|
|
| (One intermediate revision by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 03/12/2014 | | | issue date = 03/12/2014 |
| | title = Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2 | | | title = Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2 |
| | author name = Browning J G | | | author name = Browning J |
| | author affiliation = Entergy Operations, Inc | | | author affiliation = Entergy Operations, Inc |
| | addressee name = | | | addressee name = |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:0CAN031401March 12, 2014U.S. Nuclear Regulatory CommissionATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852 | | {{#Wiki_filter:Entergy Operations, Inc. |
| | 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Site Vice President Arkansas Nuclear One 0CAN031401 March 12, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Required Response 2 to March 12, 2012, Request for Information (RFI),Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation ReportArkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368License Nos. DPR-51 and NPF-6 | | Required Response 2 to March 12, 2012, Request for Information (RFI), |
| | Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 |
|
| |
|
| ==REFERENCES:== | | ==REFERENCES:== |
| : 1. NRC letter to Entergy,RFI Pursuant to Title 10 of the Code ofFederal Regulations 50.54(f) Regarding Recommendations 2.1,2.3, and 9.3 of the Near-Term Task Force (NTTF) Review ofInsights from the Fukushima Dai-ichi Accident , datedMarch 12, 2012 (0CNA031208) (ML12053A340)2. Entergy letter to NRC,Entergy's Response to NRC RFI Pursuantto 10 CFR 50.54(f) Regarding the Flooding Aspects ofRecommendations 2.1 and 2.3 of the NTTF Review of Insightsfrom the Fukushima Dai-ichi Accident , dated June 8, 2012 (0CAN061202)3. Entergy letter to NRC,Assistance in Obtaining Information on Dams, dated September 30, 2013 (0CAN091302)4. NRC letter to Entergy,Supplemental Information Related to RFIPursuant toTitle 10 of the Code of Federal Regulations 50.54(f)Regarding Flooding Hazard Reevaluations for Recommendation2.1 of the NTTF Review of Insights fron the Fukushima Dai-ichi Accident, dated March 1, 2013 (0CAN031302 ) (ML13044A561) | | : 1. NRC letter to Entergy, RFI Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (0CNA031208) (ML12053A340) |
| | : 2. Entergy letter to NRC, Entergys Response to NRC RFI Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.1 and 2.3 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident, dated June 8, 2012 (0CAN061202) |
| | : 3. Entergy letter to NRC, Assistance in Obtaining Information on Dams, dated September 30, 2013 (0CAN091302) |
| | : 4. NRC letter to Entergy, Supplemental Information Related to RFI Pursuant toTitle 10 of the Code of Federal Regulations 50.54(f) |
| | Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights fron the Fukushima Dai-ichi Accident, dated March 1, 2013 (0CAN031302 ) (ML13044A561) |
|
| |
|
| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| On March 12, 2012, the NRC issued Reference 1 requesting information pursuant toTitle 10 of the Code of Federal Regulations 50.54(f). Enclosure 2 of that letter containsspecific requested Information associated with NTTF Recommendation 2.1 for flooding.By Reference 2 Entergy Operations, Inc. (Entergy) committed to submit the flood hazardevaluation for Arkansas Nuclear One (ANO), Units 1 and 2 as a Category 2 site byMarch 12, 2014.Entergy Operations, Inc. | | |
| 1448 S.R. 333Russellville, AR 72802Tel 479-858-3110Jeremy G. BrowningSite Vice PresidentArkansas Nuclear One 0CAN031401 Page 2 of 3In September 2013 (Reference 3), Entergy requested the assistance of the NRC toobtain information from three Districts of the United States Army Corps of Engineers(USACE) to support the flood hazard reevaluation at ANO. Pursuant to the guidance inReference 4, Entergy is revising its commitment for submittal of the flood hazardreevaluation report to six months after USACE data is received.Reason for the Delay:The NRC recently notified Entergy that the kickoff meeting with the USACE and theNRC is expected to be scheduled in the near future. Receipt of the USACE informationis not expected for several months subsequent to the meeting.
