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| number = ML17219A016
| number = ML17219A016
| issue date = 08/14/2017
| issue date = 08/14/2017
| title = Catawba Nuclear Station, Unit 2 - Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2016 Refueling Outage 21 (CAC No. MF9079)
| title = Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2016 Refueling Outage 21
| author name = Mahoney M
| author name = Mahoney M
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Tom Simril Site Vice President Catawba Nuclear Station, Unit 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 297 45 August 14, 2017
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 14, 2017 Mr. Tom Simril Site Vice President Catawba Nuclear Station, Unit 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745


==SUBJECT:==
==SUBJECT:==
CATAWBA NUCLEAR STATION, UNIT 2-REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2016 REFUELING OUTAGE 21 (CAC NO. MF9079)  
CATAWBA NUCLEAR STATION, UNIT 2- REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2016 REFUELING OUTAGE 21 (CAC NO. MF9079)


==Dear Mr. Simril:==
==Dear Mr. Simril:==
By letter dated January 6, 2017 (Agencywide Documents Access and Management System, (ADAMS) Accession No. ML 1701 OA282), as supplemented by letter dated May 24, 2017 (ADAMS Accession No. ML 17146A907), Duke Energy Carolinas, LLC (the licensee) submitted information summarizing the results of their fall 2016 steam generator (SG) tube inservice inspections at the Catawba Nuclear Station (Catawba), Unit 2. These inspections were performed during refueling outage 21. The U. S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information and concludes that the licensee has provided the information required by _the Catawba, Unit 2, Technical Specifications. No additional follow up is necessary at this time. The NRC staff's review of the SG inspection report is enclosed. If you have any questions, please contact me at 301-415-3867 or via e-mail at Michael. Mahoney@nrc.gov. Docket Nos. 50-414  
 
By letter dated January 6, 2017 (Agencywide Documents Access and Management System, (ADAMS) Accession No. ML 1701 OA282), as supplemented by letter dated May 24, 2017 (ADAMS Accession No. ML17146A907), Duke Energy Carolinas, LLC (the licensee) submitted information summarizing the results of their fall 2016 steam generator (SG) tube inservice inspections at the Catawba Nuclear Station (Catawba), Unit 2. These inspections were performed during refueling outage 21.
The U. S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information and concludes that the licensee has provided the information required by _the Catawba, Unit 2, Technical Specifications. No additional follow up is necessary at this time.
The NRC staff's review of the SG inspection report is enclosed.
If you have any questions, please contact me at 301-415-3867 or via e-mail at Michael. Mahoney@nrc.gov.
Since;el,Y.  ,    .
0M;f//1
                                            ..  *.* I            /
Michael Mahoney, P Ject Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-414


==Enclosure:==
==Enclosure:==
As stated cc w/encl: Distribution via ListServ Since;el,Y. , . 0M;f//1 .. *.* I / Michael Mahoney, P Ject Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RESULTS OF THE 2016 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNIT 2 DOCKET NO. 50-414 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated January 6, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No .. ML 1701 OA282), as supplemented by letter dated May 24, 2017 (ADAMS Accession No. ML 17146A907), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of their fall 2016 steam generator (SG) tube inservice inspections. The inspections were performed during the end of cycle 21 refueling outage (RFO) at the Catawba Nuclear Station (Catawba), Unit 2. Catawba, Unit 2, has four Westinghouse model D5 SGs, which are designated 2A through 2D. Each SG has 4,570 thermally treated Alloy 600 tubes with a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by Type 405 stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes in rows 1 through 9 was thermally treated after bending, in order to reduce stress. The licensee provided the scope, extent, methods, and results of their 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.
 
