RBG-47870, License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List: Difference between revisions
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~. | ~. Entergx RBG-47870 June 6, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Entergy Operations. Inc. | ||
Entergy Operations. Inc. | R,Vflr Bend Station 5485 US Highway 61 N St Francisville. LA 70775 f el 225*381-4374 William F. Maguire Site Vice President River Bend Station | ||
R,Vflr Bend Station 5485 US Highway 61 N St Francisville. LA 70775 f el 225*381-4374 William F. Maguire Site Vice President River Bend Station | |||
==SUBJECT:== | ==SUBJECT:== | ||
License Renewal Application , Revised Updated Safety Analysis Report Supplement, Appendix A, Section A.4, License Renewal Commitment List River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47 | License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix A, Section A.4, License Renewal Commitment List River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47 | ||
==References:== | ==References:== | ||
: 1) Entergy Letter: License Renewal Application (RBG-47735 dated May 25, 2017) | : 1) Entergy Letter: License Renewal Application (RBG-47735 dated May 25, 2017) | ||
==Dear Sir or Madam :== | ==Dear Sir or Madam:== | ||
In Reference 1, Entergy Operations, Inc (Entergy) submitted an application for renewal of the operating license for River Bend Station (RBS) for an additional 20 years beyond the current expiration date. Included in the application for renewal of the operating license was the Updated Safety Analysis Report Supplement, Appendix A, Section A.4, License Renewal Commitment List. During the license renewal application review, Section A.4, License Renewal Commitment List was updated to include new and revised information resulting from the review. provides the complete updated license renewal commitment list. | |||
In Reference 1, Entergy Operations, Inc (Entergy) submitted an application for renewal of the operating license for River Bend Station (RBS) for an additional 20 years beyond the current expiration date. Included in the application for renewal of the operating license was the Updated Safety Analysis Report Supplement, Appendix A, Section A.4, License Renewal Commitment List. During the license renewal application review, Section A.4 , License Renewal Commitment List was updated to include new and revised information resulting from the review. | If you require additional information, please contact Mr. Tim Schenk at (225)-381-4177 or tschenk@entergy.com. | ||
If you require additional information , please contact Mr. Tim Schenk at (225)-381-4177 or tschenk@entergy.com. | |||
RBG-47870 Page 2 of 2 In accordance with 10 CFR 50.91 (b)(1), Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the designated State Official. | RBG-47870 Page 2 of 2 In accordance with 10 CFR 50.91 (b)(1), Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the designated State Official. | ||
I declare under penalty of perjury that the foregoing is true and correct. Executed on June 6,2018. | I declare under penalty of perjury that the foregoing is true and correct. Executed on June 6,2018. | ||
Sincerely, WFM/RMC/dp : Updated Safety Analysis Report Supplement, Appendix A, Section A.4 - River Bend Station cc: | Sincerely, WFM/RMC/dp : Updated Safety Analysis Report Supplement, Appendix A, Section A.4 - River Bend Station cc: | ||
U. S. Nuclear Regulatory Commission Attn : Emmanuel Sayoc 11555 Rockville Pike Rockville, MD 20852 cc : | (with Enclosure) | ||
U. S. Nuclear Regulatory Commission Attn: Emmanuel Sayoc 11555 Rockville Pike Rockville, MD 20852 cc: | |||
(w/o Enclosure) | |||
U. S. Nuclear Regulatory Commission Attn: Lisa Regner 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd. | U. S. Nuclear Regulatory Commission Attn: Lisa Regner 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd. | ||
Arlington, TX 76011 -4511 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave . | Arlington, TX 76011 -4511 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave. | ||
Austin, TX 78711-3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge , LA 70821-4312 RBF1-18-0107 | Austin, TX 78711-3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 RBF1-18-0107 | ||
RBG-47870 | RBG-47870 License Renewal Application Updated Safety Analysis Report Supplement, Appendix A, Section A.4 License Renewal Commitment List | ||
RBG-47870 Page 1 of 6 A.4 LICENSE RENEWAL COMMITMENT LIST | RBG-47870 Page 1 of 6 A.4 LICENSE RENEWAL COMMITMENT LIST No. | ||
Program or Activity Commitment 1 | |||
Aboveground Metallic Implement the Aboveground Metallic Tanks Program as Tanks described in LRA Section A.1.1. | |||
2 Bolting Integrity Enhance the Bolting Integrity Program as described in LRA Section A.1.2. | |||
3 Neutron Absorbing Implement the Neutron Absorbing Material Monitoring Material Monitoring Program as described in LRA Section A.1.3. | |||
