodoako, NRR/DCI Date: September 11, 2012

ML12249A193

  • Transmitted by memo dated 8/24/12 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/CSGB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME RMartin SFigueroa GKulesa* RPascarelli RMartin DATE 09/10/12 09/05/12 08/24/12 09/11/12 09/11/12
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