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| | 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) |
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| =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}} |
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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)
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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
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NRR E-mail Capture - RAI: Hatch Emergency TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LAR
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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)
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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
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Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008)
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PIR Notification Letter 2017
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NRR E-mail Capture - Hatch 1 and 2 - Draft Request for Additional Information Request for Alternative No. HNP-ISI-ALT-05-05
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Request for Additional Information, Fourth 10-Year ISI Interval Relief Requests
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ML16330A1282016-12-0505 December 2016
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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
