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Category:Letter
MONTHYEARIR 05000321/20240022024-08-0808 August 2024 Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002 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-24-0276, 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-24-0261, 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 ML24198A1252024-07-16016 July 2024 Edwin I Hatch Nuclear Plant Units 1 - 2 Notification of Conduct of Title 10 of the Code of Federal Regulations 50 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 ML24163A0532024-06-14014 June 2024 Audit Plan - Alternative Seismic Method LAR 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 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, 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 IR 05000321/20240902024-05-15015 May 2024 NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation 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 IR 05000032/20240112024-04-25025 April 2024 Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011 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 05000321/20240012024-04-22022 April 2024 Plants, Units 1 & 2 - Integrated Inspection Report 05000321/2024001 and 05000366/2024001 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 ML24069A0012024-03-0909 March 2024 – Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3) NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission ML24047A0362024-03-0404 March 2024 Response to Hatch and Vogtle FOF Dates Change Request (2025) NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 IR 05000321/20230062024-02-28028 February 2024 Annual Assessment Letter Edwin I. Hatch Nuclear Plant Units 1 and 2 - Nrc Inspection Report 05000321/2023006 and 05000366/2023006 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 IR 05000321/20230042024-01-31031 January 2024 Integrated Inspection Report 05000321/2023004 and 05000366/2023004 ML24012A0652024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 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. IR 05000321/20233012024-01-17017 January 2024 NRC Operator License Examination Report 05000321/2023301 and 05000366/2023301 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) 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 IR 05000321/20234022023-11-29029 November 2023 Security Baseline Inspection Report 05000321/2023402, 05000366/2023402, and 07200036/2023401 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 IR 05000321/20230112023-11-17017 November 2023 Biennial Problem Identification and Resolution Inspection Report 050003212023011 and 050003662023011 ML23324A4472023-11-14014 November 2023 302 Exam Approval Letter IR 05000321/20230032023-11-0202 November 2023 Integrated Inspection Report 05000321/2023003, and 05000366/2023003 IR 05000321/20234032023-10-26026 October 2023 Cyber Security Inspection Report 05000321/2023403 and 05000366/2023403 IR 05000321/20234012023-10-17017 October 2023 Security Baseline Inspection Report 05000321 2023401 and 05000366 2023401 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report IR 05000321/20230052023-08-27027 August 2023 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Report 05000321/2023005 and 05000366/2023005 2024-08-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24208A1742024-07-26026 July 2024 Request for Additional Information Regarding License Amendment Request to Revise TS SRs (3.4.3.1 & 3.1.7.7) to Increase S/Rv Setpoints ML24211A0162024-07-26026 July 2024 NRR E-mail Capture - Request for Additional Information - Hatch, Units 1 and 2, Revise TS SRs (3.4.3.1 & 3.1.7.7) to Increase SRV Setpoints LAR ML24193A1182024-07-10010 July 2024 Email to SNC with RAI for Hatch Exemption Request ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23354A2032023-12-18018 December 2023 Document Request for Hatch Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-01 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23264A0142023-09-14014 September 2023 NRR E-mail Capture - (External_Sender) Draft Round-2 RAI - Hatch, Units 1 and 2, Revise TS 1.1-1 Modes LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23018A1872023-01-17017 January 2023 2023 HNP CGD Inspection Information Request ML22355A2082022-12-21021 December 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, Reactor Pressure Vessel 'Rpv Head Studs' LAR ML23026A2372022-11-16016 November 2022 2023001 Hatch RP RFI Final ML22208A1332022-07-26026 July 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-208 LAR ML22157A3542022-06-0606 June 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-505 LAR ML22140A1192022-05-20020 May 2022 NRR E-mail Capture - RAIs - Hatch, Units 1 and 2, TSTF-505 LAR ML22073A0842022-03-21021 March 2022 an NRC Fire Protection