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| Line 3: |
Line 3: |
| | issue date = 06/21/2011 | | | issue date = 06/21/2011 |
| | title = Request for Additional Information Regarding Extended Power Uprate, License No. NPF-29 | | | title = Request for Additional Information Regarding Extended Power Uprate, License No. NPF-29 |
| | author name = Krupa M A | | | author name = Krupa M |
| | author affiliation = Entergy Operations, Inc | | | author affiliation = Entergy Operations, Inc |
| | addressee name = | | | addressee name = |
Letter Sequence Request |
|---|
TAC:ME4679, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting
Results
Other: GNRO-2012/00150, Final Report for Replacement Steam Dryer, GNRO-2017/00039, Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages, ML102660403, ML111720830, ML112560396, ML12167A257, ML12167A269, ML12177A287, ML13108A217, NRC-2012-0105, Environmental Assessment and Finding of No Significant Impact Related Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
|
MONTHYEARML1026604002010-08-20020 August 2010
GE-Hitachi Nuclear Energy Americas LLC - Affidavit of Edward Schrull Withholding from Public Disclosure Proprietary Report NEDC-33477P
Project stage: Request
ML1026603992010-08-31031 August 2010
NEDO-33477, Revision 0, Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate.
Project stage: Request
ML1026604032010-09-0808 September 2010
License Amendment Request Extended Power Uprate
Project stage: Other
GNRO-2010/00056, NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix E Through Appendix G2010-09-30030 September 2010
NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix E Through Appendix G
Project stage: Request
ML1026604062010-09-30030 September 2010
NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix B Through Appendix D
Project stage: Request
ML1026604012010-09-30030 September 2010
NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Cover Through Appendix a
Project stage: Request
ML1030102002010-11-0909 November 2010
Supplemental Information Needed for Acceptance of License Amendment Request, Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Megawatts Thermal
Project stage: Acceptance Review
GNRO-2010/00071, Supplemental Information, License Amendment Request, Extended Power Uprate2010-11-18018 November 2010
Supplemental Information, License Amendment Request, Extended Power Uprate
Project stage: Supplement
GNRO-2010/00073, Supplemental Information License Amendment Request, Extended Power Uprate2010-11-23023 November 2010
Supplemental Information License Amendment Request, Extended Power Uprate
Project stage: Supplement
ML1034201082010-12-16016 December 2010
Request for Withholding Information from Public Disclosure, 9/7/10 Affidavit Executed by E. Schrull, GEH Re NEDC-33601P
Project stage: Withholding Request Acceptance
ML1034705862011-01-0505 January 2011
Request for Withholding Information from Public Disclosure, 11/19/10 Affidavit Executed by E. Schrull, GE-Hitachi, Regarding NEDC-33621P
Project stage: Withholding Request Acceptance
ML1102602812011-01-26026 January 2011
E-mail, Request for Additional Information Instrument and Controls, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1102602872011-01-26026 January 2011
E-mail, Request for Additional Information Fire Protection, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1102701872011-01-27027 January 2011
Request for Additional Information, Emcb Non-Steam Dryer Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1103103902011-01-31031 January 2011
E-mail, Request for Additional Information, Vessels and Internal Integrity Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1103901732011-02-0808 February 2011
Email, Request for Additional Information, Nrr/Dci/Csgb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00012, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00011, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML1105407052011-02-23023 February 2011
E-mail, Request for Additional Information, Nrr/Dirs/Ihpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1105407122011-02-23023 February 2011
E-mail, Request for Additional Information, Nrr/Dra/Apla Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00013, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML1034200962011-02-25025 February 2011
Request for Withholding Information from Public Disclosure, 8/20/10 Affidavit Executed by E. Schrull, GEH, for NEDC-33477P
Project stage: Withholding Request Acceptance
ML1106007172011-03-0101 March 2011
Email Request for Additional Information, Round 2, Nrr/Dci/Cvib Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00016, Request for Additional Information Regarding Extended Power Uprate2011-03-0909 March 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML1107501322011-03-16016 March 2011
