|
---|
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
MONTHYEARML24214A2752024-08-0202 August 2024 Acknowledgement of Readiness for Supplemental Inspection RBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024 Notification of Readiness for Supplemental Inspection IR 05000458/20240022024-07-30030 July 2024 Integrated Inspection Report 05000458/2024002 and Notice of Violation ML24164A0862024-06-12012 June 2024 Notification of Commercial Grade Dedication Inspection (05000458/2024010) and Request for Information IR 05000458/20240012024-05-14014 May 2024 Integrated Inspection Report 05000458/2024001 ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000458/20230402024-01-18018 January 2024 95001 Supplemental Inspection Supplemental Report 05000458/2023040 and Follow-Up Assessment Letter 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 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 ML24011A1742024-01-11011 January 2024 Security Baseline Inspection Report (Cover Letter) 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 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 IR 05000458/20230102023-12-12012 December 2023 Biennial Problem Identification and Resolution Inspection Report 05000458/2023010 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 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1432023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A0322023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 IR 05000458/20230032023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 ML23311A4322023-11-0909 November 2023 Notification of NRC Supplemental Inspection (95001) and Request for Information 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 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 ML23278A2402023-10-0606 October 2023 Regulatory Audit Plan in Support of License Amendment Requests to Revise TSs to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 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 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 ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000458/20234012023-09-26026 September 2023 Cyber Security Inspection Report 05000458/2023401 IR 05000458/20234032023-09-21021 September 2023 NRC Security Inspection Report 05000458/2023403 (Cover Letter) IR 05000458/20230012023-09-21021 September 2023 NRC Inspection Report 05000458/2023001, Disputed Non-Cited Violation Rescinded 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 IR 05000458/20230122023-09-0101 September 2023 Comprehensive Engineering Team Inspection Report 05000458/2023012 IR 05000458/20230052023-08-21021 August 2023 Updated Inspection Plan for River Bend Station (Report 05000458/2023005) - Mid Cycle Letter RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 IR 05000458/20230922023-08-15015 August 2023 Final Significance Determination of a White Finding, Notice of Violation, and Follow-Up Assessment Letter; NRC Inspection Report 05000458/2023092 IR 05000458/20230022023-08-0909 August 2023 Integrated Inspection Report 05000458/2023002 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 ML23195A0692023-07-24024 July 2023 2023 River Bend Station Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000458/20230912023-07-20020 July 2023 Final Significance Determination of a White Finding, Notice of Violation, and Follow-Up Assessment Letter; NRC Inspection Report 05000458/2023091 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23195A0222023-07-11011 July 2023 4-2022-012 Letter - OI Closure to Licensee IR 05000458/20234042023-07-11011 July 2023 NRC Security Inspection Report 05000458/2023404 (Cover Letter Only) IR 05000458/20230902023-06-26026 June 2023 NRC Inspection Report 05000458/2023090 and Preliminary White Finding 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) 2024-08-02
[Table view] |
Text
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%.