|
|
(4 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML11187A002 | | | number = ML11187A002 |
| | issue date = 07/11/2011 | | | issue date = 07/11/2011 |
| | title = Catawba Nuclear Station, Unit 1 - Review of the 2008 Steam Generator Tube Inspections During Refueling Outage 17 End of Cycle (TAC No. ME5751) | | | title = Review of the 2008 Steam Generator Tube Inspections During Refueling Outage 17 End of Cycle |
| | author name = Thompson J H | | | author name = Thompson J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Morris J R | | | addressee name = Morris J |
| | addressee affiliation = Duke Energy Carolinas, LLC | | | addressee affiliation = Duke Energy Carolinas, LLC |
| | docket = 05000413 | | | docket = 05000413 |
| | license number = NPF-035 | | | license number = NPF-035 |
| | contact person = Thompson J H, NRR/DORL/LPL2-1, 415-1119 | | | contact person = Thompson J, NRR/DORL/LPL2-1, 415-1119 |
| | case reference number = TAC ME5751 | | | case reference number = TAC ME5751 |
| | document type = Letter, Safety Evaluation | | | document type = Letter, Safety Evaluation |
| | page count = 4 | | | page count = 4 |
| | project = TAC:ME5751 | | | project = TAC:ME5751 |
| | stage = Other | | | stage = Approval |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11, 2011 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745 |
| | |
| | ==SUBJECT:== |
| | CATAWBA NUCLEAR STATION, UNIT 1 (CATAWBA 1) - REVIEW OF THE 2008 STEAM GENERATOR (SG) TUBE INSPECTIONS DURING REFUELING OUTAGE 17 END OF CYCLE (EOC 17) (TAC NO. ME5751) |
| | |
| | ==Dear Mr. Morris:== |
| | |
| | By letter dated September 4,2008 (Agencywide Documents Access and Management System, Accession No. ML092750008), Duke Energy Carolinas. LLC (the licensee). submitted information summarizing the results of the 2008 SG tube inspections at Catawba 1. These inspections were performed during EOC 17. The Nuclear Regulatory Commission (NRC) staff conducted a conference call with the licensee on April 28. 2011, a summary of which is enclosed within, to clarify a few items in this letter. |
| | The NRC staff has completed its review of the submittal and concludes that the licensee provided the information required by the Catawba 1 Technical SpeCifications. No additional follow up is required at this time. The NRC staff's review of the letter dated September 4, 2008. |
| | is enclosed. |
| | If you have any questions, please call me at 301-415-1119. |
| | Sincerely. |
| | Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-413 |
| | |
| | ==Enclosure:== |
| | |
| | Staff Evaluation 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 2008 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 17 CATAWBA NUCLEAR STATION, UNIT 1 DOCKET NO. 50-413 By letter dated September 4, 2008 (Agencywide Documents Access and Management System, Accession No. ML092750008), Duke Energy Carolinas, LLC, (Duke, the licensee), submitted information summarizing the results of the 2008 steam generator (SG) tube inspections at Catawba Nuclear Station, Unit 1 (Catawba 1). The U.S. Nuclear Regulatory Commission (NRC) staff held a follow-up phone call on April 28, 2011, with the licensee to clarify a few minor pOints of information, the details of which are summarized below. |
| | Catawba 1 has four replacement model CFR 80 SGs, installed in 1996, designed and fabricated by Babcock and Wilcox International (BWI). Each SG has 6633 thermally treated Alloy 690 tubes that have an outside diameter of 0.6875 inch and a nominal wall thickness of 0.040 inch. |
| | The tubes were hydraulically expanded at each end for the full depth of the tubesheet. The tubesheet is 27.1 inches thick with the clad. The tubes are supported by lattice grid tube supports and fan/connector bars. All supports are constructed from Type 410 stainless steel. |
| | 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 (e.g., |
| | tube plugging) taken in response to the inspection findings. On April 28, 2011, the licensee provided the following additional clarifying information via a phone conference with the NRC staff: |
| | : 1. A tube plug inspection was performed on each SG with no degradation noted. |
| | : 2. Secondary side inspections performed in each SG included: |
| | : a. Sludge lancing in each SG. |
| | : b. Top of tube sheet inspections at the hot and cold leg. 86 loose parts total were found in all four SGs. Twenty-eight loose parts were able to be removed. Of the remaining parts left in the SGs, three loose parts, believed to be flexatallic gasket pieces, were in SG C and SG D, required 23 total tubes to be preventatively plugged. An analysis performed by the SG vender determined that the remaining 58 parts left in the SGs would not challenge tube integrity during the next operating cycle. |
| | Enclosure |
| | |
| | - 2 |
| | : 3. The cumulative effective full power years since SG replacement for EOC16 and EOC17 are 9.19 and 10.52, respectively. |
| | : 4. The following tubes were plugged in SG C: |
| | Row Column Row Column 98 43 99 42 99 44 100 43 101 42 101 44 102 41 102 43 103 42 104 43 The following tubes were plugged in SG D: |