Email, Dose Assessment Branch, Request for Additional Information, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1108202242011-03-23023 March 2011
Email, Request for Additional Information, Nrr/Dss/Srxb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1108202272011-03-23023 March 2011
Request for Additional Information, Nrr/Dss/Srxb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00018, Request for Additional Information Regarding Extended Power Uprate2011-03-30030 March 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00021, Response to Request for Additional Information Regarding Extended Power Uprate2011-03-31031 March 2011
Response to Request for Additional Information Regarding Extended Power Uprate
Project stage: Response to RAI
ML1109401362011-04-0404 April 2011
Email, Request for Additional Information, Nrr/Dci/Csgb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1109502722011-04-0505 April 2011
Email, Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1109502812011-04-0505 April 2011
Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1110301112011-04-12012 April 2011
Email, Request for Additional Information, Nrr/Dss/Snpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00024, Response to Request for Additional Information Regarding Extended Power Uprate2011-04-14014 April 2011
Response to Request for Additional Information Regarding Extended Power Uprate
Project stage: Response to RAI
ML11112A0982011-04-21021 April 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML1110401002011-04-27027 April 2011
Request for Withholding Information from Public Disclosure, 3/28/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00018
Project stage: Withholding Request Acceptance
ML1110401252011-04-27027 April 2011
Request for Withholding Information from Public Disclosure, 2/20/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00013
Project stage: Withholding Request Acceptance
ML1110401132011-04-27027 April 2011
Request for Withholding Information from Public Disclosure, 2/20/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00011
Project stage: Withholding Request Acceptance
ML1110401072011-04-27027 April 2011
Request for Withholding Information from Public Disclosure, 2/17/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00012
Project stage: Withholding Request Acceptance
ML1110401162011-04-27027 April 2011
Request for Withholding Information from Public Disclosure, 3/30/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00021
Project stage: Withholding Request Acceptance
GNRO-2011/00035, Response to Request for Additional Information Regarding Extended Power Uprate2011-05-0505 May 2011
Response to Request for Additional Information Regarding Extended Power Uprate
Project stage: Response to RAI
ML1113001562011-05-10010 May 2011
Email, Request for Additional Information, Nrr/Dss/Scvb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00037, Request for Additional Information Regarding Extended Power Uprate2011-05-11011 May 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML1114002992011-05-20020 May 2011
E-mail, Request for Additional Information, Nrr/Dci/Emcb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1113905252011-05-31031 May 2011
Request for Withholding Information from Public Disclosure, 4/21/2011 Affidavit Executed by E. Schrull, GEH, for Attachment 1 to GNRO-2011/00025
Project stage: Withholding Request Acceptance
ML1115204582011-06-0101 June 2011
Email, Request for Additional Information, Nrr/Dra/Aadb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1115304392011-06-0606 June 2011
(Redacted) Request for Additional Information from Nrr/De/Emcb Steam Dryer, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00043, Request for Additional Information Regarding Extended Power Uprate2011-06-0808 June 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00046, Response to Request for Additional Information Regarding Extended Power Uprate2011-06-15015 June 2011
Response to Request for Additional Information Regarding Extended Power Uprate
Project stage: Response to RAI
ML1117200422011-06-20020 June 2011
Licensee Response Regarding Request for Additional Information on Training for Prnms (TAC No. 4679)
Project stage: Request
2011-03-30
[Table View] |
|
|---|
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:Request for Additional Information (RAI)
MONTHYEARML23348A1222023-12-14014 December 2023
NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems
ML23116A1462023-04-26026 April 2023
NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019)
ML23059A0742023-02-27027 February 2023
Information Request, Security IR 2023402
ML22353A6122022-12-19019 December 2022
March 2023 Emergency Preparedness Exercise Inspection - Request for Information
ML22271A8572022-10-0303 October 2022