As stated cc w/encl: Distribution via ListServ
 
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RESULTS OF THE 2016 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNIT 2 DOCKET NO. 50-414 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated January 6, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No ..
ML 1701 OA282), as supplemented by letter dated May 24, 2017 (ADAMS Accession No. ML17146A907), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of their fall 2016 steam generator (SG) tube inservice inspections. The inspections were performed during the end of cycle 21 refueling outage (RFO) at the Catawba Nuclear Station (Catawba), Unit 2.
Catawba, Unit 2, has four Westinghouse model D5 SGs, which are designated 2A through 2D.
Each SG has 4,570 thermally treated Alloy 600 tubes with a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by Type 405 stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes in rows 1 through 9 was thermally treated after bending, in order to reduce stress.
The licensee provided the scope, extent, methods, and results of their 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.
* At the end of operational cycle 18 (i.e., in RFO 18), the replacement SGs had 21.50 cumulative effective full power years (EFPY) of operation. In RFO 19, RFO 20, and RFO 21, the replacement SGs had 22.89, 24.24, and 25.67 EFPY of operation, respectively.
* At the end of operational cycle 18 (i.e., in RFO 18), the replacement SGs had 21.50 cumulative effective full power years (EFPY) of operation. In RFO 19, RFO 20, and RFO 21, the replacement SGs had 22.89, 24.24, and 25.67 EFPY of operation, respectively.
* During RFO 21, the licensee plugged 16 tubes in SG 2A, 13 tubes in SG 28, 12 tubes in SG 2C, and six tubes in SG 2D for a total of 47 plugged tubes in all SGs. In response to the NRC staff's request for additional information dated April 25, 2017 (ADAMS Accession No. ML 17115A142), the licensee clarified in their letter dated May 24, 2017, the number of plugged tubes in SG 2C. All but four tubes were high stress (2-sigma) tubes that were plugged preventatively since the licensee plans to skip inspection during RFO 22. The remaining four tubes were located either adjacent to, or downstream of a foreign object. No new foreign objects were identified in the SGs during RFO 21. Enclosure
* During RFO 21, the licensee plugged 16 tubes in SG 2A, 13 tubes in SG 28, 12 tubes in SG 2C, and six tubes in SG 2D for a total of 47 plugged tubes in all SGs. In response to the NRC staff's request for additional information dated April 25, 2017 (ADAMS Accession No. ML17115A142), the licensee clarified in their letter dated May 24, 2017, the number of plugged tubes in SG 2C. All but four tubes were high stress (2-sigma) tubes that were plugged preventatively since the licensee plans to skip inspection during RFO 22. The remaining four tubes were located either adjacent to, or downstream of a foreign object. No new foreign objects were identified in the SGs during RFO 21.
* During the SG bowl cladding inspections, the licensee identified an area of missing stainless steel cladding in the SG 2D hot leg channel head. The irregularly shaped area is approximately 5 1 /8 inches long and 15/16 inches wide. The original equipment manufacturer performed an evaluation of the area and concluded that grinding activities in this region during fabrication resulted in very thin cladding and/or exposed base metal.
Enclosure
* During the SG bowl cladding inspections, the licensee identified an area of missing stainless steel cladding in the SG 2D hot leg channel head. The irregularly shaped area is approximately 5 1/8 inches long and 15/16 inches wide. The original equipment manufacturer performed an evaluation of the area and concluded that grinding activities in this region during fabrication resulted in very thin cladding and/or exposed base metal.
* The licensee's evaluation determined that it was not credible for a large fragment of cladding to break away and enter the reactor coolant system. The thinned cladding area was not repaired since analysis supported operation until the next refueling outage. This area of the 2D SG channel head will be re-inspected during the next steam generator inspection.
* The licensee's evaluation determined that it was not credible for a large fragment of cladding to break away and enter the reactor coolant system. The thinned cladding area was not repaired since analysis supported operation until the next refueling outage. This area of the 2D SG channel head will be re-inspected during the next steam generator inspection.
* No degradation was detected during the upper bundle visual inspection in SG 2A.
* No degradation was detected during the upper bundle visual inspection in SG 2A.
* No primary to secondary leakage was detected during operating cycle 21 and the calculated leakage rate from the portion of the tubes more than 14.01 inches from the top of the tubesheet was zero. Based on the above, the NRC staff concludes that the licensee provided the information required by their Technical Specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time. 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: P. Klein, NRR Dated: August 14, 2017
* No primary to secondary leakage was detected during operating cycle 21 and the calculated leakage rate from the portion of the tubes more than 14.01 inches from the top of the tubesheet was zero.
Based on the above, the NRC staff concludes that the licensee provided the information required by their Technical Specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time. 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: P. Klein, NRR Dated: August 14, 2017


ML17219A016 *Via Memo Dated OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1 /LA NRR/DLR/RCCB/BC NRR/DORL/LPL2-1 /BC NAME MMahoney KGoldstein SBloom* MMarkley DATE 08/01/2017 08/10/2017 07/26/2017 08/11/2017 OFFICE NRR/DORL/LPL2-1 /PM NAME MMahoney DATE 08/14/2017}}
ML17219A016                                         *Via Memo Dated OFFICE   NRR/DORL/LPL2-1 /PM   NRR/DORL/LPL2-1 /LA   NRR/DLR/RCCB/BC     NRR/DORL/LPL2-1 /BC NAME     MMahoney             KGoldstein           SBloom*             MMarkley DATE     08/01/2017           08/10/2017           07/26/2017           08/11/2017 OFFICE   NRR/DORL/LPL2-1 /PM NAME     MMahoney DATE     08/14/2017}}