4 Buried and Implement the Buried and Underground Piping and Underground Piping Tanks Inspection Program as described in LRA Section and Tanks Inspection A.1.4. | |||
5 BWR Vessel Internals Enhance the BWR Vessel Internals Program as described in LRA Section A.1.1 O. | |||
6 Coating Integrity Implement the Coating Integrity Program as described in LRA Section A.1.11. | |||
7 Compressed Air Enhance the Compressed Air Monitoring Program as Monitoring described in LRA Section A.1.12. | |||
Implementation Source Schedule (Letter Number) | |||
Prior to February 28, RBG-47735 2025. | |||
RBG-47818 Prior to February 28, RBG-47735 2025. | |||
RBG-47828 Prior to February 28, RBG-47735 2025, or the end of the RBG-47830 last refueling outage RBG-47848 prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47813 last refueling outage RBG-47850 prior to August 29, RBG-47860 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025. Initial RBG-47818 inspections will be performed prior to August 29, 2030. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47805 last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025. | |||
RBG-47870 Page 2 of 6 | RBG-47870 Page 2 of 6 No. | ||
8 9 | |||
10 11 11a Program or Activity Containment Inservice Inspection - IWE Diesel Fuel Monitoring External Surfaces Monitoring Fatigue Monitoring Fatigue Monitoring Commitment Enhance the CII-IWE Program as described in LRA Section A.1.13. | |||
Enhance the Diesel Fuel Monitoring Program as described in LRA Section A.1.15. | |||
Enhance the External Surfaces Monitoring Program as described in LRA Section A.1.1 7. | |||
Enhance the Fatigue Monitoring Program as described in LRA Section A.1.18. | |||
Revise the Fatigue Monitoring Program description (Section 7B) of RBS-EP-15-00006, "Aging Management Program Evaluation Report Class 1 Mechanical," to state acceptable corrective actions include repair of the component, replacement of the component, and a more rigorous analysis of the component to demonstrate that the design code limit will not be exceeded during the period of extended operation. | |||
Implementation Source Schedule (Letter Number) | |||
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47812 last refueling outage RBG-47849 prior to August 29, RBG-47860 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later. | |||
Enhancement to RBG-47735 develop a set of fatigue usage calculations: | |||
prior to August 29, 2023. | prior to August 29, 2023. | ||
Remaining enhancements: prior to February 28, 2025. | Remaining enhancements: prior to February 28, 2025. | ||
Prior to February 28, RBG-47846 2025. | |||
RBG-47870 Page 3 of 6 | RBG-47870 Page 3 of 6 No. | ||
12 12a 13 14 15 16 17 18 Program or Activity Fire Water System Fire Water System Flow-Accelerated Corrosion Inservice Inspection - | |||
IWF Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Internal Surfaces in Miscellaneous Piping and Ducting Components Masonry Wall Non-EO Electrical Cable Connections Commitment Enhance the Fire Water System Program as described in LRA Section A.1.20. | |||
Remove existing coating, perform bottom thickness measurements and recoat the fire water storage tanks. | |||
Enhance the Flow-Accelerated Corrosion Program as described in LRA Section A.1.21. | |||
Enhance the ISI-IWF Program as described in LRA Section A.1.23. | |||
Enhance the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Program as described in LRA Section A.1.24. | |||
I | Implement the Internal Surfaces in Miscellaneous Piping and Ducting Components Program as described in LRA Section A.1.25. | ||
Enhance the Masonry Wall Program as described in LRA Section A.1.26. | |||
Implement the Non-EO Electrical Cable Connections Program as described in LRA Section A.1.27. | |||
Implementation Source Schedule (Letter Number) | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47805 last refueling outage RBG-47818 prior to August 29, 2025, whichever is later. | |||
Within seven years RBG-47818 prior to February 28, 2025. | |||
Prior to February 28, RBG-47735 2025. | |||
RBG-47860 Prior to February 28, RBG-47735 2025. | |||
Prior to February 28, RBG-47735 2025. | |||
Prior to February 28, RBG-47735 2025. | |||
RBG-47835 RBG-47860 Prior to February 28, RBG-47735 2025. | |||
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, I | |||
2025, whichever is I | |||
later. | |||
RBG-47870 Page 4 of 6 | RBG-47870 Page 4 of 6 No. | ||
19 20 21 22 23 Program or Activity Non-EO Inaccessible Power Cables (<! 400 V) | |||
perform an engineering evaluation in the corrective actions program element. | Non-EO Insulated Cables and Connections Non-EO Sensitive Instrumentation Circuits Test Review One-Time Inspection One-Time Inspection-Small-Bore Piping Commitment Implement the Non-EO Inaccessible Power Cables | ||
(<! 400 V) Program as described in LRA Section A.1.28. | |||
Implement the Non-EO Insulated Cables and Connections Program as described in LRA Section A.1.29. | |||
