|
|
(8 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML14261A255 | | | number = ML14261A255 |
| | issue date = 09/23/2014 | | | issue date = 09/23/2014 |
| | title = Hatch Nuclear Plant, Units and 2 - Request for Additional Information (TAC Nos. MF4586 and MF4587) | | | title = Units and 2 - Request for Additional Information |
| | author name = Martin R E | | | author name = Martin R |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Pierce C R | | | addressee name = Pierce C |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000321, 05000366 | | | docket = 05000321, 05000366 |
| | license number = DPR-057, NPF-005 | | | license number = DPR-057, NPF-005 |
| | contact person = Martin R E | | | contact person = Martin R |
| | case reference number = TAC MF4586, TAC MF4587 | | | case reference number = TAC MF4586, TAC MF4587 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 *september 23, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 SUBJECT: HATCH NUCLEAR PLANT, UNITS 1 AND 2-REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF4586 AND MF4587) Dear Mr. Pierce: On August 15, 2014, the Southern Nuclear Operating Company (SNC) submitted a license amendment request to change Edwin I. Hatch Nuclear Plant, Units 1 and 2, Technical Specifications to add Critical Instrumentation Buses (Buses 1A and 1 B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems-Operating." The changes are propqsed in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, the critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source. The NRC staff finds that additional information is needed as set forth in the Enclosure. Please provide the additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Docket Nos. 50-321 and 50-366 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REQULATION REGARDING LICENSE AMENDMENT REQUEST TO ADD A CRITICAL INSTRUMENTATION ELECTRICAL BUS IN LCO 3.8.7 SOUTHERN NUCLEAR OPERATING COMPANY. INC. EDWIN I. HATCH NUCLEAR PLANT. UNITS 1 AND 2 By letter dated August 15, '2014 (Agencywide Document Access Management System (ADAMS) Accession No. ML 14227A921), Southern Nuclear Operating Company (SNC, the licensee) requested an amendment to the Facility Operating License for the Edwin L Hatch Nuclear Plant, Units 1 and 2 (HNP). The proposed amendment would revise the Technical Specifications (TS) to add Critical Instrumentation Buses (Buses 1A and 1 B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems-Operating." The changes are being made as a result of the licensee's decision to reconfigure its buses in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, th_e critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source. In order to complete its review of the license amendment request (LAR), the NRC staff needs the following additional information: 1. In the LAR, the licensee stated that the critical instruments to be relocated to the new critical instrumentation bus will include primary containment pressure, reactor and suppression pool water level, and drywall and suppression pool temperature indications. Additionally, the new critical instrument bus will be providing power and position indication to some Primary Containment Isolation Valves, as well as to the hardened vent valves, as required by the EA-13-1 09 Order [Order Modifying Licenses with Regard to Reliable Containment Vents]. Regarding each of the critical instruments to be relocated/added to the new critical instrumentation buses, please provide the following information: a) Instrument function. b) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 |
| * Critical Instrument Bus Number (e.g., A or B), and the original Instrument Bus Number/Essential Cabinet Number. c) For any new critical instrument which is not currently part of the "Post Accident Monitoring Instrumentation" listed in TS Table 3.3.3.1-1, explain why it is not included in the TS Table 3.3.3.1-1. Enclosure | | *september 23, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. |
| -2 -d) For each instrument being relocated/added, identify whether it will meet the requirements of NRC Order EA-12-049 or EA-13-109. 2. In its Overall Integrated Plan for HNP dated February 27, 2013, the licensee identified Spent Fuel Pool (SFP) Level as essential instrumentation during a BDBEE. Please provide details of the source of power for SFP Level instrumentation, if not planned to be fed from the critical instrument bus. 3. Please provide a summary of the analysis performed to determine the impact of adding additional loads on battery and battery charger sizing, and load profiles for surveillance tests. Confirm that the minimum battery voltage will continue to provide the minimum required voltage at the downstream devices to perform their safety function. I 4. Please provide details on the physical separation between the two trains of critical instrument buses, and a discussion of the adequacy of physical separation between the buses. 5. Please provide details on the protection coordination between the largest breaker located on each of the critical instrument bus and its upstream protection device. 6. Final Safety Analysis Report (FSAR) Se_ction 8.3.1.1.4 provides the description of the instrument power supply. Please provide a design description of the new AC inverters and critical instrument buses, which will be added to the FSAR.
| | Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| * 7. The LAR Section 3.0 states that the new equipment will be environmentally qualified to the appropriate IEEE standards. Clarify whether the new equipment will be subjected to harsh environment, and therefore qualified in accordance with 10 CFR 50.49. If they will be installed in a harsh environment, please provide a summary of the qualification report.
| | |
| September 23, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 SUBJECT: HATCH NUCLEAR PLANT, UNITS 1 AND 2-REQUEST FOR ADDITIONAL INFORMATION (TAG NOS. MF4586 AND MF4587) Dear Mr. Pierce: On August 15, 2014, the Southern Nuclear Operating Company (SNC) submitted a license amendment request to change Edwin I. Hatch Nuclear Plant, Units 1 and 2, Technical Specifications to add Critical Instrumentation Buses (Buses 1A and 1 B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems-Operating." The changes are proposed in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, the critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source. The NRC staff finds that additional information is needed as set forth in the Enclosure. Please provide the additional information within thirty (30) days of the date of this letter. Docket Nos. 50-321 and 50-366 Sincerely, /RAJ Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-1 R/F VGoel, NRR RidsAcrsAcnw_MaiiCTR Resource RidsNrrLASFigueroa Resource RidsNrrDoriDpr Resource RidsRgn2MaiiCenter Resource RidsNrrDorllpl2-1 Resource RidsNrrPMHatch Resource ADAMS A ccess1on N ML14261A2 o.: 55 *B *1 d t d sy ema1 ae OFFICE DORL/LPL2-1 /PM DORULPL2-1 /LA DE/EEEB/BC DORL/LPL2-1 /BC DORULPL2-1 /PM NAME RMartin SFigueroa JZimmerman RPascarelli RMartin DATE . 09/23/14 09/22/14 09/16/14 09/23/14 09/23/14 OFFICIAL RECORD COPY | | ==SUBJECT:== |
| }} | | HATCH NUCLEAR PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF4586 AND MF4587) |
| | |
| | ==Dear Mr. Pierce:== |
| | |
| | On August 15, 2014, the Southern Nuclear Operating Company (SNC) submitted a license amendment request to change Edwin I. Hatch Nuclear Plant, Units 1 and 2, Technical Specifications to add Critical Instrumentation Buses (Buses 1A and 1B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems- Operating." The changes are propqsed in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, the critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source. |
| | The NRC staff finds that additional information is needed as set forth in the Enclosure. Please provide the additional information within thirty (30) days of the date of this letter. |
| | Sincerely, fL~/11~ |
| | 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 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REQULATION REGARDING LICENSE AMENDMENT REQUEST TO ADD A CRITICAL INSTRUMENTATION ELECTRICAL BUS IN LCO 3.8.7 SOUTHERN NUCLEAR OPERATING COMPANY. INC. |
| | EDWIN I. HATCH NUCLEAR PLANT. UNITS 1 AND 2 By letter dated August 15, '2014 (Agencywide Document Access Management System (ADAMS) Accession No. ML14227A921), Southern Nuclear Operating Company (SNC, the licensee) requested an amendment to the Facility Operating License for the Edwin L Hatch Nuclear Plant, Units 1 and 2 (HNP). The proposed amendment would revise the Technical Specifications (TS) to add Critical Instrumentation Buses (Buses 1A and 1B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems- Operating." The changes are being made as a result of the licensee's decision to reconfigure its buses in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, th_e critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source. |
| | In order to complete its review of the license amendment request (LAR), the NRC staff needs the following additional information: |
| | : 1. In the LAR, the licensee stated that the critical instruments to be relocated to the new critical instrumentation bus will include primary containment pressure, reactor and suppression pool water level, and drywall and suppression pool temperature indications. Additionally, the new critical instrument bus will be providing power and position indication to some Primary Containment Isolation Valves, as well as to the hardened vent valves, as required by the EA-13-1 09 Order [Order Modifying Licenses with Regard to Reliable Containment Vents]. |
| | Regarding each of the critical instruments to be relocated/added to the new critical instrumentation buses, please provide the following information: |
| | a) Instrument function. |
| | b) |
| | * Critical Instrument Bus Number (e.g., A or B), and the original Instrument Bus Number/Essential Cabinet Number. |
