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Category:Acceptance Review Letter
MONTHYEARML20317A2922020-10-15015 October 2020 Entergy Operations, Inc. (River Bend Station, Unit 1) - Acceptance Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML19095B7622019-04-0303 April 2019 Acceptance Review Results for License Amendment Request to Adopt TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio), for Grand Gulf Nuclear Station, Unit 1 and River Bend Station, Unit 1 (EPID L-22019-LLA-0051) ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML17187A0352017-08-0707 August 2017 Determination of Acceptability and Sufficiency for Docketing and Proposed Review Schedule Regarding the Application from Entergy Operations, Inc. for Renewal of the Operating License for River Bend Station, Unit 1 (CAC No. MF9747 and MF9778 ML14071A4542014-03-12012 March 2014 Acceptance Review Email, License Amendment Request to Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML13274A0992013-10-0707 October 2013 Supplemental Information Needed for Acceptance of Licensing Action, Relief Request RBS-R&R-2013-001, Alternative to ASME Code Section III for Postweld Heat Treatment Exemption, Third 10-Year ISI Interval ML13268A4202013-09-25025 September 2013 Acceptance Review Email, License Amendment Request, Changes to Technical Requirements Manual and Updated Safety Analysis Report to Add Permanent Exception Allowing Heavy Load Movement Over Fuel Assemblies ML13211A3902013-07-30030 July 2013 Acceptance Review Email, License Amendment Request to Adopt Revise Shutdown Margin Definition to Address Advanced Fuel Designs ML13204A0062013-07-22022 July 2013 Acceptance Review E-mail, License Amendment Request to Adopt TSTF-423, Revision 0, Technical Specifications End States, NEDC-32988-A Using Consolidated Line Item Improvement Process ML13197A2622013-07-16016 July 2013 Acceptance Review Email, License Amendment Request, Revise Technical Specification 2.1.1., Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation ML12311A1342012-11-0505 November 2012 Entergy Fleet and ISFSI-Acceptance Review Email, Direct License Transfer and Conforming Amendments for Arkansas Nuclear Units 1 & 2; Grand Gulf Unit 1, and Grand Gulf Early Site Permit; Indirect License Transfer for River Bend and Waterford ML12305A0492012-10-29029 October 2012 Acceptance Review Email, Request for Relief RBS-R&R-2011-001 from ASME Code Class 3 Table ND-4622.7(b)-1 Requirements for Post-Weld Heat Treatment Exemption of Valves, Third 10-Year Inservice Inspection Interval ML12299A4352012-10-25025 October 2012 E-mail - Acceptance Review, Request for Relief RBS-ISI-018 for Reactor Pressure Vessel Support Skirt, Second 10-Year Inservice Inspection Interval ML12271A2592012-09-27027 September 2012 Acceptance Review E-mail, Request for Exemption to 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Related to the Definition of Pa ML12201A2662012-07-18018 July 2012 Acceptance Review Email, License Amendment Request, Revise Physical Protection License Condition Related to Cyber Security Plan Implementation ML1203202222012-02-0101 February 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specification (TS) 3.3.8.1, Loss of Power Instrumentation, to Extend Frequency of SR 3.3.8.1.3 and Revise Allowable Values for Certain Functions ML1202607432012-01-26026 January 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Acceptance Review Email, Amendment to Revise Quality Assurance Program Manual and Staff Qualification Technical Speci ML1202502212012-01-25025 January 2012 Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.8.1, AC Sources - Operating for Testing of Automatic Transfer Function to Offsite Power for Division III Bus ML1131202922011-11-0808 November 2011 E-mail River Bend Station - Acceptance Review Email Following Supplement, License Amendment Request, Emergency Plan Change to Relocate Alternate Emergency Operations Facility from 23 to 28 Miles from the Technical Support Center ML1126303632011-09-20020 September 2011 Email, Acceptance Following Supplement - Request to Revise Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, for Main Steam Tunnel Temperature Function Setpoints ML1117303552011-06-22022 June 2011 Acceptance Review Email, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-427, Revision 3, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML1113806002011-05-18018 May 2011 Acceptance Review Email, License Amendment Request, Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML1013901052010-05-24024 May 2010 License Amendment Request for Approval of the Cyber Security Plan ML1006009362010-03-0101 March 2010 Acceptance