Notification of Commercial Grade Dedication Inspection (05000416/2023011) and Request for Information
ML22110A1172022-04-19019 April 2022
(GG) 2022 Emergency Preparedness (EP) Program Inspection RFI Sdh 041922
ML21179A1202021-06-28028 June 2021
Notification of NRC Supplemental Inspection of Action Matrix Column 3 (Degraded Performance) Inputs and Request for Information
ML21074A0822021-03-15015 March 2021
Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000416/2021002) and Request for Information
ML20363A1462020-12-22022 December 2020
Request for Information: Grand Gulf EP Exercise Inspection - March 2021
ML20258A0202020-09-0909 September 2020
EP Program Inspection RFI, Request for Information to Support and Prepare for Emergency Preparedness (EP) Program Inspection Scheduled to Occur the Week of November 16, 2020
ML20260H4422020-09-0808 September 2020
NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Official RAIs for RR Associated with Updating ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019)
ML20155K7172020-06-0303 June 2020
Notification of NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000416/2020013) and Request for Information
ML20150A6012020-05-29029 May 2020
NRR E-mail Capture - Grand Gulf - Official RAI for LAR Associated with Containment ILRT Interval Change from 10 Years to 15 Years
ML19302E1082019-10-29029 October 2019
Document Request - GG 95001 - August 2 2019
ML19078A3772019-03-19019 March 2019
NRR E-mail Capture - Grand Gulf - Official Rais for Relief Request GG-ISI-023, Inservice Inspection Impracticality, Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval
ML19063B4882019-03-0404 March 2019
Notification of NRC Triennial Heat Sink Performance Inspection (05000416/2019002) and Request for Information
ML18304A4602018-10-31031 October 2018
NRR E-mail Capture - Final Request for Additional Information - TSTF-425 (L-2018-LLA-0106)
ML18250A3042018-08-30030 August 2018
NRR E-mail Capture - Final Request for Additional Information - Emergency Action Level Scheme Change (L-2018-LLA-0116)
ML18250A3032018-08-0101 August 2018
NRR E-mail Capture - Correction: Draft RAI - EAL Scheme Change (L-2018-LLA-0116)
ML18187A3292018-07-20020 July 2018
Request for Additional Information, Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis
ML18138A4682018-05-23023 May 2018
Supplemental Information Needed for Acceptance of Request for Licensing Action Adoption of TSTF-425, Relocate Surveillance Frequencies to License Control
ML18058A0572018-02-23023 February 2018
Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update)
ML17257A1422017-09-14014 September 2017
NRR E-mail Capture - Grand Gulf - Official Requests for Additional Information (Rais) for RR GG-ISI-020 to Use BWRVIP Guidelines
ML17235B1752017-08-23023 August 2017
NRR E-mail Capture - Grand Gulf - Official RAI for Relief Request GG-ISI-021 Associated with Fourth Interval Inservice Inspection Using Code Case N-702
ML17214A0992017-08-0202 August 2017
NRR E-mail Capture - Grand Gulf - Official RAIs for LAR Associated with One Cycle Extension of Appendix J Type a ILRT and Drywell Bypass Test Interval
ML17142A2582017-05-19019 May 2017
Notification of NRC Design Bases Assurance Inspection (05000416/2017007) and Initial Request for Information
ML16181A1122016-07-12012 July 2016
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
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2023-04-26
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Text
GNRO-2011/00050 June 21, 2011
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Request for Additional Information Regarding Extended Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416
License No.
NPF-29
REFERENCES:
- 1. Email from A. Wang to F. Burford dated June 1, 2011, GGNS EPU Request for Additional Information Related to Accident Dose Branch Review (ME4679) (NRC ADAMS Accession Number ML111520458) 2. License Amendment Request, Extended Power Uprate, dated September 8, 2010 (GNRO-2010/00056, NRC ADAMS Accession Number ML102660403)
Dear Sir or Madam:
The Nuclear Regulatory Commission (NRC) requ ested additional information (Reference 1) regarding certain aspects of the Grand Gulf Nuclear Station, Unit 1 (GGNS) Extended Power Uprate (EPU) License Amendment Request (LAR) (Reference 2). Attachment 1 provides responses to the additional information requested by the Accident Dose Branch.
No change is needed to the no significant hazards consideration included in the initial LAR (Reference 2) as a result of the additional information provided. There are no new commitments included in this letter.
If you have any questions or require additional information, please contact Jerry Burford at
601-368-5755.
Entergy Operations, Inc. P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6684 GNRO-2011/00050 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on June 21, 2011.