| | On March 12, 2012, the NRC issued Reference 1 requesting information pursuant to Title 10 of the Code of Federal Regulations 50.54(f). Enclosure 2 of that letter contains specific requested Information associated with NTTF Recommendation 2.1 for flooding. |
| Proposed Schedule:Subsequent to receipt of the USACE information, six months are necessary to: Complete the Dam Failure calculation. Use Dam Failure calculation as input to complete the Combined Effects calculation. Perform anticipated stepwise model refinements (consistent with the hierarchicalhazard assessment approach) to the Probable Maximum Precipitation, ArkansasRiver Probable Maximum Flood (PMF) flow, and Arkansas River PMF elevation calculations. Perform iterations to the Dam Failure and Combined Effects calculations. Complete flood hazard reevaluation report for submittal.Basis for Acceptability: Preliminary results to date based on publicly available information including theUSACE districts and National Inventory of Dams indicate the flood hazard isexpected be bounded by the current design basis flood level. The NRC has previously determined in their March 2012, 50.54(f) letter that thecurrent regulatory approach and the resultant plant capabilities provide confidencethat an accident with consequences similar to the Fukushima accident is unlikely tooccur in the United States. The NRC letter concluded that continued plant operationand the continuation of licensing activities do not pose an imminent risk to publichealth and safety. The events being analyzed in the flooding hazard reevaluation are beyond theplant's design basis (and licensing basis). The reevaluation results do not constitutean operability concern. The reevaluated flooding hazard is a very low probability event. The timeframe ofthe submittal delay is short relative to the probability of occurrence of the flood eventbeing evaluated. | | By Reference 2 Entergy Operations, Inc. (Entergy) committed to submit the flood hazard evaluation for Arkansas Nuclear One (ANO), Units 1 and 2 as a Category 2 site by March 12, 2014. |
| 0CAN031401 Page 3 of 3This letter contains a revised regulatory commitment which is identified in theattachment. Should you have any questions concerning the content of this letter, pleasecontact Stephenie Pyle at 479.858.4704.I declare under penalty of perjury that the foregoing is true and correct. Executed onMarch 12, 2014. | | |
| Sincerely,Original signed by Jeremy G. Browning JGB/nbm | | 0CAN031401 Page 2 of 3 In September 2013 (Reference 3), Entergy requested the assistance of the NRC to obtain information from three Districts of the United States Army Corps of Engineers (USACE) to support the flood hazard reevaluation at ANO. Pursuant to the guidance in Reference 4, Entergy is revising its commitment for submittal of the flood hazard reevaluation report to six months after USACE data is received. |
| | Reason for the Delay: |
| | The NRC recently notified Entergy that the kickoff meeting with the USACE and the NRC is expected to be scheduled in the near future. Receipt of the USACE information is not expected for several months subsequent to the meeting. |
| | Proposed Schedule: |
| | Subsequent to receipt of the USACE information, six months are necessary to: |
| | * Complete the Dam Failure calculation. |
| | * Use Dam Failure calculation as input to complete the Combined Effects calculation. |
| | * Perform anticipated stepwise model refinements (consistent with the hierarchical hazard assessment approach) to the Probable Maximum Precipitation, Arkansas River Probable Maximum Flood (PMF) flow, and Arkansas River PMF elevation calculations. |
| | * Perform iterations to the Dam Failure and Combined Effects calculations. |
| | * Complete flood hazard reevaluation report for submittal. |
| | Basis for Acceptability: |
| | * Preliminary results to date based on publicly available information including the USACE districts and National Inventory of Dams indicate the flood hazard is expected be bounded by the current design basis flood level. |
| | * The NRC has previously determined in their March 2012, 50.54(f) letter that the current regulatory approach and the resultant plant capabilities provide confidence that an accident with consequences similar to the Fukushima accident is unlikely to occur in the United States. The NRC letter concluded that continued plant operation and the continuation of licensing activities do not pose an imminent risk to public health and safety. |
| | * The events being analyzed in the flooding hazard reevaluation are beyond the plants design basis (and licensing basis). The reevaluation results do not constitute an operability concern. |
| | * The reevaluated flooding hazard is a very low probability event. The timeframe of the submittal delay is short relative to the probability of occurrence of the flood event being evaluated. |
| | |
| | 0CAN031401 Page 3 of 3 This letter contains a revised regulatory commitment which is identified in the attachment. Should you have any questions concerning the content of this letter, please contact Stephenie Pyle at 479.858.4704. |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on March 12, 2014. |
| | Sincerely, Original signed by Jeremy G. Browning JGB/nbm |
|
| |
|
| ==Attachment:== | | ==Attachment:== |
| List of Regulatory Commitmentscc: Mr. Marc L. DapasRegional AdministratorU. S. Nuclear Regulatory Commission, Region IV1600 East Lamar BoulevardArlington, TX 76011-4511NRC Senior Resident Inspector Arkansas Nuclear OneP.O. Box 310London, AR 72847U. S. Nuclear Regulatory CommissionAttn: Mr. Alan WangMS O-88B1One White Flint North11555 Rockville PikeRockville, MD 20852U. S. Nuclear Regulatory CommissionAttn: Mr. Michael OrenakMS O-8G9AOne White Flint North11555 Rockville PikeRockville, MD 20852 Attachment to0CAN031401List of Regulatory Commitments Attachment to 0CAN031401 Page 1 of 1List of Regulatory CommitmentsThe following table identifies those actions committed to by Entergy Operations, Inc. in thisdocument. Any other statements in this submittal are provided for information purposes andare not considered to be regulatory commitments.COMMITMENT TYPE(Check One) | | List of Regulatory Commitments cc: Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan Wang MS O-88B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Attn: Mr. Michael Orenak MS O-8G9A One White Flint North 11555 Rockville Pike Rockville, MD 20852 |
| SCHEDULEDCOMPLETIONDATE(If Required)
| | |
| ONE-TIMEACTIONCONTINUINGCOMPLIANCESubmit Flood Hazard Evaluation Reportto the NRC.
