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| | number = ML13364A253 | | | number = ML13364A253 |
| | issue date = 01/08/2014 | | | issue date = 01/08/2014 |
| | title = Seabrook Station, Unit No. 1 - Request for Additional Information for License Amendment Request 11-04, Changes to Technical Specifications for New Fuel Vault (TAC No. MF3283) | | | title = Request for Additional Information for License Amendment Request 11-04, Changes to Technical Specifications for New Fuel Vault |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Walsh K | | | addressee name = Walsh K |
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| | docket = 05000443 | | | docket = 05000443 |
| | license number = | | | license number = |
| | contact person = Lamb J G | | | contact person = Lamb J |
| | case reference number = "TAC MF3283" | | | case reference number = "TAC MF3283" |
| | 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 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 January 8, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 8, 2014 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SEABROOK STATION, UNIT NO. 1-REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 11-04, CHANGES TO TECHNICAL SPECIFICATIONS FOR NEW FUEL VAULT (TAC NO. MF3283) | | SEABROOK STATION, UNIT NO. 1- REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 11-04, CHANGES TO TECHNICAL SPECIFICATIONS FOR NEW FUEL VAULT (TAC NO. MF3283) |
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| ==Dear Mr. Walsh:== | | ==Dear Mr. Walsh:== |
| By letter dated January 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12038A036), as supplemented by letter dated May 10, 2012, September 20, 2012, and March 27, 2013 (ADAMS Accession Nos. ML 12136A126, ML 12271A276, and ML 13099A022, respectively), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 11-04 for Seabrook Station, Unit No. 1 (Seabrook). The proposed change revises the technical specifications (TSs) for new and spent fuel storage, as a result of the new criticality analyses for the new fuel vault (NFV) and the spent fuel pool (SFP). The proposed amendment would revise the TSs to: (1) reflect elimination of the need to credit Boraflex neutron absorbing material for reactivity control in the SFP; (2) credit soluble boron, burn up, cooling time, peripheral leakage, and rod cluster control assemblies within the storage racks to maintain SFP reactivity within the effective neutron multiplication factor (kett) limits of Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.68(b)(4); and (3) revise the requirements for fuel storage within the NFV. By letter dated December 20, 2013 (ADAMS Accession No. ML 13360A045), NextEra requested that the SFP and NFV be separated into two separate LARs. The SFP LAR will be reviewed under TAC No. ME8688, and the NFV LARwill be reviewed under TAC No. MF3283. Please note the application dated January 30, 2012, included a mark-up of changes to the TS index. The TS index page mark-up was omitted from the supplement dated December 30, 2013, since Amendment No. 137, issued on June 17, 2013, removed the TS index from the Seabrook TSs, making any future TS index changes obsolete. | | |
| K. Walsh The NRC staff has determined that additional information is required to complete its review under TAC No. MF3283. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff on September 25, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Conference calls were held on October 24, 2013, and on January 6, 2014, and Mr. Kilby agreed that NextEra would respond to the RAI by March 15, 2014. Please note that if you do not respond to the RAI by March 15, 2014, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of 10 CFR, Section 2.1 08, "Denial of application for failure to supply information." If you have questions, you can contact me at 301-415-3100 or by e-mail at John. Lamb@nrc.gov. Docket No. 50-443 | | By letter dated January 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12038A036), as supplemented by letter dated May 10, 2012, September 20, 2012, and March 27, 2013 (ADAMS Accession Nos. ML12136A126, ML12271A276, and ML13099A022, respectively), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 11-04 for Seabrook Station, Unit No. 1 (Seabrook). |
| | The proposed change revises the technical specifications (TSs) for new and spent fuel storage, as a result of the new criticality analyses for the new fuel vault (NFV) and the spent fuel pool (SFP). |
| | The proposed amendment would revise the TSs to: (1) reflect elimination of the need to credit Boraflex neutron absorbing material for reactivity control in the SFP; (2) credit soluble boron, burn up, cooling time, peripheral leakage, and rod cluster control assemblies within the storage racks to maintain SFP reactivity within the effective neutron multiplication factor (kett) limits of Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.68(b)(4); and (3) revise the requirements for fuel storage within the NFV. |
| | By letter dated December 20, 2013 (ADAMS Accession No. ML13360A045), NextEra requested that the SFP and NFV be separated into two separate LARs. The SFP LAR will be reviewed under TAC No. ME8688, and the NFV LARwill be reviewed under TAC No. MF3283. |
| | Please note the application dated January 30, 2012, included a mark-up of changes to the TS index. The TS index page mark-up was omitted from the supplement dated December 30, 2013, since Amendment No. 137, issued on June 17, 2013, removed the TS index from the Seabrook TSs, making any future TS index changes obsolete. |
