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| {{#Wiki_filter:' EnteigyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61 NSt. Francisville, LA 70775December 8, 2015RBG-47634U.S. Nuclear Regulatory CommissionATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852 | | {{#Wiki_filter:' EnteigyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61 NSt. Francisville, LA 70775December 8, 2015RBG-47634 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852 |
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| ==Subject:== | | ==Subject:== |
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| ==References:== | | ==References:== |
| High-frequency SUpplement to Seismic Hazard Screening Report, Response NRCRequest for Information Pursuant to 10 CER 50.54(f) Regarding Recommendation 2.1 ofthe Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentRiver Bend Station -Unit 1Docket No. 50-458License No. NPF-471. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-TermTask Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12,"20112, ADAMS Accession Number M/L12053A340*2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "SeismicEvaluation GuidanCe: Augmented Approach for the Resolution of Fukushima Near-TermTask Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMSAccession Number ML 131 06A3313. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287),dated November 27, 2012, ADAMS Accession Number ML12333A168 andML1 2333A1 704. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report1025287, "Seismic Evaluation Guidance", dated February 15, 2013, ADAMS AccessionNumber ML1 231 9A0745. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and ScreeningReport (ML 14091A429)6. NRC Letter, Screening and Prioritization Results regarding information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) regarding Seismic HazardReevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews ofInsights from the Fukushima Dai-ichi accident, dated May 9, 2014, (ML14111A147)7. NEI Letter, Request for NRC Endorsement of High Frequency Program: ApplicationGuidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), datedJuly 30, 20158. NRC letter dated September 15, 2015, Endorsement of Electric Power ResearchInstitute Final Draft Report 3002004396, "High Frequency Program: Application GuidanceFor Functional Confirmation And Fragility"' (ML1 521 8A569) / p RBG-47634December 8, 2015Page 2 of 3 | | |
| | High-frequency SUpplement to Seismic Hazard Screening Report, Response NRCRequest for Information Pursuant to 10 CER 50.54(f) |
| | Regarding Recommendation 2.1 ofthe Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentRiver Bend Station -Unit 1Docket No. 50-458License No. NPF-471. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f) |
| | Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi |
| | : Accident, dated March 12,"20112, ADAMS Accession Number M/L12053A340 |
| | *2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "SeismicEvaluation GuidanCe: |
| | Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," |
| | as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMSAccession Number ML 131 06A3313. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287), |
| | dated November 27, 2012, ADAMS Accession Number ML12333A168 andML1 2333A1 704. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report1025287, "Seismic Evaluation Guidance", |
| | dated February 15, 2013, ADAMS Accession Number ML1 231 9A0745. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and Screening Report (ML 14091A429) |
| | : 6. NRC Letter, Screening and Prioritization Results regarding information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) regarding Seismic HazardReevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews ofInsights from the Fukushima Dai-ichi |
| | : accident, dated May 9, 2014, (ML14111A147) |
| | : 7. NEI Letter, Request for NRC Endorsement of High Frequency Program: |
| | Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), |
| | datedJuly 30, 20158. NRC letter dated September 15, 2015, Endorsement of Electric Power ResearchInstitute Final Draft Report 3002004396, "High Frequency Program: |
| | Application GuidanceFor Functional Confirmation And Fragility"' |
| | (ML1 521 8A569) / p RBG-47634 December 8, 2015Page 2 of 3 |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 yearsfrom the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRCletter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening andprioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference4). In accordance with the screening, prioritization, and implementation details report (SPID) andaugmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used todetermine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluatedhorizontal ground motion response spectrum (GMRS) at the control point elevation is compared to theexisting safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required toperform a high-frequency confirmation. As noted in the May 9, 2014 letter, River Bend Station is toconduct a limited scope high-frequency confirmation.Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations willrequire additional development of the assessment process. By Reference 7, Nuclear Energy Institute(NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRCreview and endorsement. NRC endorsement was provided by Reference 8.The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of thecontrol point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less thanor equal to 0.2g). Therefore, no additional evaluation is necessary. The attachment to this letter providesthe SSE (or IHS) and GMRS information from Reference 5.This transmittal completes commitments from Reference 4. This letter contains no new regulatorycommitments. Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177.I declare Under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2015.Sincerely,Sergio VazquezDirector -Engineering | | On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f) |