Revise RBS report, Aging Management Program Evaluation Results - Electrical, to include directions to perform an engineering evaluation in the corrective actions program element. | |||
prior to August 29, 2025 , whichever is later. | Implement the Non-EO Sensitive Instrumentation Circuits Test Review Program as described in LRA Section A.1.30. | ||
Implement the One-Time Inspection Program as described in LRA Section A.1.32. | |||
Implement the One-Time Inspection - Small-Bore Piping Program as described in LRA Section A.1.33. | |||
Implementation Source Schedule (Letter Number) | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47828 last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47828 last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the I, | |||
last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47834 last refueling outage RBG-47860 prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later. | |||
RBG-47870 Page 5 of 6 | RBG-47870 Page 5 of 6 No. | ||
2025, whichever is later. | 24 25 26 27 28 Program or Activity Periodic Surveillance and Preventive Maintenance Reactor Head Closure Studs RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Selective Leaching Structures Monitoring Commitment Enhance the PSPM Program as described in LRA Section A.1.34. | ||
Enhance the Reactor Head Closure Studs Program as described in LRA Section A.1.36. | |||
Enhance the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Program as described in LRA Section A.1.38. | |||
Implement the Selective Leaching Program as described in LRA Section A.1.39. | |||
Enhance the Structures Monitoring Program as described in LRA Section A.1.41. | |||
Implementation Source Schedule (Letter Number) | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47805 last refueling outage RBG-47835 prior to August 29, RBG-47846 2025, whichever is RBG-47860 later. | |||
RBG-47861 RBG-47867 Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47812 last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47735 2025, or the end of the RBG-47842 last refueling outage RBG-47860 prior to August 29, 2025, whichever is later. | |||
RBG-47870 Page 6 of 6 | RBG-47870 Page 6 of 6 No. | ||
29 30 31 32 Program or Activity Water Chemistry Control - Closed Treated Water Systems Control Rod Drive Return Line Nozzle Program Service Water Integrity Neutron Absorbing Material Monitoring Commitment Enhance the Water Chemistry Control-Closed Treated Water Systems Program as described in LRA Section A.1.43. | |||
Enhance the Control Rod Drive Return Line Nozzle Program as described in LRA Section A.1.5. | |||
Enhance the Service Water Integrity Program as described in LRA Section A.1.40. | |||
Install aluminum boron-carbide neutron absorbing material before the period of extended operation so that the Boraflex material in the spent fuel pool will not be credited to perform a neutron absorption function. | |||
material, confirming that the Boraflex material is no longer credited for neutron absorption. | Entergy shall submit a letter to the NRC, within 60 days following installation of the new neutron absorbing material, confirming that the Boraflex material is no longer credited for neutron absorption. | ||
-~ | |||
-~ | |||
Implementation Source Schedule (Letter Number) | |||
Prior to February 28, RBG-47735 2025. | |||
Prior to February 28, RBG-47812 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later. | |||
Prior to February 28, RBG-47834 2025. | |||
Prior to February 28, RBG-47830 2025, or the end of the RBG-47848 last refueling outage prior to August 29, 2025, whichever is later.}} | |||
Latest revision as of 18:31, 5 January 2025
| ML18158A137 | |
| Person / Time | |
|---|---|
| Site: | River Bend |
| Issue date: | 06/06/2018 |
| From: | Maguire W Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-47870 | |
| Download: ML18158A137 (9) | |
Text
~. Entergx RBG-47870 June 6, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Entergy Operations. Inc.
R,Vflr Bend Station 5485 US Highway 61 N St Francisville. LA 70775 f el 225*381-4374 William F. Maguire Site Vice President River Bend Station
SUBJECT:
License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix A, Section A.4, License Renewal Commitment List River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47
References:
- 1) Entergy Letter: License Renewal Application (RBG-47735 dated May 25, 2017)
Dear Sir or Madam:
In Reference 1, Entergy Operations, Inc (Entergy) submitted an application for renewal of the operating license for River Bend Station (RBS) for an additional 20 years beyond the current expiration date. Included in the application for renewal of the operating license was the Updated Safety Analysis Report Supplement, Appendix A, Section A.4, License Renewal Commitment List. During the license renewal application review, Section A.4, License Renewal Commitment List was updated to include new and revised information resulting from the review. provides the complete updated license renewal commitment list.
