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| | number = ML15261A598 | | | number = ML15261A598 |
| | issue date = 09/30/2015 | | | issue date = 09/30/2015 |
| | title = Joseph M. Farley Nuclear Plant, Unit 2 - Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2014 Refueling Outage (TAC No. MF6207) | | | title = Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2014 Refueling Outage |
| | author name = Williams S A | | | author name = Williams S |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Pierce C R | | | addressee name = Pierce C |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000364 | | | docket = 05000364 |
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| | page count = 3 | | | page count = 3 |
| | project = TAC:MF6207 | | | project = TAC:MF6207 |
| | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc. P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295 September 30, 2015 SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 -REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2014 REFUELING OUTAGE (TAC NO. MF6207) Dear Mr. Pierce: By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator tube inspections performed at Joseph M. Farley Nuclear Plant, Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML 15240A372). The 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 up is required at this time. The NRC staff's review is enclosed. If you have any questions, please me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov. Docket No. 50-364 Enclosure: As stated cc w/encl: Distribution via Listserv Sincerely, Shawn Williams, Project 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 REVIEW OF THE 2014 STEAM GENERATOR TUBE INSPECTIONS JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 DOCKET No. 50-364 TAC NO. MF6207 By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator (SG) tube inspections performed at Joseph M. Farley Nuclear Plant (Farley), Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML 15240A372). Farley, Unit 2, has three Westinghouse Model 54F replacement steam generators, each containing 3,592 thermally treated Alloy 690 tubes. These SGs were installed in 2001. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by stainless steel tube support plates and stainless steel anti-vibration bars. The licensee provided the scope, extent, methods, and results of the Farley, Unit 2, 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. Based on a review of the information provided by the licensee, 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. Enclosure Mr. C. R. Pierce Regulatory Affairs Director September 30, 2015 Southern Nuclear Operating Co., Inc. P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295 SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 -REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2014 REFUELING OUTAGE (TAC NO. MF6207) Dear Mr. Pierce: By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator tube inspections performed at Joseph M. Farley Nuclear Plant, Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML 15240A372). The 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 up is required at this time. The NRC staff's review is enclosed. If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov. Docket No. 50-364 Enclosure: As stated Sincerely, IRA/ Shawn Williams, Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC RidsNrrDorlDpr Resource RidsNrrLASFigueroa Resource AJohnson, NRR ADAMS A ccess1on N o.: OFFICE LPL2-1/PM NAME SWilliams DATE 9/29/15 LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrDe Resource RidsAcrsAcnw_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource ML 15261A598 *b 1y memo LPL2-1/LA DE/ESGB/BC LPL2-1/BC LPL2-1/PM SFiqueroa GKulesa* RPascarelli SWilliams 9/29/15 9/16/15 9/2915 9/30/15 OFFICIAL RECORD COPY | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 30, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc. |
| }} | | P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 - REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2014 REFUELING OUTAGE (TAC NO. MF6207) |
| | |
| | ==Dear Mr. Pierce:== |
| | |
| | By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator tube inspections performed at Joseph M. Farley Nuclear Plant, Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML15240A372). |
| | The 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 is enclosed. |
| | If you have any questions, please me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov. |
| | Sincerely, Shawn Williams, Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REVIEW OF THE 2014 STEAM GENERATOR TUBE INSPECTIONS JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 DOCKET No. 50-364 TAC NO. MF6207 By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator (SG) tube inspections performed at Joseph M. Farley Nuclear Plant (Farley), Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML15240A372). |
| | Farley, Unit 2, has three Westinghouse Model 54F replacement steam generators, each containing 3,592 thermally treated Alloy 690 tubes. These SGs were installed in 2001. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by stainless steel tube support plates and stainless steel anti-vibration bars. |
| | The licensee provided the scope, extent, methods, and results of the Farley, Unit 2, 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. |
| | Based on a review of the information provided by the licensee, 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. |
| | Enclosure |
| | |
| | ML15240A372). |
| | The 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 is enclosed. |
| | If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov. |
| | Sincerely, IRA/ |
| | Shawn Williams, Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsNrrDe Resource RidsNrrPMFarley Resource AJohnson, NRR ADAMS A ccess1on No.: ML15261A598 *b1y memo OFFICE LPL2-1/PM LPL2-1/LA DE/ESGB/BC LPL2-1/BC LPL2-1/PM NAME SWilliams SFiqueroa GKulesa* RPascarelli SWilliams DATE 9/29/15 9/29/15 9/16/15 9/2915 9/30/15}} |
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Category:Letter
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in 05000348/LER-2024-002-01, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 05000348/LER-2024-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 05000364/LER-2024-002, For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 For Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 2024-09-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 30, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 - REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2014 REFUELING OUTAGE (TAC NO. MF6207)
Dear Mr. Pierce:
By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator tube inspections performed at Joseph M. Farley Nuclear Plant, Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML15240A372).
The 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 is enclosed.
If you have any questions, please me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Sincerely, Shawn Williams, Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364
Enclosure:
As stated cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REVIEW OF THE 2014 STEAM GENERATOR TUBE INSPECTIONS JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 DOCKET No. 50-364 TAC NO. MF6207 By letter dated May 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15131A333), Southern Nuclear Operating Company, Inc. (the licensee), submitted information summarizing the results of the 2014 steam generator (SG) tube inspections performed at Joseph M. Farley Nuclear Plant (Farley), Unit 2. These inspections were performed during refueling outage 23. The licensee provided additional information concerning the inspections in a letter dated August 28, 2015 (ADAMS Accession No. ML15240A372).
Farley, Unit 2, has three Westinghouse Model 54F replacement steam generators, each containing 3,592 thermally treated Alloy 690 tubes. These SGs were installed in 2001. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by stainless steel tube support plates and stainless steel anti-vibration bars.
The licensee provided the scope, extent, methods, and results of the Farley, Unit 2, 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.
Based on a review of the information provided by the licensee, 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.
Enclosure
ML15240A372).
The 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 is enclosed.
If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Sincerely, IRA/
Shawn Williams, Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsNrrDe Resource RidsNrrPMFarley Resource AJohnson, NRR ADAMS A ccess1on No.: ML15261A598 *b1y memo OFFICE LPL2-1/PM LPL2-1/LA DE/ESGB/BC LPL2-1/BC LPL2-1/PM NAME SWilliams SFiqueroa GKulesa* RPascarelli SWilliams DATE 9/29/15 9/29/15 9/16/15 9/2915 9/30/15