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| | K. Walsh The NRC staff has determined that additional information is required to complete its review under TAC No. MF3283. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff on September 25, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Conference calls were held on October 24, 2013, and on January 6, 2014, and Mr. Kilby agreed that NextEra would respond to the RAI by March 15, 2014. Please note that if you do not respond to the RAI by March 15, 2014, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of 10 CFR, Section 2.1 08, "Denial of application for failure to supply information." |
| | If you have questions, you can contact me at 301-415-3100 or by e-mail at John. Lamb@nrc.gov. |
| | Sincerely,~~ |
| | G. Lamb, Acting Chief nt Licensing Branch 1-2 ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-443 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/encl: Distribution via Listserv G. Lamb, Acting Chief nt Licensing Branch 1-2 ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 11-04 NEXTERA ENERGY SEABROOK. LLC. SEABROOK STATION. UNIT NO.1 DOCKET NO. 50-443 By letter dated January 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12038A036), as supplemented by letter dated May 10, 2012, September 20, 2012, and March 27, 2013 (ADAMS Accession Nos. ML 12136A126, ML 12271A276, and ML 13099A022, respectively), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 11-04 for Seabrook Station, Unit No. 1 (Seabrook). The proposed change revises the technical specifications (TSs) for new and spent fuel storage, as a result of the new criticality analyses for the new fuel vault (NFV) and the spent fuel pool (SFP). The proposed amendment would revise the TSs to: (1) reflect elimination of the need to credit Boraflex neutron absorbing material for reactivity control in the SFP; (2) credit soluble boron, burnup, cooling time, peripheral leakage, and rod cluster control assemblies within the storage racks to maintain SFP reactivity within the effective neutron multiplication factor (kett) limits of Title 10 of the Code of Federal Regulations, Section 50.68(b)(4); and (3) revise the requirements for fuel storage within the NFV. By letter dated December 20, 2013 (ADAMS Accession No. ML 13360A045), NextEra requested that the SFP and NFV be separated into two separate LARs. The SFP LARwill be reviewed under TAC No. ME8688 and the NFV LARwill be reviewed under TAC No. MF3283. Please note the application dated January 30, 2012, included a mark-up of changes to the TS index. The TS index page mark-up was omitted from the supplement dated December 30, 2013, since Amendment No. 137, issued on June 17, 2013, removed the TS index from the Seabrook TSs, making any future TS index changes obsolete. The NRC staff has determined that additional information is necessary to complete its review under MF3283. REQUEST FOR ADDITIONAL INFORMATION (RAI) 1. In response to a previous RAI, the licensee has indicated " ... the exact isotopic composition of the concrete and their uncertainties in the Seabrook NFV is unknown, .. . " To determine the importance of the concrete composition for the NFV, the NRC staff performed a sensitivity study using the concrete composition used by the licensee, other concrete compositions in the licensee's cited reference, and those available in SCALE 6.1.2. That sensitivity study indicates two issues with the concrete composition the licensee used in its analysis for optimum moderation conditions. First, the concrete Enclosure composition the licensee used is likely the least conservative compositions sampled in the sensitivity study. Second, the licensee's uncertainty study did not cover the full range of isotopic compositions in the licensee's cited reference. The NRC staff's sensitivity study suggests the effect of the concrete composition may be enough to preclude approval of the licensee's requested change to its NFV storage requirements. Therefore, the NRC staff requests the licensee provide one of the following: | | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
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| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 11-04 NEXTERA ENERGY SEABROOK. LLC. |
| | SEABROOK STATION. UNIT NO.1 DOCKET NO. 50-443 By letter dated January 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12038A036), as supplemented by letter dated May 10, 2012, September 20, 2012, and March 27, 2013 (ADAMS Accession Nos. ML12136A126, ML12271A276, and ML13099A022, respectively), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 11-04 for Seabrook Station, Unit No. 1 (Seabrook). |
| | The proposed change revises the technical specifications (TSs) for new and spent fuel storage, as a result of the new criticality analyses for the new fuel vault (NFV) and the spent fuel pool (SFP). |
| | The proposed amendment would revise the TSs to: (1) reflect elimination of the need to credit Boraflex neutron absorbing material for reactivity control in the SFP; (2) credit soluble boron, burnup, cooling time, peripheral leakage, and rod cluster control assemblies within the storage racks to maintain SFP reactivity within the effective neutron multiplication factor (kett) limits of Title 10 of the Code of Federal Regulations, Section 50.68(b)(4); and (3) revise the requirements for fuel storage within the NFV. |
| | By letter dated December 20, 2013 (ADAMS Accession No. ML13360A045), NextEra requested that the SFP and NFV be separated into two separate LARs. The SFP LARwill be reviewed under TAC No. ME8688 and the NFV LARwill be reviewed under TAC No. MF3283. |
| | Please note the application dated January 30, 2012, included a mark-up of changes to the TS index. The TS index page mark-up was omitted from the supplement dated December 30, 2013, since Amendment No. 137, issued on June 17, 2013, removed the TS index from the Seabrook TSs, making any future TS index changes obsolete. |
