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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 NL-22-0365, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1R30 NL-21-0905, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1R292022-01-26026 January 2022 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1R29 NL-19-1491, Update to the Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval2019-12-0909 December 2019 Update to the Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval NL-19-0726, Inservice Inspection Program Owner'S Activity Report for Outage 2R252019-06-17017 June 2019 Inservice Inspection Program Owner'S Activity Report for Outage 2R25 NL-19-0317, Submittal of Fifth Ten-Year Interval Lnservice Testing Program Update2019-04-0202 April 2019 Submittal of Fifth Ten-Year Interval Lnservice Testing Program Update NL-17-1194, Submittal of Response to Request for Information Fourth Interval Relief Requests RR-13, RR-14, RR-18, RR19, RR-23, and RR-242017-07-10010 July 2017 Submittal of Response to Request for Information Fourth Interval Relief Requests RR-13, RR-14, RR-18, RR19, RR-23, and RR-24 NL-17-0951, Inservice Inspection Program, Owner'S Activity Report for Outage 2R242017-05-30030 May 2017 Inservice Inspection Program, Owner'S Activity Report for Outage 2R24 NL-16-2707, Units 1 and 2; Fourth 10-year Interval In-service Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements (NL-16-2707)2016-12-27027 December 2016 Units 1 and 2; Fourth 10-year Interval In-service Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements (NL-16-2707) ND-16-1437, Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval2016-08-24024 August 2016 Snubber Program Plan for the Fifth Ten-Year Inservice Testing Interval NL-16-0795, Inservice Inspection Program - Owner'S Activity Report for Outage IR272016-06-0101 June 2016 Inservice Inspection Program - Owner'S Activity Report for Outage IR27 NL-16-0421, Full Structural Weld Overlays on Reactor Recirculation and Residual Heat Removal Systems, Nondestructive Examination Results - Spring 2016 Outage (1R27)2016-03-17017 March 2016 Full Structural Weld Overlays on Reactor Recirculation and Residual Heat Removal Systems, Nondestructive Examination Results - Spring 2016 Outage (1R27) NL-15-1096, Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval2015-06-18018 June 2015 Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval NL-15-1032, E. I. Hatch, Unit 2 - Inservice Inspection Program Owner'S Activity Report for Outage 2R232015-06-12012 June 2015 E. I. Hatch, Unit 2 - Inservice Inspection Program Owner'S Activity Report for Outage 2R23 NL-15-0784, Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval2015-05-0404 May 2015 Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval NL-14-1821, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 - Supplemental Information2014-11-13013 November 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 - Supplemental Information NL-14-1276, Snubber Inspection Plan Submittal in Accordance with ASME OM Code2014-10-31031 October 2014 Snubber Inspection Plan Submittal in Accordance with ASME OM Code NL-14-1250, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.02014-09-19019 September 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0 NL-14-0840, Lnservice Inspection Program Owner'S Activity Report for Outage 1R262014-06-0303 June 2014 Lnservice Inspection Program Owner'S Activity Report for Outage 1R26 NL-14-0231, Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 1.02014-03-0606 March 2014 Proposed Inservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 1.0 NL-12-1266, Inservice Inspection Program, Owner'S Activity Report for Outage 1R252012-06-14014 June 2012 Inservice Inspection Program, Owner'S Activity Report for Outage 1R25 NL-10-0989, Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Requests2010-07-0808 July 2010 Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Requests NL-10-1023, Inservice Inspection Program, Owner'S Activity Report for Outage 1R242010-06-11011 June 2010 Inservice Inspection Program, Owner'S Activity Report for Outage 1R24 NL-08-1798, Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Request RR-012008-12-19019 December 2008 Fourth 10-Year Interval Lnservice Inspection Program Submittal of Relief Request RR-01 NL-08-0901, Unit 1, Inservice Inspection Program Owner'S Activity Report for Outage 1R23 and Structural Integrity Design Report for the N9 CRD Nozzle-to-Cap Full Structural Weld Overlay2008-06-13013 June 2008 Unit 1, Inservice Inspection Program Owner'S Activity Report for Outage 1R23 and Structural Integrity Design Report for the N9 CRD Nozzle-to-Cap Full Structural Weld Overlay NL-07-0987, Fourth Interval Inspection (ISI) Plan Correction2007-05-0909 May 2007 Fourth Interval Inspection (ISI) Plan Correction