| | c) For any new critical instrument which is not currently part of the "Post Accident Monitoring Instrumentation" listed in TS Table 3.3.3.1-1, explain why it is not included in the TS Table 3.3.3.1-1. |
| | Enclosure |
| | |
| | d) For each instrument being relocated/added, identify whether it will meet the requirements of NRC Order EA-12-049 or EA-13-109. |
| | : 2. In its Overall Integrated Plan for HNP dated February 27, 2013, the licensee identified Spent Fuel Pool (SFP) Level as essential instrumentation during a BDBEE. Please provide details of the source of power for SFP Level instrumentation, if not planned to be fed from the critical instrument bus. |
| | : 3. Please provide a summary of the analysis performed to determine the impact of adding additional loads on battery and battery charger sizing, and load profiles for surveillance tests. Confirm that the minimum battery voltage will continue to provide the minimum required voltage at the downstream devices to perform their safety function. |
| | I |
| | : 4. Please provide details on the physical separation between the two trains of critical instrument buses, and a discussion of the adequacy of physical separation between the buses. |
| | : 5. Please provide details on the protection coordination between the largest breaker located on each of the critical instrument bus and its upstream protection device. |
| | : 6. Final Safety Analysis Report (FSAR) Se_ction 8.3.1.1.4 provides the description of the instrument power supply. Please provide a design description of the new AC inverters and critical instrument buses, which will be added to the FSAR. * |
| | : 7. The LAR Section 3.0 states that the new equipment will be environmentally qualified to the appropriate IEEE standards. Clarify whether the new equipment will be subjected to harsh environment, and therefore qualified in accordance with 10 CFR 50.49. If they will be installed in a harsh environment, please provide a summary of the qualification report. |
| | |
| | September 23, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. |
| | Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | HATCH NUCLEAR PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION (TAG NOS. MF4586 AND MF4587) |
| | |
| | ==Dear Mr. Pierce:== |
| | |
| | On August 15, 2014, the Southern Nuclear Operating Company (SNC) submitted a license amendment request to change Edwin I. Hatch Nuclear Plant, Units 1 and 2, Technical Specifications to add Critical Instrumentation Buses (Buses 1A and 1B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems- Operating." The changes are proposed in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, the critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source. |
| | The NRC staff finds that additional information is needed as set forth in the Enclosure. Please provide the additional information within thirty (30) days of the date of this letter. |
| | Sincerely, |
| | /RAJ 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 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPL2-1 R/F VGoel, NRR RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsRgn2MaiiCenter Resource RidsNrrLASFigueroa Resource RidsNrrDorllpl2-1 Resource RidsNrrPMHatch Resource ADAMS Access1on No.: ML14261A255 *Bsy ema1*1 d ae t d OFFICE DORL/LPL2-1 /PM DORULPL2-1 /LA DE/EEEB/BC DORL/LPL2-1 /BC DORULPL2-1 /PM NAME RMartin SFigueroa JZimmerman RPascarelli RMartin DATE . 09/23/14 09/22/14 09/16/14 09/23/14 09/23/14 OFFICIAL RECORD COPY}} |
Similar Documents at Hatch |
---|
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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
- september 23, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
HATCH NUCLEAR PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF4586 AND MF4587)
Dear Mr. Pierce:
On August 15, 2014, the Southern Nuclear Operating Company (SNC) submitted a license amendment request to change Edwin I. Hatch Nuclear Plant, Units 1 and 2, Technical Specifications to add Critical Instrumentation Buses (Buses 1A and 1B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems- Operating." The changes are propqsed in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, the critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source.
The NRC staff finds that additional information is needed as set forth in the Enclosure. Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely, fL~/11~
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
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REQULATION REGARDING LICENSE AMENDMENT REQUEST TO ADD A CRITICAL INSTRUMENTATION ELECTRICAL BUS IN LCO 3.8.7 SOUTHERN NUCLEAR OPERATING COMPANY. INC.
