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| {{#Wiki_filter:. \. U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station NEXTera SEABROOK September 6, 2016 10 CFR 54 SBK-L-16134 Docket No. 50-443 Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application | | {{#Wiki_filter:. \. U.S. Nuclear Regulatory Commission Attention: |
| | Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station NEXTera SEABROOK September 6, 2016 10 CFR 54 SBK-L-16134 Docket No. 50-443 Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application |
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| ==References:== | | ==References:== |
| : 1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010. (Accession Number ML101590099) 2. NRC Letter, Requests for Additional Information for the Severe Accident Mitigation Alternatives ( S AM A) Review of the Seabrook Station License Renewal Application (TAC No. ME3959), July 8, 2016, (Accession Number ML16187A204) 3. Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 (Accession Number ML16125Al50) In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted an application for a renewed facility operating license for Seabrook Station Unit 1 in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54. In Reference 2, the staff requested additional information to support addressing the Commission Memorandum and Order (CLI-16-07) which directed the NRC staff to supplement the SAMA analysis performed for the Indian Point Units 2 and 3 LRA with sensitivity analyses for two factors used in the SAMA analysis (Reference 3). The NextEra Seabrook response to the RAI is provided in the enclosure to this letter. The RAI response includes the results of a sensitivity analysis for the same two input parameters addressed by the Commission in CLI-16-07. The sensitivity analysis demonstrates that the SAMA analysis previously submitted for Seabrook Station remains bounding. NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 | | : 1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," |
| ' ' United States Nuclear Regulatory Commission 'SBK-L-16134 I Page 2 No new commitments are being made in this submittal. If there are any questions or additional information is needed, please contact Mr. Edward J Carley, Engineering Supervisor -License Renewal, at (603) 773-7957. If you have any questions regarding this correspondence, please contact Mr. Ken Browne, Licensing Manager, at (603) 773-7932. I declare under penalty of perjury that the foregoing is true and correct. Executed on September ___fo__, 2016 Sincerely, | | May 25, 2010. (Accession Number ML101590099) |
| | : 2. NRC Letter, Requests for Additional Information for the Severe Accident Mitigation Alternatives |
| | ( S AM A) Review of the Seabrook Station License Renewal Application (TAC No. ME3959), |
| | July 8, 2016, (Accession Number ML16187A204) |
| | : 3. Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 (Accession Number ML16125Al50) |
| | In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted an application for a renewed facility operating license for Seabrook Station Unit 1 in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54. In Reference 2, the staff requested additional information to support addressing the Commission Memorandum and Order (CLI-16-07) which directed the NRC staff to supplement the SAMA analysis performed for the Indian Point Units 2 and 3 LRA with sensitivity analyses for two factors used in the SAMA analysis (Reference 3). The NextEra Seabrook response to the RAI is provided in the enclosure to this letter. The RAI response includes the results of a sensitivity analysis for the same two input parameters addressed by the Commission in CLI-16-07. The sensitivity analysis demonstrates that the SAMA analysis previously submitted for Seabrook Station remains bounding. NextEra Energy |
| | : Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 |
| | ' ' United States Nuclear Regulatory Commission |
| | 'SBK-L-16134 I Page 2 No new commitments are being made in this submittal. |
| | If there are any questions or additional information is needed, please contact Mr. Edward J Carley, Engineering Supervisor |
| | -License Renewal, at (603) 773-7957. |
| | If you have any questions regarding this correspondence, please contact Mr. Ken Browne, Licensing |
| | : Manager, at (603) 773-7932. |
| | I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on September |
| | : ___fo__, |
| | 2016 Sincerely, |
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| ==Enclosure:== | | ==Enclosure:== |
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| Response to RAI Related to Severe Accident Mitigation Alternatives cc: D. H. Dorman J.C. Poole P. C. Cataldo T. M. Tran L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal NRC Project Manager, License Renewal Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 | | Response to RAI Related to Severe Accident Mitigation Alternatives cc: D. H. Dorman J.C. Poole P. C. Cataldo T. M. Tran L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal NRC Project Manager, License Renewal Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 |
| . ,, U.S. Nuclear Regulatory Commission | | . ,, U.S. Nuclear Regulatory Commission |
| * SBK-L-16134 /Enclosure I Page 1 Enclosure to SBK-L-16134 NextEra Energy Seabrook Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application | | * SBK-L-16134 |
| . \ U.S. Nuclear Regulatory Commission 'SBK-L-16134 /Enclosure I Page 2 NRC RAI for Licensees regarding CLI-16-07 BACKGROUND: On May 4, 2016, the Commission issued a Memorandum and Order (CLI-16-07) in the Indian Point license renewal proceeding, in which it directed the Staff to supplement the Indian Point Severe Accident Mitigation Alternatives (SAMA) analysis with sensitivity analyses. Specifically, the Commission held that documentation was lacking for two inputs (TIMDEC and CDNFRM) used in the MACCS computer analyses, and that uncertainties in those input values could potentially affect the SAMA analysis cost-benefit conclusions. The Commission therefore directed the Staff to perform additional sensitivity analyses. The two inputs (TIMDEC and CDNFRM), are commonly used in the SAMA analyses performed for license renewal applications (LRAs ). These two input values were generally based on the values provided in NUREG-1150, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants" and NUREG/CR-3673, "Economic Risks of Nuclear Power Reactor Accidents." The TIMDEC input value defines the time required for completing decontamination to a specified degree. The CDNFRM input parameter defines the cost (on a per person basis) of decontaminating non-farmland by a specified decontamination factor. The CDNFRM values used in NUREG-1150 ($3,000/personfor decontamination factor of 3 and $8,000/person for decontamination factor of 15) stem from decontamination cost estimates provided in NUREG/CR-3673, the same 1984 economic risk study referenced in support of the decontamination time inputs. These decontamination cost inputs are commonly escalated to account for inflation. REQUEST FOR ADDITIONAL INFORMATION: The NRC Staff believes the Commission's decision in CLI-16-07 may be applicable to the SAMA analysis performed for Seabrook Station, Unit 1 (Seabrook), inasmuch as that analysis may have also relied upon the NUREG-1150 values for TIMDEC and CDNFRM. We therefore request that NextEra Energy Seabrook, LLC (NextEra), either justify why CLI-16-07 does not apply to the SAMA analysis performed for Seabrook or supplement the SAMA analysis with sensitivity analyses for the CDNFRM and TIMDEC values. NextEra is requested to review the input values specified_in CLI-16-07 for the Indian Point LRA, and (1) to apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000 for the CDNFRM values for the decontamination factor of 15) or, in the alternative, (2) to explain, with sufficient justification, its rationale for choosing any other value(s) for its sensitivity analyses. In any event, NextEra should execute sensitivity analyses for the release categories modeled that exceed 1015 Becquerels ofCs-137 released. NextEra is requested to evaluate how these sensitivity analyses may affect its identification of potentially cost-beneficial SAMAs. Finally, upon completing its sensitivity analysis, NextEra is requested to submit the spreadsheet (or equivalent table if another method is used) that conveys the population dose and off-site economic cost for each release category and integrates the results into a Population Dose Risk and an Offsite Economic Cost Risk for Seabrook. | | /Enclosure I Page 1 Enclosure to SBK-L-16134 NextEra Energy Seabrook Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application |
| . \. ' U.S. Nuclear Regulatory Commission 'SBK-L-16134 /Enclosure I Page 3 NextEra Seabrook Response | | . \ U.S. Nuclear Regulatory Commission |
