Letter Sequence Supplement |
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TAC:MF2798, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARGNRO-2013/00012, Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request2013-09-25025 September 2013 Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request Project stage: Request 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 Project stage: Acceptance Review ML13364A2862013-12-30030 December 2013 Maximum Extended Load Mine Limit Analysis Plus (Mella+) License Amendment Request-Responses to Requests for Supplemental Information Project stage: Supplement ML14023A5802014-01-23023 January 2014 NRR E-mail Capture - Acceptance Review of Grand Guld Nuclear Station License Amendment Request Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Acceptance Review ML14037A1492014-02-0606 February 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI GNRO-2014/00024, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/20142014-03-10010 March 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/2014 Project stage: Response to RAI ML14080A2722014-03-18018 March 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI ML14119A0092014-04-28028 April 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Audit Plan Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: Other ML14101A0432014-05-0808 May 2014 Request for Withholding from Public Disclosure - 12/19/2013 Affidavit Executed by L. Dolan, GE-Hitachi Nuclear Energy Americas LLC Related to Responses to Request for Supplemental Information Project stage: Other ML14101A0872014-05-0808 May 2014 Request for Withholding from Public Disclosure - 9/10/2013 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Nedc - 33612P, Revision 0 Project stage: Other ML14140A3012014-05-19019 May 2014 NRR E-mail Capture - Grand Gulf Nuclear Station, Unit 1, Request for Additional Information Regarding Maximum Load Line Limit Analysis Plus Project stage: RAI ML14211A1362014-07-30030 July 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI GNRO-2014/00051, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 7/2/20142014-08-14014 August 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 7/2/2014 Project stage: Response to RAI GNRO-2014/00045, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/20142014-08-26026 August 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014 Project stage: Response to RAI GNRO-2014/00064, Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-09-0404 September 2014 Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 Project stage: Response to RAI GNRO-2014/00052, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 7/29/20142014-09-10010 September 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 7/29/2014 Project stage: Request ML14265A4222014-10-23023 October 2014 Request for Withholding from Public Disclosure - 6/25/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 3 to GNRO-2014/00045 Dated 8/26/14 Project stage: Other ML14265A3842014-10-23023 October 2014 Request for Withholding from Public Disclosure - 6/19/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00045 Dated 8/26/14 Project stage: Other ML14265A3702014-10-23023 October 2014 Request for Withholding from Public Disclosure - 7/1/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00064 Dated 9/4/14 Project stage: Other ML14111A0582014-10-23023 October 2014 Request for Withholding from Public Disclosure - 3/4/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Enclosure to GNRO-2014/00024 Responses to Request for Additional Information Project stage: RAI ML14262A3972014-11-12012 November 2014 Request for Withholding from Public Disclosure - 7/22/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Enclosure 1 to GNRO-2014/00051 Dated 8/14/14 Project stage: Other ML14262A3722014-11-12012 November 2014 Request for Withholding from Public Disclosure - 8/20/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00052 Dated 9/10/14 Project stage: Other ML14260A1302014-11-25025 November 2014 April 23-25, 2014, Audit Report Regarding Maximum Extended Load Line Limit Analysis Plus Amendment Including Minimum Stable Film Boiling Temperature and Quench Model Project stage: Other GNRO-2014/00083, Traversing Incore Probe (TIP) Comparisons TIP Comparisons for Current Operating Conditions in Support of the Grand Gulf Nuclear Station (GGNS) Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request2014-12-15015 December 2014 Traversing Incore Probe (TIP) Comparisons TIP Comparisons for Current Operating Conditions in Support of the Grand Gulf Nuclear Station (GGNS) Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request Project stage: Request GNRO-2014/00088, Response to Item 20 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/20142015-01-20020 January 2015 Response to Item 20 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014 Project stage: Request GNRO-2015/00003, Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus, Amendment Request, Dated 5/19/20142015-02-0909 February 2015 Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus, Amendment Request, Dated 5/19/2014 Project stage: Request GNRO-2015/00011, Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method2015-02-18018 February 2015 Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method Project stage: Supplement ML15050A0772015-02-19019 February 2015 Request to Convert Regulatory Commitments for Time Critical Operator Actions Listed in Letter GNRO-2015/00003, Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit. Project stage: Request ML15040A1262015-03-19019 March 2015 Request for Withholding Information from Public Disclosure - 10/30/14 Affidavit Executed by James F. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Related to Attachment 1 to GNRO-2014/00088 Dated 1/20/15 (TAC MF27 Project stage: Withholding Request Acceptance ML15085A2272015-04-14014 April 2015 October 15, 2014, Onsite Audit Report Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Other ML15040A0932015-06-24024 June 2015 Request for Withholding Information from Public Disclosure-10/12/14 Affidavit Executed by James F. Harrison, GE-Hitachi Nuclear Energy Amenricas LLC Related to Attachment 1 to GNRO-2014/00083 Dated 12/15/2014 (MF2798) Project stage: Withholding Request Acceptance GNRO-2015/00059, Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/20132015-08-14014 August 2015 Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013 Project stage: Request ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request Project stage: Approval 2014-05-08
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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
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<Q;6' Entergy Entergy Operations, Inc.
