Letter Sequence Response to RAI |
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Category:Letter
MONTHYEARIR 05000321/20230042024-01-31031 January 2024 Integrated Inspection Report 05000321/2023004 and 05000366/2023004 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. ML24012A0652024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 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 IR 05000321/20234022023-11-29029 November 2023 Security Baseline Inspection Report 05000321/2023402, 05000366/2023402, and 07200036/2023401 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 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 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 IR 05000321/20230022023-08-0808 August 2023 Integrated Inspection Report 07200036/2023001, 05000321/2023002, and 05000366/2023002 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 ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23201A0292023-07-20020 July 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML23178A0012023-06-27027 June 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000321 2023403 and 05000366 2023403 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 IR 05000321/20230102023-06-0909 June 2023 Focused Engineering Inspection Report 05000321 2023010 and 05000366 2023010 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. ML23136B2942023-05-19019 May 2023 Summary of May 02, 2023, Observation Public Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a LAR for the Reactor Pressure Vessel Head Closure Bolts for Edwin I. Hatch Nuclear Plant, Units 1 and 2 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 ML23123A2222023-05-0101 May 2023 Notification of Licensed Operator Initial Examination 05000321/2023301, and 05000366/2023301 IR 05000321/20230012023-04-26026 April 2023 Integrated Inspection Report 05000321/2023001 and 05000366/2023001 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-23-0014, 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-23-0208, 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-23-0228, 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 ML23065A1092023-03-0808 March 2023 Correction of Relief Request HNP-ISI-RR-05-02 Allowing to Continue Operation with a Flaw Indication on One Reactor Pressure Vessel Closure Bolt Until December 31, 2025 ML23053A2182023-03-0303 March 2023 Correction of Amendment Nos. 321 and 266 Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program IR 05000321/20220062023-03-0101 March 2023 Annual Assessment Letter Edwin I. Hatch Nuclear Plant, Units 1 and 2 - NRC Inspection Report 05000321/2022006 and 05000366/2022006 NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 2024-01-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNL-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-23-0658, 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-23-0003, 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-22-0801, Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of .2022-10-14014 October 2022 Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of . NL-22-0650, Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-08-19019 August 2022 Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0590, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten2022-08-18018 August 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten NL-21-0862, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable - RAI Responses2021-09-23023 September 2021 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable - RAI Responses NL-21-0423, Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump - PRA RAI Response2021-04-22022 April 2021 Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump - PRA RAI Response NL-21-0415, Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump - RAI Response2021-04-20020 April 2021 Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump - RAI Response NL-20-1273, Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for2020-11-20020 November 2020 Response to NRC Requests for Information License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for NL-20-1000, Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time2020-08-23023 August 2020 Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time NL-20-0670, Response to Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2020-06-0202 June 2020 Response to Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request NL-19-1248, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations - TSTF-51, SNC Response to NRC Request for Additional Information2019-10-17017 October 2019 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations - TSTF-51, SNC Response to NRC Request for Additional Information NL-19-1203, Response to Request to Additional Information Regarding Application to Adopt National Fire Protection Association Standard 8052019-10-0707 October 2019 Response to Request to Additional Information Regarding Application to Adopt National Fire Protection Association Standard 805 NL-19-1028, Response to NRC Request for Additional Information Concerning License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Unit 1 Degraded Voltage Protection2019-08-28028 August 2019 Response to NRC Request for Additional Information Concerning License Amendment Request for Technical Specifications 3.3.8.1 and 3.8.1 Regarding Unit 1 Degraded Voltage Protection NL-19-0850, Response to Request for Addition Information Regarding Application to Adopt Title 10 of Code of Federal Regulations (CFR) 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and ...2019-07-16016 July 2019 Response to Request for Addition Information Regarding Application to Adopt Title 10 of Code of Federal Regulations (CFR) 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and ... NL-19-0698, License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function SNC Response to NRC Request for ...2019-06-12012 June 2019 License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function SNC Response to NRC Request for ... NL-19-0188, Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test SNC Response to NRC Request...2019-02-20020 February 2019 Emergency License Amendment Request for Technical Specification 3.8.1 Regarding Voltage Limit Increase for Emergency Diesel Generator Load Rejection Surveillance Test SNC Response to NRC Request... NL-18-1514, Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift.2019-01-31031 January 2019 Response to Request for Information Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-Shift. NL-19-0009, Supplemental Response to Alternative Request HNP-ISI-ALT-05-042019-01-0808 January 2019 Supplemental Response to Alternative Request HNP-ISI-ALT-05-04 NL-18-1480, Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04)2018-11-29029 November 2018 Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04) NL-18-0639, Response to Request for Information Regarding Safety Relief Valve Main Valve Body Testing Extension2018-05-10010 May 2018 Response to Request for Information Regarding Safety Relief Valve Main Valve Body Testing Extension NL-18-0541, Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements2018-04-17017 April 2018 Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements ML18088A0802018-03-29029 March 2018 Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements NL-18-0211, Response to Request for Additional Information Regarding Alternative HNP-181-ALT-05-05 to Adopt Code Case N-7022018-02-20020 February 2018 Response to Request for Additional Information Regarding Alternative HNP-181-ALT-05-05 to Adopt Code Case N-702 NL-18-0085, Response to NRC RAIs Regarding Generic Letter 2016-012018-02-0505 February 2018 Response to NRC RAIs Regarding Generic Letter 2016-01 NL-17-2015, Response to NRC RAIs Regarding Decommissioning Funding Status Reports2018-01-22022 January 2018 Response to NRC RAIs Regarding Decommissioning Funding Status Reports NL-17-1161, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Supplemental Responses to NRC Second Set of Requests for Additional Information2017-07-12012 July 2017 License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Supplemental Responses to NRC Second Set of Requests for Additional Information NL-17-0766, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Second Set of Requests for Additional Information2017-06-0101 June 2017 License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Second Set of Requests for Additional Information NL-17-0917, Response to Request for Additional Information Regarding Relief Requests RR-16, RR-17. RR-21 and RR-222017-05-31031 May 2017 Response to Request for Additional Information Regarding Relief Requests RR-16, RR-17. RR-21 and RR-22 NL-17-0063, Response to Verbal Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-write2017-02-0606 February 2017 Response to Verbal Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-write NL-16-2494, Units 1 and 2 - Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2016-12-15015 December 2016 Units 1 and 2 - Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... NL-16-2457, Supplemental Information Regarding Proposed Safety Limit Minimum Critical Power Ratio (SLMCPR) License Amendment2016-11-18018 November 2016 Supplemental Information Regarding Proposed Safety Limit Minimum Critical Power Ratio (SLMCPR) License Amendment NL-16-2109, Response to Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500. DC Electrical Re-write2016-11-16016 November 2016 Response to Request for Additional Information on Technical Specifications Revision Request to Implement TSTF-500. DC Electrical Re-write NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C2016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C2016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C ML16314A5052016-11-0303 November 2016 Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1B of 1C NL-16-1169, Response to Request for Additional Information on Technical Specifications - Revision Request to Implement TSTF-500, DC Electrical Re-Write.2016-08-12012 August 2016 Response to Request for Additional Information on Technical Specifications - Revision Request to Implement TSTF-500, DC Electrical Re-Write. NL-16-0628, Southern Nuclear Operating Company Response to Third Request for Additional Information Regarding Standard Emergency Plan: Cover Letter, Attachment 1 and Enclosures 1 - 102016-06-0909 June 2016 Southern Nuclear Operating Company Response to Third Request for Additional Information Regarding Standard Emergency Plan: Cover Letter, Attachment 1 and Enclosures 1 - 10 NL-16-0739, Corrected Response to Second Request for Additional Information Regarding Standard Emergency Plan2016-05-26026 May 2016 Corrected Response to Second Request for Additional Information Regarding Standard Emergency Plan NL-16-0660, Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specification Amendment Request2016-05-16016 May 2016 Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specification Amendment Request NL-16-0655, Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specifications Amendment Request2016-05-0909 May 2016 Response to Request for Additional