If you require additional information, please contact Mr. Tim Schenk at (225)-381-4177 or tschenk@entergy.com.
RBG-47870 Page 2 of 2 In accordance with 10 CFR 50.91 (b)(1), Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the designated State Official.
I declare under penalty of perjury that the foregoing is true and correct. Executed on June 6,2018.
Sincerely, WFM/RMC/dp : Updated Safety Analysis Report Supplement, Appendix A, Section A.4 - River Bend Station cc:
(with Enclosure)
U. S. Nuclear Regulatory Commission Attn: Emmanuel Sayoc 11555 Rockville Pike Rockville, MD 20852 cc:
(w/o Enclosure)
U. S. Nuclear Regulatory Commission Attn: Lisa Regner 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011 -4511 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.
Austin, TX 78711-3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 RBF1-18-0107
RBG-47870 License Renewal Application Updated Safety Analysis Report Supplement, Appendix A, Section A.4 License Renewal Commitment List
RBG-47870 Page 1 of 6 A.4 LICENSE RENEWAL COMMITMENT LIST No.
Program or Activity Commitment 1
Aboveground Metallic Implement the Aboveground Metallic Tanks Program as Tanks described in LRA Section A.1.1.
2 Bolting Integrity Enhance the Bolting Integrity Program as described in LRA Section A.1.2.
3 Neutron Absorbing Implement the Neutron Absorbing Material Monitoring Material Monitoring Program as described in LRA Section A.1.3.
4 Buried and Implement the Buried and Underground Piping and Underground Piping Tanks Inspection Program as described in LRA Section and Tanks Inspection A.1.4.
5 BWR Vessel Internals Enhance the BWR Vessel Internals Program as described in LRA Section A.1.1 O.
6 Coating Integrity Implement the Coating Integrity Program as described in LRA Section A.1.11.
7 Compressed Air Enhance the Compressed Air Monitoring Program as Monitoring described in LRA Section A.1.12.
Implementation Source Schedule (Letter Number)
Prior to February 28, RBG-47735 2025.
RBG-47818 Prior to February 28, RBG-47735 2025.
RBG-47828 Prior to February 28, RBG-47735 2025, or the end of the RBG-47830 last refueling outage RBG-47848 prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47813 last refueling outage RBG-47850 prior to August 29, RBG-47860 2025, whichever is later.
Prior to February 28, RBG-47735 2025. Initial RBG-47818 inspections will be performed prior to August 29, 2030.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47805 last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025.
RBG-47870 Page 2 of 6 No.
8 9
10 11 11a Program or Activity Containment Inservice Inspection - IWE Diesel Fuel Monitoring External Surfaces Monitoring Fatigue Monitoring Fatigue Monitoring Commitment Enhance the CII-IWE Program as described in LRA Section A.1.13.
Enhance the Diesel Fuel Monitoring Program as described in LRA Section A.1.15.
Enhance the External Surfaces Monitoring Program as described in LRA Section A.1.1 7.
Enhance the Fatigue Monitoring Program as described in LRA Section A.1.18.
Revise the Fatigue Monitoring Program description (Section 7B) of RBS-EP-15-00006, "Aging Management Program Evaluation Report Class 1 Mechanical," to state acceptable corrective actions include repair of the component, replacement of the component, and a more rigorous analysis of the component to demonstrate that the design code limit will not be exceeded during the period of extended operation.
Implementation Source Schedule (Letter Number)
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47812 last refueling outage RBG-47849 prior to August 29, RBG-47860 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later.
Enhancement to RBG-47735 develop a set of fatigue usage calculations:
prior to August 29, 2023.
Remaining enhancements: prior to February 28, 2025.
Prior to February 28, RBG-47846 2025.
RBG-47870 Page 3 of 6 No.
12 12a 13 14 15 16 17 18 Program or Activity Fire Water System Fire Water System Flow-Accelerated Corrosion Inservice Inspection -
IWF Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Internal Surfaces in Miscellaneous Piping and Ducting Components Masonry Wall Non-EO Electrical Cable Connections Commitment Enhance the Fire Water System Program as described in LRA Section A.1.20.
Remove existing coating, perform bottom thickness measurements and recoat the fire water storage tanks.
