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MONTHYEARML14225A6742014-08-12012 August 2014 NRR E-mail Capture - Acceptance Review: River Bend Relief Request to Use OMN-17 and for Relief from from OMN-17 Requirements (TACs MF4125 & MF4448) Project stage: Acceptance Review ML15071A1412015-03-23023 March 2015 Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval Project stage: Other ML15114A3512015-05-0404 May 2015 Correction to Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval Project stage: Other 2015-03-23
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Category:Letter
MONTHYEARIR 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 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 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 05000458/20230012023-09-21021 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 IR 05000458/20234032023-09-21021 September 2023 NRC Security Inspection Report 05000458/2023403 (Cover Letter) 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) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined 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-48237, Response to NRC Integrated Inspection Report 05000458/20230012023-05-25025 May 2023 Response to NRC Integrated Inspection Report 05000458/2023001 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23116A2352023-05-0101 May 2023 Integrated Inspection Report 05000458/2023001 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report 2024-01-18
[Table view] Category:Safety Evaluation
MONTHYEARML23270B9932023-09-29029 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 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22265A1802022-09-27027 September 2022 Proposed Alternative to the Requirements of ASME Code of Operation and Maintenance of Nuclear Power Plants for Pressure Isolation Valve Testing Frequency ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines ML21162A2112021-07-0202 July 2021 Issuance of Amendment No. 208 to Adopt Generic Letter 86-10 Standard License Condition for Fire Protection ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20339A5182021-01-0606 January 2021 Issuance of Amendment No. 203 Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20244A0112020-09-28028 September 2020 Issuance of Amendment No. 202 Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- RITSTF Initiative 5b ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19071A2992019-06-19019 June 2019 Issuance of Amendment No. 198 Removal of Table of Contents from Renewed Operating License Technical Specifications ML19066A0082019-04-29029 April 2019 Issuance of Amendment Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18360A0252019-01-17017 January 2019 Redacted Version - Issuance of Amendment No. 195 Correction of a Non-Conservative Technical Specification for Pressure-Temperature Limits ML18345A3422018-12-21021 December 2018 Issuance of Amendment No. 194 Relocation of the Reactor Core Isolation Cooling Injection Point to the a Feedwater Line ML18310A0132018-11-16016 November 2018 Relief from the Requirements of the ASME Code to Use Boiling Water Reactor Vessel Internals Guidelines as an Alternative ML18267A3412018-11-0707 November 2018 Issuance of Amendment No. 193 Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18299A2732018-11-0707 November 2018 Request for Relief from Requirements of Asme Code RBS-ISI-016 from the Requirements of the ASME Code for Pressure Retaining Welds in Control Rod Housings (EPID-L-2018-LLR-0042) ML18212A1512018-07-31031 July 2018 License Renewal Safety Evaluation Report ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML17138A1442017-05-24024 May 2017 Relief from the Requirements of the ASME Code ML16287A5992016-10-27027 October 2016 Issuance of Amendment No. 191, Revise Technical Specifications for Extension of Containment Leakage Tests Frequency ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML15292A5082016-08-11011 August 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16124A6882016-06-21021 June 2016 Issuance of Amendment No. 190 Cyber Security Plan Implementation Schedule ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML15195A0612015-09-21021 September 2015 Issuance of Amendment No. 188 Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation ML15187A1272015-07-30030 July 2015 Issuance of Amendment Application for Changes to Technical Specification 3.8.1, AC Sources-Operating ML15156A8602015-06-30030 June 2015 Safety Evaluation Input - Regarding Application for Change to Technical Specifications 3.8.1, AC Sources - Operating ML15117A5752015-06-0202 June 2015 Issuance of Amendment No. 186 Heavy Load Movement Over Fuel Assemblies ML15114A3512015-05-0404 May 2015 Correction to Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval ML15071A1412015-03-23023 March 2015 Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval ML15071A4752015-03-19019 March 2015 Correction to License Amendment No. 185 Adoption of TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A ML14106A1672015-02-27027 February 2015 Issuance of Amendment No. 185, Adopt TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A Using Consolidated Line Item Improvement Process ML13350A1612015-02-10010 February 2015 Correction to Safety Evaluation Related to Amendment No. 168 Which Modified Techical Specification Surveillance Requirement Frequencies from 18- to 24-Month Fuel Cycle Intervals; Enclosed New SE Section 3.1.7B ML14304A1812014-12-12012 December 2014 Issuance of Amendment No. 184, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML14225A4442014-12-12012 December 2014 Issuance of Amendment No. 183, Revise Technical Specification Surveillance Requirements Related to Ventilation Filter Testing Program for Heaters in Safety-Related Charcoal Filter Trains ML14192A8312014-12-11011 December 2014 Issuance of Amendment No. 182, Revise Technical Specification 2.1.1, Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation ML14183A0862014-11-13013 November 2014 Correction to Relief Request RBS-ISI-019, Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Issued 5/30/14 to Change Fourth 10-Year Inservice Inspection Interval to Third-10-Year Interval 2023-09-29
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4, 2015 Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - CORRECTION TO RELIEF REQUEST NO. VRR-RBS-2014-1 REGARDING THE THIRD 10-YEAR INSERVICE TESTING INTERVAL (TAC NO. MF4125)
Dear Sir or Madam:
By letter dated March 23, 2015 (Agencywide Documents Access and Management System Accession No. ML15071A141 ), the U.S. Nuclear Regulatory Commission (NRC) authorized the use of Relief Request VRR-RBS-2014-1 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1 (RBS), in response to your application dated May 14, 2014, as supplemented by letter dated October 8, 2014. The relief request provides an alternative to certain inservice test (IST) requirements of the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers, Code for Operation and Maintenance of Nuclear Power Plants, for the IST program at RBS, for the remainder of the third 10-year IST program interval.