NL-07-0802, Response to Request for Additional Information Regarding the Third 10-Year Interval Inservice Inspection (ISI) Relief Requests2007-04-13013 April 2007 Response to Request for Additional Information Regarding the Third 10-Year Interval Inservice Inspection (ISI) Relief Requests ML0704300922006-11-20020 November 2006 E. I. Hatch, Unit 2, Volume 1, Revision 2, Introduction Fourth Ten-Year Examination Plan. ML0704301002006-11-20020 November 2006 E. I. Hatch, Unit 2, Volume 3, Revision 1.0, Class 1, 2 and 3 Figures Fourth Ten-Year Inservice Inspection Plan. ML0704300942006-11-20020 November 2006 E. I. Hatch, Unit 2, Volume 2, Revision 1, Class 1, 2 and 3 Components Fourth Ten-Year Examination Plan. ML0704301012006-08-10010 August 2006 E. I. Hatch, Unit 2, Version 1.0, Pressure Test Section Fourth Ten-Year Examination Plan. NL-06-1358, Inservice Inspection Program, Owner'S Activity Report for Outage 1R222006-06-29029 June 2006 Inservice Inspection Program, Owner'S Activity Report for Outage 1R22 ML0704300812006-02-0606 February 2006 E. I. Hatch, Unit 1, Volume 1, Revision 1, Introduction Fourth Ten-Year Inservice Inspection Plan. ML0704300832006-02-0606 February 2006 E. I. Hatch, Unit 1, Volume 2, Revision 1, Class 1, 2 and 3 Components Fourth Ten-Year Inservice Inspection Plan. ML0704300872006-02-0606 February 2006 E. I. Hatch, Unit 1, Volume 3, Revision 1, Class 1, 2 and 3 Figures, Fourth Ten-Year Inservice Inspection Plan. ML0704300962005-08-31031 August 2005 E. I. Hatch, Unit 1, Version 1.0, Pressure Test Section Fourth Ten-Year Examination Plan. NL-05-1190, Fourth 10-Year Interval Inservice Testing (Ist)Program Updates Submittal for Edwin I. Hatch Nuclear Plant2005-07-11011 July 2005 Fourth 10-Year Interval Inservice Testing (Ist)Program Updates Submittal for Edwin I. Hatch Nuclear Plant ML0516403852005-06-0707 June 2005 Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report NL-04-0813, Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report2004-06-0707 June 2004 Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report NL-04-0478, Third 10-Year Interval Inservice Inspection Program Submittal of Relief Requests (RR) RR-38, RR-39, and RR-402004-03-29029 March 2004 Third 10-Year Interval Inservice Inspection Program Submittal of Relief Requests (RR) RR-38, RR-39, and RR-40 NL-03-1380, Third 10-Year Interval Inservice Testing Program, Submittal of Relief Requests RR-V-182003-07-11011 July 2003 Third 10-Year Interval Inservice Testing Program, Submittal of Relief Requests RR-V-18 ML0230903562002-11-0101 November 2002 Third 10-Year Interval Inservice Inspection (ISI) Program, Revision of Relief Request RR-11 ML0228200262002-10-0404 October 2002 Third 10-Year Interval Inservice Inspection Program, Response to Request for Additional Information (RAI) ML0226604362002-09-17017 September 2002 Third 10-Year Interval Inservice Inspection Program Owner'S Activity Report 2024-07-09
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0357, Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines2024-10-30030 October 2024 Notification of Deviation from the Inspection Frequency Requirements of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption 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-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 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 NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis 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-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. 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-24-0165, 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 NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 NL-24-0067, 10 CFR 72.48(d)(2) Biennial Report2024-02-26026 February 2024 10 CFR 72.48(d)(2) Biennial Report NL-24-0051, License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-02-20020 February 2024 License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0422, Inservice Inspection Program Owners Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owners Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 NL-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error 2024-09-09
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Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN * \
NUCLEAR Fax 205.992.7601 A SOUTHERN COMPANY MAR 1 7 2016 Docket Nos.: 50-321 NL-16-0421 U. S. Nuclea r Regulatory Commi ssion A TIN: Docum ent Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclea r Plant- Unit 1 Full Structural Weld Overlays on Reacto r Recirculation and Residual Heat Removal System s Nondestructive Examination Result s- Spring 2016 Outage (1R27)
Ladies and Gentlemen:
By letter dated Decem ber 18, 2015, the Nuclea r Regula tory Commi ssion (NRC) approv ed the use of inservice inspection (lSI) Alternative HNP-ISI-ALT-1 5-01.