| | Attachment to 0CAN031401 List of Regulatory Commitments |
| XSix months after receipt ofinformation from theUnited States ArmyCorps of Engineers}}
| | |
| | Attachment to 0CAN031401 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy Operations, Inc. in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. |
| | TYPE SCHEDULED (Check One) COMPLETION COMMITMENT DATE ONE-TIME CONTINUING (If Required) |
| | ACTION COMPLIANCE Submit Flood Hazard Evaluation Report X Six months after to the NRC. receipt of information from the United States Army Corps of Engineers}} |
Letter Sequence Request |
|---|
|
|
MONTHYEAR0CAN091302, Assistance in Obtaining Information on Dams2013-09-30030 September 2013
Assistance in Obtaining Information on Dams
Project stage: Request
L-PI-14-024, Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendation 2.1, Flooding, of the Near-Term Task For2014-03-10010 March 2014
Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(0 Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force
Project stage: Request
L-14-113, Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights.2014-03-11011 March 2014
Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights.
Project stage: Request
0CAN031401, Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 22014-03-12012 March 2014
Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2
Project stage: Request
0CAN041402, Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report2014-04-14014 April 2014
Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report
Project stage: Request
ML14168A0182014-05-16016 May 2014
Xcel Energy Responses to NRC Questions Regarding Flood Hazard Reevaluation Report Extension Requests
Project stage: Other
ML14153A0242014-05-16016 May 2014
Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants
Project stage: Meeting
ML14153A0252014-06-20020 June 2014
Meeting Summary - Public Meeting on May 16, 2014, to Discuss Xcel Energy'S Flood Hazard Reevaluation Extension Request for the Monticello and Prairie Island Nuclear Generating Plants
Project stage: Meeting
ML14162A3712014-06-26026 June 2014
5/22/2014 Summary of Meeting with Entergy Operations, Inc. to Discuss Flooding Hazard Reevaluation Extension Request for Arkansas Nuclear One, Units 1 and 2; Near-Term Task Force Recommendation 2.1
Project stage: Meeting
ML14171A5292014-07-17017 July 2014
Relaxation of Response Due Date Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident
Project stage: Approval
ML14171A1662014-07-29029 July 2014
Relaxation of Response Due Date Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident
Project stage: Approval
ML15155A6312015-06-0808 June 2015
Nuclear Regulatory Commission Plan for the Audit of Duke Energy Carolinas, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Catawba Nuclear Station, Units 1 and 2
Project stage: Other
2014-05-16
[Table View] |
|
|---|
Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024
U.S. Additional Protocol
2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024
Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
0CAN012401, Registration of Cask Use2024-01-10010 January 2024
Registration of Cask Use
1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023
Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)
2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023
Submittal of Amendment 31 to Safety Analysis Report
0CAN102303, Registration of Cask Use2023-10-24024 October 2023
Registration of Cask Use
0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023
(ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3
0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023
Evacuation Time Estimate (ETE) Study
1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023
Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023
Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)
2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023
Reply to a Notice of Violation
0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023
Emergency Plan Implementing Procedure Revision
0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023
Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341
2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023
Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)
0CAN072301, Registration of Cask Use2023-07-18018 July 2023
Registration of Cask Use
1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023
Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023
Status of Actions to Return to Compliance
0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023
Submittal of Revision 22 of the ANO Fire Hazards Analysis
1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023
Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)
0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023
Annual 10 CFR 50.46 Report for Calendar Year 2022
0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023
Emergency Plan Rev. 48
0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023
Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022
2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023
Cycle 30 Core Operating Limits Report (COLR)
0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023
Annual Occupational Radiation Exposure Report for 2022
0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023
Radioactive Effluent Release Report for 2022
2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023
License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023
License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure
2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023
Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46
2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023
Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46
2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023
03 Post Examination Analysis
1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023
Inspection Summary Report for the Thirtieth Refueling Outage (1R30)
1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023
Responses to Request for Additional Information for Request for Relief ANO1-ISI-035
2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023
U.S. Additional Protocol
2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023
Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46
1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022
