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Category:Letter type:GNRO
MONTHYEARGNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019 Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation. GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval ML19023A3282019-01-23023 January 2019 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2017/00068, Response to Official Requests for Additional Information (RAI) for RR GG-ISI-020 to Use BWRVIP Guidelines2017-10-12012 October 2017 Response to Official Requests for Additional Information (RAI) for RR GG-ISI-020 to Use BWRVIP Guidelines ML17269A0782017-09-22022 September 2017 Response to Request for Additional Information (RAI) for Relief Request GG-ISl-021 Associated with Fourth Interval Inservice Inspection Using Code CAS N-702, Dated August 8, 2017 GNRO-2017/00053, Response to Eseb RAI-1, Results of IWE and Iwl Inspections2017-08-25025 August 2017 Response to Eseb RAI-1, Results of IWE and Iwl Inspections GNRO-2016/00059, Response to Generic Letter 2016-01 Regarding Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-11-0101 November 2016 Response to Generic Letter 2016-01 Regarding Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools GNRO-2016/00040, Response to Request for Additional Information (RAI) on Severe Accident Mitigation Alternatives (SAMA) for Grand Gulf Nuclear Station License Renewal Environmental Review2016-09-0707 September 2016 Response to Request for Additional Information (RAI) on Severe Accident Mitigation Alternatives (SAMA) for Grand Gulf Nuclear Station License Renewal Environmental Review GNRO-2016/00036, Response to Requests for Additional Information (Rais) Regarding Final Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2016-07-29029 July 2016 Response to Requests for Additional Information (Rais) Regarding Final Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) GNRO-2016/00013, Supplemental Correction Response to License Renewal Amendment Request for Additional Information Set 472016-02-26026 February 2016 Supplemental Correction Response to License Renewal Amendment Request for Additional Information Set 47 CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, ML15348A4022015-12-14014 December 2015 Amended Response to Request for Additional Information (RAI) 4.2.3-2, Dated October 28, 2015 GNRO-2015/00091, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing/2015-12-10010 December 2015 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing/ CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 GNRO-2015/00077, Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours.2015-11-24024 November 2015 Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours. GNRO-2015/00079, Responses to Request for Additional Information (RAI) Set 53, Dated October 28, 20152015-11-23023 November 2015 Responses to Request for Additional Information (RAI) Set 53, Dated October 28, 2015 GNRO-2015/00063, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing2015-10-28028 October 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Containment Leak Rate Testing GNRO-2015/00064, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5 Amendment Request, 08/28/20152015-10-15015 October 2015 Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5 Amendment Request, 08/28/2015 GNRO-2015/00060, Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours..2015-10-12012 October 2015 Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF) TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours.. GNRO-2015/00058, Response to License Renewal Application (LRA) Request for Additional Information (RAI) Set 47, Question 4.2.1-2c (5) (a) I2015-09-0101 September 2015 Response to License Renewal Application (LRA) Request for Additional Information (RAI) Set 47, Question 4.2.1-2c (5) (a) I GNRO-2015/00042, Response to License Amendment Request for Revision of Five Technical Specification Allowable Value Setpoints Request for Additional Information, Set No. 2, Revision 12015-06-30030 June 2015 Response to License Amendment Request for Revision of Five Technical Specification Allowable Value Setpoints Request for Additional Information, Set No. 2, Revision 1 2024-01-12
[Table view] |
Text
~Entergy Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Vincent Fallacara Site Vice-President Grand Gulf Nuclear Station Tel. (601) 437-2129 GNRO-2016/00040 September 7,2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information (RAI) on Severe Accident Mitigation Alternatives (SAMA) for Grand Gulf Nuclear Station License Renewal Environmental Review Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. Entergy Letter GNRO-2012/00144, "Reanalysis of Severe Accident Mitigation Alternatives," date November 19, 2012
- 2. U.S. NRC Letter, "Request for Additional Information on Severe Accident Mitigation Alternatives for the Review of the Grand Gulf Nuclear Station, Unit 1, License Renewal Application Environmental Review", dated July 12,2016 (ML16181A112)
Dear Sir or Madam:
Entergy Operations, Inc. is providing, in the Attachment, response to the Request for Additional Information (RAI) on Severe Accident Mitigation Alternatives (SAMA).
This letter contains no new commitments.
If you have any questions or require additional information, please contact James Nadeau at 601-437 -2103.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of September, 2016.
VF/ras
GNRO-2016/00040 Page 2 of 2
Attachment:
Response to Request for Additional Information on Severe Accident Mitigation Alternatives for Grand Gulf Nuclear Station License Renewal Environmental Report cc: with Attachment U.S. Nuclear Regulatory Commission ATTN: Mr. David Drucker, NRR/DLR Sr. Project Manager Environmental Review and Projects Branch Division of License Renewal Office of Nuclear Reactor Regulation Mail Stop OWFN-11-F1 Washington, DC 20555 cc: without Attachment U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss Kennedy Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission ATTN: Mr. J. Kim, NRR/DORL Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2016/00040 Response to Request for Additional Information on Severe Accident Mitigation Alternatives for Grand Gulf Nuclear Station License Renewal Environmental Report
Attachment to GNRO-2016/00040 Page 1 of 3 Response to Request for Additional Information on Severe Accident Mitigation Alternatives for Grand Gulf Nuclear Station License Renewal Environmental Report Request for Additional Information:
On May 4,2016, the Commission issued a decision (CLI-16-07) in the Indian Point license renewal proceeding, in which it directed the NRC 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 NRC 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,OOO/person for 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.