This Alternative allowed the installation of full structural weld overlay s (FSWOL) on four welds at Edwin I. Hatch Nuclea r Plant (HNP) Unit 1 during the spring 2016 refueling outage. Below is the lSI weld identification numbe r for each of the four welds:
- 1E11-1 RHR-2 4A-R-1 3 The lSI Alternative stated (in part) that Southern Nuclea r Operating Compa ny (SNC) will provide the NRC, within 14 days after the completion of the ultrasonic examination of the weld overlay installations, (1) the examination results of the weld overlays, and (2) a discussion of any repairs to the overlay materia l and/or base metal and the reason for repair."
The nondestructive examination (NDE) was completed on March 6, 2016.
The attache d Table 1 docum ents the examination results and includes a description of any repairs and the reasons for the repairs. These NDE examination results suppor t the position that the weld overlays are acceptable for service The Alternative requires the lSI ultrasonic examination to be repeate d in either the 1 R28 or the 1R29 outage. This letter satisfies the 14-day examin ation reporting requirements.
U.S. Nuclear Regulatory Commission NL Page2 This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted,
- c. -R. B>>
C. R. Pierce Regulatory Affairs Director CRP/RMJ
Enclosure:
Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outage cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice Preside nt- Hatch Mr. M. D. Meier, Vice Preside nt- Regulatory Affairs Mr. D. R. Madison, Vice Preside nt- Fleet Operations Mr. B. J. Adams, Vice Preside nt- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager - Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manag er- Hatch Mr. D. H. Hardage, Senior Resident Inspect or- Hatch E-2
Edwin I. Hatch Nuclear Plant - Unit 1 Full Structural Weld Overlays on Reactor Recirculation and Residual Heat Removal Systems Nondestructive Examination Results - Spring 2016 Outage (1 R27)
Enclosure Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outage
Enclosure to NL-16-0421 Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outage Weld Sacrificial Completed WOL Base Metal PT POl UT Exam Post-WOL Overlay Layer PT PT Results/Repairs Results/Repairs Repair Remarks
{WOL) No. Results Results/Repairs Exams 1831-1 RC- NRI NRI NRI The original axially- N/A N/A 12BR-C-5 oriented UT indication first observed during the 1988 outage was not observed during the 2016 (1 R27) outage. An embedded reflector in the original weld material was also noted. This indication was acceptable per ASME Section XI, Table IWB-3514-2.
NRI - No Recordable Indications E-1
Enclosure to NL-16-0421 Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outages Weld Sacrificial Completed WOL Post-WOL Base Metal PT PDI UT Exam Overlay Layer PT PT Repair Remarks Results/Repairs Results/Repairs (WOL) No. Results Results/Repairs Exams 1831-1RC- Two linear PT indications NRI NRI The UT examination of N/A N/A 12BR-E-5 larger than the 1/16-inch the new WOL resulted in criteria per lSI Alternative six indications recorded.