| | 'SBK-L-16134 |
| | /Enclosure I Page 2 NRC RAI for Licensees regarding CLI-16-07 BACKGROUND: |
| | On May 4, 2016, the Commission issued a Memorandum and Order (CLI-16-07) in the Indian Point license renewal proceeding, in which it directed the Staff to supplement the Indian Point Severe Accident Mitigation Alternatives (SAMA) analysis with sensitivity analyses. |
| | Specifically, the Commission held that documentation was lacking for two inputs (TIMDEC and CDNFRM) used in the MACCS computer |
| | : analyses, and that uncertainties in those input values could potentially affect the SAMA analysis cost-benefit conclusions. |
| | The Commission therefore directed the Staff to perform additional sensitivity analyses. |
| | The two inputs (TIMDEC and CDNFRM), |
| | are commonly used in the SAMA analyses performed for license renewal applications (LRAs ). These two input values were generally based on the values provided in NUREG-1150, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants" and NUREG/CR-3673, "Economic Risks of Nuclear Power Reactor Accidents." |
| | The TIMDEC input value defines the time required for completing decontamination to a specified degree. The CDNFRM input parameter defines the cost (on a per person basis) of decontaminating non-farmland by a specified decontamination factor. The CDNFRM values used in NUREG-1150 |
| | ($3,000/personfor decontamination factor of 3 and $8,000/person for decontamination factor of 15) stem from decontamination cost estimates provided in NUREG/CR-3673, the same 1984 economic risk study referenced in support of the decontamination time inputs. These decontamination cost inputs are commonly escalated to account for inflation. |
| | REQUEST FOR ADDITIONAL INFORMATION: |
| | The NRC Staff believes the Commission's decision in CLI-16-07 may be applicable to the SAMA analysis performed for Seabrook |
| | : Station, Unit 1 (Seabrook), |
| | inasmuch as that analysis may have also relied upon the NUREG-1150 values for TIMDEC and CDNFRM. We therefore request that NextEra Energy Seabrook, LLC (NextEra), |
| | either justify why CLI-16-07 does not apply to the SAMA analysis performed for Seabrook or supplement the SAMA analysis with sensitivity analyses for the CDNFRM and TIMDEC values. NextEra is requested to review the input values specified_in CLI-16-07 for the Indian Point LRA, and (1) to apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000 for the CDNFRM values for the decontamination factor of 15) or, in the alternative, (2) to explain, with sufficient justification, its rationale for choosing any other value(s) for its sensitivity analyses. |
| | In any event, NextEra should execute sensitivity analyses for the release categories modeled that exceed 1015 Becquerels ofCs-137 released. |
| | NextEra is requested to evaluate how these sensitivity analyses may affect its identification of potentially cost-beneficial SAMAs. Finally, upon completing its sensitivity |
| | : analysis, NextEra is requested to submit the spreadsheet (or equivalent table if another method is used) that conveys the population dose and off-site economic cost for each release category and integrates the results into a Population Dose Risk and an Offsite Economic Cost Risk for Seabrook. |
| | . \. ' U.S. Nuclear Regulatory Commission |
| | 'SBK-L-16134 |
| | /Enclosure I Page 3 NextEra Seabrook Response |
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| ==Background:== | | ==Background:== |
| As discussed in the RAI, the NRC Commissioners issued a Memorandum and Order (CLI-16-07) in the matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) on May 4, 2016 (Enclosure Reference 1-1 ). The Commissioners directed the NRC staff to supplement Indian Point's SAMA analysis with a sensitivity analysis using values of 365 days for the TIMDEC input parameter and $100,000/person for heavy decontamination for the CDNFRM input parameter in the MACCS2 (MELCOR Accident Consequence Code) code for at least the four most severe accident categories modeled. The RAI issued to NextEra Energy Seabrook Station requests that Seabrook apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000/person for the CDNFRM values for the decontamination factor of 15) for the release categories modeled that exceed 1015 Becquerels of Cs-137 released or, in the alternative, explain the rationale for choosing other values for the sensitivity analyses. NextEra Energy has performed a SAMA sensitivity analysis for Seabrook Station using the maximum input parameter values specified by the Commission in CLl-16-07 and by the NRC Staff in the RAI. The results of that analysis are described and summarized below. Decontamination Sensitivity Analysis A sensitivity analysis to determine the Modified Maximum Averted Cost Risk (MMACR) using the highest values allowed in MACCS2 for inputs TIMDEC and CDNFRM, 365 days and $100,000/person, respectively, for the decontamination factor of 15 (heavy decontamination), was performed as specified in CLI-16-07 and in the RAI. All other inputs into the MACCS2 code were unchanged. The evaluation used the higher TIMDEC and CDNFRM input parameter values in the same sensitivity analysis, so that the effects of increasing both values are evaluated concurrently. The RAI indicates that the severe accident categories that exceed 1015 Becquerels of Cs-13 7 released should be considered. Accident releases from Seabrook are modeled via 13 release categories (RC). 10 of the 13 accident release categories exceed the 1015 Becquerels for Cs-137, all of the release categories except SEl, INTACTl and INTACT2. However, as a conservative approach, all of Seabrook's release categories are included in this sensitivity analysis. This includes the following release categories: LEl -Large/Early Cont. Bypass-SG Tube Rupture LE2 -Large/Early Cont. Bypass -ISLOCA LE3 -Large/Early Cont. Penetration Failure to Isolate LE4 -Large Cont. Basemat Failure with Delayed Evacuation SEl -Small/Early Cont. Bypass-SG Tube Rupture w/ Scrubbed Release SE2 -Small/Early Cont. Bypass -ISLOCA w/ Scrubbed Release SE3 -Small/Early Cont. Penetration Failure to Isolate LL3 -Large/Late Cont. Venting LL4 -Large/Late Cont. Overpressure Failure LL5 -Large/Late Cont. Basemat Failure
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| ' . U.S. Nuclear Regulatory Commission 'SBK-L-16134*/Enclosure I Page 4 SELL -Small/Early Cont. Pen. Failure to Isolate & Large/Late Cont. Basemat Failure INTACT! -Nominal Cont. Leakage (mapped to INTACT) INTACT2 -Excessive Cont. Leakage (mapped to INTACT) INTACT-Weighted summation ofINTACTl and INTACT2 After determining the revised population dose and economic costs using the maximum values for CDNFRM and TIMDEC for the above release categories, a Maximum Averted Cost Risk (MACR) was calculated for both the 7% (base) and 3% (sensitivity) discount rates as done in the Seabrook SAMA analysis. In addition, the MACR is increased by a factor of 2.1 to account for the potential risk increase due to seismic hazards. The seismic multiplier was derived and justified as discussed on page 29 of 96 in Enclosure Reference 1-2. The seismic-adjusted MACR is referred to as the "modified" Maximum Averted Cost Risk (MMACR). Note that in the previous Seabrook SAMA documentation, MMACR was referred to as the Maximum Averted (Attainable) Benefit (MAB), which provided the same measure of benefit. The MMACR calculated in this RAI sensitivity analysis is then compared to the 95th percentile MMACR determined in the Seabrook SAMA analysis. The 95th percentile MMACR is obtained by multiplying the MMACR by a factor of2.35 to account for the 95th percentile of the consequence as discussed on page 35of96 in Enclosure Reference 1-2. RAI Sensitivity Results I Comparison Table 1 presents the Level 3 base case results of Public Dose and Economic Risk from the previous Seabrook SAMA evaluation, page 27of96 in Enclosure Reference 1-2. The results of this RAI sensitivity analysis are presented in Tables 2 and 3. Table 2 provides the Population Dose Risk and Economic Cost Risk for each release category. Table 3 compares the Modified Maximum Averted Cost Risk (MMACR) results calculated for both the SAMA base case and the RAI sensitivity case. The results show that the MMACR for the RAI sensitivity case, which used CDNFRM and TIMDEC set to their maximum allowable values for heavy decontamination, is $9,607,670/year for a 7% discount rate. This MMACR is bounded by the 95th percentile of the MMACR in the Seabrook SAMA evaluation which was derived as 2.35 x $6,401,871/year = $15.04M/year. Likewise, the RAI sensitivity analysis MMACR calculated with maximum values for CDNFRM and TIMDEC using a 3% discount rate is $13.67M, which is also bounded by the 95th percentile base case of $15.04M/yr.