| | The NRC staff has determined that additional information is necessary to complete its review under MF3283. |
| | REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | : 1. In response to a previous RAI, the licensee has indicated "... the exact isotopic composition of the concrete and their uncertainties in the Seabrook NFV is unknown, .. |
| | ." To determine the importance of the concrete composition for the NFV, the NRC staff performed a sensitivity study using the concrete composition used by the licensee, other concrete compositions in the licensee's cited reference, and those available in SCALE 6.1.2. That sensitivity study indicates two issues with the concrete composition the licensee used in its analysis for optimum moderation conditions. First, the concrete Enclosure |
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| | composition the licensee used is likely the least conservative compositions sampled in the sensitivity study. Second, the licensee's uncertainty study did not cover the full range of isotopic compositions in the licensee's cited reference. The NRC staff's sensitivity study suggests the effect of the concrete composition may be enough to preclude approval of the licensee's requested change to its NFV storage requirements. |
| | Therefore, the NRC staff requests the licensee provide one of the following: |
| * A revised nuclear criticality safety analysis that accounts for the actual concrete composition along with changes that are expected over time, along with how the actual concrete composition was determined. | | * A revised nuclear criticality safety analysis that accounts for the actual concrete composition along with changes that are expected over time, along with how the actual concrete composition was determined. |
| * A revised nuclear criticality safety analysis with a bounding concrete composition, which includes changes that are expected over time, along with the justification for using that concrete composition. | | * A revised nuclear criticality safety analysis with a bounding concrete composition, which includes changes that are expected over time, along with the justification for using that concrete composition. |
| * A withdrawal of that portion of the LAR concerning the NFV. 2. The NRC staff has reviewed the licensee's response to a previous RAI regarding the applicability of the criticality code validation at elevated temperatures for the NFV. The NRC staff requests the licensee provide a technical justification for using the validation at the elevated temperatures and to adequately account for the elevated temperatures in the analysis. | | * A withdrawal of that portion of the LAR concerning the NFV. |
| K. Walsh The NRC staff has determined that additional information is required to complete its review under TAC No. MF3283. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff on September 25, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Conference calls were held on October 24, 2013, and on January 6, 2014, and Mr. Kilby agreed that NextEra would respond to the RAI by March 15, 2014. Please note that if you do not respond to the RAI by March 15, 2014, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of 10 CFR, Section 2.1 08, "Denial of application for failure to supply information." If you have questions, you can contact me at 301-415-3100 or by e-mail at John.Lamb@nrc.gov. Docket No. 50-443
| | : 2. The NRC staff has reviewed the licensee's response to a previous RAI regarding the applicability of the criticality code validation at elevated temperatures for the NFV. The NRC staff requests the licensee provide a technical justification for using the validation at the elevated temperatures and to adequately account for the elevated temperatures in the analysis. |
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| ==Enclosure:==
| | ML13364A253 OFFICE LPL 1-2/PM LPL 1-2/LA SRXB/BC LPL 1-2/PM NAME REnnis for Jlamb A Baxter CJackson* Jlamb DATE 1/7/14 1/8/14 09/24/13 1/8/14}} |
| Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNRRDoriLpl1-2 Resource RidsAcrsAcnw_MaiiCTR Resource Sincerely, Ira/ John G. Lamb, Acting Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPLI-2 R/F RidsNrrPMSeabrook Resource RidsNrrDoriDpr Resource RidsNrrLAABaxter Resource RidsRgn 1 MaiiCenter Resource ADAMS Accession No: ML 13364A253 OFFICE LPL 1-2/PM LPL 1-2/LA SRXB/BC LPL 1-2/PM NAME REnnis for Jlamb A Baxter CJackson* Jlamb DATE 1/7/14 1/8/14 09/24/13 1/8/14 OFFICIAL RECORD COPY
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Letter Sequence RAI |
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MONTHYEARML13364A2532014-01-0808 January 2014
Request for Additional Information for License Amendment Request 11-04, Changes to Technical Specifications for New Fuel Vault
Project stage: RAI
ML14078A6242014-04-18018 April 2014
Request for Withholding Information from Public Disclosure Regarding License Amendment Request 11-04, Changes to Technical Specifications for New Fuel Vault
Project stage: Withholding Request Acceptance
ML15118A6322015-05-18018 May 2015
Issuance of Amendment Regarding License Amendment Request Regarding New Fuel Valut
Project stage: Approval
2014-04-18
[Table View] |
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Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
ML24022A0652024-01-22022 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024
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Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023
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L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023
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L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023
Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule
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IR 05000443/20234032023-11-0707 November 2023
Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401
IR 05000443/20230032023-11-0606 November 2023
Integrated Inspection Report 05000443/2023003
IR 05000443/20230102023-10-19019 October 2023
Triennial Fire Protection Inspection Report 05000443/2023010
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IR 05000443/20234012023-09-0808 September 2023
Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only)
IR 05000443/20234202023-09-0505 September 2023
Security Baseline Inspection Report 05000443/2023420
IR 05000443/20230052023-08-31031 August 2023
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IR 05000443/20233022023-08-16016 August 2023
Operator Licensing Retake Examination Report 05000443/2023302
IR 05000443/20230022023-08-0808 August 2023
Integrated Inspection Report 05000443/2023002
L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
ML23201A0872023-08-0303 August 2023
Audit Plan in Support of Review of License Amendment
L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023
Preparation and Scheduling of Operator Licensing Examinations
L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023
Inservice Inspection Examination Report
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Operator Licensing Retake Examination Approval
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ML23157A0722023-06-0606 June 2023
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Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update
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IR 05000443/20233012023-05-15015 May 2023
Initial Operator Licensing Examination Report 05000443/2023301
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License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves
IR 05000443/20230012023-05-11011 May 2023
Integrated Inspection Report 05000443/2023001
ML23129A0312023-05-0909 May 2023
Reactor Operator Retake License Examination
ML23117A3652023-05-0404 May 2023
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves
SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023
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SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023
2022 Annual Radioactive Effluent Release Report
SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023
2022 Annual Environmental Operating Report
L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023
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ML23088A1522023-03-29029 March 2023
Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
ML23073A1562023-03-23023 March 2023
Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code
L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023
License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves
L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023
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L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023
Revised Steam Generator Tube Inspection Report
ML23020A1002023-03-0303 March 2023
OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter
2024-01-29
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23318A0772023-11-14014 November 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011
ML23173A1522023-06-22022 June 2023
Request for Additional Information NextEra Fleet Emergency Plan Amendment Request
ML23011A3082023-01-11011 January 2023
Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074)
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Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep
ML22228A0552022-08-15015 August 2022
Request for Additional Information Steam Generator Tube Inspection Report Review
ML22153A4152022-05-31031 May 2022
Request for Additional Information Re 120V Inverter LAR from TS Branch - Final
ML22062B6642022-02-0707 February 2022
Request for Additional Information 120V Inverter LAR from the Electrical Branch
ML22063A0002022-01-25025 January 2022
Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR
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ML21054A0482021-02-23023 February 2021
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2023-06-22
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 8, 2014 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1- REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 11-04, CHANGES TO TECHNICAL SPECIFICATIONS FOR NEW FUEL VAULT (TAC NO. MF3283)
Dear Mr. Walsh:
By letter dated January 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12038A036), as supplemented by letter dated May 10, 2012, September 20, 2012, and March 27, 2013 (ADAMS Accession Nos. ML12136A126, ML12271A276, and ML13099A022, respectively), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 11-04 for Seabrook Station, Unit No. 1 (Seabrook).
The proposed change revises the technical specifications (TSs) for new and spent fuel storage, as a result of the new criticality analyses for the new fuel vault (NFV) and the spent fuel pool (SFP).
The proposed amendment would revise the TSs to: (1) reflect elimination of the need to credit Boraflex neutron absorbing material for reactivity control in the SFP; (2) credit soluble boron, burn up, cooling time, peripheral leakage, and rod cluster control assemblies within the storage racks to maintain SFP reactivity within the effective neutron multiplication factor (kett) limits of Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.68(b)(4); and (3) revise the requirements for fuel storage within the NFV.
By letter dated December 20, 2013 (ADAMS Accession No. ML13360A045), NextEra requested that the SFP and NFV be separated into two separate LARs. The SFP LAR will be reviewed under TAC No. ME8688, and the NFV LARwill be reviewed under TAC No. MF3283.