15-01 were observed: (1) a Four fabrication flaws in 1-1 /8-inch linear indication the 52M weld overlay in the weld overlay remnant which had no measurable and (2) a %-inch linear through-wall and were indication in the dissimilar less than 3-inches in metal weld within 1/8-inch length. Also observed of the P3 ferritic material. was a fabrication flaw in Grinding was performed on the original Alloy 182 the indications but it did not nozzle buttering. These reduce the flaw lengths to five indications were an acceptable size. These acceptable per ASME PT indications are aligned Section XI, Table IWB-azimuthally with the 2006 3514-2. The original and 2016 UT indications. axially-oriented UT Resolution consisted of a indication first observed combined seal weld repair during the 1988 outage of shielded metal arc had advanced to the welding (SMAW) on the repaired area but did not weld overlay remnant and go into the 2016 weld gas tungsten arc welding overlay material. The UT (GTAW) on the dissimilar data for weld 1831-1 RC-metal weld surface 12BR-E-5 has been temperbead. PT was shared with EPRI NDE performed on 02-21 (after Center personnel for the 48-hour hold) with no further evaluation and recordable indications. review to support a future potential industry i
recommendation.
NRI - No Recordable Indications E-2
Enclosure to NL-16-0421 Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outages Weld Overlay Base Metal PT Sacrificial Completed WOL Post-WOL Layer PT PT POl UT Exam (WOL) No. Results/Repairs Results/Repairs Repair Remarks Results Results/Repairs Exams 1E11-1 AHA- NRI NRI NRI The original axially- N/A N/A 24A-R-12-13 oriented UT indication on (NewWO L Weld 13 which was first covers both observed during the 1984 welds 12 and outage was not observed 13} during the 2016 (1 R27) outage. UT fabrication flaws were noted in the original weld 12 (Valve to Pipe) and the valve body 00 clad. These indications were acceptable per ASME Section XI, Table IWB-3514-2.
NRI- No Recordable Indications E-3
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 SOUTHERN * \
NUCLEAR Fax 205.992.7601 A SOUTHERN COMPANY MAR 1 7 2016 Docket Nos.: 50-321 NL-16-0421 U. S. Nuclea r Regulatory Commi ssion A TIN: Docum ent Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclea r Plant- Unit 1 Full Structural Weld Overlays on Reacto r Recirculation and Residual Heat Removal System s Nondestructive Examination Result s- Spring 2016 Outage (1R27)
Ladies and Gentlemen:
By letter dated Decem ber 18, 2015, the Nuclea r Regula tory Commi ssion (NRC) approv ed the use of inservice inspection (lSI) Alternative HNP-ISI-ALT-1 5-01.
This Alternative allowed the installation of full structural weld overlay s (FSWOL) on four welds at Edwin I. Hatch Nuclea r Plant (HNP) Unit 1 during the spring 2016 refueling outage. Below is the lSI weld identification numbe r for each of the four welds:
- 1E11-1 RHR-2 4A-R-1 3 The lSI Alternative stated (in part) that Southern Nuclea r Operating Compa ny (SNC) will provide the NRC, within 14 days after the completion of the ultrasonic examination of the weld overlay installations, (1) the examination results of the weld overlays, and (2) a discussion of any repairs to the overlay materia l and/or base metal and the reason for repair."
The nondestructive examination (NDE) was completed on March 6, 2016.
The attache d Table 1 docum ents the examination results and includes a description of any repairs and the reasons for the repairs. These NDE examination results suppor t the position that the weld overlays are acceptable for service The Alternative requires the lSI ultrasonic examination to be repeate d in either the 1 R28 or the 1R29 outage. This letter satisfies the 14-day examin ation reporting requirements.