Enhance the Flow-Accelerated Corrosion Program as described in LRA Section A.1.21.
Enhance the ISI-IWF Program as described in LRA Section A.1.23.
Enhance the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Program as described in LRA Section A.1.24.
Implement the Internal Surfaces in Miscellaneous Piping and Ducting Components Program as described in LRA Section A.1.25.
Enhance the Masonry Wall Program as described in LRA Section A.1.26.
Implement the Non-EO Electrical Cable Connections Program as described in LRA Section A.1.27.
Implementation Source Schedule (Letter Number)
Prior to February 28, RBG-47735 2025, or the end of the RBG-47805 last refueling outage RBG-47818 prior to August 29, 2025, whichever is later.
Within seven years RBG-47818 prior to February 28, 2025.
Prior to February 28, RBG-47735 2025.
RBG-47860 Prior to February 28, RBG-47735 2025.
Prior to February 28, RBG-47735 2025.
Prior to February 28, RBG-47735 2025.
RBG-47835 RBG-47860 Prior to February 28, RBG-47735 2025.
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, I
2025, whichever is I
later.
RBG-47870 Page 4 of 6 No.
19 20 21 22 23 Program or Activity Non-EO Inaccessible Power Cables (<! 400 V)
Non-EO Insulated Cables and Connections Non-EO Sensitive Instrumentation Circuits Test Review One-Time Inspection One-Time Inspection-Small-Bore Piping Commitment Implement the Non-EO Inaccessible Power Cables
(<! 400 V) Program as described in LRA Section A.1.28.
Implement the Non-EO Insulated Cables and Connections Program as described in LRA Section A.1.29.
Revise RBS report, Aging Management Program Evaluation Results - Electrical, to include directions to perform an engineering evaluation in the corrective actions program element.
Implement the Non-EO Sensitive Instrumentation Circuits Test Review Program as described in LRA Section A.1.30.
Implement the One-Time Inspection Program as described in LRA Section A.1.32.
Implement the One-Time Inspection - Small-Bore Piping Program as described in LRA Section A.1.33.
Implementation Source Schedule (Letter Number)
Prior to February 28, RBG-47735 2025, or the end of the RBG-47828 last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47828 last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the I,
last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47834 last refueling outage RBG-47860 prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later.
RBG-47870 Page 5 of 6 No.
24 25 26 27 28 Program or Activity Periodic Surveillance and Preventive Maintenance Reactor Head Closure Studs RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Selective Leaching Structures Monitoring Commitment Enhance the PSPM Program as described in LRA Section A.1.34.
Enhance the Reactor Head Closure Studs Program as described in LRA Section A.1.36.
Enhance the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Program as described in LRA Section A.1.38.
Implement the Selective Leaching Program as described in LRA Section A.1.39.
Enhance the Structures Monitoring Program as described in LRA Section A.1.41.
Implementation Source Schedule (Letter Number)
Prior to February 28, RBG-47735 2025, or the end of the RBG-47805 last refueling outage RBG-47835 prior to August 29, RBG-47846 2025, whichever is RBG-47860 later.
RBG-47861 RBG-47867 Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47812 last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47735 2025, or the end of the RBG-47842 last refueling outage RBG-47860 prior to August 29, 2025, whichever is later.
RBG-47870 Page 6 of 6 No.
29 30 31 32 Program or Activity Water Chemistry Control - Closed Treated Water Systems Control Rod Drive Return Line Nozzle Program Service Water Integrity Neutron Absorbing Material Monitoring Commitment Enhance the Water Chemistry Control-Closed Treated Water Systems Program as described in LRA Section A.1.43.
Enhance the Control Rod Drive Return Line Nozzle Program as described in LRA Section A.1.5.
Enhance the Service Water Integrity Program as described in LRA Section A.1.40.
Install aluminum boron-carbide neutron absorbing material before the period of extended operation so that the Boraflex material in the spent fuel pool will not be credited to perform a neutron absorption function.
Entergy shall submit a letter to the NRC, within 60 days following installation of the new neutron absorbing material, confirming that the Boraflex material is no longer credited for neutron absorption.
-~
-~
Implementation Source Schedule (Letter Number)
Prior to February 28, RBG-47735 2025.
Prior to February 28, RBG-47812 2025, or the end of the last refueling outage prior to August 29, 2025, whichever is later.
Prior to February 28, RBG-47834 2025.
Prior to February 28, RBG-47830 2025, or the end of the RBG-47848 last refueling outage prior to August 29, 2025, whichever is later.