Team Inspection (NRC Inspection Report Nos. 05000321/2022011 and 05000366/2022011) and Request for Information ML22025A2142022-01-21021 January 2022 Plant Hatch 2022001 RP Baseline Inspection Information Request ML21265A3402021-09-22022 September 2021 NRR E-mail Capture - Request for Additional Information - Hatch, Unit 1, Emergency TS 3.7.2 LAR ML21111A3032021-04-21021 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21110A6842021-04-20020 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21013A4112021-01-13013 January 2021 Notification of Edwin I. Hatch Nuclear Plant Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000321/2021010 and 05000366/2021010 ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20253A2732020-09-0909 September 2020 Requalification Program Inspection Hatch Nuclear Station ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests NL-19-1532, Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors2019-12-18018 December 2019 Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors ML19336A0142019-12-0101 December 2019 NRR E-mail Capture - RAI: Hatch Emergency TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LAR ML19280A0082019-10-0404 October 2019 NRR E-mail Capture - Request for Additional Information (RAI) - Hatch TSTF-51 LAR (L-2019-LLA-0091) ML19224C0552019-08-12012 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Degraded Voltage (L-2019-LLA-0108) ML19220A0362019-08-0808 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Adoption of NFPA 805, Request for Additional Information, EPID L-2018-LLA-0107 ML19164A2582019-06-13013 June 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML19107A4962019-04-17017 April 2019 NRR E-mail Capture - Request for Additional Information - Hatch 1 & 2 Application to Adopt Title 10 of Code of Federal Regulations 50.69 RISK-INFORMED Categorization and Treatment of Structures, Systems and Components for Power Reactors ML19088A0092019-03-29029 March 2019 NRR E-mail Capture - Hatch 1 and 2 - LAR to Adopt NFPA 805 Fire Protection Standard, EPID L-2018-LLA-0107, Request for Additional Information ML19029B3402019-01-23023 January 2019 Southern Nuclear Operating Company, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 Draft Request for Additional Information for the License Amendment Requests to Adopt the Risk-Informed Provisions of Title 10 of the Code of Federal Regulat ML19016A3422019-01-10010 January 2019 U2 ISI 2019001 RFI - Bcc ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18085A0132018-03-0808 March 2018 Draft Request for Additional Information on Alternative RR-V-11, Proposed Extension to Main Steam Safety Relief Valve Testing Requirements ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17284A3542017-11-0707 November 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools ML17270A1402017-09-27027 September 2017 PIR Notification Letter 2017 ML17290A3172017-09-19019 September 2017 NRR E-mail Capture - Hatch 1 and 2 - Draft Request for Additional Information Request for Alternative No. HNP-ISI-ALT-05-05 ML17111A5792017-04-26026 April 2017 Request for Additional Information, Fourth 10-Year ISI Interval Relief Requests ML17110A2112017-04-24024 April 2017 Request for Additional Information ML16330A1282016-12-0505 December 2016 Request for Additional Information ML16307A1842016-11-0202 November 2016 Request for Additional Information (Non-Proprietary) ML16271A1692016-10-17017 October 2016 Request for Additional Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16205A0012016-07-22022 July 2016 Requalification Program Inspection - Plant Hatch ML16195A4002016-07-13013 July 2016 Request for Additional Information License Amendment Request to Revise Technical Specifications Regarding TSTF-500 ML16194A4282016-07-12012 July 2016 E-mail Draft Request for Additional Information for Technical Clarification 2024-07-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 18, 2015 SUBJECT: EDWIN I. HATCH NUCLEAR PLANT, UNIT 1 (HNP)-REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE HNP-ISl-ALT-15-01 (TAC NO. MF6453) Dear Mr. Pierce: By letter dated July 2, 2015, the Southern Nuclear Operating Company (SNC) proposed an In-service Inspection (ISi) Alternative to install full structural weld overlays (FSWOL) on four welds at the HNP, Unit 1, during the spring 2016 refueling outage. The licensee has used a previously U.S. Nuclear Regulatory Commission (NRC)-approved ISi Alternative, HNP-ISl-ALT-08-02, through a majority of the fourth ISi interval for the installation of FSWOLs on both units. However, the licensee submitted the new ISi alternative, T-15-01, on the unique configuration of the four subject welds. In particular, existing weld overlay material is either adjacent to or located at those locations which are