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| . \ U.S. Nuclear Regulatory Commission -SBK-L-16134 /Enclosure I Page 5 Table 1 Seabrook SAMA Base Case Level 3 Results (*) Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REI\ll) ($) (events/yr) (person ($/yr) REM/yr) LE-1 1.26E+07 5.60E+ I 0 5.19E-08 6.54E-OI 2.91E+03 LE-2 4.27E+07 7.14E+l0 l.8 lE-08 7.73E-Ol l.29E+03 LE-3 2.41E+07 6.80E+l0 8.61E-10 2.08E-02 5.85E+Ol LE-4 l.1 lE+07 4.91E+l0 2.11 E-08 2.34E-Ol l .04E+03 SE-1 2.43E+05 3.27£+08 5.08E-07 1.23£-01 l.66E+02 SE-2 8.60E+06 3.09E+IO 2.79£-08 2.40£-01 8.62E+02 SE-3 l.36E+06 2.67£+09 9.97£-07 1.36£+00 2.66E+03 LL-3 3.63E+06 9.05£+09 1.75£-07 6.35£-01 l.58E+03 LL-4 7.27E+06 3.lOE+lO 5.79E-08 4.21E-01 I .79E+03 LL-5 1.03£+07 5.24£+10 3.IOE-06 3.19E+Ol 1.62£+05 SELL l .48E+07 6.53E+10 9.84E-08 l.46E+OO 6.43E+03 INTACT 2.77E+03 2.18£+03 7.14£-06 1.98£-02 l .56E-02 Totals 1.37E+08 4.36E+ll 1.22E-05 3.79E+Ol 1.81E+05 (*) Table 1 is reproduced from table of release category public dose and economic risk results -Level 3 Model provided in letter SBK-L-12053 (Enclosure Reference 1-2), page 27 of96. Table 2 Seabrook SAMA RAI Sensitivity Level 3 Results Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REM) ($) (events/yr) (person ($/yr) REM/yr) LE-1 l.24E+07 l.l!E+ll 5.19£-08 6.44E-01 5.76E+03 LE-2 4.29E+07 1.34E+ 11 1.81E-08 7.76E-01 2.43E+03 LE-3 2.46E+07 l.39E+ 11 8.61E-10 2.12E-02 l.20E+02 LE-4 1.14E+07 9.89E+l0 2. l IE-08 2.4 lE-01 2.09E+03 SE-1 2.47E+05 7.18E+08 5.08E-07 1.25£-01 3.65E+02 SE-2 9.04E+06 6.69E+l0 2.79E-08 2.52E-Ol 1.87£+03 SE-3 l.35E+06 4.01E+09 9.97E-07 l.35E+OO 4.00E+03 LL-3 3.68E+06 J.68E+IO J.75E-07 6.44E-O 1 2.94E+03 LL-4 7.90E+06 6.41E+l0 5.79E-08 4.57E-Ol 3.71E+03 LL-5 9.64E+06 9.40£+10 3.lOE-06 2.99E+Ol 2.9JE+05 SELL 1.47E+07 l .26E+ 11 9.84£-08 1.45£+00 1.24£+04 INTACT 2.77E+03 2.18E+03 7.14£-06 l .98E-02 1.56E-02 Totals 1.38E+08 8.55E+ll 1.22E-05 3.59E+Ol 3.27E+05
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| .. U.S. Nuclear Regulatory Commission 'SBK-L-16134 /Enclosure I Page 6 Table 3 Seabrook Modified Maximum Averted Cost Risk Results I Comparison Base Case Results RAI Sensitivity Results Description 7% Real 3% Discount 7% Real 3% Discount Discount Rate Rate Sensitivity Discount Rate Rate Sensitivity Averted Public Exposure Cost (APE) $815,072 $1,138,946 $771,886 $1,078,600 Averted Offsite Property Damage Cost $1,950,586 $2,725,665 $3,520,343 $4,919, 175 (AOC) Averted Occupational Exposure Cost (AOE) $4,642 $7,549 $4,642 $7,549 Averted Onsite Cost (AOC) $278,210 $506,062 $278,210 $506,062 Maximum Averted Cost Risk ($/yr) $3,048,510 $4,378,222 $4,575,081 $6,511,386 Seismic Hazard Multiplier 2.10 2.10 2.10 2.10 Modified Maximum Averted Cost Risk $6,401,871 $9,194,265 $9,607,670 $13,673,911 ($/yr) Uncertainty Factor ( 95th Percentile) 2.35 Total MMACR at 95111 Percentile Uncertainty $15.04M Distribution
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| == Conclusion:==
| | As discussed in the RAI, the NRC Commissioners issued a Memorandum and Order (CLI-16-07) in the matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) on May 4, 2016 (Enclosure Reference 1-1 ). The Commissioners directed the NRC staff to supplement Indian Point's SAMA analysis with a sensitivity analysis using values of 365 days for the TIMDEC input parameter and $100,000/person for heavy decontamination for the CDNFRM input parameter in the MACCS2 (MELCOR Accident Consequence Code) code for at least the four most severe accident categories modeled. |
| As summarized in Table 3, the sensitivity values for the Modified Maximum Averted Cost Risk (MMACR) are bounded by the previous Seabrook SAMA MMACR, which accounted for the 95th percentile in averted cost risk. Additionally, the maximum increase in benefit of an individual SAMA candidate is bounded by the previous 95th percentile case. The maximum increased value of an individual SAMA candidate could be no greater than the largest ratio of the population dose risk or economic risk of the decontamination sensitivity case to the population dose risk or economic risk in the previous Seabrook SAMA case (Table 1) for all of the modeled release categories. The maximum increase ratio is less than the factor of 2.35 used in Seabrook's SAMA evaluation to judge each individual SAMA candidate against the benefit, which considered the benefit at the 951h percentile. Therefore, the results of the evaluation of potential SAMA candidates previously provided in the SAMA analysis bounds the results of the RAI sensitivity analysis. While the use of the higher RAI decontamination input parameters results in an increase in the MMACR, the RAI sensitivity analysis shows that the results are less than Seabrook's base SAMA MMACR, which considered the MMACR at the 95th percentile. Based on the above, the RAI sensitivity results do not present any new and significant information that could necessitate supplementation of the Final Supplemental Environmental Impact Statement for the Seabrook Station license renewal. | | The RAI issued to NextEra Energy Seabrook Station requests that Seabrook apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000/person for the CDNFRM values for the decontamination factor of 15) for the release categories modeled that exceed 1015 Becquerels of Cs-137 released or, in the alternative, explain the rationale for choosing other values for the sensitivity analyses. |
| *, ' U.S. Nuclear Regulatory Commission *sBK-L-16134 /Enclosure I Page 7 Enclosure | | NextEra Energy has performed a SAMA sensitivity analysis for Seabrook Station using the maximum input parameter values specified by the Commission in CLl-16-07 and by the NRC Staff in the RAI. The results of that analysis are described and summarized below. Decontamination Sensitivity Analysis A sensitivity analysis to determine the Modified Maximum Averted Cost Risk (MMACR) using the highest values allowed in MACCS2 for inputs TIMDEC and CDNFRM, 365 days and $100,000/person, respectively, for the decontamination factor of 15 (heavy decontamination), |
| | was performed as specified in CLI-16-07 and in the RAI. All other inputs into the MACCS2 code were unchanged. |
| | The evaluation used the higher TIMDEC and CDNFRM input parameter values in the same sensitivity |
| | : analysis, so that the effects of increasing both values are evaluated concurrently. |
| | The RAI indicates that the severe accident categories that exceed 1015 Becquerels of Cs-13 7 released should be considered. |