Sincerely, MAK/FGB/dm
Attachments:
- 1. Response to Request for Additional Information, Accident Dose Branch
cc: Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2) ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only
Mail Stop OWFN/8 B1 11555 Rockville Pike
Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment 1 GNRO-2011/00050 Grand Gulf Nuclear Station Extended Power Uprate Response to Request for Additional Information Accident Dose Branch to GNRO-2011/ 00050
Page 1 of 7 Response to Request for Additional Information Accident Dose Branch By letter dated September 8, 2010, Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) for an Extended Power Uprate (EPU) for Grand Gulf Nuclear Station, Unit 1 (GGNS). By letter dated April 14, 2011, Entergy submitted responses to the initial request for additional information (RAI) from the Accident Dose Branch (NRC ADAMS Accession No. ML111050134). Subsequently, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following additional information requested by the Accident Dose
Branch is needed for the NRC staff to complete their review of the amendment. Entergy's response to each item is provided below.
RAI # 1 In Attachment 1 to the letter dated April 14, 2011, it is stated that a weighted dose scaling factor is used to calculate the EPU dose results for the fuel handling accident (FHA), the control rod drop accident (CRDA), and the pressure controller failure event. Please provide additional information describing the methodology used or provide the calculations used to develop the weighted dose scaling factors for the EAB, LPZ, and CR for the FHA, CRDA, and the pressure controller failure event Please provide the basis for the weighted dose scaling factors that were used. Please provide any values that were used to develop the weighted dose scaling factors and describe any models that were used to calculate those values.
Response As described in Entergy's letter to the NRC dated April 14, 2011, the EPU dose is estimated for certain events based on the contribution of each isotope to the calculated dose in the calculation-of-record and the predicted increase in each isotope for EPU. The current licensed thermal power (CLTP) doses are then increased by this weighted scaling factor to develop an accurate estimate of the doses at the EPU power level. The following three tables address the fuel handling accident, control rod drop accident, and the pressure controller failure events. As shown in each table, the contributions to the calculated doses from each isotope are presented for the CLTP case at each location. To generate the EPU dose, these CLTP doses are then adjusted by the EPU-related increase or decrease for each isotope as reported in Tables 1 and 2 of the April 14, 2011 letter. At each location, the doses from each isotope are then summed for a total dose and the weighted dose scaling factor can be calculated based on the ratio of the total doses.