P.o. Box 756 Port Gibson, MS 39150 Kevin Mulligan Site Vice President
. PROPRIETARY .Inf ormation Att ac hment s 2 an d 3 contain . Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2015/00011 February 18, 2015 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Supplement to License Amendment Request Application to Revise Grand Gulf Nuclear Station Unit 1'~ Current Fluence Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. U.S. Nuclear Regulatory Commission Letter, "Requests for Additional Information for the Review of the Grand Gulf Nuclear Station, License ReneWal Application," dated August 28, 2013 (Accession No. ML13227A394)
- 2. Grand Gulf Nuclear Station Letter, "Response to Requests for Additional Information (RAI) set 47," dated September 23, 2013 (Accession No. ML13266A368)
- 3. U.S. Nuclear Regulatory Commission Regulatory Guide, Regulatory Guide 1.190, dated March 2001 (Accession No. ML010890301)
- 4. Grand Gulf Nuclear Station Letter GNRO-2014/00080, "Application to Revise Grand Gulf Nuclear Station Unit 1's Current Fluence Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method," dated November 21,2014.
Dear Sir or Madam:
In accordance with the provisions of Section 50.90 of Title 10 Code of Federal Regulations (10 CFR), Entergy Operations, Inc. (Entergy) is submitting a Supplement to an amendment request to revise our existing license basis for Grand Gulf Nuclear Station, Unit 1.
The supplement is for the proposed amendment to revise Grand Gulf Nuclear Station, Unit 1's license basis to adopt a single fluence method. This supplement is needed to address the Staff's request for additional information regarding Benchmarking analysis of the proposed single fluence method.
When Attachments 2 and 3 are removed from this letter, the entire document is NON-PROPRIETARY
GNRO-2015/00011 Page 2 of 3 provides responses to the Request for Additional Information. Attachment 2 provides the revised topical report from MP Machinery and Testing, LLC. Attachment 3 provides the revised report documenting the application of the single fluence method at GGNS.
This letter contains no new commitments. If you have any questions or require additional information, please contact Mr. James Nadeau at (601) 437-2103.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 18, 2015.