Please note the application dated January 30, 2012, included a mark-up of changes to the TS index. The TS index page mark-up was omitted from the supplement dated December 30, 2013, since Amendment No. 137, issued on June 17, 2013, removed the TS index from the Seabrook TSs, making any future TS index changes obsolete.
K. Walsh The NRC staff has determined that additional information is required to complete its review under TAC No. MF3283. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff on September 25, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Conference calls were held on October 24, 2013, and on January 6, 2014, and Mr. Kilby agreed that NextEra would respond to the RAI by March 15, 2014. Please note that if you do not respond to the RAI by March 15, 2014, or provide an acceptable alternate date in writing, the NRC staff may reject your LAR under the provisions of 10 CFR, Section 2.1 08, "Denial of application for failure to supply information."
If you have questions, you can contact me at 301-415-3100 or by e-mail at John. Lamb@nrc.gov.
Sincerely,~~
G. Lamb, Acting Chief nt Licensing Branch 1-2 ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 11-04 NEXTERA ENERGY SEABROOK. LLC.
SEABROOK STATION. UNIT NO.1 DOCKET NO. 50-443 By letter dated January 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12038A036), as supplemented by letter dated May 10, 2012, September 20, 2012, and March 27, 2013 (ADAMS Accession Nos. ML12136A126, ML12271A276, and ML13099A022, respectively), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 11-04 for Seabrook Station, Unit No. 1 (Seabrook).
The proposed change revises the technical specifications (TSs) for new and spent fuel storage, as a result of the new criticality analyses for the new fuel vault (NFV) and the spent fuel pool (SFP).
The proposed amendment would revise the TSs to: (1) reflect elimination of the need to credit Boraflex neutron absorbing material for reactivity control in the SFP; (2) credit soluble boron, burnup, cooling time, peripheral leakage, and rod cluster control assemblies within the storage racks to maintain SFP reactivity within the effective neutron multiplication factor (kett) limits of Title 10 of the Code of Federal Regulations, Section 50.68(b)(4); and (3) revise the requirements for fuel storage within the NFV.
By letter dated December 20, 2013 (ADAMS Accession No. ML13360A045), NextEra requested that the SFP and NFV be separated into two separate LARs. The SFP LARwill be reviewed under TAC No. ME8688 and the NFV LARwill be reviewed under TAC No. MF3283.
Please note the application dated January 30, 2012, included a mark-up of changes to the TS index. The TS index page mark-up was omitted from the supplement dated December 30, 2013, since Amendment No. 137, issued on June 17, 2013, removed the TS index from the Seabrook TSs, making any future TS index changes obsolete.
The NRC staff has determined that additional information is necessary to complete its review under MF3283.
REQUEST FOR ADDITIONAL INFORMATION (RAI)
- 1. In response to a previous RAI, the licensee has indicated "... the exact isotopic composition of the concrete and their uncertainties in the Seabrook NFV is unknown, ..
." To determine the importance of the concrete composition for the NFV, the NRC staff performed a sensitivity study using the concrete composition used by the licensee, other concrete compositions in the licensee's cited reference, and those available in SCALE 6.1.2. That sensitivity study indicates two issues with the concrete composition the licensee used in its analysis for optimum moderation conditions. First, the concrete Enclosure
composition the licensee used is likely the least conservative compositions sampled in the sensitivity study. Second, the licensee's uncertainty study did not cover the full range of isotopic compositions in the licensee's cited reference. The NRC staff's sensitivity study suggests the effect of the concrete composition may be enough to preclude approval of the licensee's requested change to its NFV storage requirements.
Therefore, the NRC staff requests the licensee provide one of the following:
- A revised nuclear criticality safety analysis that accounts for the actual concrete composition along with changes that are expected over time, along with how the actual concrete composition was determined.
- A revised nuclear criticality safety analysis with a bounding concrete composition, which includes changes that are expected over time, along with the justification for using that concrete composition.
- A withdrawal of that portion of the LAR concerning the NFV.
- 2. The NRC staff has reviewed the licensee's response to a previous RAI regarding the applicability of the criticality code validation at elevated temperatures for the NFV. The NRC staff requests the licensee provide a technical justification for using the validation at the elevated temperatures and to adequately account for the elevated temperatures in the analysis.
ML13364A253 OFFICE LPL 1-2/PM LPL 1-2/LA SRXB/BC LPL 1-2/PM NAME REnnis for Jlamb A Baxter CJackson* Jlamb DATE 1/7/14 1/8/14 09/24/13 1/8/14