to GNRO-2011/ 00050
Page 2 of 7 Table 1: FHA Dose Consequence -
Isotope-Weighted EPU Dose Scaling Factor Pre-EPU EPU EAB TEDE (Rem) Control Room TEDE (Rem)
EPU Source Change % EAB TEDE (Rem) Control Room TEDE (Rem) Br-82 7.04E-04 5.67E-04 10.75% 7.80E-04 6.28E-04 Br-83 5.16E-07 7.20E-07 -5.74% 4.77E-07 6.79E-07 I-130 2.79E-03 2.94E-03 7.38% 3.00E-03 3.16E-03 I-131 1.68E+00 2.44E+00 11.73% 1.88E+00 2.73E+00 I-132 6.24E-02 2.60E-02 12.25% 7.00E-02 2.92E-02 I-133 1.94E-01 2.69E-01 9.05% 2.12E-01 2.93E-01 I-135 1.08E-02 9.57E-03 10.09% 1.19E-02 1.05E-02 Kr-83M 6.78E-08 5.65E-09 -5.70% 6.39E-08 5.33E-09 Kr-85 1.76E-04 1.47E-05 92.92% 3.40E-04 2.84E-05 Kr-85M 4.93E-03 4.10E-04 -10.18% 4.43E-03 3.68E-04 Kr-88 2.22E-02 1.85E-03 -12.80% 1.94E-02 1.61E-03 Xe-129M 2.77E-06 2.31E-07 2.52% 2.84E-06 2.37E-07 Xe-131M 3.18E-04 2.65E-05 10.93% 3.53E-04 2.94E-05 Xe-133 2.05E-01 1.70E-02 16.12% 2.38E-01 1.97E-02 Xe-133M 5.23E-03 4.35E-04 18.15% 6.18E-03 5.14E-04 Xe-135 4.15E-01 3.45E-02 53.85% 6.38E-01 5.31E-02 Xe-135M 3.55E-02 2.95E-03 11.19% 3.95E-02 3.28E-03 Total 2.64E+00 2.80E+00 3.12E+00 3.14E+00 Weighted Scaling Factor 1.18 1.12 EAB - Exclusion Area Boundary TEDE - Total Effective Dose Equivalent to GNRO-2011/ 00050
Page 3 of 7 Table 2: CRDA Dose Consequence - Isotope-Weighted EPU Dose Scaling Factor Pre-EPU EPU Bundle Source (1.7 peaking factor) (Ci/bundle)
EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Bundle Source (1.7 peaking factor) (Ci/bundle)
EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Br-82 2.717E+03 2.30E-05 2.07E-05 8.97E-05 3.028E+03 2.56E-05 2.30E-05 1.00E-04 Br-83 3.798E+04 7.99E-06 2.83E-06 1.24E-05 3.599E+04 7.58E-06 2.68E-06 1.17E-05 Br-84 7.107E+04 8.05E-05 1.91E-05 3.87E-06 6.460E+04 7.32E-05 1.74E-05 3.52E-06 Kr-83M 3.796E+04 1.31E-07 4.25E-08 9.47E-09 3.599E+04 1.24E-07 4.03E-08 8.97E-09 Kr-85 3.102E+03 1.20E-06 1.46E-06 5.90E-07 4.760E+03 1.85E-06 2.25E-06 9.05E-07 Kr-85M 8.844E+04 1.85E-03 9.16E-04 2.94E-04 7.982E+04 1.67E-03 8.26E-04 2.65E-04 Kr-87 1.786E+05 1.46E-02 4.14E-03 7.23E-04 1.567E+05 1.28E-02 3.63E-03 6.34E-04 Kr-88 2.525E+05 6.64E-02 2.61E-02 7.16E-03 2.213E+05 5.82E-02 2.28E-02 6.28E-03 Kr-89 3.207E+05 4.08E-03 9.33E-04 1.06E-05 2.754E+05 3.50E-03 8.01E-04 9.12E-06 I-128 8.534E+03 6.70E-07 1.56E-07 1.09E-07 9.131E+03 7.17E-07 1.67E-07 1.17E-07 I-130 2.002E+04 2.11E-04 1.44E-04 7.84E-04 2.157E+04 2.27E-04 1.56E-04 8.44E-04 I-131 2.394E+05 2.35E-02 2.05E-02 1.93E-01 2.691E+05 2.64E-02 2.31E-02 2.17E-01 I-132 3.415E+05 1.19E-03 4.22E-04 5.31E-04 3.861E+05 1.35E-03 4.77E-04 6.01E-04 I-133 4.781E+05 8.47E-03 6.22E-03 5.02E-02 5.243E+05 9.28E-03 6.82E-03 5.50E-02 I-134 5.369E+05 1.21E-03 3.10E-04 1.00E-04 5.804E+05 1.30E-03 3.35E-04 1.09E-04 I-135 4.455E+05 2.52E-03 1.40E-03 5.59E-03 4.932E+05 2.78E-03 1.55E-03 6.19E-03 Xe-129M 9.566E+00 3.29E-08 3.89E-08 1.56E-08 9.744E+00 3.36E-08 3.96E-08 1.59E-08 Xe-131M 2.711E+03 3.43E-06 