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Category:Letter
MONTHYEARRBG-48306, Report of Changes and Errors to 10CFR50.462024-09-24024 September 2024 Report of Changes and Errors to 10CFR50.46 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 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 RBG-48294, 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 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 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 IR 05000458/20240012024-05-14014 May 2024 Integrated Inspection Report 05000458/2024001 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 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 05000458/20244022024-04-15015 April 2024 Security Baseline Inspection Report 05000458/2024402 (Full Report) RBG-48288, Louisiana Pollutant Discharge Elimination System Permit Renewal2024-04-15015 April 2024 Louisiana Pollutant Discharge Elimination System Permit Renewal ML24106A0432024-04-11011 April 2024 June 2024 Emergency Preparedness Exercise Inspection Request for Information RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report 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 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 IR 05000458/20240402024-03-15015 March 2024 – 95001 Supplemental Inspection Report 05000458/2024040 and Follow-Up Assessment ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) 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)) 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 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) 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 ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection 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 2024-09-24
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August 19, 2004 Mr. Tom Hunt Entergy Operations 5485 U.S. Highway 61 St. Francisville, LA 70775
SUBJECT:
TRANSMITTAL OF REVISION 1 SIGNIFICANCE DETERMINATION PROCESS RISK-INFORMED INSPECTION NOTEBOOK AND INFORMATION REQUEST FOR NEXT REVISION
Dear Mr. Hunt:
On September 30, 2003, the NRC completed a two-year benchmarking activity for 71 Significance Determination Process (SDP) risk-informed inspection notebooks. All 71 notebooks were issued as revision 1, incorporating information obtained during the initial benchmarking visits. The NRC appreciates the support of each licensee in this resource intensive, first-of-a-kind effort which has greatly improved the quality of each SDP notebook to reflect the plant design-features, operational procedures and, in many cases, reduced unnecessary conservatism.
Over the course of this two year effort, insights were gained and it became apparent that these lessons learned would need to be captured in all of the notebooks, with additional effort needed for updating the notebooks that were benchmarked early in the process. It was also recognized that periodic maintenance would be required to achieve a reasonable level of accuracy as a screening tool, given changes in plant design, procedures, and revisions to the plant-specific probabilistic risk assessment (PRA) models since the original benchmarking visit.
In April of 2004, the NRC and its contractor Brookhaven National Laboratory (BNL) embarked on an SDP notebook enhancement/standardization effort for all 71 notebooks through a revision 2 process. Each revision 2 SDP notebook will contain a target set of equipment that is pre-solved in a manner similar to what was performed as part of the revision 1 benchmarking effort, in addition to capturing the lessons learned, and requesting information specific to gaps in the individual notebooks. The NRC estimates completion of the revision 2 SDP notebooks by June 30, 2005.
In order to achieve this milestone with minimal burden, the NRC requests that the plant-specific information for River Bend specified on the enclosed CD be sent to the address provided below.
The CD also contains the revision 1 SDP notebook generated from the initial benchmarking visit. The NRC requests that your response to the plant-specific information be provided on a CD within 30 days of receipt of this request. In addition to the plant-specific request, the NRC welcomes your comments on the revision 1 SDP notebook.
T. Hunt 2 Mailing address for response:
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch MS: O10-H4 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 The NRC staff is continuing to review the appropriate classification of the enclosed CD documents within the records management program considering changes in our practices following the events of September 11, 2001. Pending a final determination, the information request and the notebooks have been marked as Proprietary Information in accordance with Section 2.390(d) of Title 10 of the Code of Federal Regulations (10 CFR 2.390). Please control the document accordingly (i.e., treat the document as trade secrets and commercial or financial information that you considered privileged or confidential). We will inform you if the designation of the documents change as a result of our ongoing assessments.
If you have any questions regarding the request, please contact Ogbonna Hopkins at 301-415-1153.
Sincerely,
/RA/
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation Nuclear Regulatory Commission
Enclosure:
As stated
T. Hunt 2 Mailing address for response:
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch MS: O10-H4 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 The NRC staff is continuing to review the appropriate classification of the enclosed CD documents within the records management program considering changes in our practices following the events of September 11, 2001. Pending a final determination, the information request and the notebooks have been marked as Proprietary Information in accordance with Section 2.390(d) of Title 10 of the Code of Federal Regulations (10 CFR 2.390). Please control the document accordingly (i.e., treat the document as trade secrets and commercial or financial information that you considered privileged or confidential). We will inform you if the designation of the documents change as a result of our ongoing assessments.
If you have any questions regarding the request, please contact Ogbonna Hopkins at 301-415-1153.
Sincerely,
/RA/
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation Nuclear Regulatory Commission DISTRIBUTION PUBLIC (w/o enclosure)
Adams Accession No. ML042360385 NRR-106 OFFICE SPSB-B SPSB-B SPSB-B/SC SPSB/BC NAME TValentine RPerch MCaruso MTschiltz DATE 8/ 16 /04 8/16 /04 8/ 16 /04 8/ 19 /04 OFFICIAL RECORD COPY