scheduled for the installation of new FSWOLs. To complete its review, the NRC staff requests the following additional information. Docket No. 50-321 cc: Distribution via Listserv Sincerely, ob Martin, Senior Project Manager ant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION (RAI) SOUTHERN NUCLEAR OPERATING COMPANY, INC. EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 By letter dp.ted July 2, 2015 {Agencywide Documents Access and Management System * (ADAMS) Accession No. ML 15183A354), Southern Nuclear proposed an In-service Inspection (ISi) Alternative to install full structural weld overlays (FSWOL) on four welds at Edwin I. Hatch Nuclear Plant, Unit 1, during the spring 2016. refueling outage. The licensee has used a previously U.S. Nuclear Regulatory Commission (NRC)-approved ISi Alternative, HNP-ISl-AL T-08-02, through a majority of the fourth ISi interval for the installation of FSWOLs on both units. However, the licensee submitted the new ISi alternative, HNP-ISl-ALT-15-01, on the unique configuration of the four subject welds. In particular, existing weld overlay material is either adjacent to or located at those locations which are scheduled for the installation of new FSWOLs. To complete its review, NRC staff requests the following additional information. 1. In the cover letter dated July 2, 2015, the licensee states that the proposed ISi Alternative involves applying FSWOL on four welds. However, page 1 of Enclosure identifies only three welds, 1 E11-1 RHR-24A.-R-12, 1831-1 RC-12BR-C-5 and 1831-1 RC-12BR-E-5. Also, the last sentence on page 2 of the ISi Alternative states that "the RHR weld and two recirculation welds". The proposed ISi Alternative does mention weld 1 E11-1 RHR-24A-R-13 which has already been weld overlaid in 1984. (a) It is not clear to the NRC staff exactly how many welds are affected. Confirm that the affected welds are welds 1 E11-1 RHR-24A-R-12, 1 E11-1 RHR-24A-R-13, 1831-1 RC-12BR-C-5 and 1831-1 RC-12BR-E-5. (b) Clarify whether the original weld 1 E11-1 RHR-24A-R-13 is made of Alloy 82/182 filler material or stainless steel filler material. 2. Figures 1 and 2 in Appendix 6 present the weld configurations of the RHR piping and Recirculation riser line, respectively. Figure 1 shows the existing weld overlay on R-13 weld. (a) Confirm that weld R-12 has no weld overlay at present. * (b) Describe what represents the hash lines on the nozzle that is located horizontally in Figure 1. (c) Figure 2 in Appendix 6 shows one weld is made of stainless steel and one weld is made of Alloy 82/182 material on the recirculation riser line. However, Page 1 of the ISi Alternative appears to suggest that both C-5 and E-5 are dissimilar metal welds. Clarify which of the two welds 1831-1 RC-12BR-C-5 and 1831-1 RC-12BR-E-5 is the alloy 82/182 weld and which is the stainless steel weld? Include both weld identification number on Figure 2. Enclosure
-2 -(d) Page 1 of the ISi Alternative discusses the base materials that are adjacent to weld R-12, but not adjacent to weld R-13. Page 1 also discusses the base materials that are adjacent to C-5 or E-5, but it is not clear to the NRC staff the exact base materials that are associated with welds C-5 and E-5. Discuss the adjacent base materials to welds R-13, C-5 and E-5. 3. Fourth paragraph on page 3 of the ISi Alternative states that " ... In the present configuration,
- the lnconel weld overlay does not completely cover the weld and buttering but tapers to
- approximately the centerline of the weld. These two weld overlays have seen continuous service since that outage with UT examinations performed during several outages ... " Figure 2 of Appendix 6 does not show the existence of the current weld overlay. (a) Provide a sketch or draw on Figure 2 of the current weld overlay configuration on 1831-1 RC-128R-C-5 and 1831-1 RC-128R-E-5 including dimensions. (b) Clarify where the two existing weld overlays are located as referenced in the above quote. 4. Discuss the maximum and minimum design thickness of the proposed FSWOL. 5. Section 1.0 of the ISi Alternative states that " ... The surface of the existing weld overlays will be ground to prepare the surface for receipt of a new Alloy 52M overlay ... After performance of a satisfactory liquid penetrant surface examination, a stainless steel buffer layer {ER308L) will be deposited over the stainless steel ... The portion of the overlay deposited over the low alloy . steel material will be applied directly at ambient temperature using the temper bead technique and the Alloy 182 butt weld will be spanned and tied into the stainless steel material using a single layer of Alloy 82 ... " (a) Identify the stainless steel surfaces that the buffer layer will be applied on Figures 1 and 2 of Appendix 6 (or on sketches) of the four weld configurations and draw the buffer layer on the diagrams. (b) Provide a step-by-step welding of how the Alloy 82, Alloy 182, and Alloy 52M layers are deposited on the subject welds. Illustration these layers on Figures 1 and 2 of Appendix 6 {or on sketches). 