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Category:Response to Request for Additional Information (RAI)
MONTHYEARML19207A2572019-07-26026 July 2019 LLC Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19207A2742019-07-26026 July 2019 LLC Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML18243A4682018-08-31031 August 2018 Korea Hydro & Nuclear Power Co., Ltd - WO 89 Response to Digital I&C Questions ML18243A4652018-08-31031 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of LTR-RAM-17-81, Revision 4, Work Order 89: Response to Digital I&C Questions. ML18225A1382018-08-13013 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 520-8693 for Question 06.02.02-43, (Rev.1) ML18222A3502018-08-10010 August 2018 Korea Hydro & Nuclear Power Co., Ltd. - Response to RAI Er 1-8428 for Question EIS ACC/SA-15 (Rev.4) ML18221A5162018-08-0909 August 2018 Korea Hydro & Nuclear Power Co., Ltd. - Response to RAI 452-8545 for the Question 10.03.06-21 (Rev.1) ML18218A2092018-08-0606 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 271-8290 for Question 19-15 (Rev. 5) ML18218A2072018-08-0606 August 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 271-8290 for Question 19-15 (Rev. 5) ML18218A2032018-08-0606 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 312-8343 for Question 19-16 (Rev. 3) ML18218A1952018-08-0606 August 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 434-8352 for Question 19-92 (Rev.5) ML18205A7322018-07-24024 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 558-9456 for Question 14.03.01-1 (Rev.1) ML18205A7312018-07-24024 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 558-9456 for Question 14.03.01-1 (Rev.1) ML18205A6372018-07-24024 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 356-7881 for the Question 07-18 (Rev.3) ML18207A4562018-07-20020 July 2018 Korea Hydro - Revised Response to Request for Additional Information, APR1400 Design Certification, RAI No. 112-8015 ML18201A4002018-07-20020 July 2018 LLC Response to NRC Request for Additional Information No. 491 (Erai No. 9557) on the NuScale Design Certification Application ML18197A2972018-07-13013 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 88-8046 for Question 03.05.02-4 (Rev.1) ML18197A2962018-07-13013 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 88-8046 for Question 03.05.02-4 (Rev.1) ML18194A8572018-07-13013 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 432-8377 for Question 19-64 (Rev.7) ML18194A8552018-07-13013 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 432-8377 for Question 19-64 (Rev.7) ML18194A8232018-07-13013 July 2018 Korea Hydro & Nuclear Power Co., Ltd, Revised Response to RAI 316-8305 for the Question 17.04-1 (Rev. 4) ML18190A1622018-07-0909 July 2018 Korea Hydro & Nuclear Power Co, Ltd., Revised Response to RAI 420-8482 for Question 19.03-36 (Rev.2) ML18184A3682018-07-0303 July 2018 Korea Hydro & Nuclear Power Co., Ltd - Response to RAI 301-8280 for the Question 07.01-45 ML18178A5772018-06-27027 June 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI Er 1-8428 for Question EIS ACC/SA-15 (Rev.3) ML18172A3142018-06-21021 June 2018 Korea Hydro & Nuclear Power Co., Ltd - Response to Action Item 5-6 Section 5.4.2.1 Mcb Issue List Regarding APR-1400, FSAR Section 5.4.2.1 ML18172A3132018-06-21021 June 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to Action Item 5-6.11 Regarding Mcb Issue for DCD Section 5.4 ML18170A0592018-06-19019 June 2018 Korea Hydro & Nuclear Power Co, Ltd - Revised Response to RAI 329-8424 for Question 14.03.08-13 (Rev.1) ML18162A3432018-06-11011 June 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 557-9199 for the Question 03.08.05-20 (Rev. 2) ML18155A4082018-06-0404 June 2018 Korea Hydro & Nuclear Power Co, Ltd. - Revised Response to RAI 61-7984 for Question 08.03.01-5 (Rev. 1) ML18155A4012018-06-0404 June 2018 Korea Hydro & Nuclear Power Co, Ltd. - Revised Response to RAI 297-8309 for Question 19.03-1 (Rev.2) ML18155A3932018-06-0404 June 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 297-8309 for Question 19.03-2 (Rev. 1) ML18155A3922018-06-0404 June 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 297-8309 for Question 19.03-2 (Rev. 1) ML18155A3822018-06-0404 June 2018 Korea Hydro & Nuclear Power Co., Ltd'S Revised Response to RAI 420-8482 for Question 19.03-36 (Rev. 1) ML18150A5832018-05-30030 May 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 557-9199 for the Question 03.08.05-20 ML18150A5802018-05-30030 May 2018 Korea Hydro & Nuclear Power Co., Ltd - Submittal of Revised Response to RAI 557-9199 for the Question 03.08.05-20 ML18145A0842018-05-25025 May 2018 Korea Hydro & Nuclear Power Co, Ltd. - Revised Response to RAI 301-8280 for the Question 07.01-45 (Rev.2) ML18142A2992018-05-18018 May 2018 Korea Hydro & Nuclear Power Co, Ltd. - Revised Response to RAI 255-8285 for the Question 03.08.05-7 (Rev. 5) ML18142A3062018-05-17017 May 2018 Korea Hydro & Nuclear Power Co., Ltd. - Response to RAI 554-9146 for Question 07.02-18 (Rev. 1) ML18137A4822018-05-17017 May 2018 Korea Hydro & Nuclear Power Co, Ltd. - Response to RAI 558-9456 for Question 14.03.01-1 ML18137A4742018-05-17017 May 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 128-7980 for the Question 18-18 (Rev. 1) ML18137A4722018-05-17017 May 2018 Korea Hydro & Nuclear Power Co., Ltd - Transmittal of Revised Response to RAI 128-7980 for the Question 18-18 (Rev. 1) ML18131A1042018-05-11011 May 2018 Korea Hydro & Nuclear Power Co, Ltd - Revised Response to RAI 7-8567 for Question APR1400-4 (Rev. 1) ML18131A1062018-05-11011 May 2018 Korea Hydro & Nuclear Power Co, Ltd - Revised Response to RAI 7-8567 for Question APR1400-4 (Rev. 1) ML18131A1132018-05-11011 May 2018 Revised Response to RAI 412-8525 for Question 08.04-15 (Rev. 1) ML18129A3882018-05-0909 May 2018 Korea Hydro & Nuclear Power Co., Ltd - Revised Response to Request for Additional Information for Question No. 08.01-21 ML18124A1132018-05-0404 May 2018 Korea Hydro & Nuclear Power Co, Ltd - Revised Response to RAI 45-7883 for the Question 07.09-2 (Rev.6) ML18124A1512018-05-0404 May 2018 Korea Hydro & Nuclear Power Co, Ltd - Revised Response to RAI 555-9163 for the Question 07.02-19 (Rev. 2) ML18121A4162018-05-0101 May 2018 Korea Hydro & Nuclear Power Co, Ltd - Revised Response to RAI 433-8363 for Question 19-83 (Rev.2) ML18120A3042018-04-30030 April 2018 Korea Hydro & Nuclear Power Co., Ltd - Response to RAI 342-8291 for Question 07.08-10 (Rev.2) ML18115A3332018-04-25025 April 2018 Korea Hydro & Nuclear Power Co, Ltd. - Revised Response to RAI 553-9084 for the Question 18-134 (Rev.2) 2019-07-26
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EA ACC/SAMDA 1 / 3 KEPCO/KHNP RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION APR1400 Design Certification Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., LTD Docket No.52-046 RAI No.: ER 3-8655 SRP Section: Environmental Report Application Section: APR1400 Environmental Report Date of RAI Issued: 11/30/2016 Question No. EA ACC/SAMDA-1 On May 4, 2016, the Commission issued a decision (CLI-16-07; Agency-wide Documents Access and Management System (ADAMS) Accession No. ML16125A150) in the Indian Point license renewal proceeding. The Commission found that none of the parties involved in the Indian Point Severe Accident Mitigation Alternatives (SAMA) contention could provide a documented description outlining the technical foundation for two inputs (the time to decontaminate, TIMDEC, and the cost to decontaminate non-farmland, CDNFRM) used in the MACCS computer analyses. It was noted by the Commission that sensitivity analyses help demonstrate whether and to what extent variations in an uncertain input value might affect the overall cost-benefit conclusions. The Commission therefore directed the Staff to perform additional sensitivity analyses varying the TIMDEC and CDNFRM input parameters using specific values.
