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| | number = ML110940136 | | | number = ML110940136 |
| | issue date = 04/04/2011 | | | issue date = 04/04/2011 |
| | title = 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 (TAC No. ME4679) | | | title = 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 |
| | author name = Wang A B | | | author name = Wang A |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Burford J, Millar D | | | addressee name = Burford J, Millar D |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Wang, Alan Sent: Monday, April 04, 2011 10:10 AM To: Jerry Burford; 'Dana Millar' Cc: Lent, Susan; Burkhardt, Janet; Obodoako, Aloysius | | {{#Wiki_filter:From: Wang, Alan Sent: Monday, April 04, 2011 10:10 AM To: Jerry Burford; 'Dana Millar' Cc: Lent, Susan; Burkhardt, Janet; Obodoako, Aloysius |
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| ==Subject:== | | ==Subject:== |
| GG EPU SG and Chemical Engineering Branch Request for Additional Information (ME4679) Dana and Jerry, By letter dated September 8, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102660403), Entergy Operations, Inc. (Entergy, the licensee), submitted a request to amend the Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee proposed a license amendment request (LAR) for an extended power uprate (EPU) to increase the maximum reactor core power operating limit from 3898 megawatts thermal (MWt) to 4408 MWt. By letter dated February 8, 2011 (ADAMS Accession No. Ml110390173), the U.S. Nuclear Regulatory Commission (NRC) staff issued RAIs. By letter dated March 9, 2011 (ADAMS Accession No. ML110680507), Entergy provided a response to these RAIs. Based on the review of this response, the NRC staff has determined that the following additional information is needed for the NRC staff to complete our review of this amendment . This request for additional information (RAI) was discussed with Mr. Jerry Burford of your staff on April 1, 2011, and it was agreed that a response would be provided within 30 days of receipt of this E-mail. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1445 or via e-mail at Alan.Wang@nrc.gov. 1. Based on industry operating experience, degradation of Boraflex panels occur in a much less uniform configuration than is shown in the spent fuel pool map provided in your letter dated March 9, 2011. That map shows that Region II racks (the racks that are degraded beyond a usable condition) are located together in the center of the pool. Please provide a map of the spent fuel pool which shows the cumulative dose to each panel in the pool. Also, discuss why Region II cells would be located in one specific area of the pool, and other cells outside of that area would not experience similar degradation after housing recently discharged fuel. | | GG EPU SG and Chemical Engineering Branch Request for Additional Information (ME4679) |
| : 2. In your response letter dated March 9, 2011, it states, "an additional BADGER [Boron-10 Areal Density Gauge for Evaluating Racks] measurement will be performed prior to the end of 2012. The need for additional tests will be determined following the 2012 test campaign, based on the test results along with projected rack performance." The NRC staff believes that the data from the performance of a one-time BADGER campaign is insufficient to ensure that the Boraflex neutron absorber material will continue to perform its intended function. | | Dana and Jerry, By letter dated September 8, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102660403), Entergy Operations, Inc. (Entergy, the licensee), |
| : a. Please provide the future (i.e., after 2012) surveillance approach and BADGER testing for the Boraflex material. The NRC staff has provided the details of one acceptable program for periodic surveillance of Boraflex neutron absorbing materials in the Generic Aging Lessons Learned, Rev 2, program XI.M22, "Boraflex Monitoring." | | submitted a request to amend the Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee proposed a license amendment request (LAR) for an extended power uprate (EPU) to increase the maximum reactor core power operating limit from 3898 megawatts thermal (MWt) to 4408 MWt. By letter dated February 8, 2011 (ADAMS Accession No. Ml110390173), the U.S. Nuclear Regulatory Commission (NRC) staff issued RAIs. By letter dated March 9, 2011 (ADAMS Accession No. ML110680507), Entergy provided a response to these RAIs. Based on the review of this response, the NRC staff has determined that the following additional information is needed for the NRC staff to complete our review of this amendment . This request for additional information (RAI) was discussed with Mr. |
| Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation}} | | Jerry Burford of your staff on April 1, 2011, and it was agreed that a response would be provided within 30 days of receipt of this E-mail. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1445 or via e-mail at Alan.Wang@nrc.gov. |