4.08E-06 1.64E-06 3.029E+03 3.83E-06 4.56E-06 1.83E-06 Xe-133 4.502E+05 2.28E-03 2.63E-03 1.05E-03 5.243E+05 2.65E-03 3.07E-03 1.23E-03 Xe-133M 1.490E+04 6.57E-05 7.15E-05 2.84E-05 1.657E+04 7.31E-05 7.95E-05 3.15E-05 Xe-135 1.573E+05 5.66E-03 3.94E-03 1.43E-03 2.028E+05 7.30E-03 5.08E-03 1.85E-03 Xe-135M 9.684E+04 1.20E-03 2.75E-04 1.35E-05 1.083E+05 1.34E-03 3.08E-04 1.51E-05 Xe-137 4.213E+05 3.64E-03 8.32E-04 1.13E-05 4.590E+05 3.97E-03 9.06E-04 1.23E-05 Xe-138 4.380E+05 1.39E-02 3.19E-03 1.44E-04 4.502E+05 1.43E-02 3.28E-03 1.48E-04 Rb-86 1.048E+03 2.44E-07 2.17E-07 6.91E-07 1.203E+03 2.80E-07 2.49E-07 7.94E-07 to GNRO-2011/ 00050
Page 4 of 7 Table 2: CRDA Dose Consequence - Isotope-Weighted EPU Dose Scaling Factor Pre-EPU EPU Bundle Source (1.7 peaking factor) (Ci/bundle)
EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Bundle Source (1.7 peaking factor) (Ci/bundle)
EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Rb-88 2.546E+05 8.27E-07 1.90E-07 3.47E-08 2.241E+05 7.28E-07 1.67E-07 3.06E-08 Rb-89 3.323E+05 2.46E-06 5.62E-07 3.62E-08 2.900E+05 2.14E-06 4.91E-07 3.16E-08 Cs-132 1.140E+02 6.26E-09 5.86E-09 1.38E-08 1.280E+02 7.03E-09 6.58E-09 1.55E-08 Cs-134 1.002E+05 1.65E-04 1.48E-04 4.69E-04 1.453E+05 2.39E-04 2.15E-04 6.80E-04 Cs-134M 2.432E+04 3.59E-08 1.38E-08 2.52E-08 2.729E+04 4.03E-08 1.55E-08 2.83E-08 Cs-136 2.653E+04 7.80E-06 7.20E-06 1.94E-05 3.633E+04 1.07E-05 9.87E-06 2.66E-05 Cs-137 3.544E+04 3.98E-05 3.58E-05 1.15E-04 5.948E+04 6.69E-05 6.01E-05 1.92E-04 Cs-138 4.718E+05 8.14E-06 1.93E-06 2.63E-07 4.942E+05 8.52E-06 2.02E-06 2.76E-07 Total 1.51E-01 7.23E-02 2.62E-01 1.48E-01 7.36E-02 2.91E-01 Weighted Scaling Factor 0.98* 1.02 1.11
- Although the isotope-specific weighting factor approach concludes that the CRDA EAB dose decreases with EPU, EPU LAR Attachment 5 Table 2.9-9, CRDA Radiological Consequences, conservatively assumes no change in dose.
EAB - Exclusion Area Boundary LPZ - Low Population Zone
to GNRO-2011/ 00050
Page 5 of 7 Table 3: Pressure Controller Failure Dose Consequence Isotope-Weighted EPU Scaling Factor Pre-EPU EPU EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Isotope-Specific Scaling Factor based on core source terms EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Br-82 9.88E-05 2.26E-05 5.87E-04 2.79% 1.02E-04 2.32E-05 6.03E-04 Br-83 5.73E-05 1.31E-05 3.84E-04 9.69% 6.28E-05 1.44E-05 4.21E-04 Kr-83m 4.61E-12 1.05E-12 1.70E-09 9.69% 5.06E-12 1.16E-12 1.86E-09 Br-84 1.17E-03 2.67E-04 1.63E-03 8.28% 1.26E-03 2.89E-04 1.76E-03 Kr-85 1.47E-05 3.37E-06 9.41E-06 3.73% 1.53E-05 3.49E-06 9.76E-06 Kr-85m 2.17E-02 4.97E-03 1.05E-02 -10.03% 1.96E-02 4.47E-03 9.46E-03 Rb-86 7.43E-06 1.70E-06 3.63E-05 5.13% 7.81E-06 1.79E-06 3.81E-05 Kr-87 2.18E-01 4.98E-02 6.57E-02 -4.99% 2.07E-01 4.73E-02 6.24E-02 Rb-87 3.40E-18 7.77E-19 1.04E-14 -4.99% 3.23E-18 7.39E-19 9.87E-15 Kr-88 7.28E-01 1.66E-01 3.09E-01 -0.90% 7.21E-01 1.65E-01 3.06E-01 Rb-88 