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| | issue date = 04/12/2018 | | | issue date = 04/12/2018 |
| | title = Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015) | | | title = Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015) |
| | author name = Schenk T A | | | author name = Schenk T |
| | author affiliation = Entergy Operations, Inc | | | author affiliation = Entergy Operations, Inc |
| | addressee name = | | | addressee name = |
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| | document type = Letter type:RBG | | | document type = Letter type:RBG |
| | page count = 2 | | | page count = 2 |
| | | project = |
| | | stage = Supplement |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:* Entergx |
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| | Entergy Operations, Inc. |
| | River Bend Station 5485 U.S. Highway 61N SI. Francisville, LA 70775 Tel 225-38 1-4 177 Timothy Schenk Regu latory Assurance Manager River Bend Station RBG-47854 April 12, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 |
| | |
| | ==SUBJECT:== |
| | Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) |
| | Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR- RBS-ISI-015) |
| | River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47 |
| | |
| | ==Dear Sir or Madam :== |
| | |
| | In accordance with 10 CFR 50.55a, "Codes and Standards," paragraph (z)(1), Entergy previously requested NRC approval of the proposed alternative to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Sub Article IWB-2500 to allow reduced requirements for nozzle-to-vessel weld and inner radius examinations for River Bend Station (RBS). |
| | Entergy originally submitted this request by RBS letter RBG-47825, dated February 13, 2018 |
| | [ADAMS Accession Number ML18045A028]. |
| | It has recently been determined that the title of the letter contained a typographical error and the Attachment 1 to the letter is missing a reference to ASME Code Case N-648-1 , Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles. This supplement is to clarify the following. |
| | * The correct code referenced in the title is 10 CFR 50.55a (z)(1) |
| | * Entergy has adopted ASME Code Case N-648-1 , Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles, with the provisions stipulated in Regulatory Guide 1.147, in the RBS Forth Interval lSI Program Plan . Entergy may therefore perform examinations on inner radius sections with either the VT -1 or the volumetric examination method. |
| | The supplemental information provided does not change the scope of the original submittal. |
| | Entergy requests approval of this request by November 30, 2018, in order to support refueling outage twenty (RF-20) scheduled for January 2019. |
| | |
| | RBG-47854 Page 2 of 2 There are no regulatory commitments contained in this submittal. If you require additional information , please contact Mr. Tim Schenk at (225) -381 -4177 or tschenk@entergy.com. |
| | TAS/alc cc : 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 RBF1-18-0080 LAR-2018-02}} |
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Category:Letter type:RBG
MONTHYEARRBG-48271, 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, Risk2024-01-12012 January 2024 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 RBG-48267, Reply to a Notice of Violation, NRC Inspection Report 05000458/20230032023-12-0707 December 2023 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 12023-11-0606 November 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 1 RBG-48260, Notification of Readiness for Supplemental Inspection2023-10-12012 October 2023 Notification of Readiness for Supplemental Inspection RBG-48258, Notification of Readiness for Supplemental Inspection2023-10-0505 October 2023 Notification of Readiness for Supplemental Inspection RBG-48259, Revision to Reply to Notice of Violation; EA-23-0552023-10-0303 October 2023 Revision to Reply to Notice of Violation; EA-23-055 RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 RBG-48249, Reply to a Notice of Violation, EA-23-0712023-09-14014 September 2023 Reply to a Notice of Violation, EA-23-071 RBG-48253, Submittal of Owner'S Activity Report Form for Cycle 222023-09-12012 September 2023 Submittal of Owner'S Activity Report Form for Cycle 22 RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 02023-05-31031 May 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 0 RBG-48237, Response to NRC Integrated Inspection Report 05000458/20230012023-05-25025 May 2023 Response to NRC Integrated Inspection Report 05000458/2023001 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RBG-48221, 2022 Annual Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Radiological Environmental Operating Report RBG-48142, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-27027 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-27027 February 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RBG-48198, Report of Changes and Errors to 10CFR50.462022-09-22022 September 2022 Report of Changes and Errors to 10CFR50.46 RBG-48187, Notification of Spent Fuel Cask Use2022-08-15015 August 2022 Notification of Spent Fuel Cask Use RBG-48184, Notification of Spent Fuel Cask Use2022-07-18018 July 2022 Notification of Spent Fuel Cask Use RBG-48178, Notification of Spent Fuel Cask Use2022-06-29029 June 2022 Notification of Spent Fuel Cask Use RBG-48166, Supplement to Special Report for Tritium Discovered Onsite2022-05-12012 May 2022 Supplement to Special Report for Tritium Discovered Onsite RBG-48149, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report RBG-48148, 2021 Annual Radiological Environmental Operating Report2022-04-27027 April 2022 2021 Annual Radiological Environmental Operating Report RBG-48134, Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency2021-11-29029 