License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
0CAN122202, Registration of Cask Use2022-12-21021 December 2022
Registration of Cask Use
0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022
Reply to a Notice of Violation; EA-22-099
0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022
Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022
Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022
Cycle 31 Core Operating Limits Report
1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022
Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations
0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022
Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements
1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022
Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period
0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022
License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements
1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022
Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period
2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022
Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods
0CAN072201, Registration of Cask Use2022-07-14014 July 2022
Registration of Cask Use
0CAN062202, Registration of Cask Use2022-06-0909 June 2022
Registration of Cask Use
1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022
Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations
1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022
Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035
2024-01-17
[Table view] |
Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Site Vice President Arkansas Nuclear One 0CAN031401 March 12, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Required Response 2 to March 12, 2012, Request for Information (RFI),
Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6
REFERENCES:
- 1. NRC letter to Entergy, RFI Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (0CNA031208) (ML12053A340)
- 2. Entergy letter to NRC, Entergys Response to NRC RFI Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.1 and 2.3 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident, dated June 8, 2012 (0CAN061202)
- 3. Entergy letter to NRC, Assistance in Obtaining Information on Dams, dated September 30, 2013 (0CAN091302)
- 4. NRC letter to Entergy, Supplemental Information Related to RFI Pursuant toTitle 10 of the Code of Federal Regulations 50.54(f)
Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights fron the Fukushima Dai-ichi Accident, dated March 1, 2013 (0CAN031302 ) (ML13044A561)
Dear Sir or Madam:
On March 12, 2012, the NRC issued Reference 1 requesting information pursuant to Title 10 of the Code of Federal Regulations 50.54(f). Enclosure 2 of that letter contains specific requested Information associated with NTTF Recommendation 2.1 for flooding.
By Reference 2 Entergy Operations, Inc. (Entergy) committed to submit the flood hazard evaluation for Arkansas Nuclear One (ANO), Units 1 and 2 as a Category 2 site by March 12, 2014.
0CAN031401 Page 2 of 3 In September 2013 (Reference 3), Entergy requested the assistance of the NRC to obtain information from three Districts of the United States Army Corps of Engineers (USACE) to support the flood hazard reevaluation at ANO. Pursuant to the guidance in Reference 4, Entergy is revising its commitment for submittal of the flood hazard reevaluation report to six months after USACE data is received.
Reason for the Delay:
The NRC recently notified Entergy that the kickoff meeting with the USACE and the NRC is expected to be scheduled in the near future. Receipt of the USACE information is not expected for several months subsequent to the meeting.
Proposed Schedule:
Subsequent to receipt of the USACE information, six months are necessary to:
- Complete the Dam Failure calculation.
- Use Dam Failure calculation as input to complete the Combined Effects calculation.
- Perform anticipated stepwise model refinements (consistent with the hierarchical hazard assessment approach) to the Probable Maximum Precipitation, Arkansas River Probable Maximum Flood (PMF) flow, and Arkansas River PMF elevation calculations.
- Perform iterations to the Dam Failure and Combined Effects calculations.
- Complete flood hazard reevaluation report for submittal.
Basis for Acceptability:
- Preliminary results to date based on publicly available information including the USACE districts and National Inventory of Dams indicate the flood hazard is expected be bounded by the current design basis flood level.
- The NRC has previously determined in their March 2012, 50.54(f) letter that the current regulatory approach and the resultant plant capabilities provide confidence that an accident with consequences similar to the Fukushima accident is unlikely to occur in the United States. The NRC letter concluded that continued plant operation and the continuation of licensing activities do not pose an imminent risk to public health and safety.
- The events being analyzed in the flooding hazard reevaluation are beyond the plants design basis (and licensing basis). The reevaluation results do not constitute an operability concern.
- The reevaluated flooding hazard is a very low probability event. The timeframe of the submittal delay is short relative to the probability of occurrence of the flood event being evaluated.
0CAN031401 Page 3 of 3 This letter contains a revised regulatory commitment which is identified in the attachment. Should you have any questions concerning the content of this letter, please contact Stephenie Pyle at 479.858.4704.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March 12, 2014.
Sincerely, Original signed by Jeremy G. Browning JGB/nbm
Attachment:
List of Regulatory Commitments cc: Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan Wang MS O-88B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Attn: Mr. Michael Orenak MS O-8G9A One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 0CAN031401 List of Regulatory Commitments
Attachment to 0CAN031401 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy Operations, Inc. in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE SCHEDULED (Check One) COMPLETION COMMITMENT DATE ONE-TIME CONTINUING (If Required)
ACTION COMPLIANCE Submit Flood Hazard Evaluation Report X Six months after to the NRC. receipt of information from the United States Army Corps of Engineers
