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Category:Letter
MONTHYEARIR 05000458/20240102024-10-31031 October 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000458/2024010 IR 05000458/20240032024-10-31031 October 2024 Integrated Inspection Report 05000458/2024003 RBG-48315, Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement2024-09-24024 September 2024 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement RBG-48306, Report of Changes and Errors to 10CFR50.462024-09-24024 September 2024 Report of Changes and Errors to 10CFR50.46 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24255A1192024-09-16016 September 2024 Notification of NRC Follow Up Inspection for One Severity Level (SL) III and Two SL IV or Three or More SL IV Violations and Request for Additional Information RBG-48311, Reply to a Notice of Violation, NRC Inspection Report 05000458/20240022024-08-28028 August 2024 Reply to a Notice of Violation, NRC Inspection Report 05000458/2024002 IR 05000458/20240052024-08-22022 August 2024 Updated Inspection Plan for River Bend Station (Report 05000458/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24214A2752024-08-0202 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 05000458/LER-2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String2024-06-0404 June 2024 Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24081A0072024-05-16016 May 2024 Issuance of Amendment No. 213 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24093A0892024-05-16016 May 2024 Issuance of Amendment No. 214 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 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 ML24102A2842024-05-0707 May 2024 Summary of Regulatory Audit in Support of LARs to Revise Technical Specifications to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report RBG-48288, Louisiana Pollutant Discharge Elimination System Permit Renewal2024-04-15015 April 2024 Louisiana Pollutant Discharge Elimination System Permit Renewal IR 05000458/20244022024-04-15015 April 2024 Security Baseline Inspection Report 05000458/2024402 (Full Report) ML24106A0432024-04-11011 April 2024 June 2024 Emergency Preparedness Exercise Inspection Request for Information ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000458/20243012024-04-0202 April 2024 Notification of NRC Initial Operator Licensing Examination 05000458/2024301 ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) IR 05000458/20240402024-03-15015 March 2024 – 95001 Supplemental Inspection Report 05000458/2024040 and Follow-Up Assessment ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24066A1802024-03-0707 March 2024 Notification of NRC Follow-Up Inspection for Any Severity Level I or II Traditional Enforcement Violation IR 05000458/20230062024-02-28028 February 2024 Annual Assessment Letter for River Bend Station - Report 05000458/2023006 RBG-48278, 2023 Spent Fuel Storage Radioactive Effluent Release Report2024-02-27027 February 2024 2023 Spent Fuel Storage Radioactive Effluent Release Report RBG-48286, Revision to Owners Activity Report Form (OAR) for Cycle 222024-02-27027 February 2024 Revision to Owners Activity Report Form (OAR) for Cycle 22 ML24031A0042024-02-21021 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0052 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000458/LER-2023-006, Automatic Reactor Scram Due to a Turbine Trip Following a Disconnect Failure at Switchyard2024-02-0808 February 2024 Automatic Reactor Scram Due to a Turbine Trip Following a Disconnect Failure at Switchyard RBG-48274, Notification of Readiness for Supplemental Inspection2024-02-0505 February 2024 Notification of Readiness for Supplemental Inspection IR 05000458/20230042024-01-30030 January 2024 Integrated Inspection Report 05000458/2023004 IR 05000458/20230402024-01-18018 January 2024 – 95001 Supplemental Inspection Supplemental Report 05000458/2023040 and Follow-Up Assessment Letter 05000458/LER-2023-005, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String2024-01-16016 January 2024 Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String 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 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 ML24011A1742024-01-11011 January 2024 Security Baseline Inspection Report (Cover Letter) 05000458/LER-2023-004, Drywall Post Accident Radiation Monitor Inoperable Due to Unrecognized Surveillance Failure2023-12-28028 December 2023 Drywall Post Accident Radiation Monitor Inoperable Due to Unrecognized Surveillance Failure 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 2024-09-24
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Entergy Operations, Inc.River Bend Station 5485 U.S. Highway 61 N___..__ nSt. Francisville, LA 70775 E bew Tel 225 381 4149 n 1Fax 225 635 5068-0 jrober3@entergy.com Jerry C. Roberts Director, Nuclear Safety Assurance May 3, 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, Maryland, 20852
Subject:
Response to Generic Letter 2007-01 River Bend Station -Unit 1 Docket No. 50-458 License Number NPF-47 File Code: G9.5 File No.: RBF1-07-0070 RBG-46692
References:
- 1. NRC Generic Letter 2007-01, dated February 7, 2007 "Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients" 2. NEI letter from J. H. Riley to Administrative Points of Contact dated March 16, 2007 "Guidance for Response to GL 2007-01" 3. NRC letter from Michael J. Case, to J. H. Riley dated April 13, 2007,"Response to Nuclear Energy Institute (NEI) Letter Dated March 26, 2007 -Re: Interpretation of Generic Letter (GL) 2007-01, Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients."
Dear Sir or Madam:
Per Reference 1, the NRC issued Generic Letter (GL) 2007-01 to request facilities to submit the following information to the NRC within 90 days of the date of the Generic Letter: (1) Provide a history of inaccessible or underground power cable failures for all cables that are within the scope of 10CFR50.65 (Maintenance Rule) and for all voltage levels. Indicate the type, manufacturer, date of failure, type of service, voltage class, years of service, and the root causes for the failure.(2) Describe inspection, testing and monitoring programs to detect the degradation of inaccessible or underground power cables that support EDGs, offsite power, ESW, service water, component cooling water, and other systems that are within the scope of 10CFR50.65.
The response to Question 1 is provided in the attachment to this letter. In researching plant records for the requested information, River Bend Station used the NEI and NRC guidance provided in References 2 and 3 to clarify the population of cables of interest.
Electronic searches of the corrective action and maintenance databases were performed.
The data indicate that River Bend Station has experienced one cable failure within the scope of the Generic Letter.With regard to Question 2, River Bend's inspection, testing, and monitoring practices include meggering of cables and connected equipment as needed during corrective maintenance activities.
The station's corrective action program is used to determine root cause and the extent of conditions, where deemed necessary, and would be the mechanism for determining the need for and extent of any increased cable monitoring.
No new commitments are identified in this submittal.
If you have any questions or require additional information, please contact Mr. Danny Williamson at 225-381-4279.The requested information is being provided pursuant the requirements of 10 CFR50.54(f).
I declare under the penalty of perjury that the foregoing information is true and correct.Executed on May 3, 2007 XJerry C. Rob~erts Director, Nuclear Safety Assurance Attachment cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Sr. Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 Attachment Page 1 of 1 RBF1-01-0070 River Bend Station Response to Generic Letter 2007-01 Date of failure: Time in service: Cable type: Voltage class: Manufacturer:
Type of service: Root cause: May 23, 1989 4 years 750 MCM copper triplex, EP insulation, Hypalon jacket with metal shield 15kv Anaconda Cable 1NPSBNJ320, "C" phase output of 13.8 kv reserve station service transformer "B", installed in ductline, continuously energized No formal root cause analysis was performed.
Since this failure occurred concurrent with a failure of the associated station service transformer, it is suspected that the cable insulation was stressed beyond design limits by the transformer failure.Condition Report 89-0784 documented this event.