Similar Documents at Hatch |
---|
Category:Letter type:NL
MONTHYEARNL-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 Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S 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 NL-23-0003, 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 Specification Table 12023-01-20020 January 2023 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 Specification Table 1 NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 2024-07-09
[Table view] |
Text
Mark J. Ajluni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 March 22, SOUTHERN'\'
COMPANY Docket 50-321 NL-11-0482 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant, Units 1 and Request for Additional Information Fourth 10-Year Intervallnservice inspection Ladies and Gentlemen:
By letter dated July 8, 2010, Southern Nuclear Operating Company, Inc. (SNC), submitted relief requests for the Fourth 10-Year Intervallnservice Inspection Program for Edwin I. Hatch Nuclear Plant, Units 1 and 2. By letter dated November 23,2010, SNC provided response to NRC requested additional information in letters dated October 5, 2010, regarding review of relief requests ISI-RR-02, ISI-RR-06 and ISI-RR-07, and October 22,2010, regarding review of relief requests ISI-RR-03, ISI-RR-04, ISI-RR-05, ISI-RR-08, ISI-RR-09, 10, and ISI-RR-11.
By letter dated February 23, 2011, the NRC requested additional information in support of review of relief requests ISI-RR-04 and ISI-RR-10.
The SNC response to the NRC RAls is provided in the Enclosure.
This letter contains no NRC commitments.
If you have any questions, please contact Jack Stringfellow at (205) 992-7037.
Respectfully submitted, M. J. Ajluni Nuclear licensing Director MJA/LPHllac
Enclosure:
Hatch Nuclear Plant -Units 1 and 2, Response to Request for Additional Information Regarding Proposed Relief Requests for the Fourth ISllntervaIISI-RR-04 and ISI-RR-10 U. S. Nuclear Regulatory Commission NL-11-0482 Page 2 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President
-Hatch Ms. P. M. Marino, Vice President
-Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Mr. V.M. McCree, Regional Administrator Mr. P. G. Boyle, NRR Project Manager Mr. E. D. Morris, Senior Resident Inspector
-Hatch Edwin I. Hatch Nuclear Plant, Units 1 and Response to Request for Additional Information Proposed Relief Requests for the Fourth lSI Interval ISI-RR-04 and ISI-RR-10
Response to Request for Additional Information Proposed Relief Requests for the Fourth ISllntervaIISI-RR-04 and ISI-RR-04, (HNP, Unit 2) ASME Code,Section XI, Examination Category B-J, Dissimilar Metal Pressure Retaining Welds in Piping NPS 4 or Larger Circumferential Weld NRCRAI For Weld 2B21-1FW-12AA-8: What is the weld metal? What is the Generic Letter 88-01 category of this weld? Please discuss the susceptibility of this weld to Intergranular Stress Corrosion Cracking. The NRC staff acknowledges that the weld overlay was applied prior to the Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a mandated implementation of Appendix VIII, and that the subject welds has been mitigated by the mechanical stress improvement process. However, the significant lack of creditable coverage for Appendix VIII examinations as a result of the licensee's decision to stop the overlay at the toe of the weld concerns the staff. Please discuss whether plans are in place to increase the creditable coverage of this weld by means such as extending the overlay or performing a Supplement 11 qualification demonstration on a site-specific mockup and if not, then why not? SNC Response Weld 2B21-1 FW-12AA-8 joins an Inconel600 Safe End Extension to a Steel Transition Piece using Inconel 182 weld material.
This is shown on The Generic Letter 88-01 category of weld 2B21-1 FW -12AA-8 is Category This is due to the weld material not being made of Intergranular Stress Cracking (IGSCC) resistant material, and the weld has been given a improvement (SI) after more than two years of operation.
The weld received mechanical stress improvement process (MSIP) in Per the NRC staff positions in Generic Letter 88-01, carbon steel is resistant to IGSCC, while Inconel 82 is the only nickel base alloy considered be resistant to IGSCC. Therefore, MSIP was used to reduce the susceptibility the Inconel portions of this weldment to Due to the significant lack of coverage for Appendix VIII examinations, this is scheduled to receive an overlay prior to the end of the 4th Inservice Interval which ends December 31 ,
Response to Request for Additional Information Proposed Relief Requests for the Fourth lSI Interval ISI-RR-04 and 151-RR-10, (HNP, Unit 2) ASME Code,Section XI, Examination Category B-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzle-to Safe End Welds NPS 4 or Larger NRC RAI In the response to the NRC's Request for Additional Information, it was noted that two subsurface, circumferentially oriented, planar flaws were detected in Weld 10A-21 and one subsurface, circumferentially oriented, planar flaw was detected in weld 2E21-1 CS-1 OB-20. Please describe how these flaws were determined to be subsurface.
Is there a reinspection plan in place for these welds? Also, please explain how it is that weld shrinkage created the exact same examination limitation on two different welds. SNC Response SNC is aware of previous examination issues in the industry where only the upper portion of a flaw was detected during an examination and was evaluated as a subsurface flaw. Subsequently, after further weld preparation and re-examination, it was determined that the flaw was actually connected to the inside surface. This situation occurred at Hatch on a recirculation inlet nozzle-to-safe end weld during the same 2009 outage in which the subject Core Spray welds were examined.
However, for the Core Spray welds, the automated phased-array display clearly showed that no flaws are closer than 1/4" to the inside surface. Prior to the Core Spray weld examinations, the weld crowns were removed and the only examination interference was from shrinkage at the downstream toe of the welds. A review of the data sheets indicates that there was no interference during the examination of the welds for circumferentially-oriented flaws; therefore, the circumferentially-oriented indications were determined to be subsurface. These flaws were evaluated as subsurface and acceptable in size. Therefore, there are no plans to re-inspect these welds per IWB-2420(b). These Core Spray welds are both safe end-to-nozzle welds (Train A and B) that have essentially the same configuration.
Therefore, the weld shrinkage area causing the limitation was in the same location.
Response to Request for Additional Information Proposed Relief Requests for the Fourth lSI Interval ISI-RR-04 and 1!lEHTlflCA 11111 1/110 . liJrn.r TO vtSS!1 2N4A, B, C, 2. I(JZ1lE Ilt£lI RADIUS 10 3. TRANS-PlECE m lelzm BJ BJ B!' BJ IJI' 8. PIP[ m TRANS PIW BJ 12' sct! 80 Sl\-11l6 ij/ B (CARD SITED Il!V N.lllY VELD 182 TlIANSTIlllH PIIT£ CARD STm p[rc(CARD mEl. <12' FTEDIrIATER NOZZLE ASSEMBL Y-4 NOZZl ES) R[ACI(Ji I'R[SSLIIf GIl D ClASS 1 _____ L w,* " '--"""-'9.7'
- I IIl'X8' SCH 80S 304 sst 219116' 823*004 REV 7 22A3836Af REV I SOUTHERN NUCLEAR B 245-270 REV 0 ITS A-35, A-36 628-001 REV 0