Review E-mail, License Amendment Request LAR, Change to Emergency Plan Table 13.3-17, Repair and Corrective Actions to Modify Positions of On-Shift Personnel ML0935800722009-12-23023 December 2009 Acceptance Review Email Relief Request RBS-ISI-015, Request for Alternative to ASME Boiler and Pressure Vessel Code, Section XI, Sub Article IWB-2500 ML0935702002009-12-23023 December 2009 Acceptance Review Email, Relief Request RBS-ISI-014, Proposed Alternative to Examination Requirements for Reactor Pressure Vessel Weld. Inspections, for Third 10-Year Inservice Inspection Interval ML0926604942009-09-23023 September 2009 Acceptance Review Email, License Amendment Request, Modify Technical Specification Surveillance Requirement Frequencies from 18- to 24-Month Fuel Cycle Intervals ML0920103642009-07-20020 July 2009 Acceptance Review Email, License Amendment Request, Revise Technical Specification 5.5.6, Inservice Testing Program. ML0917510622009-06-24024 June 2009 Acceptance Review Email, Relief Request Nos. RBS-ISI-007, -008, -009, -010,and -011, Volumetric and Visual Exams, for Second 10-year Inservice Inspection Interval ML0913200592009-05-12012 May 2009 Entergy - Acceptance Review for License Amendment Request (TAC Nos. ME1198 - ME1207) ML0906200672009-03-0303 March 2009 Acceptance Review ML0901300832009-01-13013 January 2009 E-mail Acceptance Review for License Amendment Request ML0820010842008-07-25025 July 2008 River Bend Station, and Waterford Steam Electric Station, Unit 3 - Acceptance Review, Relief Request No. CEP-ISI-011 for 10-Year Inservice Testing Interval (TAC MD8826, MD8827, MD8828, & MD8829) ML0822102662005-08-0808 August 2005 Acceptance Review Email, License Amendment Request, Application for Technical Specification Changes Dated 7/28/08, TSTF-475, Using the Consolidated Line Item Improvement Process (Cliip). (RBG-46690) 2020-10-15
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML23311A4322023-11-0909 November 2023 Notification of NRC Supplemental Inspection (95001) and Request for Information ML23195A0692023-07-24024 July 2023 2023 River Bend Station Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML23116A1462023-04-26026 April 2023 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23081A4602023-03-22022 March 2023 RFI River Bend CETI 2023012 Drr ML23004A0422023-01-0404 January 2023 License Renewal Phase 1 Request for Information ML22354A0812022-12-20020 December 2022 Inservice Inspection Request for Information ML22235A1082022-08-19019 August 2022 RBS Emergency Preparedness (EP) Exercise Inspection October 2022 RFI ML22180A0612022-06-29029 June 2022 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000458/2022010) and Request for Information ML20350B8112020-12-11011 December 2020 2021 RBS PIR Request for Information ML20337A4452020-12-0202 December 2020 Riverbend Station Inservice Inspection Request for Information ML20255A1892020-09-0909 September 2020 Email 09Sept2020 - RFI for RBS EP Exercise Inspection ML20260H4422020-09-0808 September 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Official RAIs for RR Associated with Updating ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20162A1122020-06-10010 June 2020 Notification of Inspection (NRC Inspection Report 05000458/2020003) and Request for Information ML20126G3922020-05-0101 May 2020 Request for Information, May 01, 2020, River Bend Station Special Inspection, NRC Inspection Report 2020050 ML20038A2092020-02-0404 February 2020 05000458 Request for Information IR2020-001 Occupational Radiation Safety ML19102A0722019-04-11011 April 2019 NRR E-mail Capture - River Bend Station, Unit 1 - Final Request for Additional Information Relief Request RBS-ISI-021 ML18250A3112018-09-0404 September 2018 NRR E-mail Capture - Final RAI - RBS EAL Scheme Change LAR (L-2018-LLA-0130) ML18229A0082018-08-16016 August 2018 NRR E-mail Capture - Final Request for Additional Information for P-T Curves - NON-PROPRIETARY Version ML18250A3102018-08-0101 August 2018 NRR E-mail Capture - Draft RAI - RBS EP EAL Scheme Change LAR (L-2018-LLA-0130) ML18151A0822018-05-30030 May 2018 Summary of a Telephone Conference Call Held on May 21, 2018, Between NRC and Entergy Regarding the Need for Additional Information to Support the River Bend Station License Renewal Application RBG-47861, Response to License Renewal Application NRC Request for Additional Information Sets 14,15 and Operating Experience Review Clarification2018-05-29029 May 2018 Response to License Renewal Application NRC Request for Additional Information Sets 14,15 and Operating Experience Review Clarification ML18149A2882018-05-24024 May 2018 NRR E-mail