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Category:Fuel Cycle Reload Report
MONTHYEARRBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 12023-11-0606 November 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 1 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-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 12021-08-19019 August 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 1 RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 02021-03-14014 March 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 0 ML18297A3132018-10-24024 October 2018 River Bend Station Core Operating Limits Report Cycle 20 Revision 2 RBG-47738, Cycle Core Operating Limits Report, Cycle 20, Revision 02017-03-0303 March 2017 Cycle Core Operating Limits Report, Cycle 20, Revision 0 RBG-47648, Nineteenth Fuel Cycle Core Operating Limits Report, Revision 2 River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-472016-02-11011 February 2016 Nineteenth Fuel Cycle Core Operating Limits Report, Revision 2 River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 RBG-47635, Nineteenth Fuel Cycle Core Operating Limits Report, Revision 12016-01-18018 January 2016 Nineteenth Fuel Cycle Core Operating Limits Report, Revision 1 RBG-47567, Submittal of Nineteenth Fuel Cycle Core Operating Limits Report (COLR)2015-05-12012 May 2015 Submittal of Nineteenth Fuel Cycle Core Operating Limits Report (COLR) RBG-47351, Eighteenth Fuel Cycle Core Operating Limits Report (COLR)2013-04-0303 April 2013 Eighteenth Fuel Cycle Core Operating Limits Report (COLR) RBG-47144, Cycle 17 Startup Report2011-05-11011 May 2011 Cycle 17 Startup Report RBG-47120, Unit 1, Seventeenth Fuel Cycle Core Operating Limits Report (COLR)2011-02-17017 February 2011 Unit 1, Seventeenth Fuel Cycle Core Operating Limits Report (COLR) RBG-46965, Submittal of Sixteenth Fuel Cycle Core Operating Limits Report2009-10-21021 October 2009 Submittal of Sixteenth Fuel Cycle Core Operating Limits Report RBG-46958, Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)2009-09-17017 September 2009 Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR) RBG-46938, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)2009-08-0303 August 2009 Fifteenth Fuel Cycle Core Operating Limits Report (COLR) RBG-46792, Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR)2008-03-0303 March 2008 Unit 1, Fifteenth Fuel Cycle Core Operating Limits Report (COLR) RBG-46583, License Amendment Request, Changes to the Analytical Methods Referenced in Technical Specification 5.6.5, Core Operating Limits Report (Colr).2006-10-16016 October 2006 License Amendment Request, Changes to the Analytical Methods Referenced in Technical Specification 5.6.5, Core Operating Limits Report (Colr). RBG-46358, Thirteenth Fuel Cycle Core Operating Limits Report (COLR)2004-11-17017 November 2004 Thirteenth Fuel Cycle Core Operating Limits Report (COLR) RBG-46102, Unit 1, Twelfth Fuel Cycle Core Operating Limits Report (COLR)2003-04-14014 April 2003 Unit 1, Twelfth Fuel Cycle Core Operating Limits Report (COLR) 2023-05-31
[Table view] Category:Letter type:RBG
MONTHYEARRBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024 Notification of Readiness for Supplemental Inspection RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report RBG-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 2024-07-31
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En te. rgy River Bend Station 5485 U.S. Highway 61N St. Francisville, LA 70775 Tel 225-381-4157 David N. Lorfing Manager, Licensing RBG-47144 May 11, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Cycle 17 Startup Report River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47
Dear Sir or Madam:
In accordance with River Bend Station (RBS) Technical Requirements'Manual TR 5.6.8, enclosed is a Startup Report that provides a summary of the startup physics testing conducted on the Cycle 17 core reload.If you have any questions or require additional information, please contact David Lorfing, Manager, Licensing at (225) 381-4157.Sincerely, DNL/bmb Attachment RBG-47144 Page 2 of 2 cc: Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS 0-7 D1 Washington, DC 20555-0001 Mr. Jeffrey P. Meyers Louisiana Department of Environmental Quality Office of Environmental Compliance Attn. OEC -ERSD P. O. Box 4312 Baton Rouge, LA 70821-4312 RBS- 47144 Page 1 of 1 RBG-47144 RBF1-11-0077 File codes; G9.5, G9.25.1.4 ATTACHMENT TO RBG-47144 Cycle 17 Startup Physics Test Summary Attachment to RBG-47144 Page 1 of 4 ENTERGY OPERATIONS, INC.RIVER BEND STATION Cycle 17 Startup Physics Test Summary OVERVIEW River Bend Station (RBS) resumed commercial operation in Cycle 17 on February 12, 2011 following a Refueling/Maintenance Outage. The Cycle 17 reload consisted of replacing 240 Atrium 10 AREVA fuel assemblies with 240 Global Nuclear Fuel (GNF) GNF2 fuel assemblies.