| | Accident releases from Seabrook are modeled via 13 release categories (RC). 10 of the 13 accident release categories exceed the 1015 Becquerels for Cs-137, all of the release categories except SEl, INTACTl and INTACT2. |
| | : However, as a conservative |
| | : approach, all of Seabrook's release categories are included in this sensitivity analysis. |
| | This includes the following release categories: |
| | LEl -Large/Early Cont. Bypass-SG Tube Rupture LE2 -Large/Early Cont. Bypass -ISLOCA LE3 -Large/Early Cont. Penetration Failure to Isolate LE4 -Large Cont. Basemat Failure with Delayed Evacuation SEl -Small/Early Cont. Bypass-SG Tube Rupture w/ Scrubbed Release SE2 -Small/Early Cont. Bypass -ISLOCA w/ Scrubbed Release SE3 -Small/Early Cont. Penetration Failure to Isolate LL3 -Large/Late Cont. Venting LL4 -Large/Late Cont. Overpressure Failure LL5 -Large/Late Cont. Basemat Failure |
| | ' . U.S. Nuclear Regulatory Commission |
| | 'SBK-L-16134*/Enclosure I Page 4 SELL -Small/Early Cont. Pen. Failure to Isolate & Large/Late Cont. Basemat Failure INTACT! -Nominal Cont. Leakage (mapped to INTACT) INTACT2 -Excessive Cont. Leakage (mapped to INTACT) INTACT-Weighted summation ofINTACTl and INTACT2 After determining the revised population dose and economic costs using the maximum values for CDNFRM and TIMDEC for the above release categories, a Maximum Averted Cost Risk (MACR) was calculated for both the 7% (base) and 3% (sensitivity) discount rates as done in the Seabrook SAMA analysis. |
| | In addition, the MACR is increased by a factor of 2.1 to account for the potential risk increase due to seismic hazards. |
| | The seismic multiplier was derived and justified as discussed on page 29 of 96 in Enclosure Reference 1-2. The seismic-adjusted MACR is referred to as the "modified" Maximum Averted Cost Risk (MMACR). |
| | Note that in the previous Seabrook SAMA documentation, MMACR was referred to as the Maximum Averted (Attainable) |
| | Benefit (MAB), which provided the same measure of benefit. |
| | The MMACR calculated in this RAI sensitivity analysis is then compared to the 95th percentile MMACR determined in the Seabrook SAMA analysis. |
| | The 95th percentile MMACR is obtained by multiplying the MMACR by a factor of2.35 to account for the 95th percentile of the consequence as discussed on page 35of96 in Enclosure Reference 1-2. RAI Sensitivity Results I Comparison Table 1 presents the Level 3 base case results of Public Dose and Economic Risk from the previous Seabrook SAMA evaluation, page 27of96 in Enclosure Reference 1-2. The results of this RAI sensitivity analysis are presented in Tables 2 and 3. Table 2 provides the Population Dose Risk and Economic Cost Risk for each release category. |
| | Table 3 compares the Modified Maximum Averted Cost Risk (MMACR) results calculated for both the SAMA base case and the RAI sensitivity case. The results show that the MMACR for the RAI sensitivity case, which used CDNFRM and TIMDEC set to their maximum allowable values for heavy decontamination, is $9,607,670/year for a 7% discount rate. This MMACR is bounded by the 95th percentile of the MMACR in the Seabrook SAMA evaluation which was derived as 2.35 x $6,401,871/year |
| | = $15.04M/year. |
| | : Likewise, the RAI sensitivity analysis MMACR calculated with maximum values for CDNFRM and TIMDEC using a 3% discount rate is $13.67M, which is also bounded by the 95th percentile base case of $15.04M/yr. |
| | . \ U.S. Nuclear Regulatory Commission |
| | -SBK-L-16134 /Enclosure I Page 5 Table 1 Seabrook SAMA Base Case Level 3 Results (*) Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REI\ll) ($) (events/yr) |
| | (person ($/yr) REM/yr) LE-1 1.26E+07 5.60E+ I 0 5.19E-08 6.54E-OI 2.91E+03 LE-2 4.27E+07 7.14E+l0 l.8 lE-08 7.73E-Ol l.29E+03 LE-3 2.41E+07 6.80E+l0 8.61E-10 2.08E-02 5.85E+Ol LE-4 l.1 lE+07 4.91E+l0 2.11 E-08 2.34E-Ol l .04E+03 SE-1 2.43E+05 3.27£+08 5.08E-07 1.23£-01 l.66E+02 SE-2 8.60E+06 3.09E+IO 2.79£-08 2.40£-01 8.62E+02 SE-3 l.36E+06 2.67£+09 9.97£-07 1.36£+00 2.66E+03 LL-3 3.63E+06 9.05£+09 1.75£-07 6.35£-01 l.58E+03 LL-4 7.27E+06 3.lOE+lO 5.79E-08 4.21E-01 I .79E+03 LL-5 1.03£+07 5.24£+10 3.IOE-06 3.19E+Ol 1.62£+05 SELL l .48E+07 6.53E+10 9.84E-08 l.46E+OO 6.43E+03 INTACT 2.77E+03 2.18£+03 7.14£-06 1.98£-02 l .56E-02 Totals 1.37E+08 4.36E+ll 1.22E-05 3.79E+Ol 1.81E+05 |
| | (*) Table 1 is reproduced from table of release category public dose and economic risk results -Level 3 Model provided in letter SBK-L-12053 (Enclosure Reference 1-2), page 27 of96. Table 2 Seabrook SAMA RAI Sensitivity Level 3 Results Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REM) ($) (events/yr) (person ($/yr) REM/yr) LE-1 l.24E+07 l.l!E+ll 5.19£-08 6.44E-01 5.76E+03 LE-2 4.29E+07 1.34E+ 11 1.81E-08 7.76E-01 2.43E+03 LE-3 2.46E+07 l.39E+ 11 8.61E-10 2.12E-02 l.20E+02 LE-4 1.14E+07 9.89E+l0 |
| | : 2. l IE-08 2.4 lE-01 2.09E+03 SE-1 2.47E+05 7.18E+08 5.08E-07 1.25£-01 3.65E+02 SE-2 9.04E+06 6.69E+l0 2.79E-08 2.52E-Ol 1.87£+03 SE-3 l.35E+06 4.01E+09 9.97E-07 l.35E+OO 4.00E+03 LL-3 3.68E+06 J.68E+IO J.75E-07 6.44E-O 1 2.94E+03 LL-4 7.90E+06 6.41E+l0 5.79E-08 4.57E-Ol 3.71E+03 LL-5 9.64E+06 9.40£+10 3.lOE-06 2.99E+Ol 2.9JE+05 SELL 1.47E+07 l .26E+ 11 9.84£-08 1.45£+00 1.24£+04 INTACT 2.77E+03 2.18E+03 7.14£-06 l .98E-02 1.56E-02 Totals 1.38E+08 8.55E+ll 1.22E-05 3.59E+Ol 3.27E+05 |
| | .. U.S. Nuclear Regulatory Commission |
| | 'SBK-L-16134 |
| | /Enclosure I Page 6 Table 3 Seabrook Modified Maximum Averted Cost Risk Results I Comparison Base Case Results RAI Sensitivity Results Description 7% Real 3% Discount 7% Real 3% Discount Discount Rate Rate Sensitivity Discount Rate Rate Sensitivity Averted Public Exposure Cost (APE) $815,072 $1,138,946 $771,886 $1,078,600 Averted Offsite Property Damage Cost $1,950,586 |
| | $2,725,665 $3,520,343 $4,919, 175 (AOC) Averted Occupational Exposure Cost (AOE) $4,642 $7,549 $4,642 $7,549 Averted Onsite Cost (AOC) $278,210 $506,062 |
| | $278,210 $506,062 Maximum Averted Cost Risk ($/yr) $3,048,510 $4,378,222 $4,575,081 $6,511,386 Seismic Hazard Multiplier 2.10 2.10 2.10 2.10 Modified Maximum Averted Cost Risk $6,401,871 |
| | $9,194,265 $9,607,670 $13,673,911 ($/yr) Uncertainty Factor ( 95th Percentile) 2.35 Total MMACR at 95111 Percentile Uncertainty |
| | $15.04M Distribution |
|
| |
|
| ==References:== | | == |
| 1-1 Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 1-2 NextEra Energy Seabrook Station Letter to NRC, "Seabrook Station Supplement 2 to Severe Accident Mitigation Alternatives Analysis" SBK-L-12053, dated March 19, 2012 (Accession Number ML12080Al37)}} | | Conclusion:== |
