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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 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 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 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 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 IR 05000458/20230032023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 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 ML23311A4322023-11-0909 November 2023 Notification of NRC Supplemental Inspection (95001) and Request for Information 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 2024-08-02
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September 18, 2006 Mr. Paul D. Hinnenkamp Vice President - Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - RE: RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NO. MB9847)
Dear Mr. Hinnenkamp:
The U.S. Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses, dated August 11, 2003 (Agencywide Documents and Access Management System (ADAMS)
Accession No. ML032270447), and January 25, 2005 (ADAMS Accession No. ML050310352),
to the NRC Generic Letter (GL) 2003-01, Control Room Habitability, dated June 12, 2003 (ADAMS Accession No. ML031620248).
The GL 2003-01 requested that you confirm that your control room (CR) meets its design bases (e.g., General Design Criteria (GDC) 1, 3, 4, 5, and 19, draft GDC, or principal design criteria),
with special attention to the following:
(1) GL 2003-01, Requested Information, Item 1a: Determination of the most limiting unfiltered and/or filtered inleakage into the CR and comparison to values used in your design bases for meeting CR operator dose limits from accidents.
(2) GL 2003-01, Requested Information, Item 1b: Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments.
(3) GL 2003-01, Requested Information, Item 1b: Determination that reactor control capability is maintained in the CR or at the alternate shutdown location in the event of smoke.
(4) GL 2003-01, Requested Information, Item 2: Provide information on any compensatory measures in use to demonstrate control room habitability (CRH),
and plans to retire them.
(5) GL 2003-01, Requested Information, Item 1c: Assessment of the Technical Specifications (TSs) to determine if they require verification of the integrity of the CR Envelope (CRE), including ongoing verification of the inleakage assumed in the design basis analysis for CRH, in light of the demonstrated unreliability of the P surveillance (a test to ensure positive differential pressure between CR and adjacent areas) alone to provide such verification.
P. Hinnenkamp As requested by GL 2003-01, you provided responses by letters referenced above. They are summarized below:
- a. River Bend Stations (RBSs) CR is a positive-pressure-design structure.
- b. The results of American Society of Testing Materials (ASTM) E741 tracer gas tests (ASTM, Standard Test Method, E2029-99, for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution) for RBSs CR indicate that the maximum tested unfiltered inleakage into the CRE, was 18 cubic feet per minute (cfm) which is less than the value of 300 cfm, the assumed value in the design-basis radiological analyses for CRH.
- c. The maximum tested unfiltered inleakage for toxic chemical operation mode was 18 cfm which is less than the value of 300 cfm, the assumed value in your design-basis toxic chemical analysis.
- d. The reactor control capability is maintained from either the CR or the alternate shutdown panel in the event of smoke.
- e. RBSs TSs presently contain a surveillance requirement (SR), SR 3.7.2.4, to demonstrate that the ventilation system can maintain the CRE at a positive pressure relative to outside atmosphere.
- f. RBS would submit a license amendment request (LAR) to include a new TS SR referencing an acceptable surveillance methodology to determine inleakage using ASTM E741 tracer gas or other suitable inleakage testing, within 6 months following the NRC approval of the traveler for TS Task Force (TSTF)-448, Control Room Habitability, or the publication of the notice of availability of Consolidated Line Item Improvement for TSTF-448 in the Federal Register.
The LAR will include the addition of a new TS SR to determine inleakage in accordance with the Control Room Integrity Program (CRIP), and the addition of a new TS Section 5.5, Programs and Manuals, that will specify the scope of the CRIP. The CRIP will rely on the use of ASTM E741 tracer gas or other suitable inleakge testing. RBS does not anticipate that modifications to the CRE will be required to demonstrate compliance with new SRs.
- g. There are no compensatory measures in place at RBS, to demonstrate CRH.
- h. RBSs Updated Safety Analysis Report requires compliance with the GDCs mentioned above, for CRH, except that TS Amendment No. 132 revised the dose limit requirements for the main CR following a design-basis accident from GDC 19 to those in Title 10 of the Code of Federal Regulations, Section 50.67.
P. Hinnenkamp Based on the information provided, the regulatory commitment made in your response letters referenced above, and the above discussion, the NRC staff finds the RBS responses to GL 2003-01 to be complete.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Bhalchandra Vaidya, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458 cc: See next page
ML062410539 OFFICE NRR/LPLIV/PM NRR/LPLIV/LA NRR/SCVB/BC NRR/PGCB/BC NRR/LPLIV/BC NAME BVaidya LFeizollahi RDennig CJackson DTerao DATE 9/11/06 9/11/06 9/18/06 9/18/06 9/18/06 River Bend Station cc:
Winston & Strawn LLP Director - Nuclear Safety 1700 K Street, N.W. Entergy Operations, Inc.
Washington, DC 20006 River Bend Station 5485 US Highway 61N Manager - Licensing St. Francisville, LA 70775 Entergy Operations, Inc.
River Bend Station Vice President - Operations Support 5485 US Highway 61N Entergy Operations, Inc.
St. Francisville, LA 70775 P. O. Box 31995 Jackson, MS 39286-1995 Senior Resident Inspector P. O. Box 1050 Attorney General St. Francisville, LA 70775 State of Louisiana P. O. Box 94095 President of West Feliciana Baton Rouge, LA 70804-9095 Police Jury P. O. Box 1921 Brian Almon St. Francisville, LA 70775 Public Utility Commission William B. Travis Building Regional Administrator, Region IV P. O. Box 13326 U.S. Nuclear Regulatory Commission 1701 North Congress Avenue 611 Ryan Plaza Drive, Suite 400 Austin, Texas 78701-3326 Arlington, TX 76011-8064 Richard Penrod, Senior Environmental Scientist Ms. H. Anne Plettinger State Liaison Officer 3456 Villa Rose Drive Office of Environmental Services Baton Rouge, LA 70806 Northwestern State University Russsell Hall, Room 201 Wise, Carter, Child & Caraway Natchitoches, LA 71497 P. O. Box 651 Jackson, MS 39205 Executive Vice President and Chief Operating Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 General Manager - Plant Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775 May 2006