| | : 1. Based on industry operating experience, degradation of Boraflex panels occur in a much less uniform configuration than is shown in the spent fuel pool map provided in your letter dated March 9, 2011. That map shows that Region II racks (the racks that are degraded beyond a usable condition) are located together in the center of the pool. |
| | Please provide a map of the spent fuel pool which shows the cumulative dose to each panel in the pool. Also, discuss why Region II cells would be located in one specific area of the pool, and other cells outside of that area would not experience similar degradation after housing recently discharged fuel. |
| | : 2. In your response letter dated March 9, 2011, it states, an additional BADGER [Boron-10 Areal Density Gauge for Evaluating Racks] measurement will be performed prior to the end of 2012. The need for additional tests will be determined following the 2012 test campaign, based on the test results along with projected rack performance. The NRC staff believes that the data from the performance of a one-time BADGER campaign is insufficient to ensure that the Boraflex neutron absorber material will continue to perform its intended function. |
| | : a. Please provide the future (i.e., after 2012) surveillance approach and BADGER testing for the Boraflex material. The NRC staff has provided the details of one acceptable program for periodic surveillance of Boraflex neutron absorbing materials in the Generic Aging Lessons Learned, Rev 2, program XI.M22, Boraflex Monitoring. |
| | Alan Wang, Project Manager Plant Licensing Branch IV |
| | |
| | Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation}} |
Letter Sequence RAI |
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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
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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
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Category:E-Mail
MONTHYEARML24137A2702024-05-16016 May 2024 NRR E-mail Capture - Entergy Fleet - Acceptance Review of License Amendment Request to Remove Obsolete License Conditions from Operating Licenses for GGNS, RBS, and WF3 (L-2024-LLA-0062) ML24108A1142024-04-17017 April 2024 June 2024 Emergency Preparedness Program Inspection - Request for Information ML24088A0092024-03-27027 March 2024 NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054) ML23348A1222023-12-14014 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 ML23335A0652023-12-0101 December 2023 NRR E-mail Capture - GGNS - Audit Questions for LARs Associated with TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Init. 4b and 50.69, Risk-Informed Cat. and Treatment of SSCs for Nuclear Pwr Rx (L-2023-LLA-0081/0080) ML23240A3412023-08-28028 August 2023 NRR E-mail Capture - ANO-2, Grand Gulf, and River Bend - Acceptance Review of LAR Revising TSs to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23191A8662023-07-10010 July 2023 NRR E-mail Capture - Grand Gulf - Acceptance Review of LAR Adopting 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSCs for Nuclear Power Reactors ML23191A2802023-07-10010 July 2023 NRR E-mail Capture - Grand Gulf - Acceptance Review for LAR Adopting TSTF-505, Rev. 2, Provide Risk-Informed Completion Times - RITSTF Initiative 4b 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) ML23072A3672023-03-0909 March 2023 NRR E-mail Capture - Entergy Fleet - Acceptance Review of Quality Assurance Program Manual Reduction in Commitment ML23009B6912023-01-0909 January 2023 NRR E-mail Capture - Grand Gulf, Unit 1 and River, Unit 1 - Acceptance of Requested Licensing Action Request to Update ASME Code RR SE with NRC-Approved Revision of BWRVIP Guidelines ML22353A6122022-12-19019 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22206A0152022-07-21021 July 2022 NRR E-mail Capture - Entergy (Grand Gulf, River Bend, and Waterford-3) - Acceptance Review of the RR EN-RR-22-001, Case N-752, Risk-informed Cat & Treatment for Repair/Replacement Activities in Class 2 & 3 Systems ML22173A0372022-06-21021 June 2022 NRR E-mail Capture - Entergy (Grand Gulf and River Bend) - Acceptance Review of the License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22110A1172022-04-19019 April 2022 (GG) 2022 Emergency Preparedness (EP) Program Inspection RFI Sdh 041922 ML22075A3692022-03-0303 March 2022 Email Grand Gulf 2022 PI&R Request for Information ML21312A4792021-11-0505 November 2021 Email: NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development ML21308A5602021-11-0404 November 2021 NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, Grand Gulf, River Bend, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21292A0112021-10-18018 October 2021 NRR E-mail Capture - ANO, 1 and 2, Grand Gulf, River Bend, Waterford, 3 - Acceptance Review of LAR to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21174A0342021-06-22022 June 2021 NRR E-mail Capture - Entergy Fleet (ANO, Ggulf, Rbend, & Waterford) - Acceptance Review for Relief Request to Use a Provision of a Later Edition of the ASME Code, Section XI for Periodic System Pressure Tests Exemptions