| | |
| | As summarized in Table 3, the sensitivity values for the Modified Maximum Averted Cost Risk (MMACR) are bounded by the previous Seabrook SAMA MMACR, which accounted for the 95th percentile in averted cost risk. Additionally, the maximum increase in benefit of an individual SAMA candidate is bounded by the previous 95th percentile case. The maximum increased value of an individual SAMA candidate could be no greater than the largest ratio of the population dose risk or economic risk of the decontamination sensitivity case to the population dose risk or economic risk in the previous Seabrook SAMA case (Table 1) for all of the modeled release categories |
| | . The maximum increase ratio is less than the factor of 2.35 used in Seabrook's SAMA evaluation to judge each individual SAMA candidate against the benefit, which considered the benefit at the 951h percentile. |
| | Therefore, the results of the evaluation of potential SAMA candidates previously provided in the SAMA analysis bounds the results of the RAI sensitivity analysis. |
| | While the use of the higher RAI decontamination input parameters results in an increase in the MMACR, the RAI sensitivity analysis shows that the results are less than Seabrook's base SAMA MMACR, which considered the MMACR at the 95th percentile. |
| | Based on the above, the RAI sensitivity results do not present any new and significant information that could necessitate supplementation of the Final Supplemental Environmental Impact Statement for the Seabrook Station license renewal. |
| | *, ' U.S. Nuclear Regulatory Commission |
| | *sBK-L-16134 |
| | /Enclosure I Page 7 Enclosure References |
| | : 1-1 Commissioner Memorandum and Order, CLI-16-07 |
| | , "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 1-2 NextEra Energy Seabrook Station Letter to NRC, "Seabrook Station Supplement 2 to Severe Accident Mitigation Alternati ves Analysis" SBK-L-12053 |
| | , dated March 19, 2012 (Accession Number ML12080Al37)}} |
Letter Sequence Response to RAI |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement
|
MONTHYEARML1006401882010-03-0505 March 2010
Charter for the Groundwater Contamination Task Force
Project stage: Request
SBK-L-10077, Application for Renewed Operating License2010-05-25025 May 2010
Application for Renewed Operating License
Project stage: Request
ML1016203312010-06-0101 June 2010
Drawing LR-001 Through Drawing PID-1-CO-LR20423, Rev. 14
Project stage: Request
ML1016203332010-06-0101 June 2010
Drawing PID-1-CO-LR20426, Rev. 30, Through Drawing PID-1-DW-LR20600, Rev. 11
Project stage: Request
SBK-L-10095, Drawing PID-1-MAH-LR20497, Rev. 9, Through Drawing PID-1-SF-LR204822010-06-0101 June 2010
Drawing PID-1-MAH-LR20497, Rev. 9, Through Drawing PID-1-SF-LR20482
Project stage: Request
ML1016203342010-06-0101 June 2010
Drawing PID-1-DW-LR20601, Rev. 1, Through Drawing PID-1-MAH-LR20496, Rev. 12
Project stage: Request
ML1016203292010-06-0101 June 2010
Drawing PID-1-SF-LR20483, Rev. 15, Through Drawing PID-1-WT-LR20041, Rev. 7
Project stage: Request
ML1016803692010-06-17017 June 2010
Commission Memorandum and Order (CLI-10-14)
Project stage: Request
ML1022205712010-08-10010 August 2010
License Renewal Process Overview and Scoping Public Meeting Slides
Project stage: Meeting
ML1024200372010-08-19019 August 2010
Comment (1) of Maggie Hassan on Behalf of Constituents Different Opinion on the Relicensing of Seabrook Nuclear Power Plant
Project stage: Request
ML1025202072010-08-19019 August 2010
Transcript for Evening Public Scoping Meeting ISO Seabrook LRA SEIS
Project stage: Request
ML1025201832010-08-19019 August 2010
Transcript for Afternoon Public Scoping Meeting ISO Seabrook LRA SEIS, August 19, 2010. Pp 1-88
Project stage: Request
ML1025002712010-08-23023 August 2010
Comment (2) of William R. Harris, on Behalf of Self, on Nextera Energy Seabrook, LLC Application for Renewal of License for Seabrook
Project stage: Request
ML1024200432010-08-25025 August 2010
Comment (3) of William Harris, Additional Reference Document for Seabrook Relicensing Environmental Review - Threat Assessment of Emp for Critical Infrastructure
Project stage: Request
ML1024505252010-09-0101 September 2010
Comment (4) of Geordie Vining on Behalf of Himself Opposing Relicensing Seabrook Plant for the Years 2030-2050
Project stage: Request
ML1026504862010-09-20020 September 2010
Comment (6) of Joseph W. Fahey on Behalf of Amesbury on Environmental Impact & Mitigation Scoping for Relicensing of the Seabrook Nuclear Plant
Project stage: Request
ML1026403712010-09-20020 September 2010
Comment (6) of Joyce Kemp, Opposing NRC-2010-0206-0002, Environmental Impact Statements; Availability, Etc.: Nextera Energy Seabrook; Seabrook Station (Unit 1)
Project stage: Request
ML1026603312010-09-20020 September 2010
Comment (7) of Andrew R. Port on Behalf of City of Newburyport Office of Planning & Development on Environmental Scoping Review Regarding Application for an Operating License Extension for Seabrook, Unit 1 from Year 2030 to Year 2050
Project stage: Request
ML1025202222010-09-20020 September 2010
Summary of Public License Renewal Overview and Environmental Scoping Meeting Related to the Review of the Seabrook Station License Renewal Application (TAC No. ME3959 and ME4028)
Project stage: Meeting
ML1028612172010-10-29029 October 2010
Request for Additional Information for the Review of the Seabrook Station License Renewal Application Environmental Review
Project stage: RAI
ML1030808802010-11-0404 November 2010
Letter from Nhdes to NextEra Energy Seabrook Czma Compliance for the Seabrook LRA
Project stage: Request
ML1030700562010-11-0808 November 2010
Environmental Project Manager Change for the License Renewal of Seabrook Station, Unit 1
Project stage: Other
ML1029502712010-11-10010 November 2010
10/05-07/2010-Summary of Site Audit Related to the Review of the License Renewal Application for Seabrook Station, Unit 1
Project stage: Approval
ML1030902152010-11-16016 November 2010
Request for Additional Information for the Review of the Seabrook Station License Renewal Application-SAMA Review
Project stage: RAI
ML1033701692010-11-23023 November 2010
Attachment 2, Vol. 2, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1033603262010-11-23023 November 2010
Attachment 2, Vol. 6, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
SBK-L-10185, Attachment 1 to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report.2010-11-23023 November 2010
Attachment 1 to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report.
