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Category:Letter
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Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 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 IR 05000321/20240912024-08-27027 August 2024 NRC Investigation Report 2-2023-003 and NOV - NRC Inspection Report 05000321/2024091 and 05000366/2024091 IR 05000321/20240052024-08-26026 August 2024 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2 - Report 05000321/2024005 and 05000366/2024005 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 IR 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 05000321/LER-2024-002-01, Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications2024-07-0303 July 2024 Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications 05000321/LER-2024-003, Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link2024-07-0303 July 2024 Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link 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 05000321/LER-2024-002, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024 Manual Reactor Trip Due to Loss of Feedwater 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 ML23032A3322024-04-24024 April 2024 Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes 05000366/LER-2024-002, Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications2024-04-24024 April 2024 Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications IR 05000321/20240012024-04-22022 April 2024 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 05000321/LER-2024-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2024-04-0909 April 2024 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 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. ML23275A2402024-03-22022 March 2024 SNC Fleet - Issuance of Environmental Assessment and Finding of No Significant Impact Regarding Exemption from the Requirements of 10 CFR Part 73, Section 73.2, Definitions (EPID Nos. L-2023-LLE-0018 & L-2023-LLE-0021) - Letter 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 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) 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 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A1552024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572 ML24278A0052024-10-0303 October 2024 Document Request for Hatch Nuclear Plant - IP 92702 Follow-Up Radiation Protection Inspection - Inspection Report 2024-04 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 ML24208A1742024-07-26026 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 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 2024-07-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 31,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295. Bin - 038 Birmingham. AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME9004 AND ME9005)
Dear Mr. Ajluni:
By letter dated July 5, 2012 (Agencywide Documents Access and Management System Accession No. ML12188A721), Southern Nuclear Operating Company, Inc., submitted a license amendment request to change the Technical Specification to revise the minimum water level in the plant service water pump well. The U.S. Nuclear Regulatory Commission staff finds that additional information in the hydrology area is needed as set forth in the Enclosure.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely,
() ~fYl.~
f ~ert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 cc w/encl: Distribution via Listserv
REqUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION EDWIN I. HATCH NUCLEAR PLANT. UNITS 1 AND 2 SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-321 AND 50-366
- 1. As stated in the license amendment request (LAR), Edwin I. Hatch Nuclear Plant, Units 1 and 2 (HNP 1 and 2), uses a recession formula equation to compute the projected time (in days) for the plant service water (PSW) pump well level to reach 60.0 ft mean sea level (MSL), which is the minimum level required for post-Ioss-of-coolant accident cooling requirements as limited by the Standby Service Water Pump. This formula contains a recession constant represented by the letter "k" (also known as depletion factor) which represents the type of flow (surface runoff, interflow, or base flow) that dominates the area being studied. Furthermore, the LAR states that it uses a value of 0.995 (base flow in stream flow is dominant) for the recession constant when using the equation.
However, reference 3 of the LAR states that the overlapping ranges for the selection of "k" values represent the inherent difficulties in identifying a particular recession as being surface runoff, interflow, or base flow. Furthermore, Reference 3 also lists the range for baseflow as being between 0.93 - 0.995 and the LAR states that its baseflow "k" range goes from 0.995 - 0.997.
a) Please provide additional information on the general process, criteria and analysis that has been used by the licensee in order to determine the recession constant "k" value of 0.995 for the site, with special emphasis on how the aforementioned limitations of Reference 3 were resolved, if applicable. These limitations include, but are not limited to, establishing distinctions between interflow and baseflow, seasonally variable components of baseflow analyzed over a specified period of time, etc.
b) Please provide an explanation on what effect or consequences, if any, is presented by the licensee selecting a baseflow range (0.995 - 0.997) for uk" that is higher than that stated by the source reference listed in the LAR (0.93 - 0.995). The explanation should also have a special emphasis on the acceptability of the licensee selecting values higher than those stated in the reference paper (Reference 3 of the LAR).
Additionally, the LAR states that the recession formula has been used for a number of years. Therefore past precedence and/or references should be included as part of the response, if available.
c) Please clarify if the recession formula was used using the same uk" value (0.995) for each river level in the discharge rating table or if different "k" values, as permitted by the HNP 1 and 2 range (0.995 - 0.997), were used when determining the projected time to reach 60.0 ft MSL. If a range of values were used, additional information that Enclosure
-2 justifies this method and demonstrates added conservatisms should be included. In addition, past precedence and/or references should be included as part of the response, if available.
- 2. Reference 3 of the LAR states that any individual recession is a short-term event that varies from successive recessions based on several factors. Therefore, for longer period events, it is necessary to combine individual base flow recessions in order to provide an average characterization of base flow, called a master recession curve (MRC). Furthermore, it states that the MRC represents the most frequent depletion simulation since recession rates are influenced by antecedent recharge conditions.
a) Please provide a detailed explanation that clarifies the threshold of what constitutes a short-term event versus a long-term event in terms of having to calculate a single recession or a MCR curve. The response should emphasize why the option selected to characterize baseflow at HNP 1 and 2 is acceptable in comparison to the single versus average methods and demonstrate that the most frequent depletion simulation has been obtained based on the method selected and, therefore, used to determine the projected time to reach 60.0 ft MSL. In addition, past precedence and/or references should be included as part of the response, if available.
- 3. The LAR states that, based on Table 2 of the LAR and the use of the recession equation, the time (in days) for the water level to drop to 60.0 ft MSL would be 66 days.
However, it is not clear from Table 2 how this value was obtained.
a) Please provide a summary of the calculations performed in order to obtain the value of 66 days from Table 2 of the LAR.
b) Please provide a graphical representation, similar to the example of Figure 3 provided in the LAR, which visually shows the "River Level versus Time" plot using the obtained results from the recession equation and discharge table. This figure should clearly demonstrate the availability of water for 66 days before reaching river level 60.0 ft MSL, as required by the limiting Standby Service Water Pump.
October 31, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME9004 AND ME9005)
Dear Mr. Ajluni:
By letter dated July 5,2012 (Agencywide Documents Access and Management System Accession No. ML12188A721), Southern Nuclear Operating Company, Inc., submitted a license amendment request to change the Technical Specification to revise the minimum water level in the plant service water pump well. The U.S. Nuclear Regulatory Commission staff finds that additional information in the hydrology area is needed as set forth in the Enclosure.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely, IRA!
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource G. Purciarello, NRR G. Casto, NRR RidsNrrPMHatch Resource LPL2-1R/F
. N0.: ML12297A246 ADAMS A ccesslon *Bsyemal'1 dated ** V'la Emal'I OFFICE DORULPL2-1/PM DORULPL2-1/LA ** DLR/RERBIIBC* DORULPL2-1/BC DORULPL2-1/PM NAME RMartin SFigueroa MMurphy RPascarelii RMartin DATE 10/24112 10/24/12 10/22112 10/26/12 10/31/12 OFFICIAL RECORD COPY