|
---|
Category:Letter
MONTHYEARML24012A1422024-01-31031 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 ML23340A2222023-12-13013 December 2023 Project Manager Assignment 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 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 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-2023/00014, 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 ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
[Table view] |
Text
- -=-Entergy Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150
- Eric L. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 GNR0-2017/00079 December 7, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Supplement to License Amendment Request for One Cycle Extension Of Appendix J Type A Integrated Leakage Rate Test and Drywall Bypass Test Interval Grand Gulf Nuclear Station, Unit No. 1 ...,
Docket No. 50-416 License No. NPF-29
REFERENCE:
GNR0-2016/00062, License Amendment Request for One Cycle Extension Of Appendix J Type A Integrated Leakage Rate Test and Drywall Bypass Test Interval, dated December 29, 2016
Dear Sir or Madam:
This letter provides a supplemental change to the previously provided Technical Specification Markup, pages 3.6.53 and 5.0-16. Please replace the previously submitted pages with those provided in the attachment.
This letter contains no Regulatory Commitments.
If you have any questions or require add.itional information, please contact Robert Peters at 601-437-2318 or Douglas Neve, Manager Regulatory Assurance at (601)-437-2103.
Sincerely, Eric A. Larson Site Vice President EAL/saw
Attachment:
Revised (Clean) Technical Specification Pages
G NR0-2017/00079 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S.
Nuclear Regulatory I
Commission ATTN: Mr. Kriss Kennedy Region Administrator, Region IV 1600 East Lamar Blvd, Suite 400 Arlington, TX 76011-4005 Mr. John P. Boska, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2 Washington, DC 20555 Thomas J. Wengert U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to GNR02017-00079 Revised (CLEAN) Technical Specification Pages
'----/
Drywell 3.6.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1.1 Verify bypass leakage is less than or equal to the bypass 24 months following 2 leakage limit. consecutive tests with bypass leakage greater However, during the first unit startup following drywell than the bypass bypass leak rate testing performed in accordance with this SR, leakage limit until 2 the acceptance criterion is leakage 5 10% of the bypass consecutive tests are leakage limit. less than or equal to the bypass leakage limit 48 months following a test with bypass leakage greater than the bypass leakage limit
NOTE-----
SR 3.0.2 is not applicable for extensions >. 12 months.
120 months, except that the next drywell bypass leak rate test performed after the October 19, 2008 test shall be performed no later than the plant restart after the End of Cycle 22 Refueling Outage.
(continued)
GRAND GULF 3.6-53 Amendment No.~' _ __
Programs and Manuals
- 5. 5.
5.5 Programs and Manuals ( continued)
- 5. 5 .11 Technical Specificatio~s (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b. Licensees may make changes to Bases without prior NRC apptoval provided the changes do not require either,of the following:
- 1. A change in the TS incorporated in the license; or
- 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
- d. Proposed- changes that do not meet the criteria of either Specification 5 .. 5.11.b.l or Specification 5.5.11.b.2 above shall be ~eyie0ed and approved by the NRC prior to implementation.,: Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consi~fent with 10 CFR 50.71(e).
r 5.5.12 10 CFR 5 0, Appendix -.~J, Testing Program This program establishes the leakage rate testing program of the containment as 'required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be implemented in accordance with the Safety Evaluation issued by the Office of Nuclear Reactor Regulation dated April 26, 1995 (GNRI-95/00087) as modified by the Safety Evaluation issued fqr Amendment No. 135 to the Operating License, except that the next*. Type A test performed after the October 19, 2008 Type A test shall be performed no later than the plant restart after the Er:id of Cycle 22 Refueling Outage. For Type B and Type C local le~kage rate testing, this program shall be in accordanqe with the *guidelines contained in NEI 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50r .;.,,ppendix J," dated July 2012. Consistent with standard scheduling practices for Technical Specifications required surveillances, intervals for the recommended surveillance frequency for Type A testing may be extended by up to 25 percent of the test interval, not to exceed 15 months. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 12.1 psig.
GRAND GULF _5.0-16 Amendment No. 9-§-, G-9-,