Project stage: Response to RAI
SBK-L-10190, Response to Request for Additional Information, Submittal of Cultural Resource Plan in Accordance with 36 CFR 800.11 (C)2010-11-23023 November 2010
Response to Request for Additional Information, Submittal of Cultural Resource Plan in Accordance with 36 CFR 800.11 (C)
Project stage: Response to RAI
ML1033506392010-11-23023 November 2010
Seabrook Station - Response to Request for Additional Information - NextEra Energy Seabrook License Renewal Environmental Report
Project stage: Response to RAI
ML1101003122010-11-23023 November 2010
Attachment 2, Vol. 1, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1101003112010-11-23023 November 2010
Attachment 2, Vol. 1, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1033701672010-11-23023 November 2010
Attachment 3 to SBK-L-10185 -Seabrook Station Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Environmental Report
Project stage: Response to RAI
ML1033700922010-11-23023 November 2010
Attachment 2, Vol. 3, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1033603112010-11-23023 November 2010
Attachment 2, Vol. 2, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1033603062010-11-23023 November 2010
Attachment 2, Vol. 4, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1033603002010-11-23023 November 2010
Attachment 2, Vol. 7, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1033602982010-11-23023 November 2010
Attachment 2, Vol. 5, to SBK-L-10185, Seabrook Station Response to Request for Additional Information NextEra Energy Seabrook License Renewal Environmental Report, References Requested for Docketing at the Seabrook Station Environmental Sit
Project stage: Response to RAI
ML1029806932010-12-21021 December 2010
Summary of Telephone Conference Call Held on 10/21/10 Btw the USNRC and NextEra Energy Seabrook, LLC, Concerning the Request for Additional Information Pertaining to the Seabrook Station License Renewal Application
Project stage: RAI
ML1033602122010-12-31031 December 2010
NUREG-1437 Supplement 38 Vol 2, (3:3) Appendix A-761 - End Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 Public Comments
Project stage: Other
ML1033602092010-12-31031 December 2010
NUREG-1437 Supplement 38 Vol 2, (2:3) Appendix A-454 - A-760 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 Public Comments
Project stage: Other
ML1033504382010-12-31031 December 2010
NUREG-1437 Supplement 38 Vol 2, (1:3) Cover - Appendix A-453 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3 Public Comments
Project stage: Acceptance Review
ML1033504422010-12-31031 December 2010
NUREG-1437 Supplement 38 Vol 3 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3, Public Comments Continued, Appendices
Project stage: Acceptance Review
ML1035704012011-01-0303 January 2011
12/21/2010-Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning the RAI Pertaining to the Seabrook Station, License Renewal Application
Project stage: RAI
SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal Application2011-01-13013 January 2011
Response to Request for Additional Information, NextEra Energy License Renewal Application
Project stage: Response to RAI
SBK-L-11031, Environmental Permit Renewals2011-02-18018 February 2011
Environmental Permit Renewals
Project stage: Request
ML1104901652011-02-28028 February 2011
02/15/2011 Summary of Telephone Conference Call with the USNRC and NextEra Energy Seabrook, LLC, to Clarify the Responses to the RAIs Pertaining to the SAMA Review of the Seabrook Station License Renewal Application
Project stage: RAI
ML1105603622011-03-0101 March 2011
2/3/11 Summary of Telephone Conference Calls Held Between the USNRC and Nextera Energy Seabrook, LLC, to Clarify Information Pertaining to the Review of the Seabrook Station License Renewal Application
Project stage: Approval
ML1101001132011-03-0101 March 2011
Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by Nextera Energy Seabrook, LLC for Renewal of the Operating License for Seabrook Station
Project stage: Approval
ML1105906382011-03-0404 March 2011
Schedule Revision and Request for Additional Information for the Review of the Seabrook Station License Renewal Application Environmental Review
Project stage: RAI
SBK-L-11044, Response to Request for Additional Information Regarding License Renewal Environmental Report2011-03-16016 March 2011
Response to Request for Additional Information Regarding License Renewal Environmental Report
Project stage: Response to RAI
2010-08-10
[Table View] |
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Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024
Integrated Inspection Report 05000443/2024003
L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024
Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
ML24303A0352024-10-29029 October 2024
Operator Licensing Examination Approval
IR 05000443/20244022024-10-17017 October 2024
Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only)
L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024
Core Operating Limits Report for Reload Cycle 24
L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes
ML24254A2552024-09-25025 September 2024
Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval
L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24239A5382024-09-20020 September 2024
Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
IR 05000443/20240052024-08-29029 August 2024
Updated Inspection Plan for Seabrook Station (Report 05000443/2024005)
ML24232A1142024-08-21021 August 2024
Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves
L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024
Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be
L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024
Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .
IR 05000443/20240022024-08-0606 August 2024
Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024
Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent
L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024
Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024
Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024
Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
L-2024-102, Official Service List Update2024-06-19019 June 2024
Official Service List Update
L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024
Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
IR 05000443/20240102024-05-29029 May 2024
Biennial Problem Identification and Resolution Inspection Report 05000443/2024010
IR 05000443/20240112024-05-24024 May 2024
Age-Related Degradation Inspection Report 05000443/2024011
IR 05000443/20240012024-05-13013 May 2024
Integrated Inspection Report 05000443/2024001
L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024
NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio
ML24046A0512024-05-0707 May 2024
Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024
2023 Annual Radioactive Effluent Release Report
L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024
2023 Annual Radiological Environmental Operating Report
IR 05000443/20245012024-04-22022 April 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501
05000443/LER-2024-001, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024
Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources
SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024
2023 Annual Environmental Operating Report
L-2024-011, 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 Applications2024-03-13013 March 2024
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
ML24067A2622024-03-0808 March 2024
Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances)
L-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024
To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-037, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024
To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024
Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
ML24065A2522024-03-0505 March 2024
Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033)
L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024
Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B
L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024
Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
IR 05000443/20230062024-02-28028 February 2024
Annual Assessment Letter for Seabrook Station (Report 05000443/2023006)
L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024
Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024
Radiological Emergency Plan (Ssrep), Revision 82
IR 05000443/20230042024-02-12012 February 2024
Integrated Inspection Report 05000443/2023004
ML24009A1152024-01-29029 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)
2024-09-25
[Table view]
Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024
Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be
L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024
Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .
L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024
Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
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
L-2023-005, Response to Request for Additional Information for Seabrook Relief Request 4RA-22-0012023-01-26026 January 2023
Response to Request for Additional Information for Seabrook Relief Request 4RA-22-001
ML22307A1682022-11-0303 November 2022
Cover Memo and Response to C-10 Questions Regarding 2Q2022 Inspection Report - Corrected
L-2022-157, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report2022-09-28028 September 2022
Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report
L-2022-106, Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-06-27027 June 2022
Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
ML22109A0342022-04-19019 April 2022
Cover Memo and Response to C-10 Questions Regarding 4Q2021 Inspection Report
SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022
Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
ML21280A2622021-10-0707 October 2021
Response Letter to N. Treat (C-10 Research and Education Foundation) Regarding 2Q 2021 Integrated Inspection Report Questions
SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021
Revision to Updated Final Response to NRC Generic Letter 2004-02
SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021
Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:
SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021
Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements
SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020
Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic
SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020
Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request
SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020
Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418
SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020
Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request
SBK-L-19120, Response to Request for Additional Information Related to Seabrook Inverter Amendment2019-10-30030 October 2019
Response to Request for Additional Information Related to Seabrook Inverter Amendment
SBK-L-18106, Response to Requests for Additional Information Related to License Renewal Application Environmental Review2018-06-14014 June 2018
Response to Requests for Additional Information Related to License Renewal Application Environmental Review
SBK-L-18074, Response to Request for Additional Information Regarding License Amendment Request 16-032018-06-0707 June 2018
Response to Request for Additional Information Regarding License Amendment Request 16-03
L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018
Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations
SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program2018-02-28028 February 2018
0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program
SBK-L-18027, Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program2018-02-28028 February 2018
Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program
SBK-L-17202, Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption2017-12-14014 December 2017
Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption
SBK-L-17204, Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)2017-12-11011 December 2017
Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)
SBK-L-17180, Supplement 58, Revised Alkali-Silica Reaction Aging Management Program2017-11-0303 November 2017
Supplement 58, Revised Alkali-Silica Reaction Aging Management Program
SBK-L-17169, Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-171552017-10-17017 October 2017
Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-17155
SBK-L-17170, Non-Proprietary Enclosure 1 to SBK-L-171562017-10-17017 October 2017
Non-Proprietary Enclosure 1 to SBK-L-17156
SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction2017-10-0303 October 2017
Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction
SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction2017-10-0303 October 2017
Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction
SBK-L-17133, Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program2017-08-11011 August 2017
Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program
SBK-L-17103, Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program2017-06-20020 June 2017
Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program
SBK-L-17087, Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-05-25025 May 2017
Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components
SBK-L-17082, Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components2017-05-19019 May 2017
Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components
SBK-L-17063, Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality2017-04-0808 April 2017
Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality
SBK-L-16205, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-22016-12-30030 December 2016
Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-2
SBK-L-16196, Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...2016-12-15015 December 2016
Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...
SBK-L-16186, Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations2016-11-23023 November 2016
Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations
SBK-L-16190, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-11-17017 November 2016
Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
ML16314D4272016-11-0707 November 2016
Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Submittal of Flooding Hazards Reevaluation Report, Revision 1
L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016
Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)
SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2016-10-27027 October 2016
Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
SBK-L-16170, Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report2016-10-27027 October 2016
Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report
SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-10-27027 October 2016
Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
SBK-L-16156, Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations2016-10-0707 October 2016
Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations
SBK-L-16134, Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application2016-09-0606 September 2016
Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application
2024-09-16
[Table view] |
Text
. \. U.S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station NEXTera SEABROOK September 6, 2016 10 CFR 54 SBK-L-16134 Docket No. 50-443 Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application
References:
- 1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License,"
May 25, 2010. (Accession Number ML101590099)
- 2. NRC Letter, Requests for Additional Information for the Severe Accident Mitigation Alternatives
( S AM A) Review of the Seabrook Station License Renewal Application (TAC No. ME3959),
July 8, 2016, (Accession Number ML16187A204)
- 3. Commissioner Memorandum and Order, CLI-16-07, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 (Accession Number ML16125Al50)
In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted an application for a renewed facility operating license for Seabrook Station Unit 1 in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54. In Reference 2, the staff requested additional information to support addressing the Commission Memorandum and Order (CLI-16-07) which directed the NRC staff to supplement the SAMA analysis performed for the Indian Point Units 2 and 3 LRA with sensitivity analyses for two factors used in the SAMA analysis (Reference 3). The NextEra Seabrook response to the RAI is provided in the enclosure to this letter. The RAI response includes the results of a sensitivity analysis for the same two input parameters addressed by the Commission in CLI-16-07. The sensitivity analysis demonstrates that the SAMA analysis previously submitted for Seabrook Station remains bounding. NextEra Energy
- Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
' ' United States Nuclear Regulatory Commission
'SBK-L-16134 I Page 2 No new commitments are being made in this submittal.