No other revision to the design or operation of the station were conducted which would affect the scope of this report.The following startup tests were performed during Refueling Outage RF16 or while' attaining full power after RF16, and are summarized in this report: 1) Core Loading Verification
- 2) Control Rod Scram Time Testing 3) Shutdown Margin Determination
- 4) TIP Symmetry In addition to the above startup physics tests, the startup test program included:
Core Monitoring System Verification, and other surveillance testing required by RBS Technical Specifications.
The additional test results are available at the site on request.CORE LOADING VERIFICATION Purpose Ensure each reactor fuel assembly is:* In its correct core location* Oriented properly* Seated properly in its support piece Attachment to RBG-Page 2 of 4 Criteria The reactor core is visually checked to verify conformance to the vendor supplied core loading pattern. Fuel assembly serial numbers, orientations, and core locations are-recorded.
A height check is performed to verify all assemblies are properly seated.Results The as-loaded core was verified for proper fuel assembly serial numbers, locations, orientation and seating in accordance with the RBS Cycle 17 core loading pattern. There were no location or orientation deviations from the Cycle 17 core loading pattern.The core verification procedure was successfully completed on February 5, 2011.CONTROL ROD FUNCTIONAL TESTING Purpose Verify functionality of each control rod by:* Performing normal withdrawals and insertions
- Ensuring it is latched to its control rod drive Criteria Testing of each control rod is performed in accordance with technical specification to ensure proper operability.
This testing includes coupling verification, and scram time testing.Results All control rods were scram timed tested and coupling verified as discussed below.Fifteen (15) Control Rod Drive Mechanisms and eleven (11) Control Rod Blades were replaced during the outage. Seven (7) hydraulic control units had maintenance completed.
All maintenance related rods with the exception of 20-45 and 16-53 were scram time tested prior to startup during the vessel pressure test in accordance with TechnicalSpecification Surveillance Requirements 3.1.4.3 and 3.1.4.4 with satisfactory results. Control rod 20-45 remained inoperable
(@ position 00) and reactor power below 40% CTP until tested. Control rod 16-53 was tested at zero pressure to restore operability for the approach to critical.The remaining control rods were scram time tested during the vessel pressure test in accordance with RBS Technical Specification Surveillance Requirement 3.1.4.4 (fuel movement) with the exception of 12-45 and 04-37.Control rods 20-45, 16-53, 12-45 and 04-37 were tested and satisfactorily met the acceptance criteria prior to exceeding 40 percent rated core thermal power.
Attachment to RBG-Page 3 of 4 A control rod coupling check was performed in accordance with RBS Technical Specification Surveillance Requirement 3.1.3.5 each time a control rod was fully withdrawn.
SHUTDOWN MARGIN DETERMINATION
/ REACTIVITY ANOMALY CHECK Purpose To ensure that: The reactor can be made sub-critical from all operating conditions The reactivity transients associated with postulated accident conditions are controllable within acceptable limits The reactor will be maintained sufficiently sub-critical to preclude inadvertent critically in the shutdown condition Criteria The in-sequence rod withdrawal shutdown margin calculation begins by withdrawing control rods in their standard sequence until criticality is achieved.
The shutdown margin of the core is determined from calculations based on the critical rod pattern, the reactor period and the moderator temperature to satisfy SR 3.1.1 .1 .a.Reactivity Anomaly verification is performed in accordance with Technical Specification Surveillance Requirement 3.1.2.1 after reaching equilibrium xenon concentrations at 100%reactor power.Results The in-sequence critical shutdown margin surveillance procedure was completed on February 11, 2011. The shutdown margin (SDM) at the beginning-of-cycle (BOC) was calculated to be 0.778 % delta k/k which is bounded by RBS Technical Specification
3.1.1 requirement
of 0.38% delta k/k. Final steady state full power operation was achieved on February 23, 2011.It was verified on February 23, 2011, that no reactivity anomaly was present by performance of Technical Specification Surveillance Requirement 3.1.2.1.
Attachment to RBG-Page 4 of 4 TIP SYMMETRY CHECK Purpose To determine the reproducibility of the Traversing Incore Probe (TIP) system readings Criteria This procedure applies to BWR plants operating with Global Nuclear Fuel (GNF)reduced uncertainties safety limit Minimum Critical Power Ratio (MCPR) methodology and using 3D MONICORE version 6.58 and higher. This MCPR methodology requires that a TIP symmetry check be conducted each cycle to confirm its assumptions.
Results The TIP symmetry calculation was performed on April 4, 2011, using 3D Monicore at 100%core thermal power.The determined TIP uncertainty is 5.59% which is bounded by the acceptance criteria of 6%.