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MONTHYEARGNRO-2011/00017, Request for Additional Information Regarding Extended Power Uprate2011-03-0909 March 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request GNRO-2011/00034, Request for Additional Information Regarding Extended Power Uprate2011-05-0303 May 2011 Request for Additional Information Regarding Extended Power Uprate Project stage: Request GNRO-2011/00076, License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality2011-09-0909 September 2011 License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality Project stage: Request ML1127700622011-10-0303 October 2011 Acceptance Review Email, License Amendment Request, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition Project stage: Acceptance Review ML12271A3022012-07-25025 July 2012 E-mail Grand Gulf Station, Unit 1 - Redacted, Request for Additional Information, Amendment Request to Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Co Project stage: RAI GNRO-2012/00120, Responses to NRC Requests for Additional Information GGNS Criticality Safety Analysis License Amendment Request2012-10-0101 October 2012 Responses to NRC Requests for Additional Information GGNS Criticality Safety Analysis License Amendment Request Project stage: Response to RAI ML12312A2382013-01-0202 January 2013 Request for Withholding Information from Public Disclosure, 9/28/12 Affidavit Executed by L. Trosman, GNF-A, for Attachment 1 to GNRO-2012/00120 Dated 10/1/12 Project stage: Withholding Request Acceptance ML13071A1542013-04-0101 April 2013 Redacted Version, Request for Additional Information, Round 2, License Amendment Request, Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition Project stage: RAI ML13091A1952013-04-0101 April 2013 Proposed Audit Plan for 4/3/13-4/4/13 Audit of the Criticality Safety Analysis; Request to Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition Project stage: Other ML13091A1922013-04-0101 April 2013 Email, Proposed Audit Plan for 4/3/13-4/4/13 Audit of the Criticality Safety Analysis; Request to Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition Project stage: Other ML13121A3332013-05-17017 May 2013 Audit Report for the April 3-4, 2013 Audit of the Calculations Related to the Request to Revise the Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition Project stage: Other GNRO-2013/00050, Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information2013-07-0202 July 2013 Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information Project stage: Response to RAI GNRO-2013/00066, Criticality Safety Analysis License Amendment Request - Supplemental Information2013-09-0505 September 2013 Criticality Safety Analysis License Amendment Request - Supplemental Information Project stage: Supplement GNRO-2013/00073, Criticality Safety Analysis License Amendment Request - Supplemental Information2013-09-16016 September 2013 Criticality Safety Analysis License Amendment Request - Supplemental Information Project stage: Supplement ML13261A2642013-09-25025 September 2013 Redacted Version, Issuance of Amendment No. 195, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition Project stage: Approval ML13197A1922013-11-25025 November 2013 Request for Withholding Information from Public Disclosure, 6/26/13 Affidavit Executed by L. Trosman, GNF-A, for Attachment 1 to GNRO-2013/00050 Dated 7/2/2013 Project stage: Withholding Request Acceptance 2013-01-02
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Category:Letter type:GNRO
MONTHYEARGNRO-2013/00079, 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013)2023-10-11011 October 2023 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013) GNRO-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 2023-06-06
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Text
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368-5516 GNRO-2013/00066 September 5, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Criticality Safety Analysis License Amendment Request -
Supplemental Information Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCE:
Entergy Operations, Inc. letter to the NRC (GNRO-2011/00076), License Amendment Request - Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, September 9, 2011 (ADAMS Accession No. ML1125321287)
Dear Sir or Madam:
In the referenced letter, Entergy Operations, Inc. (Entergy) submitted to the NRC a license amendment request (LAR), which proposes to: 1) revise the criticality safety analysis (CSA) for the spent fuel and new fuel storage racks; 2) impose additional requirements for the spent fuel and new fuel storage racks in Technical Specification (TS) 4.3.1, Criticality; and 3) delete the spent fuel pool loading criteria Operating License (OL) condition.
In a recent telephone call, the NRC discussed with Entergy the CSA LAR. As a result of that call, Entergy proposes the following limitation be included in the issued license amendment:
The licensee will maintain a minimum distance of 12 inches between any fuel stored in the Control Blade/Defective Fuel Storage Rack (Module H1) and in the surrounding high density spent fuel pool storage racks.
In addition to the above, Entergy is submitting an administrative change to the CSA LAR. In the referenced letter, Entergy provided in Attachment 2 a markup of the OL page that was current at the time of submittal. However, since that time, the NRC has issued TS amendments, which have revised that page. Therefore, Entergy is providing in Attachment 1 to this letter a markup of the current OL pages associated with the CSA LAR. Please replace Page 1 of 4 in Attachment 2 to the referenced letter with the marked-up pages provided in .
This letter contains one new commitment, which is identified in Attachment 2.
GNRO-2013/00066 Page 2 of 2 If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.
I declare under penalty of perjury that the foregoing is true and correct; executed on September 5, 2013.
Sincerely, BSF/ghd Attachments: 1. Marked-Up Operating License Pages
- 2. List of Regulatory Commitments cc: Mr. Steven A. Reynolds State Health Officer Regional Administrator (acting), Region IV Mississippi Department of Health U. S. Nuclear Regulatory Commission P. O. Box 1700 1600 East Lamar Blvd. Jackson, MS 39215-1700 Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission NRC Senior Resident Inspector ATTN: Mr. A. B. Wang, NRR/DORL (w/2) Grand Gulf Nuclear Station ATTN: ADDRESSEE ONLY Port Gibson, MS 39150 ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378
ATTACHMENT 1 GRAND GULF NUCLEAR STATION GNRO-2013/00066 MARKED-UP OPERATING LICENSE PAGES
to GNRO-2013/00066 Page 2 of 2 Regiell II 4X4 S LoLage eon£ig uzaLio11 (46) This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer) for power ascension from the CLTP (3898 MWt) to the EPU level of 4408 MWt (or 113 percent of CLTP or 11S percent of OLTP) .
(a) The following requirements are placed on operation of the facility before and during the power ascension to 3898 MWt:
- 1. GGNS shall provide a Power Ascens i on Test (PAT) Plan for the Steam Dryer testing. This plan shall include:
- Criteria for comparison and evaluation of projected strain and acceleration with on-dryer instrument data.
- Acceptance limits developed for each on-dryer strain gauge and accelerometer.
- Tables of predicted dryer stresses at CLTP, strain amplitudes and PSDs at strain gauge locations, acceleration amplitudes and PSDs at accelerometer locations, and maximum stresses and locations.
The PAT plan shall provide correlations between measured accelerations and strains and the corresponding maximum stresses. The PAT plan shall be submitted to the NRC Project Manager no later than 10 days before start-up.
- 2. GGNS shall monitor the main steam line (MSL) strain gages and on-dryer instrumentation at a minimum of three power levels up to 3898 MWt. Based on a comparison of projected and measured strains and accelerations, GGNS will assess whether the dryer acoustic and structural models have adequately captured the response significant to peak stress projections.
16b Amendment No. ~
ATTACHMENT 2 GRAND GULF NUCLEAR STATION GNRO-2013/00066 LIST OF REGULATORY COMMITMENTS to GNRO-2013/00066 Page 1 of 1 LIST OF REGULATORY COMMITMENTS This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRCs information and are not regulatory commitments.
TYPE SCHEDULED (Check one)
COMMITMENT COMPLETION DATE ONE-TIME CONTINUING (If Required)
ACTION COMPLIANCE Entergy will maintain a minimum distance of 12 Upon implementation inches between any fuel stored in the Control of the approved Blade/Defective Fuel Storage Rack (Module H1) license amendment and in the surrounding high density spent fuel pool storage racks.