Information on Secondary Containment Drawdown Time Technical Specifications Amendment Request NL-16-0292, Response to Request for Additional Information on Revision to Secondary Containment Drawdown Time Technical Specifications Amendment Request2016-03-16016 March 2016 Response to Request for Additional Information on Revision to Secondary Containment Drawdown Time Technical Specifications Amendment Request NL-16-0169, Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Encl2016-02-17017 February 2016 Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Enclos ML16060A3282016-02-17017 February 2016 Southern Nuclear Operating Company Response to First Request for Additional Information Re Standard Emergency Plan. Attachment 1: SNC Response to NRC RAI-1 Fleet Standard Emergency Plan and Enclosure 1: Evaluation of Proposed Changes Enclos NL-16-0172, Response to Request for Information Regarding Changes to Technical Specification Section 1.0, 3.4.9, and 5.02016-02-0909 February 2016 Response to Request for Information Regarding Changes to Technical Specification Section 1.0, 3.4.9, and 5.0 NL-15-2270, Response to Request for Additional Information for Alternative HNP-ISI-ALT-5-012015-12-16016 December 2015 Response to Request for Additional Information for Alternative HNP-ISI-ALT-5-01 NL-15-2047, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 22015-11-24024 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-523, Revision 2 ML15322A0902015-11-12012 November 2015 Enclosure 4, Non-Proprietary Version of the Epri/Bwrvip Information Requested in RAI 1 2024-01-30
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~ Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 40 Inverness Center Parkway Post Oflice Box 1295 Birmingham, AL 35242 205 992 5316 tel 205 992 7601 lax MAR 2 9 2018 cagayhea@ southernco.com Docket Nos.: 50-321 NL-18-041 0 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant- Unit 2 Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Reguirements Ladies and Gentlemen:
By letter dated August 3, 2017 (Agencywide Documents Access and Management System Accession No. ML17215A558), Southern Nuclear Operating Company (SNC) submitted a request for alternative for the Edwin I. Hatch Nuclear Plant, Unit 2 (Hatch Unit 2). The requested alternative would authorize a one-time extension of the main steam safety relief valve (SRV) main body test frequency, allowing. the required testing to be performed at the next Hatch Unit 2 refueling outage in February 2019. The NRC staff has reviewed the information provided by SNC, and has determined that additional information is needed to complete its evaluation.
This additional information was requested via emailed correspondence dated March 8, 2018.
The Enclosure provides the SNC response to the NRC request for additional information Questions 1 - 3. The SNC response to Question 4 will be provided once test results are available for the Unit 1 SRVs from the recently completed February 2018 refueling outage.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Respectfully submitted, Cheryl A. art Regulatory Affairs Director CAG/RMJ
Enclosure:
Response to NRC Request for Additional Information Cc: Regional Administrator, Region II NRR Project Manager- Hatch Senior Resident Inspector- Hatch RTYPE: CHA02.004
Edwin I. Hatch Nuclear Plant - Unit 2 Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements Enclosure Response to NRC Request for Additional Information
Enclosure to NL-18-0410 Response to NRC Request for Additional Information NRC RAI #1 Discuss the as-found condition of the SRVs currently in service in Hatch Unit 2 following limited flow testing and prior to performing the Part 21 recommended actions before returning them to service.
SNC Response to NRC RAI #1 All Hatch Unit 2 safety relief valve (SRV) main valve bodies (MVBs) were replaced with pre-tested components during a forced outage in May 2016. The MVBs installed were tested with the limited flow testing and then disassembled and inspected per the Part 21 inspection (TRFS-406 Rev B). This inspection found no abnormal wear or deformation. Some main disc jam nuts were found loose, but still within tolerance. These jam nuts were tightened per procedure with the locking tab. Since the pressure boundary was broken for inspection, the valves were hydro tested to confirm no leakage was introduced. This post-test inspection confirmed that valves currently installed on Unit 2 have tight locking nuts and tabs, as well as no deformation on the main disc shoulder. The valves have not been lifted since the Part 21 inspection was completed.
NRC RAI #2 Discuss the operating, test, and examination history of the subject valve for both Hatch Unit 2 and Hatch Unit 1.
SNC Response to NRC RAI #2 The Hatch Unit 1 main valve bodies (MVBs) removed during the February 2016 refueling outage were shipped to NWS Technologies Inc. to perform post-operational as-found testing required by Technical Specifications, and to inspect these valves for susceptibility to the Part 21 notification. These valves were initially placed in service prior to the Part 21 notification. The as-found tests resulted in all 11 MVBs stroking successfully in the required time. For further Part 21 investigation into the testing methods, multiple tests were performed on the valves. Three of 11 MVBs stroked fully open, but failed to fully reseat following the second actuation test for the valve. All three valves successfully cycled once during their automatic steam test; however, the valves failed to fully reseat during subsequent attempts.