On April 15, 2015, the RBS staff notified the NRC staff that the safety evaluation for RBS Relief Request VRR-RBS-2014-1 was missing page 4. The missing page is enclosed.
Please insert page 4 of the safety evaluation with the enclosed page. The NRC staff regrets any inconvenience this may have caused.
If you have any questions, please contact me at (301) 415-1445 or by e-mail at Alan.Wang@nrc.gov.
Sincerely, Alanc;:g~Zanager Plant Licensing Branch IV-2 and Decommissioning Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosure:
Safety Evaluation page 4 cc w/encls: Distribution via Listserv
ENCLOSURE SAFETY EVALUATION PAGE 4 FOR RELIEF REQUEST NO. VRR-RBS-2014-1 DATED MARCH 23, 2015 ENTERGY OPERATIONS, INC.
RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458
outage, which includes the removal and replacement of eight SRVs, are conducted under equivalent radiological conditions and with the same personnel requirements.
Based on this data, Entergy has concluded that the expected cumulative radiation exposure to remove and replace a single SRV would be approximately 0.594 person-rem [roentgen equivalent man]. ... Therefore, absent the requested relief, replacement of eight incremental SRVs would result in approximately 4.752 additional person-rem over three refueling outages.
Proposed Alternate and Basis for Use As an alternative to the Code required 5-year test interval per Appendix I, paragraph l-1320(a), RBS proposes that the Class 1 pressure relief valves be tested at least once every three refueling cycles (approximately 6 years/72 months) with a minimum of 20% of the valves tested within any 24-month interval. This 20% would consist of valves that have not been tested during the current 72-month interval, if they exist. The test interval for any individual valve would not exceed 72 months except that a 6-month grace period is allowed to coincide with refueling outages to accommodate extended shutdown periods.
After as-found set pressure testing, the valves shall be disassembled and inspected to verify that parts are free of defects resulting from time-related degradation or service induced wear. As-left set pressure testing shall be performed following maintenance and prior to returning the valve to service.
Each valve shall have been disassembled and inspected prior to the start of the 72 month interval. Disassembly and inspection performed prior to the implementation of Code Case OMN-17 may be used.
The relief valve testing and maintenance cycle at RBS consists of removal of the SRV complement requiring testing and transportation to an off-site test facility.
Upon receipt at the off-site facility the valves are subject to an as-found inspection, seat leakage and set pressure testing. Prior to the return of a complement of SRVs for installation in the plant, the valves are disassembled and inspected to verify that internal surfaces and parts are free from defects or service induced wear prior to the start of the next test interval. During this process, anomalies or damage are identified and resolved. Damaged or worn parts, springs, gaskets and seals are replaced as necessary. The valve seats are lapped, if necessary. Following reassembly, the valve's set pressure is recertified with an acceptance criterion of +/-1 %. This existing process is in accordance with ASME OM Code Case OMN-17, Paragraphs (d) and (e).
RBS has reviewed the as-found set pressure test results for all of the SRVs tested since 2008.... RBS has had only one as-found test failure since 2008 that exceeded the as-found acceptance criteria (+3%, -5%). The one as-found failure was in the negative (or conservative) direction.
RBS submits that the proposed alternative of increasing the test interval for the Class 1 pressure relief valves from 5 years to 3 fuel cycles (approximately 6
If you have any questions, please contact me at (301) 415-1445 or by e-mail at Alan.Wang@nrc.gov.
Sincerely, IRA/
Alan B. Wang, Project Manager Plant Licensing Branch IV-2 and Decommissioning Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosure:
Safety Evaluation page 4 cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-2 r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDssStsb Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-2 Resource RidsNrrLAPBlechman Resource RidsNrrPMRiverBend Resource RidsRgn4MailCenter Resource JBillerbeck, NRR MWaters, EDO RIV ADAMS Accession No.: ML15114A351 OFFICE NRR/DORL/LPL 1-2/PM NRR/DORL/LPL4-2/PM NRR/DORL/LPL4-2/LA NRR/DORL/LPL/LPL4-2BC NRR/DORL/LPL4-2/PM NAME Tlamb AWang PBlechman MKhanna AWang DATE 4/30/15 4/30/15 4/28/15 5/4/15 5/4/15 OFFICIAL AGENCY RECORD