| | (Reference |
| | : 1) to all power reactor licensees. |
| | The required response section of Enclosure 1indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 yearsfrom the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRCletter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening andprioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) andaugmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used todetermine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to theexisting safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required toperform a high-frequency confirmation. |
| | As noted in the May 9, 2014 letter, River Bend Station is toconduct a limited scope high-frequency confirmation. |
| | Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations willrequire additional development of the assessment process. |
| | By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRCreview and endorsement. |
| | NRC endorsement was provided by Reference 8.The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of thecontrol point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less thanor equal to 0.2g). Therefore, no additional evaluation is necessary. |
| | The attachment to this letter providesthe SSE (or IHS) and GMRS information from Reference 5.This transmittal completes commitments from Reference |
| | : 4. This letter contains no new regulatory commitments. |
| | Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177. |
| | I declare Under penalty of perjury that the foregoing is true and correct. |
| | Executed on December 8, 2015.Sincerely, Sergio VazquezDirector |
| | -Engineering |
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| |
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| ==Attachment:== | | ==Attachment:== |
| High-frequency Confirmation for RBScc: U. S. Nuclear Regulatory CommissionRegion IV1600 East Lamar Blvd.Arlington, TX 76011-4511 RBG-47634December 8, 2015Page 3 of 3NRC Sr. Resident InspectorP. O. Box 1050St. Francisville, LA 70775Central Records ClerkPublic Utility 'Commission of Texas1701 N. Congress Ave.Austin, TX 78711-3326Department of Environmental QualityOffice of Environmental ComplianceRadiological Emergency Planning and Response SectionJi Young WileyP.O. Box 4312Baton Rouge, LA 70821-4312*U. S. Nuclear Regulatory CommissioniAttn: Steven S. Koenick:'-Mail Stop 8BlA11555 Rockville Pike:-.Rockville, MD 20852-2738 Attachment to RBG-47634Page 1 of 1High-frequency Confirmato for R8S(Reference Figure 3-2 in EPRI (lf! | | |
| ' EnteigyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61 NSt. Francisville, LA 70775December 8, 2015RBG-47634U.S. Nuclear Regulatory CommissionATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852 | | High-frequency Confirmation for RBScc: U. S. Nuclear Regulatory Commission Region IV1600 East Lamar Blvd.Arlington, TX 76011-4511 RBG-47634 December 8, 2015Page 3 of 3NRC Sr. Resident Inspector P. O. Box 1050St. Francisville, LA 70775Central Records ClerkPublic Utility 'Commission of Texas1701 N. Congress Ave.Austin, TX 78711-3326 Department of Environmental QualityOffice of Environmental Compliance Radiological Emergency Planning and Response SectionJi Young WileyP.O. Box 4312Baton Rouge, LA 70821-4312 |
| | *U. S. Nuclear Regulatory Commission iAttn: Steven S. Koenick:'-Mail Stop 8BlA11555 Rockville Pike:-.Rockville, MD 20852-2738 Attachment to RBG-47634 Page 1 of 1High-frequency Confirmato for R8S(Reference Figure 3-2 in EPRI (lf! |
| | ' EnteigyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61 NSt. Francisville, LA 70775December 8, 2015RBG-47634 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852 |
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| ==Subject:== | | ==Subject:== |
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| ==References:== | | ==References:== |
| High-frequency SUpplement to Seismic Hazard Screening Report, Response NRCRequest for Information Pursuant to 10 CER 50.54(f) Regarding Recommendation 2.1 ofthe Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentRiver Bend Station -Unit 1Docket No. 50-458License No. NPF-471. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-TermTask Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12,"20112, ADAMS Accession Number M/L12053A340*2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "SeismicEvaluation GuidanCe: Augmented Approach for the Resolution of Fukushima Near-TermTask Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMSAccession Number ML 131 06A3313. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287),dated November 27, 2012, ADAMS Accession Number ML12333A168 andML1 2333A1 704. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report1025287, "Seismic Evaluation Guidance", dated February 15, 2013, ADAMS AccessionNumber ML1 231 9A0745. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and ScreeningReport (ML 14091A429)6. NRC Letter, Screening and Prioritization Results regarding information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) regarding Seismic HazardReevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews ofInsights from the Fukushima Dai-ichi accident, dated May 9, 2014, (ML14111A147)7. NEI Letter, Request for NRC Endorsement of High Frequency Program: ApplicationGuidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), datedJuly 30, 20158. NRC letter dated September 15, 2015, Endorsement of Electric Power ResearchInstitute Final Draft Report 3002004396, "High Frequency Program: Application GuidanceFor Functional Confirmation And Fragility"' (ML1 521 8A569) / p RBG-47634December 8, 2015Page 2 of 3 | | |
| | High-frequency SUpplement to Seismic Hazard Screening Report, Response NRCRequest for Information Pursuant to 10 CER 50.54(f) |
| | Regarding Recommendation 2.1 ofthe Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentRiver Bend Station -Unit 1Docket No. 50-458License No. NPF-471. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f) |
| | Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi |
| | : Accident, dated March 12,"20112, ADAMS Accession Number M/L12053A340 |
| | *2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "SeismicEvaluation GuidanCe: |
| | Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," |
| | as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMSAccession Number ML 131 06A3313. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287), |
| | dated November 27, 2012, ADAMS Accession Number ML12333A168 andML1 2333A1 704. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report1025287, "Seismic Evaluation Guidance", |
| | dated February 15, 2013, ADAMS Accession Number ML1 231 9A0745. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and Screening Report (ML 14091A429) |
| | : 6. NRC Letter, Screening and Prioritization Results regarding information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) regarding Seismic HazardReevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews ofInsights from the Fukushima Dai-ichi |
| | : accident, dated May 9, 2014, (ML14111A147) |
| | : 7. NEI Letter, Request for NRC Endorsement of High Frequency Program: |
| | Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), |
| | datedJuly 30, 20158. NRC letter dated September 15, 2015, Endorsement of Electric Power ResearchInstitute Final Draft Report 3002004396, "High Frequency Program: |
| | Application GuidanceFor Functional Confirmation And Fragility"' |
| | (ML1 521 8A569) / p RBG-47634 December 8, 2015Page 2 of 3 |
|
| |
|
| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 yearsfrom the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRCletter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening andprioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference4). In accordance with the screening, prioritization, and implementation details report (SPID) andaugmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used todetermine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluatedhorizontal ground motion response spectrum (GMRS) at the control point elevation is compared to theexisting safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required toperform a high-frequency confirmation. As noted in the May 9, 2014 letter, River Bend Station is toconduct a limited scope high-frequency confirmation.Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations willrequire additional development of the assessment process. By Reference 7, Nuclear Energy Institute(NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRCreview and endorsement. NRC endorsement was provided by Reference 8.The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of thecontrol point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less thanor equal to 0.2g). Therefore, no additional evaluation is necessary. The attachment to this letter providesthe SSE (or IHS) and GMRS information from Reference 5.This transmittal completes commitments from Reference 4. This letter contains no new regulatorycommitments. Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177.I declare Under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2015.Sincerely,Sergio VazquezDirector -Engineering | | On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f) |
| | (Reference |
| | : 1) to all power reactor licensees. |
| | The required response section of Enclosure 1indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 yearsfrom the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRCletter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening andprioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) andaugmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used todetermine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to theexisting safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required toperform a high-frequency confirmation. |
| | As noted in the May 9, 2014 letter, River Bend Station is toconduct a limited scope high-frequency confirmation. |
| | Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations willrequire additional development of the assessment process. |
| | By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRCreview and endorsement. |
| | NRC endorsement was provided by Reference 8.The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of thecontrol point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less thanor equal to 0.2g). Therefore, no additional evaluation is necessary. |
| | The attachment to this letter providesthe SSE (or IHS) and GMRS information from Reference 5.This transmittal completes commitments from Reference |
| | : 4. This letter contains no new regulatory commitments. |
| | Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177. |
| | I declare Under penalty of perjury that the foregoing is true and correct. |
| | Executed on December 8, 2015.Sincerely, Sergio VazquezDirector |
| | -Engineering |
|
| |
|
| ==Attachment:== | | ==Attachment:== |
| High-frequency Confirmation for RBScc: U. S. Nuclear Regulatory CommissionRegion IV1600 East Lamar Blvd.Arlington, TX 76011-4511 RBG-47634December 8, 2015Page 3 of 3NRC Sr. Resident InspectorP. O. Box 1050St. Francisville, LA 70775Central Records ClerkPublic Utility 'Commission of Texas1701 N. Congress Ave.Austin, TX 78711-3326Department of Environmental QualityOffice of Environmental ComplianceRadiological Emergency Planning and Response SectionJi Young WileyP.O. Box 4312Baton Rouge, LA 70821-4312*U. S. Nuclear Regulatory CommissioniAttn: Steven S. Koenick:'-Mail Stop 8BlA11555 Rockville Pike:-.Rockville, MD 20852-2738 Attachment to RBG-47634Page 1 of 1High-frequency Confirmato for R8S(Reference Figure 3-2 in EPRI (lf!}} | | |
| | High-frequency Confirmation for RBScc: U. S. Nuclear Regulatory Commission Region IV1600 East Lamar Blvd.Arlington, TX 76011-4511 RBG-47634 December 8, 2015Page 3 of 3NRC Sr. Resident Inspector P. O. Box 1050St. Francisville, LA 70775Central Records ClerkPublic Utility 'Commission of Texas1701 N. Congress Ave.Austin, TX 78711-3326 Department of Environmental QualityOffice of Environmental Compliance Radiological Emergency Planning and Response SectionJi Young WileyP.O. Box 4312Baton Rouge, LA 70821-4312 |
| | *U. S. Nuclear Regulatory Commission iAttn: Steven S. Koenick:'-Mail Stop 8BlA11555 Rockville Pike:-.Rockville, MD 20852-2738 Attachment to RBG-47634 Page 1 of 1High-frequency Confirmato for R8S(Reference Figure 3-2 in EPRI (lf!}} |
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Category:Letter
MONTHYEARIR 05000458/20240102024-10-31031 October 2024
Design Basis Assurance Inspection (Programs) Inspection Report 05000458/2024010
RBG-48315, Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement2024-09-24024 September 2024
Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement
RBG-48306, Report of Changes and Errors to 10CFR50.462024-09-24024 September 2024
Report of Changes and Errors to 10CFR50.46
ML24263A2712024-09-19019 September 2024
Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
ML24255A1192024-09-16016 September 2024
Notification of NRC Follow Up Inspection for One Severity Level (SL) III and Two SL IV or Three or More SL IV Violations and Request for Additional Information
RBG-48311, Reply to a Notice of Violation, NRC Inspection Report 05000458/20240022024-08-28028 August 2024
Reply to a Notice of Violation, NRC Inspection Report 05000458/2024002
IR 05000458/20240052024-08-22022 August 2024
Updated Inspection Plan for River Bend Station (Report 05000458/2024005)
ML24220A2642024-08-20020 August 2024
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
ML24185A1522024-08-13013 August 2024
Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205
ML24214A2752024-08-0202 August 2024
Acknowledgement of Readiness for Supplemental Inspection
RBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024
Notification of Readiness for Supplemental Inspection
ML24205A0392024-07-30030 July 2024
Integrated Inspection Report 05000458/2024002 and Notice of Violation
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
05000458/LER-2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String2024-06-0404 June 2024
Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String
ML24060A2192024-05-30030 May 2024
Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752
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
ML24102A2842024-05-0707 May 2024
Summary of Regulatory Audit in Support of LARs to Revise Technical Specifications to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69
ML24128A0422024-05-0707 May 2024
License Amendment Request to Remove Obsolete License Conditions
RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024
2023 Annual Radioactive Effluent Release Report
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
ML24075A1712024-03-15015 March 2024
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
IR 05000458/20240402024-03-15015 March 2024
– 95001 Supplemental Inspection Report 05000458/2024040 and Follow-Up Assessment
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-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
RBG-48278, 2023 Spent Fuel Storage Radioactive Effluent Release Report2024-02-27027 February 2024
2023 Spent Fuel Storage Radioactive Effluent Release Report
ML24031A0042024-02-21021 February 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0052 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
RBG-48274, Notification of Readiness for Supplemental Inspection2024-02-0505 February 2024
Notification of Readiness for Supplemental Inspection
IR 05000458/20230042024-01-30030 January 2024
Integrated Inspection Report 05000458/2023004
IR 05000458/20230402024-01-18018 January 2024
– 95001 Supplemental Inspection Supplemental Report 05000458/2023040 and Follow-Up Assessment Letter
RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk2024-01-12012 January 2024
Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk
ML24012A1962024-01-12012 January 2024
Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and
ML24011A1742024-01-11011 January 2024
Security Baseline Inspection Report (Cover Letter)
ML23349A1672023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
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
2024-09-24
[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-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
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
ML18115A0612018-04-25025 April 2018
Draft Response on RAI B1.21-1 Flow Accelerated Corrosion
ML18115A0722018-04-25025 April 2018
Draft Response on RAI B.1.25-1(Internal Surfaces in Miscellaneous Piping and Ducting Components)
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-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-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-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-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
' EnteigyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61 NSt. Francisville, LA 70775December 8, 2015RBG-47634 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852
Subject:
References:
High-frequency SUpplement to Seismic Hazard Screening Report, Response NRCRequest for Information Pursuant to 10 CER 50.54(f)
Regarding Recommendation 2.1 ofthe Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentRiver Bend Station -Unit 1Docket No. 50-458License No. NPF-471. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi
- Accident, dated March 12,"20112, ADAMS Accession Number M/L12053A340
- 2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "SeismicEvaluation GuidanCe:
Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic,"
as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMSAccession Number ML 131 06A3313. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287),
dated November 27, 2012, ADAMS Accession Number ML12333A168 andML1 2333A1 704. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report1025287, "Seismic Evaluation Guidance",
dated February 15, 2013, ADAMS Accession Number ML1 231 9A0745. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and Screening Report (ML 14091A429)
- 6. NRC Letter, Screening and Prioritization Results regarding information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) regarding Seismic HazardReevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews ofInsights from the Fukushima Dai-ichi
- accident, dated May 9, 2014, (ML14111A147)
- 7. NEI Letter, Request for NRC Endorsement of High Frequency Program:
Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396),
datedJuly 30, 20158. NRC letter dated September 15, 2015, Endorsement of Electric Power ResearchInstitute Final Draft Report 3002004396, "High Frequency Program:
Application GuidanceFor Functional Confirmation And Fragility"'
(ML1 521 8A569) / p RBG-47634 December 8, 2015Page 2 of 3
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f)
(Reference
- 1) to all power reactor licensees.
The required response section of Enclosure 1indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 yearsfrom the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRCletter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening andprioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) andaugmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used todetermine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to theexisting safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required toperform a high-frequency confirmation.
As noted in the May 9, 2014 letter, River Bend Station is toconduct a limited scope high-frequency confirmation.
Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations willrequire additional development of the assessment process.
By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRCreview and endorsement.
NRC endorsement was provided by Reference 8.The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of thecontrol point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less thanor equal to 0.2g). Therefore, no additional evaluation is necessary.
The attachment to this letter providesthe SSE (or IHS) and GMRS information from Reference 5.This transmittal completes commitments from Reference
- 4. This letter contains no new regulatory commitments.
Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177.
I declare Under penalty of perjury that the foregoing is true and correct.