1.01E-03 2.32E-04 3.29E-01 -0.90% 1.00E-03 2.30E-04 3.26E-01 Rb-89 5.10E-04 1.17E-04 7.57E-05 -0.79% 5.06E-04 1.16E-04 7.51E-05 Sr-89 1.30E-08 2.97E-09 1.26E-05 -0.79% 1.29E-08 2.95E-09 1.25E-05 I-131 1.59E-01 3.64E-02 1.76E+00 13.17% 1.80E-01 4.12E-02 1.99E+00 Xe-131m 6.66E-13 1.52E-13 6.97E-10 13.17% 7.54E-13 1.72E-13 7.89E-10 I-132 1.09E-02 2.48E-03 2.15E-02 13.18% 1.23E-02 2.81E-03 2.43E-02 I-133 5.92E-02 1.35E-02 5.90E-01 14.84% 6.80E-02 1.56E-02 6.77E-01 Xe-133 2.70E-02 6.17E-03 1.70E-02 14.84% 3.10E-02 7.09E-03 1.96E-02 Xe-133m 6.67E-11 1.52E-11 6.42E-08 14.84% 7.66E-11 1.75E-11 7.38E-08 Cs-134 5.82E-03 1.33E-03 2.82E-02 -12.43% 5.10E-03 1.16E-03 2.47E-02 I-134 1.59E-02 3.64E-03 9.50E-03 14.56% 1.83E-02 4.18E-03 1.09E-02 Cs-135 1.27E-13 2.91E-14 7.13E-10 15.02% 1.46E-13 3.34E-14 8.20E-10 I-135 1.86E-02 4.26E-03 1.05E-01 15.02% 2.14E-02 4.90E-03 1.21E-01 Xe-135 8.18E-02 1.87E-02 4.58E-02 15.02% 9.41E-02 2.15E-02 5.26E-02 Xe-135m 7.68E-02 1.76E-02 7.82E-03 15.02% 8.84E-02 2.02E-02 8.99E-03 to GNRO-2011/ 00050
Page 6 of 7 Table 3: Pressure Controller Failure Dose Consequence Isotope-Weighted EPU Scaling Factor Pre-EPU EPU EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Isotope-Specific Scaling Factor based on core source terms EAB 2 hr TEDE (Rem)
LPZ TEDE (Rem) Control Room TEDE (Rem) Cs-136 3.07E-04 7.01E-05 1.32E-03 -3.66% 2.95E-04 6.75E-05 1.27E-03 Ba-137m 3.66E-07 8.38E-08 4.77E-06 1.55% 3.72E-07 8.51E-08 4.84E-06 Cs-137 2.04E-03 4.67E-04 9.97E-03 1.55% 2.07E-03 4.74E-04 1.01E-02 Cs-138 1.06E-03 2.43E-04 3.38E-04 13.64% 1.21E-03 2.76E-04 3.84E-04 Xe-138 8.49E-01 1.94E-01 7.98E-02 13.04% 9.60E-01 2.19E-01 9.02E-02 Total 2.28E+00 5.21E-01 3.39E+00 2.43E+00 5.56E-01 3.74E+00 Weighted Scaling Factor 1.07 1.07 1.10 to GNRO-2011/ 00050
Page 7 of 7 RAI # 2 It is the NRC staff's understanding that the current GGNS analyses of record for the radiological dose consequences for design basis accidents is evaluated at a power level of 3910 MWt or lower depending on the accident scenario being evaluated. Please describe what the GGNS analyses of record will consist of for the proposed change at the EPU power level, provided a weighted dose scaling factor was used to calculate the EPU dose results instead of a reanalysis of the current radiological dose analyses for DBAs.
Response The GGNS radiological analyses are maintained in accordance with 10 CFR 50, Appendix B, Part III. The weighted dose scaling factors have been developed via verified, safety-related calculations under Shaw's Quality Assurance program. The reported EPU doses developed with these weighted scaling factors represent the predicted post-EPU doses that would be anticipated if full re-analyses of the affected radiological calculations were performed. Thus, full re-analyses are not required to maintain these calculations updated for design control purposes and GGNS plans to rely on the weighted scaling factor results.