| | Row 108 Column 83 Row 109 I Column 110 73 110 111 74 111 84 112 73 112 83 113 74 113 84 114 73 114 83 115 74 |
| | : 5. The nature of indications in the tube located in row 97, column 86, in SG C, was determined to be loose part wear with no part present at the time of inspection. |
| | Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the NRC 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: C. Hunt Date: July 11, 2011 |
| | |
| | ML 11187AOO2 'no significant change to memo dated 6/13/11 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlCSGB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME JThompson MOBrien RTaylor* GKulesa (JStang for) JThompson DATE 7/11/11 7/11/11 6/13/11 7/11/11 7/11/11}} |
Letter Sequence Approval |
---|
|
|
MONTHYEARML11187A0022011-07-11011 July 2011 Review of the 2008 Steam Generator Tube Inspections During Refueling Outage 17 End of Cycle Project stage: Approval 2011-07-11
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Safety Evaluation
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22213A2532022-08-31031 August 2022 Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML22007A3452022-01-11011 January 2022 Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21266A0112021-10-0505 October 2021 Staff Evaluation Related to Aging Management Program and Inspection Plan of Reactor Vessel Internals Per MRP-227, Revision 1-A ML21253A0822021-09-20020 September 2021 Proposed Alternative Request RA-21-0145 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20174A0452020-08-0404 August 2020 Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits ML19296D1192020-01-31031 January 2020 Issuance of Amendment Nos. 305 and 301 to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19212A6552019-08-27027 August 2019 Issuance of Amendment Nos. 304 and 300 to Technical Specification 3.8.1, AC Sources - Operating ML19191A0612019-07-15015 July 2019 Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2018 Refueling Outage 24 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19121A5512019-06-17017 June 2019 Issuance of Amendments Related to the Removal of Containment Valve Injection Water System Supply from Specified Containment Isolation Valves ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18275A2782018-11-28028 November 2018 Issuance of Amendments Related to the Nuclear Service Water System New Condition for Single Pond Return Header Configuration ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18016A1782018-01-24024 January 2018 Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) ML17296A2082018-01-0404 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF8971 & MF8972, EPID L-2016-LLA-0026) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17261B2902017-10-23023 October 2017 Issuance of Amendment Nos. 296 and 292, Adopt TSTF-142-A, Revision 0, Increase the Completion Time When the Core Reactivity Balance Is Not within Limit (CAC Nos. MF8962 and MF8963); EPID L-2017-LLA-0024 ML17257A2972017-10-23023 October 2017 Issuance of Amendment Nos. 295 and 291, Adoption of TSTF-340-A, Revision 3, Allow 7-Day Completion Time for a Turbine-Driven AFW Pump Inoperable (CAC Nos. MF8979 and MF8980; EPID L-2017-LLA-0043) ML17254A1442017-10-23023 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 (CAC Nos. MF8969 and MF8970; EPID L-2017-LLA-0031) ML17249A1352017-09-29029 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Travelers TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17172A4282017-07-26026 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-315-A, Revision 0 ML17165A4412017-07-21021 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF8983 and MF8984). 08/10/2017 ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16137A3082017-02-0808 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805 ML16277A4042016-10-20020 October 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16208A2832016-08-0808 August 2016 Correction to Issuance of Amendments Regarding Use of Optimized Zirlo ML16159A3362016-07-19019 July 2016 Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486) ML16105A3262016-06-21021 June 2016 Issuance of Amendments Regarding Use of Optimized Zirlo ML16124A6942016-06-0202 June 2016 Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2023-09-25
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11, 2011 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 1 (CATAWBA 1) - REVIEW OF THE 2008 STEAM GENERATOR (SG) TUBE INSPECTIONS DURING REFUELING OUTAGE 17 END OF CYCLE (EOC 17) (TAC NO. ME5751)
Dear Mr. Morris:
By letter dated September 4,2008 (Agencywide Documents Access and Management System, Accession No. ML092750008), Duke Energy Carolinas. LLC (the licensee). submitted information summarizing the results of the 2008 SG tube inspections at Catawba 1. These inspections were performed during EOC 17. The Nuclear Regulatory Commission (NRC) staff conducted a conference call with the licensee on April 28. 2011, a summary of which is enclosed within, to clarify a few items in this letter.