The NRC staff believes the Commission's decision in CLI-16-07 may be applicable to the SAMA analysis performed for Grand Gulf Nuclear Station, inasmuch as that analysis may have also relied upon the NUREG-1150 values for TIMDEC and CDNFRM. We therefore request that Entergy Operations, Inc. (Entergy) either justify why CLI-16-07 does not apply to the SAMA analysis performed for Grand Gulf Nuclear Station or supplement the SAMA analysis with sensitivity analyses for the CDNFRM and TIMDEC values.
Entergy 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, Entergy should execute sensitivity analyses for the release categories modeled that exceed 1015 Becquerels of Cs-137 released. Entergy is requested to evaluate how these sensitivity analyses may affect its identification of potentially cost-beneficial SAMAs. Finally, upon completing its sensitivity analysis, Entergy 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 Grand Gulf Nuclear Station.
Attachment to GNRO-2016/00040 Page 2 of 3 Entergy Response Entergy has chosen to use response option "1) to apply the maximum values specified by the Commission ... for the release categories modeled that exceed 1015 Becquerels of Cs-137 released." Thus, a MACCS2 sensitivity case was developed with the following changes (as compared to the GGNS MACCS2 base case documented in the Grand Gulf Operating License Renewal Stage Applicant's Environmental Report (UEnvironment Report") as updated by the Grand Gulf Reanalysis of Severe Accident Mitigation Alternatives (USAMA Reanalysis") dated November 19, 2012 (ML12325A174):
- TIMDEC was escalated to one year (365 days) for decontamination factor (DF) =15
- CDNFRM was escalated to $1OO,OOO/person for DF=15
- These changes were applied to all release categories (those with total releases exceeding 1015 Becquerels of Cs-137 and those with total releases less than 1015 Becquerels of Cs-137).
Both the conditional and frequency-weighted MACCS2 results of this sensitivity case for offsite dose and economic cost are presented in Table 1 for each release category, as the RAI requests. The frequencies used to weight the results are those from the SAMA Reanalysis (Table E.1-13).
For the specified TIMDEC and CDNFRM input changes, the MACCS2 Offsite Economic Cost Risk (OECR) increased approximately 1000/0 and the Population Dose Risk (PDR) decreased approximately 14%) as compared to the MACCS2 base case OECR of $1.51 E+3/yr and PDR of 0.61 person-rem/yr as presented in the SAMA Reanalysis Table E.1-13.
The PDR decrease is attributed to the interplay between the relatively low land values in the region and the increased decontamination cost inputs. With the increased decontamination costs, more land is condemned rather than decontaminated because condemnation is more cost effective. For example, for the M/E release category which is the most risk significant, the population associated with condemned land increased from approximately 120 individuals (base case) to 14,300 individuals (sensitivity case). Individuals associated with condemned land are permanently relocated following the early accident phase and receive no further dose.
Individuals who are resettled following decontamination activities are modeled to receive low levels of dose for the ensuing years based on the land habitability criteria following decontamination. Therefore, condemning significantly more land results in a modest population dose decrease.
The increase in the OECR (and the decrease in the PDR) for this sensitivity case is bounded by the SAMA analysis ss" percentile uncertainty factor of 3.0, which was included as part of the SAMA candidate cost-benefit evaluation documented in Section E.2 of the Environmental Report, as updated by the SAMA Reanalysis. Therefore, no new SAMA candidates are identified as potentially cost-beneficial based on this new TIMDEC and CDNFRM sensitivity case. There are no changes to the conclusions of the SAMA analysis based on the TIMDEC and CDNFRM sensitivity case.
Attachment to GNRO-2016/00040 Page 3 of 3 Table 1 MACCS2 TIMDEC and CDNFRM Sensitivity Results Offsite Offsite Population Population PDR OECR Release Frequency Economic Economic Dose Dose Risk % of % of Category Cost Cost Risk Total Total (per yr) (p-rem) (p-rem/yr) ($) ($/yr)
HIE 1.04E-07 4.87E+05 5.06E-02 9.6% 3.51 E+09 3.65E+02 12%
H/I 1.21 E-08 4.31 E+05 5.22E-03 1.0% 2.83E+09 3.42E+01 1.1%
H/L 9.21 E-08 3.66E+05 3.37E-02 6.4% 1.94E+09 1.79E+02 5.9%
M/E 3.70E-07 4.03E+05 1.49E-01 28% 2.60E+09 9.62E+02 32%
Mil 1.81 E-07 5.18E+05 9.38E-02 18% 4.02E+09 7.28E+02 24%
MIL 3.03E-07 3.38E+05 1.02E-01 19% 2.08E+09 6.30E+02 21%
LIE 4.05E-09 9.84E+04 3.99E-04 0.08% 8.42E+07 3.41 E-01 0.01%
Lli 3.55E-08 3.05E+05 1.08E-02 2.1% 1.15E+09 4.08E+01 1.3%
LlL 4.44E-07 1.73E+05 7.68E-02 15% 1.92E+08 8.52E+01 2.8%
LLIE 2.19E-09 3.62E+02 7.93E-07 <0.001% 4.63E+05 1.01 E-03 <0.001%
LLII 2.12E-09 1.80E+02 3.82E-07 <0.001% 4.59E+05 9.73E-04 <0.001%
LLIL 7.05E-09 2.78E+05 1.96E-03 0.4% 7.02E+08 4.95E+00 0.2%
NCF 1.37E-06 3.62E+02 4.96E-04 0.09% 4.63E+05 6.34E-01 0.02%
Total 2.93E-06 -- 5.25E-01 100% -- 3.03E+03 100%