ML21165A1352021-06-14014 June 2021 NRR E-mail Capture - Grand Gulf - Acceptance Review for Inserice Testing Program Relief Request VRR-GGNS-2021-1, Pressure Isolation Valve Testing Frequency ML21119A2152021-04-28028 April 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27 ML21109A2142021-04-19019 April 2021 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Rev. Est Hours for Review of Relief Request (RR) - ASME Code RR Safety Eval with NRC-Approved Rev of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML21109A2132021-03-23023 March 2021 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Relief Request (RR) Associated with ASME Code RR Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML21068A4092021-03-0909 March 2021 NRR E-mail Capture - Entergy Fleet (GGNS and RBS) -Approval of TSTF-501 LAR, Relocate Sored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21015A3452021-01-14014 January 2021 NRR E-mail Capture - Grand Gulf and River Bend - Revised Estimated Hours for Relief Request Associated with ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20363A1462020-12-22022 December 2020 Request for Information: Grand Gulf EP Exercise Inspection - March 2021 ML20352A1192020-12-10010 December 2020 Email from Thomas Saporito 12-10-20 ML20329A1442020-11-20020 November 2020 Terrapower QAPD Preliminary Questions Email ML20323A4162020-11-18018 November 2020 Response to Choice Letter (EA-20-094) ML20337A2712020-11-0909 November 2020 Email - Grand Gulf Nuclear Station 050-00416, Requested Regulatory Conference ML20289A3542020-10-14014 October 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of TSTF-563 LAR, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program 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) ML20176A4832020-06-22022 June 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of Relief Request Associated with ASME Code RR SE with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) 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 ML20097B8032020-04-0303 April 2020 NRR E-mail Capture - Grand Gulf - Acceptance Review for the Exigent LAR Associated with One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies from 11.5 Years to 13.5 Years ML20093C3072020-04-0101 April 2020 NRR E-mail Capture - (External_Sender) Entergy Fleet - Performance-Based Cyber Security Testing Plan Fee Waiver Response Letter (EPID P-2020-PRF-0000; CAC No. 001648) ML20079D9302020-03-19019 March 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of LAR Associated with Adopting TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control ML20076B6322020-03-16016 March 2020 NRR E-mail Capture - Grand Gulf - Acceptance Review for the LAR Associated with Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies ML20057G1752020-02-24024 February 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of LAR Associated with TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems ML20057G1592020-02-24024 February 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of LAR Associated with TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19242C0122019-08-29029 August 2019 2.206 Petitioner (No Public Meeting Required) ML19339H4362019-08-26026 August 2019 Request for Information IR 05000416/2019-004 ML19115A3512019-04-25025 April 2019 LTR-19-0177 Tom Gurdziel, E-mail a Matter of Fairness Entergy Grand Gulf Seems to Be Running Rather Steadily at 100 Percent ML19151A3312019-04-0303 April 2019 (OEDO-19-00053)10 CFR 2.206 Petition Involving Grand Gulf Nuclear Station ML19095B7622019-04-0303 April 2019 Acceptance Review Results for License Amendment Request to Adopt TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio), for Grand Gulf Nuclear Station, Unit 1 and River Bend Station, Unit 1 (EPID L-22019-LLA-0051) 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 ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML19059A0292019-02-27027 February 2019 NRR E-mail Capture - Acceptance Review Results for License Amendment Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, for Entergy Fleet 2024-05-16
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24088A0092024-03-27027 March 2024 NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054) ML23348A1222023-12-14014 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 ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15286A1082015-10-28028 October 2015 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application ML15261A5652015-09-24024 September 2015 Request for Additional Information Regarding Proposed Revision of Technical Specifications for Containment Leak Rate Testing ML15085A4932015-04-0606 April 2015 Request for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application, Set 52 GNRO-2015/00002, 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 Dated 12/9/20142015-03-27027 March 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 Dated 12/9/2014 ML15036A5642015-02-18018 February 2015 Updated Fluence Methodology License Amendment Request Unacceptable with Opportunity to Supplement