The NRC staff has completed its review of the submittal and concludes that the licensee provided the information required by the Catawba 1 Technical SpeCifications. No additional follow up is required at this time. The NRC staff's review of the letter dated September 4, 2008.
is enclosed.
If you have any questions, please call me at 301-415-1119.
Sincerely.
Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-413
Enclosure:
Staff Evaluation 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 2008 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 17 CATAWBA NUCLEAR STATION, UNIT 1 DOCKET NO. 50-413 By letter dated September 4, 2008 (Agencywide Documents Access and Management System, Accession No. ML092750008), Duke Energy Carolinas, LLC, (Duke, the licensee), submitted information summarizing the results of the 2008 steam generator (SG) tube inspections at Catawba Nuclear Station, Unit 1 (Catawba 1). The U.S. Nuclear Regulatory Commission (NRC) staff held a follow-up phone call on April 28, 2011, with the licensee to clarify a few minor pOints of information, the details of which are summarized below.
Catawba 1 has four replacement model CFR 80 SGs, installed in 1996, designed and fabricated by Babcock and Wilcox International (BWI). Each SG has 6633 thermally treated Alloy 690 tubes that have an outside diameter of 0.6875 inch and a nominal wall thickness of 0.040 inch.
The tubes were hydraulically expanded at each end for the full depth of the tubesheet. The tubesheet is 27.1 inches thick with the clad. The tubes are supported by lattice grid tube supports and fan/connector bars. All supports are constructed from Type 410 stainless steel.
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 (e.g.,
tube plugging) taken in response to the inspection findings. On April 28, 2011, the licensee provided the following additional clarifying information via a phone conference with the NRC staff:
- 1. A tube plug inspection was performed on each SG with no degradation noted.
- 2. Secondary side inspections performed in each SG included:
- a. Sludge lancing in each SG.
- b. Top of tube sheet inspections at the hot and cold leg. 86 loose parts total were found in all four SGs. Twenty-eight loose parts were able to be removed. Of the remaining parts left in the SGs, three loose parts, believed to be flexatallic gasket pieces, were in SG C and SG D, required 23 total tubes to be preventatively plugged. An analysis performed by the SG vender determined that the remaining 58 parts left in the SGs would not challenge tube integrity during the next operating cycle.
Enclosure
- 2
- 3. The cumulative effective full power years since SG replacement for EOC16 and EOC17 are 9.19 and 10.52, respectively.
- 4. The following tubes were plugged in SG C:
Row Column Row Column 98 43 99 42 99 44 100 43 101 42 101 44 102 41 102 43 103 42 104 43 The following tubes were plugged in SG D:
Row 108 Column 83 Row 109 I Column 110 73 110 111 74 111 84 112 73 112 83 113 74 113 84 114 73 114 83 115 74
- 5. The nature of indications in the tube located in row 97, column 86, in SG C, was determined to be loose part wear with no part present at the time of inspection.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the NRC 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: C. Hunt Date: July 11, 2011
ML 11187AOO2 'no significant change to memo dated 6/13/11 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlCSGB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME JThompson MOBrien RTaylor* GKulesa (JStang for) JThompson DATE 7/11/11 7/11/11 6/13/11 7/11/11 7/11/11