If there are any questions or additional information is needed, please contact Mr. Edward J Carley, Engineering Supervisor
-License Renewal, at (603) 773-7957.
If you have any questions regarding this correspondence, please contact Mr. Ken Browne, Licensing
- Manager, at (603) 773-7932.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September
- ___fo__,
2016 Sincerely,
Enclosure:
Response to RAI Related to Severe Accident Mitigation Alternatives cc: D. H. Dorman J.C. Poole P. C. Cataldo T. M. Tran L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal NRC Project Manager, License Renewal Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
. ,, U.S. Nuclear Regulatory Commission
/Enclosure I Page 1 Enclosure to SBK-L-16134 NextEra Energy Seabrook Response to RAI Related to Severe Accident Mitigation Alternatives NextEra Energy Seabrook License Renewal Application
. \ U.S. Nuclear Regulatory Commission
'SBK-L-16134
/Enclosure I Page 2 NRC RAI for Licensees regarding CLI-16-07 BACKGROUND:
On May 4, 2016, the Commission issued a Memorandum and Order (CLI-16-07) in the Indian Point license renewal proceeding, in which it directed the Staff to supplement the Indian Point Severe Accident Mitigation Alternatives (SAMA) analysis with sensitivity analyses.
Specifically, the Commission held that documentation was lacking for two inputs (TIMDEC and CDNFRM) used in the MACCS computer
- analyses, and that uncertainties in those input values could potentially affect the SAMA analysis cost-benefit conclusions.
The Commission therefore directed the Staff to perform additional sensitivity analyses.
The two inputs (TIMDEC and CDNFRM),
are commonly used in the SAMA analyses performed for license renewal applications (LRAs ). These two input values were generally based on the values provided in NUREG-1150, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants" and NUREG/CR-3673, "Economic Risks of Nuclear Power Reactor Accidents."
The TIMDEC input value defines the time required for completing decontamination to a specified degree. The CDNFRM input parameter defines the cost (on a per person basis) of decontaminating non-farmland by a specified decontamination factor. The CDNFRM values used in NUREG-1150
($3,000/personfor decontamination factor of 3 and $8,000/person for decontamination factor of 15) stem from decontamination cost estimates provided in NUREG/CR-3673, the same 1984 economic risk study referenced in support of the decontamination time inputs. These decontamination cost inputs are commonly escalated to account for inflation.
REQUEST FOR ADDITIONAL INFORMATION:
The NRC Staff believes the Commission's decision in CLI-16-07 may be applicable to the SAMA analysis performed for Seabrook
- Station, Unit 1 (Seabrook),
inasmuch as that analysis may have also relied upon the NUREG-1150 values for TIMDEC and CDNFRM. We therefore request that NextEra Energy Seabrook, LLC (NextEra),
either justify why CLI-16-07 does not apply to the SAMA analysis performed for Seabrook or supplement the SAMA analysis with sensitivity analyses for the CDNFRM and TIMDEC values. NextEra is requested to review the input values specified_in CLI-16-07 for the Indian Point LRA, and (1) to apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000 for the CDNFRM values for the decontamination factor of 15) or, in the alternative, (2) to explain, with sufficient justification, its rationale for choosing any other value(s) for its sensitivity analyses.
In any event, NextEra should execute sensitivity analyses for the release categories modeled that exceed 1015 Becquerels ofCs-137 released.
NextEra is requested to evaluate how these sensitivity analyses may affect its identification of potentially cost-beneficial SAMAs. Finally, upon completing its sensitivity
- analysis, NextEra is requested to submit the spreadsheet (or equivalent table if another method is used) that conveys the population dose and off-site economic cost for each release category and integrates the results into a Population Dose Risk and an Offsite Economic Cost Risk for Seabrook.
. \. ' U.S. Nuclear Regulatory Commission
'SBK-L-16134
/Enclosure I Page 3 NextEra Seabrook Response
Background:
As discussed in the RAI, the NRC Commissioners issued a Memorandum and Order (CLI-16-07) in the matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) on May 4, 2016 (Enclosure Reference 1-1 ). The Commissioners directed the NRC staff to supplement Indian Point's SAMA analysis with a sensitivity analysis using values of 365 days for the TIMDEC input parameter and $100,000/person for heavy decontamination for the CDNFRM input parameter in the MACCS2 (MELCOR Accident Consequence Code) code for at least the four most severe accident categories modeled.
The RAI issued to NextEra Energy Seabrook Station requests that Seabrook apply the maximum values specified by the Commission (one year (365 days) for TIMDEC and $100,000/person for the CDNFRM values for the decontamination factor of 15) for the release categories modeled that exceed 1015 Becquerels of Cs-137 released or, in the alternative, explain the rationale for choosing other values for the sensitivity analyses.
NextEra Energy has performed a SAMA sensitivity analysis for Seabrook Station using the maximum input parameter values specified by the Commission in CLl-16-07 and by the NRC Staff in the RAI. The results of that analysis are described and summarized below. Decontamination Sensitivity Analysis A sensitivity analysis to determine the Modified Maximum Averted Cost Risk (MMACR) using the highest values allowed in MACCS2 for inputs TIMDEC and CDNFRM, 365 days and $100,000/person, respectively, for the decontamination factor of 15 (heavy decontamination),
was performed as specified in CLI-16-07 and in the RAI. All other inputs into the MACCS2 code were unchanged.
The evaluation used the higher TIMDEC and CDNFRM input parameter values in the same sensitivity
- analysis, so that the effects of increasing both values are evaluated concurrently.
The RAI indicates that the severe accident categories that exceed 1015 Becquerels of Cs-13 7 released should be considered.
Accident releases from Seabrook are modeled via 13 release categories (RC). 10 of the 13 accident release categories exceed the 1015 Becquerels for Cs-137, all of the release categories except SEl, INTACTl and INTACT2.
- However, as a conservative
- approach, all of Seabrook's release categories are included in this sensitivity analysis.
This includes the following release categories:
LEl -Large/Early Cont. Bypass-SG Tube Rupture LE2 -Large/Early Cont. Bypass -ISLOCA LE3 -Large/Early Cont. Penetration Failure to Isolate LE4 -Large Cont. Basemat Failure with Delayed Evacuation SEl -Small/Early Cont. Bypass-SG Tube Rupture w/ Scrubbed Release SE2 -Small/Early Cont. Bypass -ISLOCA w/ Scrubbed Release SE3 -Small/Early Cont. Penetration Failure to Isolate LL3 -Large/Late Cont. Venting LL4 -Large/Late Cont. Overpressure Failure LL5 -Large/Late Cont. Basemat Failure
' . U.S. Nuclear Regulatory Commission
'SBK-L-16134*/Enclosure I Page 4 SELL -Small/Early Cont. Pen. Failure to Isolate & Large/Late Cont. Basemat Failure INTACT! -Nominal Cont. Leakage (mapped to INTACT) INTACT2 -Excessive Cont. Leakage (mapped to INTACT) INTACT-Weighted summation ofINTACTl and INTACT2 After determining the revised population dose and economic costs using the maximum values for CDNFRM and TIMDEC for the above release categories, a Maximum Averted Cost Risk (MACR) was calculated for both the 7% (base) and 3% (sensitivity) discount rates as done in the Seabrook SAMA analysis.
In addition, the MACR is increased by a factor of 2.1 to account for the potential risk increase due to seismic hazards.
The seismic multiplier was derived and justified as discussed on page 29 of 96 in Enclosure Reference 1-2. The seismic-adjusted MACR is referred to as the "modified" Maximum Averted Cost Risk (MMACR).
Note that in the previous Seabrook SAMA documentation, MMACR was referred to as the Maximum Averted (Attainable)
Benefit (MAB), which provided the same measure of benefit.
The MMACR calculated in this RAI sensitivity analysis is then compared to the 95th percentile MMACR determined in the Seabrook SAMA analysis.
The 95th percentile MMACR is obtained by multiplying the MMACR by a factor of2.35 to account for the 95th percentile of the consequence as discussed on page 35of96 in Enclosure Reference 1-2. RAI Sensitivity Results I Comparison Table 1 presents the Level 3 base case results of Public Dose and Economic Risk from the previous Seabrook SAMA evaluation, page 27of96 in Enclosure Reference 1-2. The results of this RAI sensitivity analysis are presented in Tables 2 and 3. Table 2 provides the Population Dose Risk and Economic Cost Risk for each release category.
Table 3 compares the Modified Maximum Averted Cost Risk (MMACR) results calculated for both the SAMA base case and the RAI sensitivity case. The results show that the MMACR for the RAI sensitivity case, which used CDNFRM and TIMDEC set to their maximum allowable values for heavy decontamination, is $9,607,670/year for a 7% discount rate. This MMACR is bounded by the 95th percentile of the MMACR in the Seabrook SAMA evaluation which was derived as 2.35 x $6,401,871/year
= $15.04M/year.
- Likewise, the RAI sensitivity analysis MMACR calculated with maximum values for CDNFRM and TIMDEC using a 3% discount rate is $13.67M, which is also bounded by the 95th percentile base case of $15.04M/yr.
. \ U.S. Nuclear Regulatory Commission
-SBK-L-16134 /Enclosure I Page 5 Table 1 Seabrook SAMA Base Case Level 3 Results (*) Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REI\ll) ($) (events/yr)
(person ($/yr) REM/yr) LE-1 1.26E+07 5.60E+ I 0 5.19E-08 6.54E-OI 2.91E+03 LE-2 4.27E+07 7.14E+l0 l.8 lE-08 7.73E-Ol l.29E+03 LE-3 2.41E+07 6.80E+l0 8.61E-10 2.08E-02 5.85E+Ol LE-4 l.1 lE+07 4.91E+l0 2.11 E-08 2.34E-Ol l .04E+03 SE-1 2.43E+05 3.27£+08 5.08E-07 1.23£-01 l.66E+02 SE-2 8.60E+06 3.09E+IO 2.79£-08 2.40£-01 8.62E+02 SE-3 l.36E+06 2.67£+09 9.97£-07 1.36£+00 2.66E+03 LL-3 3.63E+06 9.05£+09 1.75£-07 6.35£-01 l.58E+03 LL-4 7.27E+06 3.lOE+lO 5.79E-08 4.21E-01 I .79E+03 LL-5 1.03£+07 5.24£+10 3.IOE-06 3.19E+Ol 1.62£+05 SELL l .48E+07 6.53E+10 9.84E-08 l.46E+OO 6.43E+03 INTACT 2.77E+03 2.18£+03 7.14£-06 1.98£-02 l .56E-02 Totals 1.37E+08 4.36E+ll 1.22E-05 3.79E+Ol 1.81E+05
(*) Table 1 is reproduced from table of release category public dose and economic risk results -Level 3 Model provided in letter SBK-L-12053 (Enclosure Reference 1-2), page 27 of96. Table 2 Seabrook SAMA RAI Sensitivity Level 3 Results Release Population Economic Frequency Population Economic Category Dose Cost Dose Risk Cost Risk (person REM) ($) (events/yr) (person ($/yr) REM/yr) LE-1 l.24E+07 l.l!E+ll 5.19£-08 6.44E-01 5.76E+03 LE-2 4.29E+07 1.34E+ 11 1.81E-08 7.76E-01 2.43E+03 LE-3 2.46E+07 l.39E+ 11 8.61E-10 2.12E-02 l.20E+02 LE-4 1.14E+07 9.89E+l0
- 2. l IE-08 2.4 lE-01 2.09E+03 SE-1 2.47E+05 7.18E+08 5.08E-07 1.25£-01 3.65E+02 SE-2 9.04E+06 6.69E+l0 2.79E-08 2.52E-Ol 1.87£+03 SE-3 l.35E+06 4.01E+09 9.97E-07 l.35E+OO 4.00E+03 LL-3 3.68E+06 J.68E+IO J.75E-07 6.44E-O 1 2.94E+03 LL-4 7.90E+06 6.41E+l0 5.79E-08 4.57E-Ol 3.71E+03 LL-5 9.64E+06 9.40£+10 3.lOE-06 2.99E+Ol 2.9JE+05 SELL 1.47E+07 l .26E+ 11 9.84£-08 1.45£+00 1.24£+04 INTACT 2.77E+03 2.18E+03 7.14£-06 l .98E-02 1.56E-02 Totals 1.38E+08 8.55E+ll 1.22E-05 3.59E+Ol 3.27E+05
.. U.S. Nuclear Regulatory Commission
'SBK-L-16134
/Enclosure I Page 6 Table 3 Seabrook Modified Maximum Averted Cost Risk Results I Comparison Base Case Results RAI Sensitivity Results Description 7% Real 3% Discount 7% Real 3% Discount Discount Rate Rate Sensitivity Discount Rate Rate Sensitivity Averted Public Exposure Cost (APE) $815,072 $1,138,946 $771,886 $1,078,600 Averted Offsite Property Damage Cost $1,950,586
$2,725,665 $3,520,343 $4,919, 175 (AOC) Averted Occupational Exposure Cost (AOE) $4,642 $7,549 $4,642 $7,549 Averted Onsite Cost (AOC) $278,210 $506,062
$278,210 $506,062 Maximum Averted Cost Risk ($/yr) $3,048,510 $4,378,222 $4,575,081 $6,511,386 Seismic Hazard Multiplier 2.10 2.10 2.10 2.10 Modified Maximum Averted Cost Risk $6,401,871
$9,194,265 $9,607,670 $13,673,911 ($/yr) Uncertainty Factor ( 95th Percentile) 2.35 Total MMACR at 95111 Percentile Uncertainty
$15.04M Distribution
==
Conclusion:==
As summarized in Table 3, the sensitivity values for the Modified Maximum Averted Cost Risk (MMACR) are bounded by the previous Seabrook SAMA MMACR, which accounted for the 95th percentile in averted cost risk. Additionally, the maximum increase in benefit of an individual SAMA candidate is bounded by the previous 95th percentile case. The maximum increased value of an individual SAMA candidate could be no greater than the largest ratio of the population dose risk or economic risk of the decontamination sensitivity case to the population dose risk or economic risk in the previous Seabrook SAMA case (Table 1) for all of the modeled release categories
. The maximum increase ratio is less than the factor of 2.35 used in Seabrook's SAMA evaluation to judge each individual SAMA candidate against the benefit, which considered the benefit at the 951h percentile.
Therefore, the results of the evaluation of potential SAMA candidates previously provided in the SAMA analysis bounds the results of the RAI sensitivity analysis.
While the use of the higher RAI decontamination input parameters results in an increase in the MMACR, the RAI sensitivity analysis shows that the results are less than Seabrook's base SAMA MMACR, which considered the MMACR at the 95th percentile.
Based on the above, the RAI sensitivity results do not present any new and significant information that could necessitate supplementation of the Final Supplemental Environmental Impact Statement for the Seabrook Station license renewal.
- , ' U.S. Nuclear Regulatory Commission
/Enclosure I Page 7 Enclosure References
- 1-1 Commissioner Memorandum and Order, CLI-16-07
, "In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)," dated May 4, 2016 1-2 NextEra Energy Seabrook Station Letter to NRC, "Seabrook Station Supplement 2 to Severe Accident Mitigation Alternati ves Analysis" SBK-L-12053
, dated March 19, 2012 (Accession Number ML12080Al37)