6. Section 1.0(b), second paragraph states that: " .. .Depending on the.chemical composition of the base materials where the weld overlay is to be applied, there may be different ways to apply the first layer of weld material. .. " Explain the "different ways" to apply the first layer of weld material '(different from standards?). 7. Section 2, page 6 states that 'This report will be submitted within 90 days after plant startup." Confirm that the report is referring to the crack growth calculation of the postulated flaw(s). 8. Section 3, under the Pre-Overlay Examination heading, the licensee stated that" ... For welds overlaid because of unacceptable indications, the flaw size would be defined by qualified ultrasonic examinations ... " This statement appears that the licensee will perform a pre-overlay examination. However, on page 12 of the ISi Alternative the licensee stated that it will not perform ultrasonic examination of the weld prior to FSWOL application. (a) Clarify whether a pre-overlay ultrasonic
-3 -examination will be performed. If not, explain why a pre-overlay examination will not be performed . . 9. Sections 3(a)4 and 3(b)2 state that: " ... Reexamination per IWB-2420 is not required because unacceptable indications will be removed and the volume will be re-welded ... " Explain why re-examination is not required after an unacceptable indication is removed and the excavated volume is backfilled.
- 10. Section 3(c) states that inservice examinations of the FSWOLs will be performed in accordance with Q-4300 and 4310 of Appendix Q to the 2004 Edition of Section XI with Addenda through 2005 with modifications. Appendix 8 presents the modified lnservice examination requirements. (1) Clarify whether paragraphs (a), (b), and (c) as stated in the Modified Q-4300 lnservice Flaw Evaluation Requirements will replace paragraphs (a) and (b) in the existing Q-4300 lnservice Examination Requirements of the ASME Code,Section XI. (2) If the Modified Q-4300 requirements will replace the existing Q-4300(a) and Q-4300(b), discuss when the subject overlaid welds will receive their first ultrasonic examination after weld overlay installation. (3) Modified Q-4300 lnservice Examinati9n Requirement Paragraphs (b) and (c) mention the "unacceptable indications". What are the acceptance criteria for the unacceptable indications and based on which subarticle of the ASME Code? (4) ASME Code,Section XI, Q-4300 contains paragraphs a, b, c, d, e, and f. Discuss whether Q-4300 paragraphs c, d, e and f will be followed because Modified Q-4300 did not mention these four subparagraphs. 11: Appendix 8, Modified Q-4300 Re-examination Requirements (b) specifies that" ... If inservice examinations reveal acceptable crack growth or new cracking in the upper 25% of the original weld or base materials ... " Discuss whether the crack is caused by stress corrosion cracking or some other degradation mechanism. The NRC staff noted that paragraph (c) provides requirements of the non-SCC flaws. However, Paragraph (b) does not reference whether the flaws are caused by sec. 12. Provide a sketch or diagram of each subject weld that is applied with a FSWOL demonstrating that the ultrasonic examination of the overlaid weld will achieve 100 percent coverage of the required volume per the ISi Alternative. The sketch/diagram should include lines that represent the ultrasonic beam angles and signal path that cover the required volume. 13. Appendix 9 presents the inspection history and results of all 4 subject welds. Welds 1E11-1RHR-24A-:R-13, 1B31-1RC-12BR-C-5and1B31-1RC-12BR-E-5 have previously . detected indications. The indications in welds E-5 and R-13 have considerable depth with respect to the wall thickness. (a) Discuss whether these indications will be removed or reduce in size prior to applying FSWOL. If not, justify. (b) Page 12 of the ISi Alternative states that ultrasonic examination will not be performed prior to FSWOL application. The indications in the above 3 welds were detected in 1984 and 1988. Without performing the ultrasonic testing prior to the FSWOL application, the current indication size would not be known. Section 2 of the ISi Alternative requires a crack growth calculation based on an initial flaw size. However, the
- indications in these three welds may have grown since the initial detection in the 1980's. Explain how the crack growth calculation can be performed if the initial flaw size is not known prior to the FSWOL application.