Latest revision as of 13:50, 4 February 2020

Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2016 Refueling Outage 21
ML17219A016
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 08/14/2017
From: Michael Mahoney
Plant Licensing Branch II
To: Simril T
Duke Energy Carolinas
Mahoney M, NRR/DORL/LPLII-1, 415-3867
References
CAC MF9079
Download: ML17219A016 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 14, 2017 Mr. Tom Simril Site Vice President Catawba Nuclear Station, Unit 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNIT 2- REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2016 REFUELING OUTAGE 21 (CAC NO. MF9079)

Dear Mr. Simril:

By letter dated January 6, 2017 (Agencywide Documents Access and Management System, (ADAMS) Accession No. ML 1701 OA282), as supplemented by letter dated May 24, 2017 (ADAMS Accession No. ML17146A907), Duke Energy Carolinas, LLC (the licensee) submitted information summarizing the results of their fall 2016 steam generator (SG) tube inservice inspections at the Catawba Nuclear Station (Catawba), Unit 2. These inspections were performed during refueling outage 21.

The U. S. Nuclear Regulatory Commission (NRC) staff has completed its review of the information and concludes that the licensee has provided the information required by _the Catawba, Unit 2, Technical Specifications. No additional follow up is necessary at this time.

The NRC staff's review of the SG inspection report is enclosed.

If you have any questions, please contact me at 301-415-3867 or via e-mail at Michael. Mahoney@nrc.gov.

Since;el,Y. , .

0M;f//1

.. *.* I /

Michael Mahoney, P Ject Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-414

Enclosure:

As stated cc w/encl: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RESULTS OF THE 2016 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNIT 2 DOCKET NO. 50-414 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated January 6, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No ..

ML 1701 OA282), as supplemented by letter dated May 24, 2017 (ADAMS Accession No. ML17146A907), Duke Energy Carolinas, LLC (the licensee), submitted information summarizing the results of their fall 2016 steam generator (SG) tube inservice inspections. The inspections were performed during the end of cycle 21 refueling outage (RFO) at the Catawba Nuclear Station (Catawba), Unit 2.

Catawba, Unit 2, has four Westinghouse model D5 SGs, which are designated 2A through 2D.

Each SG has 4,570 thermally treated Alloy 600 tubes with a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. The tubes are hydraulically expanded for the full-depth of the tubesheet at each end. The tubes are supported by Type 405 stainless steel support plates with quatrefoil-shaped holes. The U-bend region of the tubes in rows 1 through 9 was thermally treated after bending, in order to reduce stress.

The licensee provided the scope, extent, methods, and results of their 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.

  • At the end of operational cycle 18 (i.e., in RFO 18), the replacement SGs had 21.50 cumulative effective full power years (EFPY) of operation. In RFO 19, RFO 20, and RFO 21, the replacement SGs had 22.89, 24.24, and 25.67 EFPY of operation, respectively.
  • During RFO 21, the licensee plugged 16 tubes in SG 2A, 13 tubes in SG 28, 12 tubes in SG 2C, and six tubes in SG 2D for a total of 47 plugged tubes in all SGs. In response to the NRC staff's request for additional information dated April 25, 2017 (ADAMS Accession No. ML17115A142), the licensee clarified in their letter dated May 24, 2017, the number of plugged tubes in SG 2C. All but four tubes were high stress (2-sigma) tubes that were plugged preventatively since the licensee plans to skip inspection during RFO 22. The remaining four tubes were located either adjacent to, or downstream of a foreign object. No new foreign objects were identified in the SGs during RFO 21.

Enclosure

  • During the SG bowl cladding inspections, the licensee identified an area of missing stainless steel cladding in the SG 2D hot leg channel head. The irregularly shaped area is approximately 5 1/8 inches long and 15/16 inches wide. The original equipment manufacturer performed an evaluation of the area and concluded that grinding activities in this region during fabrication resulted in very thin cladding and/or exposed base metal.
  • The licensee's evaluation determined that it was not credible for a large fragment of cladding to break away and enter the reactor coolant system. The thinned cladding area was not repaired since analysis supported operation until the next refueling outage. This area of the 2D SG channel head will be re-inspected during the next steam generator inspection.
  • No degradation was detected during the upper bundle visual inspection in SG 2A.
  • No primary to secondary leakage was detected during operating cycle 21 and the calculated leakage rate from the portion of the tubes more than 14.01 inches from the top of the tubesheet was zero.

Based on the above, the NRC staff concludes that the licensee provided the information required by their Technical Specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time. 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: P. Klein, NRR Dated: August 14, 2017

ML17219A016 *Via Memo Dated OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1 /LA NRR/DLR/RCCB/BC NRR/DORL/LPL2-1 /BC NAME MMahoney KGoldstein SBloom* MMarkley DATE 08/01/2017 08/10/2017 07/26/2017 08/11/2017 OFFICE NRR/DORL/LPL2-1 /PM NAME MMahoney DATE 08/14/2017

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