GNRO-2014/00079, Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186)2014-11-13013 November 2014 Request for Additional Information Regarding Request for Adoption of TSTF-423, Revision 1, Change in Technical Specification End States (CE-NPSD-1186) GNRO-2014/00076, Response to Request for Additional (RAI) Set 51 Dated September 11, 20142014-11-0606 November 2014 Response to Request for Additional (RAI) Set 51 Dated September 11, 2014 GNRO-2014/00031, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-04-11011 April 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 ML13318A8052014-01-0202 January 2014 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 50 ML13345A1822013-12-19019 December 2013 Supplemental Information Needed for Acceptance of Licensing Action, Request to Revise Technical Specification to Allow Operation in Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Domain ML13353A6572013-12-19019 December 2013 Licensed Operator Positive Fitness-For-Duty Test ML13316B9862013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13263A2252013-11-21021 November 2013 LRA Draft RAI Set 48 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13260A0062013-09-16016 September 2013 Email, Request for Additional Information, Round 3, Request to Revise Technical Specifications and Surveillance Requirements to Support Operation with a 24-Month Fuel Cycle in Accordance with Generic Letter 91-04 ML13238A2342013-09-12012 September 2013 Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 49 ML13227A3942013-08-28028 August 2013 Request for Additional Information for the Review of the Grand Gulf Nuclear Station, License Renewal Application (TAC No. ME7493) - Set 47 ML13226A1902013-08-14014 August 2013 Request for Additional Information Email, Round 2, Request to Revise FOL to Delete 2.C(32), Partial Feedwater Heating, to Allow Plant to Operate with Final Feedwater Temperature Reduction at End of Fuel Cycle ML13207A1242013-07-30030 July 2013 Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) 2024-03-27
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Text
From: Wang, Alan Sent: Monday, April 04, 2011 10:10 AM To: Jerry Burford; 'Dana Millar' Cc: Lent, Susan; Burkhardt, Janet; Obodoako, Aloysius
Subject:
GG EPU SG and Chemical Engineering Branch Request for Additional Information (ME4679)
Dana and Jerry, By letter dated September 8, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102660403), Entergy Operations, Inc. (Entergy, the licensee),
submitted a request to amend the Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee proposed a license amendment request (LAR) for an extended power uprate (EPU) to increase the maximum reactor core power operating limit from 3898 megawatts thermal (MWt) to 4408 MWt. By letter dated February 8, 2011 (ADAMS Accession No. Ml110390173), the U.S. Nuclear Regulatory Commission (NRC) staff issued RAIs. By letter dated March 9, 2011 (ADAMS Accession No. ML110680507), Entergy provided a response to these RAIs. Based on the review of this response, the NRC staff has determined that the following additional information is needed for the NRC staff to complete our review of this amendment . This request for additional information (RAI) was discussed with Mr.
Jerry Burford of your staff on April 1, 2011, and it was agreed that a response would be provided within 30 days of receipt of this E-mail. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1445 or via e-mail at Alan.Wang@nrc.gov.
- 1. Based on industry operating experience, degradation of Boraflex panels occur in a much less uniform configuration than is shown in the spent fuel pool map provided in your letter dated March 9, 2011. That map shows that Region II racks (the racks that are degraded beyond a usable condition) are located together in the center of the pool.
Please provide a map of the spent fuel pool which shows the cumulative dose to each panel in the pool. Also, discuss why Region II cells would be located in one specific area of the pool, and other cells outside of that area would not experience similar degradation after housing recently discharged fuel.
- 2. In your response letter dated March 9, 2011, it states, an additional BADGER [Boron-10 Areal Density Gauge for Evaluating Racks] measurement will be performed prior to the end of 2012. The need for additional tests will be determined following the 2012 test campaign, based on the test results along with projected rack performance. The NRC staff believes that the data from the performance of a one-time BADGER campaign is insufficient to ensure that the Boraflex neutron absorber material will continue to perform its intended function.
- a. Please provide the future (i.e., after 2012) surveillance approach and BADGER testing for the Boraflex material. The NRC staff has provided the details of one acceptable program for periodic surveillance of Boraflex neutron absorbing materials in the Generic Aging Lessons Learned, Rev 2, program XI.M22, Boraflex Monitoring.
Alan Wang, Project Manager Plant Licensing Branch IV
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation