Letter Sequence Response to RAI |
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EPID:L-2018-LLA-0083, License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4.11-1 Minimum Temperature Required Vs. RCS Pressure by Replacing with 54 Effective Full Power Years (EFPY) Curves (Approved, Closed) |
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MONTHYEARRBG-47824, License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4.11-1 Minimum Temperature Required Vs. RCS Pressure by Replacing with 54 Effective Full Power Years (EFPY) Curves2018-04-0202 April 2018 License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4.11-1 Minimum Temperature Required Vs. RCS Pressure by Replacing with 54 Effective Full Power Years (EFPY) Curves Project stage: Request RBG-47890, Supplemental Information Related to License Renewal Application NRC Request for Additional Information Set 10 (4.2.1-1, 4.7.3-1 and 4.7.3-2)2018-08-13013 August 2018 Supplemental Information Related to License Renewal Application NRC Request for Additional Information Set 10 (4.2.1-1, 4.7.3-1 and 4.7.3-2) Project stage: Supplement RBG-47903, Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power2018-10-0404 October 2018 Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power Project stage: Response to RAI ML18348A3412019-01-0202 January 2019 Request for Withholding Information from Public Disclosure, Two Affidavits Dated November 10 and November 17, 2017, by GE-Hitachi Nuclear Energy Americas LLC and Electric Power Research Company Project stage: Withholding Request Acceptance ML18360A0252019-01-17017 January 2019 Redacted Version - Issuance of Amendment No. 195 Correction of a Non-Conservative Technical Specification for Pressure-Temperature Limits Project stage: Approval 2018-08-13
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Category:Letter type:RBG
MONTHYEARRBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024 Notification of Readiness for Supplemental Inspection 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 RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report 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 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 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 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 RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 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 RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 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 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RBG-48221, 2022 Annual Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Radiological Environmental Operating Report RBG-48142, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-27027 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-27027 February 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RBG-48198, Report of Changes and Errors to 10CFR50.462022-09-22022 September 2022 Report of Changes and Errors to 10CFR50.46 RBG-48187, Notification of Spent Fuel Cask Use2022-08-15015 August 2022 Notification of Spent Fuel Cask Use RBG-48184, Notification of Spent Fuel Cask Use2022-07-18018 July 2022 Notification of Spent Fuel Cask Use RBG-48178, Notification of Spent Fuel Cask Use2022-06-29029 June 2022 Notification of Spent Fuel Cask Use RBG-48166, Supplement to Special Report for Tritium Discovered Onsite2022-05-12012 May 2022 Supplement to Special Report for Tritium Discovered Onsite RBG-48149, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report RBG-48148, 2021 Annual Radiological Environmental Operating Report2022-04-27027 April 2022 2021 Annual Radiological Environmental Operating Report RBG-48134, Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency2021-11-29029 November 2021 Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency RBG-48136, Additional Information for the 2020 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2020 Annual Radioactive Effluent Release Report RBG-48137, Additional Information for the 2019 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2019 Annual Radioactive Effluent Release Report RBG-48128, Reply to a Notice of Violation; EA-21-017, 030 and 0502021-10-29029 October 2021 Reply to a Notice of Violation; EA-21-017, 030 and 050 RBG-48129, Payment of a Civil Penalty2021-10-21021 October 2021 Payment of a Civil Penalty RBG-48112, Report of Changes and Errors to 10CFR50.462021-09-16016 September 2021 Report of Changes and Errors to 10CFR50.46 RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 12021-08-19019 August 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 1 RBG-48104, Fitness for Duty Blind Quality Assurance Specimen Testing Error2021-06-30030 June 2021 Fitness for Duty Blind Quality Assurance Specimen Testing Error RBG-48099, Submittal of Owner'S Activity Report Form for Cycle 212021-06-16016 June 2021 Submittal of Owner'S Activity Report Form for Cycle 21 RBG-48083, Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials2021-06-15015 June 2021 Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials RBG-48093, Corrected 2020 Annual Radiological Environmental Operating Report2021-05-20020 May 2021 Corrected 2020 Annual Radiological Environmental Operating Report RBG-48082, 2020 Annual Radiological Environmental Operating Report2021-04-20020 April 2021 2020 Annual Radiological Environmental Operating Report RBG-48081, 2020 Annual Radioactive Effluent Release Report2021-04-20020 April 2021 2020 Annual Radioactive Effluent Release Report RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 02021-03-14014 March 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 0 RBG-48075, Notification of Deviation from BWRVIP Guidelines2021-02-24024 February 2021 Notification of Deviation from BWRVIP Guidelines RBG-48074, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-22022 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 RBG-48061, One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-12-0303 December 2020 One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency RBG-48054, Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program2020-11-0202 November 2020 Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program RBG-48049, Reply to a Notice of Violation; EA-20-0582020-10-26026 October 2020 Reply to a Notice of Violation; EA-20-058 RBG-48038, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic2020-10-0606 October 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic RBG-48042, Submittal of Rev. 48 to Emergency Plan2020-09-22022 September 2020 Submittal of Rev. 48 to Emergency Plan RBG-48039, Report of Changes and Errors to 10CFR50.462020-09-16016 September 2020 Report of Changes and Errors to 10CFR50.46 RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-0404 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements 2024-07-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24101A3882024-04-10010 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 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 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) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary RBG-47919, Response to Request for Additional Information for License Amendment Request, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-12-17017 December 2018 Response to Request for Additional Information for License Amendment Request, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) RBG-47906, Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-18018 October 2018 Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 ML18283A0822018-10-0909 October 2018 Supplemental Information Related to License Renewal Application NRC Request for Additional Information to Clarify Response to RAI 2.3.3.16-1 Set 11 RBG-47903, Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power2018-10-0404 October 2018 Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power RBG-47895, Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)2018-08-15015 August 2018 Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) RBG-47876, Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)2018-06-21021 June 2018 Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) ML18143B6862018-05-24024 May 2018 RBS Draft Response (Operating Experience) to Draft RAI 3-0-5 Received 052318 ML18136A7052018-05-16016 May 2018 RBS Draft Response to LRA Review RAI 4.7.3-1a Fluence Effects for Rv Internals ML18136A8212018-05-16016 May 2018 Draft Response to RAI 3.6.2.2.2.2-1a High Voltage Insulators - RBS LRA Review RBG-47867, Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement2018-05-16016 May 2018 Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement RBG-47852, Response to License Renewal Application NRC Request for Additional Information Set 132018-05-10010 May 2018 Response to License Renewal Application NRC Request for Additional Information Set 13 RBG-47860, Response to License Renewal Application NRC Request for Supplemental Information2018-05-10010 May 2018 Response to License Renewal Application NRC Request for Supplemental Information ML18121A2942018-05-0101 May 2018 Draft Response to NRC Request for Additional Information (RAI) 4.6-1a Generated from Staffs Review on the River Bend License Renewal Application RBG-47859, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-04-26026 April 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RBG-47853, Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-12018-04-26026 April 2018 Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-1 ML18115A0722018-04-25025 April 2018 Draft Response on RAI B.1.25-1(Internal Surfaces in Miscellaneous Piping and Ducting Components) ML18115A0612018-04-25025 April 2018 Draft Response on RAI B1.21-1 Flow Accelerated Corrosion RBG-47850, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-04-0404 April 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement RBG-47846, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 122018-04-0303 April 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 12 RBG-47851, Response to License Amendment Request (LAR) Technical Specification 3.7.7, Control Building Air Conditioning (Cbac) System NRC Request for Additional Information (RAI)2018-03-28028 March 2018 Response to License Amendment Request (LAR) Technical Specification 3.7.7, Control Building Air Conditioning (Cbac) System NRC Request for Additional Information (RAI) RBG-47849, Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement2018-03-27027 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement RBG-47835, Submittal of Response to License Renewal Application NRC Request for Additional Information Set 102018-03-26026 March 2018 Submittal of Response to License Renewal Application NRC Request for Additional Information Set 10 RBG-47842, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-03-22022 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement ML18059A8222018-03-0808 March 2018 Summary of Public Telephone Conference Call Held on February 27, 2018 Between the U.S. Nuclear Regulatory Commission and Entergy Regarding Requests for Additional Information Pertaining to the River Bend Station Unit 1 RBG-47819, Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a2018-02-26026 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a RBG-47828, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 82018-02-20020 February 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 8 RBG-47818, Response to License Renewal Application NRC Request for Additional Information - Set 72018-02-0707 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 RBG-47813, Response to License Renewal Application (LRA) NRC Request for Additional Information Set 52018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information Set 5 RBG-47822, Response to Request for Additional Information Re License Renewal Application Concerning Severe Accident Mitigation Alternatives2018-01-24024 January 2018 Response to Request for Additional Information Re License Renewal Application Concerning Severe Accident Mitigation Alternatives RBG-47812, Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 42018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 4 RBG-47807, Response to License Renewal Application NRC Requests for Additional Information Set 32018-01-10010 January 2018 Response to License Renewal Application NRC Requests for Additional Information Set 3 RBG-47805, Response to License Renewal Application NRC Request for Additional Information Set 22017-12-12012 December 2017 Response to License Renewal Application NRC Request for Additional Information Set 2 RBG-47803, Response to License Renewal Application (LRA) NRC Request for Additional Information, Severe Accident Mitigation Alternatives2017-12-0505 December 2017 Response to License Renewal Application (LRA) NRC Request for Additional Information, Severe Accident Mitigation Alternatives ML17353A0492017-12-0505 December 2017 Response to License Renewal Application NRC Request for Additional Information Re Environmental RBG-47709, Response to Request for Additional Information on Nineteenth Fuel Cycle Core Operating Limits Report2016-09-12012 September 2016 Response to Request for Additional Information on Nineteenth Fuel Cycle Core Operating Limits Report RBG-47695, Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies2016-07-27027 July 2016 Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies RBG-47675, Response to NRC Request for Additional Information - RBS LAR to Extend Type a and Type C Test Frequencies2016-04-19019 April 2016 Response to NRC Request for Additional Information - RBS LAR to Extend Type a and Type C Test Frequencies ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, RBG-47634, High-frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10CER50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi..2015-12-0808 December 2015 High-frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10CER50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.. CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 RBG-47582, Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating2015-07-16016 July 2015 Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating 2024-04-10
[Table view] |
Text
Proprietary Information - Withhold From Public Disclosure Under 10 CFR 2.390 The Balance Of This Letter May Be Considered Non-Proprietary Upon Removal Of Enclosure 3
~.
Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61N St. Francisville, LA 70775 Tel 225*381*4374 William F, Maguire Site Vice President River Bend Station RBG-47903 October 4, 2018 Attn: Document Control Desk U,S, Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
Response to License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 "Minimum Temperature Required vs , RCS Pressure" by Replacing with 54 Effective Full Power Years (EFPY) Curves NRC Request for Additional Information (RAI)
River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47
References:
- 1) Entergy Letter: License Amendment Request (LAR) (RBG-47824 dated April 2, 2018) (ADAMS Accession No. ML18092B187)
- 2) NRC email: River Bend Station , Unit 1, Request for Additional Information dated August 16, 2018 (ADAMS Accession No. ML18229A008)
Dear Sir or Madam:
In Reference 1, Entergy Operations, Inc (Entergy) submitted a request for the review and approval of the corrections to Technical Specification Figure 3.4.11 -1 "Minimum Temperature Required vs, RCS Pressure" by Replacing with 54 Effective Full Power Years (EFPY) Curves, In an email dated August 16, 2018, (Reference 2) the NRC staff made a request for additional information needed to complete the license amendment request. Enclosure 1 contains the non-proprietary responses to the RAls, Enclosure 3 is Proprietary in its entirety, as it contains information in RAI responses 3 and 4 that is proprietary to Global Nuclear Fuel - Americas (GNF), Attachment 1 contains the Proprietary Information Affidavit from GNF, The purpose of this attachment is to withhold the proprietary information contained in RAI responses 3 and 4 in Enclosure 3, The Affidavit, signed by as owner of the information, set forth the basis for which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390 of the Commission's regulations, Accordingly, it is
RBG-47903 Page 2 of 2 respectfully requested that the information proprietary to GNF be withheld from public disclosure in accordance with 10 CFR 2.3.90.
In addition to the RAI responses Enclosure 2 contains a supplement to RBG-47824 Attachment 2: Technical Specification (TS) Pages - Clean. The brackets surrounding 'Without Uncertainty for Instrumentation Error" at the bottom of the page have been removed to clarify that the information is not proprietary.
This letter does not contain any new commitments.
If you require additional information , please contact Mr. Tim Schenk at (225) 381-4177 or tschenk@entergy.com.
In accordance with 10 CFR 50.91 (b)(1) , Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the designated State Official.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 4, 2018.
Sincerely, WFM/bj : Responses to Request for Additional Information (Non-Proprietary) : Global Nuclear Fuel - Americas 10 CFR 2.390 Affidavit : Updated RBG-47824 Attachment 2 Technical Specification (TS) Pages - Clean : Responses to Request for Additional Information (Proprietary) cc: U.S. Nuclear Regulatory Commission Region IV U.S. Nuclear Regulatory Commission NRC Senior Resident Inspector - River Bend Station LA Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Public Utility Commission of Texas
RBG-47903 Page 1 of 5 RBG-47903 Enclosure 1 Responses to Request for Additional Information (Non-Proprietary)
RBG-47903 Page 2 of 5 REQUEST FOR ADDITIONAL INFORMATION T5 Figure 3.4.11-1 PIT Curves RIVER BEND STATION, UNIT 1 DOCKET NO.: 50-458
RAI 1
Description:
The staff is aware that instruments used to monitor reactor coolant system (RCS) pressures and temperatures during TS required P-T monitoring may include some degree of uncertainty in accuracy of pressure or temperature readings taken by the instruments. The updated P-T limit curves proposed in Attachment 2 of the LAR and the contents of NEDC-33882P, Rev. 1, both indicate that the P-T limit curves for 54 EFPY were developed ((
)). Clarify where the treatment or assessment of P-T
(( )) will be accounted for if they have not been accounted for in the calculational bases for the proposed P-T limits in Attachment 2 of the LAR.
RAI 1 Response:
Instrument Uncertainty was not included in the limits listed in Attachment 2 of the LAR. Instrument Uncertainty will be applied in RBS procedure STP-050-0700, RCS Pressure/Temperature Limits Verification . Changes to STP-050-0700 are being made following the Entergy procedure change process and are being tracked in the Paperless Condition Reporting System (PCRS) by LR-LAR-2018-00129.
RAI 2
Description:
The current SR in TS Section 3.4.11 .1 requires the licensee to perform P-T monitoring during non-nuclear heatup and cooldown operations (Service Level B conditions) and during inservice leak rate or hydrostatic pressure testing (Service Leve A conditions) of the RCS, and to verify that the "RCS pressure and temperature are within the limits of Figure 3.4.11-1 .... " If this LAR is approved by the staff, TS Figure 3.4.11 -1 will be amended to include P-T limit curves for Service Level A and B loading conditions of both the beltline and bottom head regions of the RPV. Clarify how Entergy will be capable of distinguishing the specific types of P-T monitoring activities to be performed against the P-T limits for the RPV bottom head from those for the RPV beltline region under these loading conditions. Clarify whether the SR in TS Section 3.4.11.1 needs to be amended (as part of this LAR) in order to better define specific SR P-T monitoring requirements for the RPV bottom head and for the RPV beltline region under Service Level A and B loading conditions .
RAI 2 Response:
STP-050-0700, RCS Pressure/Temperature Limits Verification, is the RBS procedure utilized to satisfy Technical Specification (TS) Surveillance Requirements associated with TS Figure 3.4.11-1 ,
Minimum Temperature Required vs . RCS Pressure. This current revision of this procedure only utilizes temperatures at the beltline region. With implementation of the proposed change to include both beltline and bottom head curves , this procedure will be revised to require the performer to verify the corresponding temperature is being maintained above the minimum metal temperature for its corresponding curve in the new Figure 3.4.11-1 . The SR in TS Section 3.4.11.1 will not need to be amended to better define specific SR P-T monitoring requirements for the RPV bottom head and
RBG-47903 Page 3 of 5 for the RPV beltline region under Service Level A and B loading conditions. Changes to STP-050-0700 are being made following the Entergy procedure change process and are being tracked in PCRS by LR-LAR-2018-00129.
RAI 3
Description:
In NEDC-33882P, Rev. 1, GEH adjusted the ((
)), even though this type basis was defined and performed in GEH Proprietary Report No. NEDC-33178P-A, Revision 1 only for the generic stress assessment of the (( )) Explain your basis for applying (( )) in the sample, plant-specific stress analysis (( )). If there is a valid technical basis for performing ((
)) for the (( )), provide a sample ((
)) and the (( )) over the entire range of pressures evaluated in the stress and P-T limit analysis for the component (i.e., 0 psi to 1400 psi) .
RAI 3 Response:
The (( )) for the (( )) is based on the assumptions and recommendation of Welding Research Council (WRC) Bulletin 175 (Reference 3-1) that provides the technical background for Appendix G (Fracture Toughness Criteria for Protection Against Failure) of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI. WRC Bulletin 175 proposes the methodology for how to estimate the stresses when the secondary and peak stresses calculated on an elastic basis exceed the yield stress. This is to consider the (( )) However, for the application to the (( )) the (( )) is not applied to ((
)) The technical detail for this method is described in Section 5.C.3 of WRC Bulletin 175. The applicability of this procedure to the pressure vessel was studied in a Pressure Vessels & Piping (PVP) conference paper (Reference 3-2).
As a sample calculation , the (( )) under a pressure of 1,070 psi is determined as follows:
(( )) (Equation 1)
Where ((
))
Applying the above data into Equation 1,
((
))
RBG*47903 Page 4 of 5
(( )) over the entire range of pressures are shown in Table 3-1.
Table 3*1: (( ))
Pressure (psig)
((
0 100 200 300 400 500 600 700 BOO 900 1000 1100 1200 1300 1400 ))
Note:
- 1. (( ))
RAI 4
Description:
In the LAR, the licensee developed proposed P-T limit curves for the RPV bottom head region using the generic methodology for (( )) in GEH Proprietary Report No. NEDC-3317BP-A, Revision 1. The staff-approved generic methodology in NEDC-3317BP-A, Revision 1, states that it is valid to use the ((
)) Provide the plant-specific (( )) for the design of the RPV bottom head at River Bend Station so that the staff can confirm that the
(( ))
RAI 4 Response:
The plant-specific bottom head dimensions are (( )) and ((
)) (Reference 4-1), resulting in:
Plant-specific: (( ))
RBG-47903 Page 5 of 5 Because the ((
)) for the reactor pressure vessel (RPV) bottom head stress assessment.
References:
3-1 Welding Research Council Bulletin 175, "PVRC Recommendations on Toughness Requirements for Ferritic Materials, " August 1972.
3-2 Mehta, H.S. , Stevens, G.L., Sommerville, D.V. , Benson , M. , Kirk, M., Griesbach , T.J. , and Kusnick, J. , "Treatment of Stresses Exceeding Material Yield Strength in ASME Code Section XI Appendix G Fracture Toughness Evaluations," 2014 ASME Pressure Vessels and Piping Conference, PVP2014-28397, July 2014.
4-1 Chicago Bridge & Iron Nuclear Company, Drawing No. VPF #3614-460, Revision 5, "Bottom Head Plate Details," September 1975.
RSG-47903 Page 1 of 4 RBG-47903 Attachment 1 Global Nuclear Fuel - Americas 10 CFR 2.390 Affidavit
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Lisa K. Schichlein, state as follows :
(1) I am a Senior Project Manager, NPP/Services Licensing, Regulatory Affairs, GE-Hitachi Nuclear Energy Americas LLC (GEH), and have been delegated the function of reviewing the infonnation described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The infonnation sought to be withheld is contained in Enclosure 1 of GEH letter DOC-0010-1238-02, "GEH Responses to Entergy River Bend Station Pressure-Temperature Limits License Amendment Request RATs 3 and 4," dated September 19, 2018. The GEH proprietary infonnation in Enclosure 1, which is entitled "GEH Responses toRAls 3 and 4 in Support of the River Bend Station Pressure-Temperature Limits LAR," is identified by a dotted underline inside double square brackets. ((D.:tj~__~~nt~n9_~..i.~_M_~~w.tlp.l~~~~!J] In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, wh ich provides the basis for the proprietary detennination .
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom oflnformationA ct ("FOIA"), 5 U.S.C. Sec. 552(b)(4), and the Trade Secrets Act, 18 U.S.C.
Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those tenns for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).
(4) The infonnation sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of infonnation that fit into the definition of proprietary infonnation are:
- a. Infonnation that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEHls competitors without license from GEH constitutes a competitive economic advantage over other companies;
- b. Infonnation that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Infonnation that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH;
- d. Infonnation that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.
Affidavit for DOC-DO 10-1 238-02 Page 1 of3
GE-Hitachi Nuclear Energy Americas LLC (5) To address 10 CFR 2.390(b)(4), the infonnation sought to be withheld is being submitted to NRC in confidence. The infonnation is of a sort customarily held in confidence by GEH, and is in fact so held. The infonnation sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary or confidentiality agreements that provide for maintaining the infonnation in confidence. The initial designation of this infonnation as proprietary infonnation, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the infonnation in relation to industry knowledge, or who is the person most likely to be subject to the tenns under which it was licensed to GEH.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and detennination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the infonnation, and then only in accordance with appropriate regulatory provisions or proprietary or confidentiality agreements.
(8) The infonnation identified in paragraph (2), above, is classified as proprietary because it contains details on the GEH fluence methodology for boiling water reactors (BWRs).
Development of these methods, techniques, and infonnation and their application for the design, modification, and analyses methodologies and processes was achieved at a significant cost to GEH.
The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience databases that constitute a major GEH asset.
(9) Public disclosure of the infonnation sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The infonnation is part of GER's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to detennine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to Affidavit for DOC-OO 10-1238-02 Page 2 of3
GE-Hitachi Nuclear Energy Americas LLC quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this 19th day of September 2018.
Lisa K. Schichlein Senior Project Manager, NPP/Services Licensing Regulatory Affairs GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Road Wilmington, NC 28401 Lisa.Schichlein@ge.com Affidavit for DOC-OO 10-123 8-02 Page 3 on
RBG-47903 Page 1 of 2 RBG-47903 Enclosure 2 Updated RBG-47824 Attachment 2 Technical Specification (TS) Pages - Clean
Res PIT Limits 3.4.11 Curve A Curve B Curve C 1400 BOTTOM !-fAD (a...RVE A)
Iii
!
ACCEPTABLE REGION OF OPERATION IS 1200 TO "THE RIGHT OF BOTTCt.II "THE
!-fAD (a...RVEB) l 1 APPLICABLE CURVE
, : J N.~ I 1100
-.s.
I i
II m 1000 ,
111 , -l
!1 ,
~ J J I
900 , HEA TUP/COOLDOWN
- r: !
)
RA TE OF COOLANT I
~ .!: 20"F/HR FOR CURVE A.
g V
.!: 100*F/HR FOR I
800 at CURVES B&C i :' I 1 /
~
II 700 G: i
~
,II
! A, B, C lIMmNG CURVES 600 J
G:
l:
I A - PRESSURE TEST WITH VI
~ FUEL I "THE VESS EL i 500 eom::tVI
!-fAD I
- J sa"F i B - NON-NUCLEAR
~ 400 ! HEATUP/COOLDOWN
~ ! CORE NOT CRITICAL
- I,,
/ 312~ 1 C -NUCLEAR V "'"V
~ 300 HEA TUP/COOLDOWN CORE CRITICAL 200 ",..
~
aRlE C 100 FlAt-.GE
~
sa"F 0
o 25 50 75 100 125 150 175 200 225 250 275 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)
Figure 3.4.11-1 (page 1 of 1)
Minimum Temperature Required vs. ReS Pressure Without Uncertainty for Instrumentation Error RIVER BEND 3.4-32 Amendment No