Capture - River Bend Station Request for Additional Information - Reactor Core Isolation Cooling Piping Modification (L-2018-LLA-0029) ML18141A3172018-05-21021 May 2018 OE Draft RAI 3-0-5 Rogers ML18141A4882018-05-21021 May 2018 Draft Response (RAI 3.6.2.2.2.2-1a) from LRA Review Revised After the May 17, 2018 Call ML18131A2412018-05-11011 May 2018 RBS 012 Item 158a Response (RAI 3.2.2.3.2-1a) Revised - Received on 05/10/2018 ML18124A0092018-05-0303 May 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 15 ML18122A2312018-05-0202 May 2018 Draft Response to NRC Request for Additional Information (RAI) B.1.40-5 Service Water Integrity Generated from Staffs Review on the River Bend Station, Unit 1 License Renewal Application ML18122A1262018-05-0202 May 2018 RAI B.1.17-1 Revised - w- header-footer-watermark ML18121A3022018-05-0101 May 2018 Draft Response to NRC Request for Additional Information (RAI) 4.6-2a Generated from Staff'S Review on the River Bend License Renewal Application ML18121A0292018-04-30030 April 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 14 ML18115A1632018-04-25025 April 2018 Draft Response on RBS LRA RAI B.1.21-2 Flow Accelerated Corrosion ML18113A3322018-04-23023 April 2018 035 RB Buried Pipe 3rd Round RAI - Allik Holston ML18103A0152018-04-12012 April 2018 NRR E-mail Capture - Summary of Public Telephone Conference Call Held on March 27, 2018, Between the U.S. Nuclear Regulatory Commission and Entergy and Final Requests for Additional Information for the Safety Review of the River Bend Statio ML18073A0912018-03-14014 March 2018 NRC and Energy Public Meeting on Fatigue Analysis Related to River Bend License Renewal ML18068A1872018-03-0909 March 2018 Revision of Final Request for Additional Information (RAI 2.3.3.17-2) for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 11 RBG-47834, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 92018-03-0808 March 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 9 ML18065A2132018-03-0606 March 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 12 ML18060A1532018-03-0101 March 2018 NRR E-mail Capture - River Bend Station: Request for Additional Information Concerning New Technical Specification for Control Building Air Conditioning (L-2017-LLA-0291) ML18058A0572018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update) ML18043A3512018-02-12012 February 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 11 ML18043A0082018-02-0808 February 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 10 ML18038B4702018-02-0707 February 2018 NRR E-mail Capture - Fyi_River Bend Station RAIs Set 9 ML18022A9412018-01-22022 January 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 8 ML18011A0462018-01-10010 January 2018 Notification of Cyber Security Inspection (NRC Inspection Report 05000458/2018406) and Request for Information IR 05000458/20184062018-01-10010 January 2018 River Bend Station - Notification of Cyber Security Inspection (NRC Inspection Report 05000458/2018406) and Request for Information ML18009A9092018-01-0909 January 2018 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 7 ML17361A3962017-12-27027 December 2017 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 6 ML17347B4242017-12-13013 December 2017 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 4 ML17347B4322017-12-13013 December 2017 Final Requests for Additional Information for the Safety Review of the River Bend Station License Renewal Application (CAC No. MF9757) - Set 5 2023-07-24
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 7, 2013 Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - UNACCEPTABLE WITH OPPORTUNITY TO SUPPLEMENT INFORMATION NEEDED FOR ACCEPTANCE OF REQUEST FOR RELIEF (TAC NO. MF2733)
Dear Sir or Madam:
By letter dated August 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13239A072), Entergy Operations, Inc. (Entergy, the licensee),
submitted a Request for Relief (RR) for the River Bend Station, Unit 1. The RR was from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III, Table ND-4622.7. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Entergy has proposed this RR pursuant to Section 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR), which states the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that Entergy supplement the application to address the information requested in the enclosure by October 30,2013. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staffs detailed technical review by separate correspondence.
-2 The information requested and associated time frame in this letter were discussed with Mr. Barry Burmeister of your staff on September 30,2013.