EDWIN I. HATCH NUCLEAR PLANT. UNITS 1 AND 2 By letter dated August 15, '2014 (Agencywide Document Access Management System (ADAMS) Accession No. ML14227A921), Southern Nuclear Operating Company (SNC, the licensee) requested an amendment to the Facility Operating License for the Edwin L Hatch Nuclear Plant, Units 1 and 2 (HNP). The proposed amendment would revise the Technical Specifications (TS) to add Critical Instrumentation Buses (Buses 1A and 1B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems- Operating." The changes are being made as a result of the licensee's decision to reconfigure its buses in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, th_e critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source.
In order to complete its review of the license amendment request (LAR), the NRC staff needs the following additional information:
- 1. In the LAR, the licensee stated that the critical instruments to be relocated to the new critical instrumentation bus will include primary containment pressure, reactor and suppression pool water level, and drywall and suppression pool temperature indications. Additionally, the new critical instrument bus will be providing power and position indication to some Primary Containment Isolation Valves, as well as to the hardened vent valves, as required by the EA-13-1 09 Order [Order Modifying Licenses with Regard to Reliable Containment Vents].
Regarding each of the critical instruments to be relocated/added to the new critical instrumentation buses, please provide the following information:
a) Instrument function.
b)
- Critical Instrument Bus Number (e.g., A or B), and the original Instrument Bus Number/Essential Cabinet Number.
c) For any new critical instrument which is not currently part of the "Post Accident Monitoring Instrumentation" listed in TS Table 3.3.3.1-1, explain why it is not included in the TS Table 3.3.3.1-1.
Enclosure
d) For each instrument being relocated/added, identify whether it will meet the requirements of NRC Order EA-12-049 or EA-13-109.
- 2. In its Overall Integrated Plan for HNP dated February 27, 2013, the licensee identified Spent Fuel Pool (SFP) Level as essential instrumentation during a BDBEE. Please provide details of the source of power for SFP Level instrumentation, if not planned to be fed from the critical instrument bus.
- 3. Please provide a summary of the analysis performed to determine the impact of adding additional loads on battery and battery charger sizing, and load profiles for surveillance tests. Confirm that the minimum battery voltage will continue to provide the minimum required voltage at the downstream devices to perform their safety function.
I
- 4. Please provide details on the physical separation between the two trains of critical instrument buses, and a discussion of the adequacy of physical separation between the buses.
- 5. Please provide details on the protection coordination between the largest breaker located on each of the critical instrument bus and its upstream protection device.
- 6. Final Safety Analysis Report (FSAR) Se_ction 8.3.1.1.4 provides the description of the instrument power supply. Please provide a design description of the new AC inverters and critical instrument buses, which will be added to the FSAR. *
- 7. The LAR Section 3.0 states that the new equipment will be environmentally qualified to the appropriate IEEE standards. Clarify whether the new equipment will be subjected to harsh environment, and therefore qualified in accordance with 10 CFR 50.49. If they will be installed in a harsh environment, please provide a summary of the qualification report.
September 23, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
HATCH NUCLEAR PLANT, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION (TAG NOS. MF4586 AND MF4587)
Dear Mr. Pierce:
On August 15, 2014, the Southern Nuclear Operating Company (SNC) submitted a license amendment request to change Edwin I. Hatch Nuclear Plant, Units 1 and 2, Technical Specifications to add Critical Instrumentation Buses (Buses 1A and 1B for Unit 1 and Buses 2A and 2B for Unit 2) to LCO 3.8.7, "Distribution Systems- Operating." The changes are proposed in order to comply with the U.S. Nuclear Regulatory Commission (NRC) Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (BDBEE)." By modification, the critical instrumentation needed following a design basis accident and a BDBEE (Phase 1) will be moved from an emergency diesel generator backed power source to a battery backed direct current power source.
The NRC staff finds that additional information is needed as set forth in the Enclosure. Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely,
/RAJ 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
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F VGoel, NRR RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsRgn2MaiiCenter Resource RidsNrrLASFigueroa Resource RidsNrrDorllpl2-1 Resource RidsNrrPMHatch Resource ADAMS Access1on No.: ML14261A255 *Bsy ema1*1 d ae t d OFFICE DORL/LPL2-1 /PM DORULPL2-1 /LA DE/EEEB/BC DORL/LPL2-1 /BC DORULPL2-1 /PM NAME RMartin SFigueroa JZimmerman RPascarelli RMartin DATE . 09/23/14 09/22/14 09/16/14 09/23/14 09/23/14 OFFICIAL RECORD COPY