Of the three MVBs that failed to reseat, one was found closed when removed from the test stand, one was manually closed following removal from the test stand, and the third was manually actuated during inspection. In all three cases, the valves exhibited free travel of the main disc assembly when moved by hand.
Internal inspection of the valves that failed to reseat found shortened spring lengths outside of prescribed acceptance criteria, loss of locking nut preload, the lock tab washer rotated and not engaged, and stem I piston thread degradation. The cause of the failure to fully reseat on the test stand was attributed to the pressure of the limited flow testing imparting impact loads greater than the local yield strength of the main disc and/or main piston. After limited flow testing, the main internals have been found in a degraded condition. When the impact load is much greater than the local yield strength, the preload on the joint is not only removed, but clearance is established between the disc and piston shoulders. The magnitude of the clearance, if greater than 0.004", allows the piston to rock on the stem shoulder, wearing grooves into the main guide fretting or increasing the relative clearance between the piston and E-1
Enclosure to NL-18-0410 Response to NRC Request for Additional Information disc threads. The induced vibration load is plant-specific and Plant Hatch has minimal vibration on these locations of steam piping.
The 1B21-F013A SRV failed to fully re-seat after its second automatic lift during post-operational testing. The main stage disc remained approximately 0.2" from full closure after testing. A tool was used to close the valve with hand pressure. The valve closed freely, and upon inspection, the piston and stem assembly was able to move freely in the guide. Although the valve had severe thread damage to the piston and stem and the piston could tilt on the stem, no signs of binding or seizure which would have been indicated by axial scoring in the guide liner were noted. Fretting was observed in the guide around the piston rings that measured to a depth of 0.003" with shallow ramp angles.
The 1B21-F013D valve failed to fully re-seat after the second automatic lift during post-operational testing. When the valve body was removed from the test stand in a hot condition, the disc closed under its own power. During inspection, the piston and stem assembly could move freely by hand in the guide cylinder. Fretting was observed in the guide around the piston rings that measured to a depth of 0.005" with shallow ramp angles. The piston and disc were measured to check for de-shouldering of the piston. Similar to the B21-F013A SRV, no signs of binding or seizure were present to indicate axial scoring in the guide liner from the two certification lifts and full re-closure.
The 1B21-F013H SRV failed to fully re-seat after the manual (solenoid) actuation during post-operational testing. Technicians did not attempt to close the valve by hand, but the disc was observed to be able to move in the open direction. During inspection and disassembly, the piston and stem assembly could be moved freely by hand in the guide cylinder. The thread damage to the piston and stem areas were similar in nature to the "A" valve (MVB SN 270), and "D" valve (MVB SN 92) with the piston able to be tilted relative to the stem, but still maintaining free movement. The piston was also able to move W' axially relative to the stem when pressure was applied in both directions; however, the threads for the jam nut were in pristine condition.
There were no indications of seizure or binding in the guide liner. Fretting was observed in the guide around the piston rings that measured to a depth of 0.015" with shallow ramp angles.
The Hatch Unit 2 MVBs removed from service during the forced outage in May 2016 were sent to NTS in Huntsville, AL. The MVBs were not as-found tested to preserve evidence and not introduce new damage from as-found limited flow testing. Based on disassembly and inspection results of the Hatch Unit 2 MVBs, no evidence was present to suggest that any of the eleven MVBs would not have passed as-found testing, and the MVBs fully stroked on the test stand. Although jam nuts were found loose and deformation was present on the MVB disc stems, the de-shouldering between the disc and the piston did not meet the threshold requirements of 0.004" that would allow rocking of the piston while in service.
NRC RAI #3 Have the valves been actuated in-service during the current Hatch Unit 2 or previous Hatch Unit 1 fuel cycles? If so, what were the results?
SNC Response to NRC RAI #3 The valves have not been lifted since installation. No valves in either unit have been stroked online/in-service since implementation of the 3-stage target rock design.
E-2