U.S. Nuclear Regulatory Commission NL Page2 This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted,
- c. -R. B>>
C. R. Pierce Regulatory Affairs Director CRP/RMJ
Enclosure:
Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outage cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice Preside nt- Hatch Mr. M. D. Meier, Vice Preside nt- Regulatory Affairs Mr. D. R. Madison, Vice Preside nt- Fleet Operations Mr. B. J. Adams, Vice Preside nt- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager - Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manag er- Hatch Mr. D. H. Hardage, Senior Resident Inspect or- Hatch E-2
Edwin I. Hatch Nuclear Plant - Unit 1 Full Structural Weld Overlays on Reactor Recirculation and Residual Heat Removal Systems Nondestructive Examination Results - Spring 2016 Outage (1 R27)
Enclosure Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outage
Enclosure to NL-16-0421 Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outage Weld Sacrificial Completed WOL Base Metal PT POl UT Exam Post-WOL Overlay Layer PT PT Results/Repairs Results/Repairs Repair Remarks
{WOL) No. Results Results/Repairs Exams 1831-1 RC- NRI NRI NRI The original axially- N/A N/A 12BR-C-5 oriented UT indication first observed during the 1988 outage was not observed during the 2016 (1 R27) outage. An embedded reflector in the original weld material was also noted. This indication was acceptable per ASME Section XI, Table IWB-3514-2.
NRI - No Recordable Indications E-1
Enclosure to NL-16-0421 Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outages Weld Sacrificial Completed WOL Post-WOL Base Metal PT PDI UT Exam Overlay Layer PT PT Repair Remarks Results/Repairs Results/Repairs (WOL) No. Results Results/Repairs Exams 1831-1RC- Two linear PT indications NRI NRI The UT examination of N/A N/A 12BR-E-5 larger than the 1/16-inch the new WOL resulted in criteria per lSI Alternative six indications recorded.
15-01 were observed: (1) a Four fabrication flaws in 1-1 /8-inch linear indication the 52M weld overlay in the weld overlay remnant which had no measurable and (2) a %-inch linear through-wall and were indication in the dissimilar less than 3-inches in metal weld within 1/8-inch length. Also observed of the P3 ferritic material. was a fabrication flaw in Grinding was performed on the original Alloy 182 the indications but it did not nozzle buttering. These reduce the flaw lengths to five indications were an acceptable size. These acceptable per ASME PT indications are aligned Section XI, Table IWB-azimuthally with the 2006 3514-2. The original and 2016 UT indications. axially-oriented UT Resolution consisted of a indication first observed combined seal weld repair during the 1988 outage of shielded metal arc had advanced to the welding (SMAW) on the repaired area but did not weld overlay remnant and go into the 2016 weld gas tungsten arc welding overlay material. The UT (GTAW) on the dissimilar data for weld 1831-1 RC-metal weld surface 12BR-E-5 has been temperbead. PT was shared with EPRI NDE performed on 02-21 (after Center personnel for the 48-hour hold) with no further evaluation and recordable indications. review to support a future potential industry i
recommendation.
NRI - No Recordable Indications E-2
Enclosure to NL-16-0421 Hatch Unit 1 Weld Overlay Examination Results and Repairs during the 1R27 Outages Weld Overlay Base Metal PT Sacrificial Completed WOL Post-WOL Layer PT PT POl UT Exam (WOL) No. Results/Repairs Results/Repairs Repair Remarks Results Results/Repairs Exams 1E11-1 AHA- NRI NRI NRI The original axially- N/A N/A 24A-R-12-13 oriented UT indication on (NewWO L Weld 13 which was first covers both observed during the 1984 welds 12 and outage was not observed 13} during the 2016 (1 R27) outage. UT fabrication flaws were noted in the original weld 12 (Valve to Pipe) and the valve body 00 clad. These indications were acceptable per ASME Section XI, Table IWB-3514-2.
NRI- No Recordable Indications E-3