Executed on December 8, 2015.Sincerely, Sergio VazquezDirector
-Engineering
Attachment:
High-frequency Confirmation for RBScc: U. S. Nuclear Regulatory Commission Region IV1600 East Lamar Blvd.Arlington, TX 76011-4511 RBG-47634 December 8, 2015Page 3 of 3NRC Sr. Resident Inspector P. O. Box 1050St. Francisville, LA 70775Central Records ClerkPublic Utility 'Commission of Texas1701 N. Congress Ave.Austin, TX 78711-3326 Department of Environmental QualityOffice of Environmental Compliance Radiological Emergency Planning and Response SectionJi Young WileyP.O. Box 4312Baton Rouge, LA 70821-4312
- U. S. Nuclear Regulatory Commission iAttn: Steven S. Koenick:'-Mail Stop 8BlA11555 Rockville Pike:-.Rockville, MD 20852-2738 Attachment to RBG-47634 Page 1 of 1High-frequency Confirmato for R8S(Reference Figure 3-2 in EPRI (lf!
' EnteigyEntergy Operations, Inc.River Bend Station5485 U.S. Highway 61 NSt. Francisville, LA 70775December 8, 2015RBG-47634 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852
Subject:
References:
High-frequency SUpplement to Seismic Hazard Screening Report, Response NRCRequest for Information Pursuant to 10 CER 50.54(f)
Regarding Recommendation 2.1 ofthe Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentRiver Bend Station -Unit 1Docket No. 50-458License No. NPF-471. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi
- Accident, dated March 12,"20112, ADAMS Accession Number M/L12053A340
- 2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "SeismicEvaluation GuidanCe:
Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic,"
as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMSAccession Number ML 131 06A3313. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287),
dated November 27, 2012, ADAMS Accession Number ML12333A168 andML1 2333A1 704. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report1025287, "Seismic Evaluation Guidance",
dated February 15, 2013, ADAMS Accession Number ML1 231 9A0745. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and Screening Report (ML 14091A429)
- 6. NRC Letter, Screening and Prioritization Results regarding information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) regarding Seismic HazardReevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews ofInsights from the Fukushima Dai-ichi
- accident, dated May 9, 2014, (ML14111A147)
- 7. NEI Letter, Request for NRC Endorsement of High Frequency Program:
Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396),
datedJuly 30, 20158. NRC letter dated September 15, 2015, Endorsement of Electric Power ResearchInstitute Final Draft Report 3002004396, "High Frequency Program:
Application GuidanceFor Functional Confirmation And Fragility"'
(ML1 521 8A569) / p RBG-47634 December 8, 2015Page 2 of 3
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10CFR 50.54(f)
(Reference
- 1) to all power reactor licensees.
The required response section of Enclosure 1indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 yearsfrom the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRCletter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening andprioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) andaugmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used todetermine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to theexisting safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required toperform a high-frequency confirmation.
As noted in the May 9, 2014 letter, River Bend Station is toconduct a limited scope high-frequency confirmation.
Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations willrequire additional development of the assessment process.
By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRCreview and endorsement.
NRC endorsement was provided by Reference 8.The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of thecontrol point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less thanor equal to 0.2g). Therefore, no additional evaluation is necessary.
The attachment to this letter providesthe SSE (or IHS) and GMRS information from Reference 5.This transmittal completes commitments from Reference
- 4. This letter contains no new regulatory commitments.
Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177.
I declare Under penalty of perjury that the foregoing is true and correct.
Executed on December 8, 2015.Sincerely, Sergio VazquezDirector
-Engineering
Attachment:
High-frequency Confirmation for RBScc: U. S. Nuclear Regulatory Commission Region IV1600 East Lamar Blvd.Arlington, TX 76011-4511 RBG-47634 December 8, 2015Page 3 of 3NRC Sr. Resident Inspector P. O. Box 1050St. Francisville, LA 70775Central Records ClerkPublic Utility 'Commission of Texas1701 N. Congress Ave.Austin, TX 78711-3326 Department of Environmental QualityOffice of Environmental Compliance Radiological Emergency Planning and Response SectionJi Young WileyP.O. Box 4312Baton Rouge, LA 70821-4312
- U. S. Nuclear Regulatory Commission iAttn: Steven S. Koenick:'-Mail Stop 8BlA11555 Rockville Pike:-.Rockville, MD 20852-2738 Attachment to RBG-47634 Page 1 of 1High-frequency Confirmato for R8S(Reference Figure 3-2 in EPRI (lf!