-4 -14. Appendix 3 to the ISi Alternative presents the preservice examination volume which is illustrated in Figure 3. Figure 3 identifies Note 1. However, Note 1 is not shown in Figure 3, nor Appendix 3. Please clarify. 15. In Section 2.1, "Procedure qualifications," on page 16, paragraph (g) of the July 2, 2015 submittal, the licensee stated: "The average lateral expansion value of the heat affected zone (HAZ) Charpy V-notch specimens shall be equal to or greater than the average lateral expansion value of the three unaffected base metal specimens. However, if the average lateral expansion value of the HAZ Charpy V-notch specimens is less than the average value of the unaffected base metal specimens and the procedure qualification meets all the other requirements of the Appendix 1 of the submittal, either of the following shall be performed: (1) The welding procedure shall be requalified. (2) An Adjustment Temperature for the procedure qualification shall be determined in accordance with the applicable provisions of NB-4335.2 of Section Ill, 2001 Edition with 2002 Addenda. The RT NDT or lowest service temperature of the materials for which the welding procedure will be used .. shall be increased by a temperature equivalent to that of the Adjusted Temperature." Based on the above information, the staff requests that the licensee provide the following information: (a) .Identify whether aforementioned option (1) or option (2) was used in the temperbead weld qualification for Hatch weld overlays. (b) If the welding procedure specification (WPS) was qualified with option (2), provide the value for the new Adjusted Temperature for the vessel component (where temperbead structural overlay is to be applied). Identify if this Adjusted Temperature value was considered in the evaluation of the vessel integrity analyses (e.g., pressure-temperature curves-if applicable).
Mr. C. R. Pierce Regulatory Affairs Director August 18, 2015 Southern Nuclear Operating Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 SUBJECT: EDWIN I. HATCH NUCLEAR PLANT, UNIT 1 (HNP) -REQUEST FOR ADDITIONAL INFORMATION ON ALTERNATIVE HNP-ISl-ALT-15-01 (TAC NO. MF6453) Dear Mr. Pierce: By letter dated July 2, 2015, the Southern Nuclear Operating Company (SNC) proposed an In-service Inspection (ISi) Alternative to install full structural weld overlays (FSWOL) on four welds at the HNP, Unit 1, during the spring 2016 refueling outage. The licensee has used a previously U.S. Nudear Regulatory Commission (NRC)-approved ISi Alternative, HNP-ISl-AL T-08-02, through a majority of the fourth ISi interval for the installation of FSWOLs on both units. However, the licensee submitted the new ISi alternative, HNP-ISl-AL T-15-01, on the unique configuration of the four subject welds. In particular, existing weld overlay materia.1 is either .. adjacent to or located at those locations which are scheduled for the installation of new FSWOLs. To complete its review, the NRC staff requests the following additional information. Docket No. 50-321 cc: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource Rids N rrLASFigueroa *Resource RidsNrrPMHatch Resource ADAMS Accession No.: ML152248464 Sincerely, /RA/ Bob Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource
- RidsRgn2MailCenter Resource JTsao, NRR GCheruvenki, NRR *email OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DE/EPNB/BC DE/EVIB/BC DORL/LPL2-1 /BC NAME RMartin SFigueroa DAiiey JMcHale RPascarelli DATE 08/14/15 08/13/15 08/03/15* 08/12/15
- 08/18/15 OFFICIAL RECORD COPY DORL/LPL2-1 /PM RMartin 08/18/15