November 2021 Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency RBG-48136, Additional Information for the 2020 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2020 Annual Radioactive Effluent Release Report RBG-48137, Additional Information for the 2019 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2019 Annual Radioactive Effluent Release Report RBG-48128, Reply to a Notice of Violation; EA-21-017, 030 and 0502021-10-29029 October 2021 Reply to a Notice of Violation; EA-21-017, 030 and 050 RBG-48129, Payment of a Civil Penalty2021-10-21021 October 2021 Payment of a Civil Penalty RBG-48112, Report of Changes and Errors to 10CFR50.462021-09-16016 September 2021 Report of Changes and Errors to 10CFR50.46 RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 12021-08-19019 August 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 1 RBG-48104, Fitness for Duty Blind Quality Assurance Specimen Testing Error2021-06-30030 June 2021 Fitness for Duty Blind Quality Assurance Specimen Testing Error RBG-48099, Submittal of Owner'S Activity Report Form for Cycle 212021-06-16016 June 2021 Submittal of Owner'S Activity Report Form for Cycle 21 RBG-48083, Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials2021-06-15015 June 2021 Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials RBG-48093, Corrected 2020 Annual Radiological Environmental Operating Report2021-05-20020 May 2021 Corrected 2020 Annual Radiological Environmental Operating Report RBG-48082, 2020 Annual Radiological Environmental Operating Report2021-04-20020 April 2021 2020 Annual Radiological Environmental Operating Report RBG-48081, 2020 Annual Radioactive Effluent Release Report2021-04-20020 April 2021 2020 Annual Radioactive Effluent Release Report RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 02021-03-14014 March 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 0 RBG-48075, Notification of Deviation from BWRVIP Guidelines2021-02-24024 February 2021 Notification of Deviation from BWRVIP Guidelines RBG-48074, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-22022 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 RBG-48061, One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-12-0303 December 2020 One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency RBG-48054, Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program2020-11-0202 November 2020 Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program RBG-48049, Reply to a Notice of Violation; EA-20-0582020-10-26026 October 2020 Reply to a Notice of Violation; EA-20-058 RBG-48038, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic2020-10-0606 October 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic RBG-48042, Submittal of Rev. 48 to Emergency Plan2020-09-22022 September 2020 Submittal of Rev. 48 to Emergency Plan RBG-48039, Report of Changes and Errors to 10CFR50.462020-09-16016 September 2020 Report of Changes and Errors to 10CFR50.46 RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-0404 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RBG-48023, Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures2020-06-0909 June 2020 Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures RBG-48019, 2019 Annual Radioactive Effluent Release Report2020-04-30030 April 2020 2019 Annual Radioactive Effluent Release Report RBG-48020, Annual Radiological Environmental Operating Report2020-04-30030 April 2020 Annual Radiological Environmental Operating Report RBG-48018, Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date2020-04-24024 April 2020 Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date 2024-01-12
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Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61N SI. Francisville, LA 70775 Tel 225-38 1-4 177 Timothy Schenk Regu latory Assurance Manager River Bend Station RBG-47854 April 12, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
Supplement to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1)
Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR- RBS-ISI-015)
River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47
Dear Sir or Madam :
In accordance with 10 CFR 50.55a, "Codes and Standards," paragraph (z)(1), Entergy previously requested NRC approval of the proposed alternative to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Sub Article IWB-2500 to allow reduced requirements for nozzle-to-vessel weld and inner radius examinations for River Bend Station (RBS).
Entergy originally submitted this request by RBS letter RBG-47825, dated February 13, 2018
[ADAMS Accession Number ML18045A028].
It has recently been determined that the title of the letter contained a typographical error and the Attachment 1 to the letter is missing a reference to ASME Code Case N-648-1 , Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles. This supplement is to clarify the following.
- Entergy has adopted ASME Code Case N-648-1 , Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles, with the provisions stipulated in Regulatory Guide 1.147, in the RBS Forth Interval lSI Program Plan . Entergy may therefore perform examinations on inner radius sections with either the VT -1 or the volumetric examination method.
The supplemental information provided does not change the scope of the original submittal.
Entergy requests approval of this request by November 30, 2018, in order to support refueling outage twenty (RF-20) scheduled for January 2019.
RBG-47854 Page 2 of 2 There are no regulatory commitments contained in this submittal. If you require additional information , please contact Mr. Tim Schenk at (225) -381 -4177 or tschenk@entergy.com.
TAS/alc cc : 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 RBF1-18-0080 LAR-2018-02