Sincerely,
~-,----
KJM/ras :2 Attachments:
- 1. Supplement to proposed Single Fluence Method LAR
- 2. Revised Topical Report from MP Machinery and Testing, LLC MPM-614993 Revision 3, "Benchmarking of MPM Methods for Nuclear Plant Neutron Transport Calculations," January, 2015
- 3. Revised Single Fluence Method Applied to GGNS MPM-814779 Revision 2, "Neutron Transport Analysis for Grand Gulf Nuclear Station,"
January, 2015 cc: with Attachment and Enclosures u.S. Nuclear Regulatory Commission ATIN: Mr. John Daily, NRR/DLR Mail Stop OWFN/11 F1 11555 Rockville Pike Rockville, MD 20852-2378
GNRO-2015/00011 Page 3 of 3 cc: without Attachment and Enclosures U.S. Nuclear Regulatory Commission ATIN: Mr. Mark Dapas, (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATIN: Mr. Alan Wang, NRR/DORL (w/2)
Mail Stop OWFN 8 B1 Washington, DC 20555-0001 Dr. Mary Currier, M.D., M.P.H State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700
Attachment 1 GNRO-2015/00011 RAI Response Supplement to proposed Single Fluence Method LAR to GNRO-2015/00011 Page 1 of 4 1.0 Methods Qualification Outside of the Beltline Region The statement below from Document GNRO-2014/000BO, Attachment 3, "Single Fluence Method Applied to GGNS, MPM-B14779 Revision 1, 'Neutron Transport Analysis for Grand Gulf Nuclear Station,' November 2014," is insufficient to qualify fluence calculations outside of the beltline region. It is stated explicitly that "there are no dosimetry data available at present from regions above and below the active core region to enable checking of 3D results in those regions of the plant." It is then implied that benchmarking the 3D method against the 2D synthesis method would be sufficient to qualify the 3D method for fluence calculations outside of the beltline region.
There are no dosimetry data available at present from regions above and below the active core region to enable checking of 3D results in those regions of the plant. Therefore, once TORT is benchmarked against the results of standard 20 synthesis, these 3D methods can be used routinely for flux' calculations in the beltline, and outside of the beltline region.
RAI 1a. To qualify the 3D fluence method for fluence calculations outside of the beltline region, some type of benchmarking of the 3D fluence method is necessary specific to the various regions-of-interest outside the beltline.
Response to RAI 1a : Installing dosimetry capsules and/or taking scrapings in specified areas outside of the beltline region would provide dosimetry data for a future benchmark analysis outside of the beltline region. The uncertainty in the fluence calculations at locations above the top of the core is dominated by uncertainty in the water density. Taking scrapings and/or inserting dosimetry in these locations (during future refueling outages) would not only provide benchmarking data, but it would also provide the data needed to check the output from thermal-hydraulics codes that can be used in future improvements of the upper region water density modeling.
to GNRO-2015/00011 Page 2 of4 Furthermore, on Page 6 of Document GNRO-2014/00080, Attachment 1, "Analysis of Proposed Single Fluence Methodology," Regulatory Position 1.4.3 of Regulatory Guide (RG) 1.190, "Calculational-and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," is quoted as follows:
[. ..] For other applications [other than RTND T determination], the accuracy should be determined using the approach described in Regulatory Position 1.4, and an uncertainty allowance should be included in the f1uence estimate as appropriate in the specific application.
Page 7 of Document GNRO-2014/00080, Attachment 1, includes the following response from licensee:
An extensive evaluation of all contributors to the uncertainty in the calculated f1uence was made for the BWR plant calculations performed to date. This evaluation indicated that the uncertainty in calculated f1uences in the reactor beltline region is below 20% as specified in the guide. In addition, the comparisons with measurements indicate agreement well within the 20% limit.
The agreement of calculations with measurements to within +/-20% uncertainty indicates that the MPM calculations can be applied for f1uence determination with no bias. This meets the requirement of RP 1.4.3.
RAI 1b. The NRC staff did not locate specific information evaluating the uncertainty of the proposed methods for locations outside the reactor vessel beltline. Information describing uncertainty allowances and application for fluence estimates outside of the reactor vessel beltline is required, or the NRC staff review of the method will be limited to the vessel beltline.
Further application of the method would require additional justification.
Response to RAI 1b:
Updated Final Reports under S&L PO 32356 with the latest fluence uncertainty results are attached. Both reports have been updated to include the latest fluence uncertainty analyses for nozzles N6 and N12. Uncertainties have been evaluated for shroud welds, top guide welds, and for nozzles located above the top of the active fuel. For the upper shroud and top guide welds, and for the N6 nozzle, the uncertainties are greater than 30%. Since the nozzles must be incorporated into the PT curves, an appropriate margin must be added to account for the higher uncertainty in accordance with the requirements of Regulatory Guide 1.190.