If you have any questions, please contact me at (301) 415-1445.
Sincerely, AI~,~e~
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosure:
Supplement Information Needed for Acceptance of Request for Relief cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUEST FOR RELIEF OFFICE OF NUCLEAR REACTOR REGULATION RIVER BEND STATION, UNIT 1 DOCKET NO. 50-416 By letter dated August 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13239A072), Entergy Operations, Inc. (Entergy, the licensee),
submitted a Request for Relief (RR) for the River Bend Station, Unit 1 (RBS). The RR was from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section III, Table ND-4622.7. As part of the acceptance review process, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the information delineated below is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed request for relief in terms of regulatory requirements and the protection of public health and safety and the environment.
- 1. In the first paragraph of the letter proposing the alternative to the Code Requirements, the licensee requests relief from ASME Code,Section III requirements under Title 10 of the Code of Federal Regulations (CFR) Section 50.55a, "Codes and Standards,"
paragraph (a)(3)(i).Section III of the ASME Code is incorporated into regulation in 10 CFR 50.55a, paragraph (b) and by reference into paragraphs (c), (d), and (e).
However, paragraphs (c), (d), and (e) only apply to plants whose application for a construction permit is docketed after May 14, 1984, which does not apply to RBS (construction permit issued March 25, 1977). As such, since Section III of the ASME Code is incorporated into 10 CFR 50.55a(b) for RBS and 10 CFR 50.55a(a)(3) does not include paragraph (b) within the requirements for which alternatives may be authorized, the NRC lacks the regulatory authority to authorize the alternative to the ASME Code requirements proposed by RBS.
The NRC staff notes that ASME Code, Section XIIWA-4221 (b)(1) states, 'When replacing an existing item, the new item shall meet the Construction Code to which the original item was constructed." The regulations in 10 CFR 50.55a(g)(4) specify that ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements set forth in the ASME Code,Section XI, except the design and access provisions and the pre-service examination requirements. Given that Section XI of the ASME Code, including repair and replacement activities, is required by 10 CFR 50.55a(g)(4), 10 CFR 50.55a(a)(3) authorizes NRC to approve alternatives to the Code, provided requirements for alternatives are met. Therefore, the NRC staff believes that the licensee's objectives would be met and that the NRC staff would have authority to authorize a proposal by Entergy for an alternative to ASME Code,Section XI, IWA 4221.
Enclosure
-2
- 2. In the first paragraph of the letter proposing the alternative to the Code requirements, the licensee indicates that pursuant to 10 CFR 50.55a(3)(i), the proposed alternatives would provide an acceptable level of quality and safety. The NRC staff finds that this determination may not be applicable. As part of the NRC staff's initial review of the documentation for the proposed alternative, the NRC staff notes some degradation of material properties associated with failure to perform the Code-required preheat. Given that the current Code requirements incorporated by reference in 10 CFR 50.55a constitute the minimum acceptable safety standard for general applicability, the NRC staff does not currently believe that the proposed alternative could be authorized under paragraph 10 CFR 50.55a(3)(i).
The NRC staff notes that the removal of the valves from service does constitute a hardship, albeit a minor one, associated with the effort and risks associated with the removal of the current valves. While the NRC staff has not reviewed the data supplied in sufficient detail to make any final determination, it appears to the NRC staff that it would be more appropriate to review this proposed alternative to the requirements of the ASME Code under 10 CFR 50.55a(a)(3)(ii) which states that compliance with the specified requirements of Section 50.55a would result in hardship or unusual di'fficulty without a compensating increase in the level of quality or safety.
- 2 The information requested and associated time frame in this letter were discussed with Mr. Barry Burmeister of your staff on September 30, 2013 If you have any questions, please contact me at (301) 415-1445.
Sincerely, IRA!
Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosure:
Supplement Information Needed for Acceptance of Request for Relief cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4 Reading File RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLA~IBurkhardt Resource RidsNrrPMRiverBend Resource RidsRgn4MailCenter Resource ADAMS Accession No. ML13274A099 NRRlDORL/LPL4/PM NRRlDORL/LPL4/PM NRRlDORL/LPL4/LA NRR/DORLlLPL4/BC NRRlDORLlLPL4/P MBartlett AWang JBurkhardt MMarkley AWang 10/2/13 10/2/13 10/2/13 10/4/13 10/7/13 OFFICIAL RECORD COpy