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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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MONTHYEARML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, “Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b” IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors” ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 GNRO-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) ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) 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 2024-07-09
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GNRO-201 3/00 066 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
-20 11/00076), 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. I n 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 amendment s, which have r e v i s e d that p a g e. Therefore, Entergy is providing in to this letter a markup of the current OL page s associated with the CSA LAR. Please replace Page 1 of 4 in Attachment 2 to the referenced letter with the marked
-up page s provided in . This letter contains one new commitment, which is identified in Attachment 2
. Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368
-5516 GNRO-2013/000 66 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 , 201 3. Sincerely, BSF/ghd Attachment s: 1. Marked-Up Operating License Page s
- 2. List of Regulatory Commitments cc: Mr. Steven A. Reynolds Regional Administrator (acting), Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Blvd.
Arlington, TX 76011
-45 11 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215
-1700 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2) ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852
-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
ATTACHMENT 1 GRAND GULF NUCLEAR STATION GNRO-2013/00066 MARKED-UP OPERATING LICENSE PAGE S
Attachment 1 to GNRO-2013/00066 Page 2 of 2 Re g iell II 4X4 S LoLa g e eon£i g 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 NRC's information and are not regulatory commitments.
COMMITMENT TYPE (Check one)
SCHEDULED COMPLETION DATE (If Required)
ONE-TIME ACTION CONTINUING COMPLIANCE Entergy 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.
Upon implementation of the approved license amendment