The N12 nozzle elevation is close to that of the top of the active fuel, and the fluence uncertainty is below 20°1<> as expected. Therefore, the calculated fluence at these nozzles can be used directly in the PT curves. However, the N6 nozzle uncertainty is dominated by uncertainty in the steam density, and the fluence uncertainty is 39°1<>. Regulatory Guide 1.190 states that if the analytical uncertainty at the 1 sigma level is greater than 30%, the methodology of the regulatory guide is not applicable and the plant application will be reviewed on an individual basis. Based on guidance provided in Equation 6 of Regulatory Guide 1.190, it would seem reasonable to multiply the calculated fluences by 1 plus the 1 sigma uncertainty for the cases where the uncertainty is over 30%. Accordingly, the fluences for the N6 nozzles have been increased by 39 % to provide sufficient margin in the PT curve calculations.
to GNRO-2015/00011 Page 3 of 4 2.0 Applicability of 20 Method Validation to 3D Method Method qualification was done primarily for the 2D synthesis method; however, the 3D method is used for calculating fluence results. The licensee uses the 3D code results with aspects of the 2D synthesis bias and uncertainty analysis. Applying the validation of one method to another is inappropriate as there may be certain deficiencies that are masked in the method that is not formally qualified.
Seven 2D synthesis calculations were compared to corresponding measurements for the PCA calculational benchmark, 25 2D synthesis calculations were compared to corresponding measurements for the BWR calculational benchmark, eight 2D synthesis calculations were compared to corresponding measurements as part of dosimetry benchmarking, and only one 3D calculation was compared to a corresponding measurement as part of dosimetry .
benchmarking. In summary, 40 calculations support the validation of the 2D synthesis method and one calculation supports the validation of the 3D method; however, the 3D method is relied upon to support all fluence projections as discussed in Section 7, "Summary and Conclusions,"
of Document GNRO-2014/00080, Attachment 3.
RAI 2. To qualify the 3D fluence method for fluence calculations inside the beltline region, completion of an independent benchmarking of the 3D method is required.
Response to RAI 2: Neutron Transport Analysis Update Project - Scope Change PCA Benchmark Analysis in Support of GGNS LAR. GGNS will provide the PC~ Benchmark Analysis Report to the NRC Project Manager by March 31, 2015.
This work involves creation of a 3D TORT model and subsequent running of the model to analyze the PCA benchmark. The post-processing will include an analysis of all 7 PCA dosimetry locations. Each PCA location has as many as 6 individual dosimeter results. The calculated-to-measured (C/M) benchmarks will be reported for all PCA measurements available.
Further, comparisons will also be made with the existing 2D synthesis results, thus giving calculated-to-calculated (C/C) results at all locations. The results will be given in a new report subsection in the MPM benchmark report.
to GNRO-2015/00011 Page 4 of 4 3.0 MELLLA+ Operating Conditions Document GNRO-2014/00080, Attachment 1, includes the following statement:
GGNS has calculated the fluence for every cycle up to the present. This gives the most accurate value of the present fluence. Extrapolations to future times are made using best estimate values of future fuel designs in a cycle 21 best estimate projection cycle. As changes in fuel core loadings are made, updated extrapolations will be made. Further, the flux values from the cycle 21 transport calculation were multiplied with a factor of 1.1 applied for projection to exposures after cycle 21. This 10% conservatism was applied by Entergy to ensure that fluence estimates remain conservative. [. ..]
RAI 3: NRC staff is presently concluding its review of Entergy's request to implement the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain. The NRC staff requires confirmation that the flux evaluation for Cycle 21 includes the water density and neutron spectral conditions reflective of a MELLLA+ core design.
Response to RAI 3: It has been confirmed that the flux evaluation for Cycle 21 includes the water density and neutron spectral conditions reflective of a MELLLA+ core design.