The TIMDEC and CDNFRM parameters used in the Indian Point SAMA analysis are also commonly used in the off-site risk calculations applied in the Severe Accident Mitigation Design Alternatives (SAMDA) cost-benefit analyses performed for new reactor standard design certification and combined license applications. 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 input values applied are set based on the level of contamination as specified by the decontamination factor parameter, DF. The CDNFRM values used in NUREG-1150 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 set to specific values associate with different levels of contamination and escalated to account for inflation.
EA ACC/SAMDA 2 / 3 KEPCO/KHNP The SAMDA analysis performed for the Advanced Power Reactor 1400 (APR1400) Standard Design Certification (DC) also relied upon the NUREG-1150 values for TIMDEC and CDNFRM.
Therefore, the staff requires the applicant to justify why the TIMDEC and CDNFRM parameters used in the SAMDA analysis for the APR1400 DC are acceptable or perform a cost-benefit sensitivity analyses based on revised TIMDEC and CDNFRM values for the applied DF levels.
If sensitivity analyses will be performed, use input values for the sensitivity analysis either (1) based on information in CLI-16-07 for the appropriate sets of DF values or, in the alternative, (2) selected by the applicant and appropriately justified for the sensitivity analyses. Since two decontamination levels are currently assessed in the APR1400 MACCS calculation (i.e., low contamination levels with a DF=3 and high contamination levels with a DF=15), apply a set of maximum values for a DF=3 and another set of maximum values for a DF=15. Explain with sufficient justification your appropriate maximum values for TIMDEC and CDNFRM for each DF value. With the revised values, re-assess the offsite risks and apply the revised results into the SAMDA cost-benefit analysis for a revised maximum averted costs. Determine if there is now a SAMDA that could be cost-beneficial based on the revised decontamination inputs and justify the resulting determination.
Upon completing the analyses, document the sensitivity analyses in an appropriate manner in the APR1400 Standard Design Certification Environmental Report and related technical document(s).
Response
The sensitivity analysis was performed and discussed in Case 10 of the Level 3 Analysis in Appendix A of the SAMDA Report (APR1400-E-P-NR-14006-P, Rev. 1). Parameter TIMDEC was increased to 3.15x107 seconds (365 days) and CDNFRM was increased to 1x105 $/person.
The sensitivity results for this case, when compared to the base case dose increased slightly in dose and more significantly in offsite economic cost.
When applied to the Level 2 at-power internal events STC frequencies, the change in dose increased from 5.33x10-1 REM/yr to 5.63 x10-1 REM/yr. Offsite economic costs increased from $1,534 to $3,466. With this dose and dollars applied to the other at-power and LPSD results, the total averted costs (TAC) increased from $909,168 to $986,940 (increase of $77,000) for this sensitivity case and 7% discounted rate. For the 3% discounted rate, TAC increased from $964,323 to $1,118,107 (increase of $154,000). The increase in dose of approximately 5%
and the increase in the TAC of approximately 15% due to the change in these parameters would not impact the overall conclusion of the SAMDA Report.
For the Level 3 analysis, the analysis does not use or reference the Level 2 STC frequencies that are in the SAMDA analysis. The sensitivity results show the general increase in values over the base case.
Impact on DCD There is no impact on the DCD.
EA ACC/SAMDA 3 / 3 KEPCO/KHNP Impact on PRA There is no impact on the PRA.
Impact on Technical Specifications There is no impact on the Technical Specifications.
Impact on Technical/Topical/Environmental Reports The SAMDA Report is updated to reflect the changes discussed above.