|
|---|
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 0CAN121502 December 22, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Commitment to Maintain Severe Accident Management Guidelines Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6
Dear Sir or Madam:
The Nuclear Energy Institute Nuclear Strategic Issues Advisory Committee recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for Arkansas Nuclear One.
These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures.
SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments are listed in the enclosed attachment.
It is expected that NRC staff personnel will conduct periodic inspection of the SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to NRC review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
Should you have any questions regarding this submittal, please contact Stephenie Pyle at 479.858.4704.
Sincerely, ORIGINAL SIGNED BY JEREMY G. BROWNING JGB/nbm
Attachment:
List of Regulatory Commitments
0CAN121502 Page 2 of 2 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: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 0CAN121502 List of Regulatory Commitments
Attachment to 0CAN121502 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy Operations, Inc. (Entergy) 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 Entergy will consider the site Severe X October 31, 2016 Accident Management Guidelines (SAMGs) within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.
Entergy will update the site SAMGs to X Within two refueling future revisions of the Pressurized Water outages or three Reactor Owners Group generic severe years of the accident technical guidelines, and the publication date of SAMGs will be integrated with other the guidelines, emergency response guideline sets and whichever is greater.
symptom-based Emergency Operating Procedures, and validated, using the guidance in Nuclear Energy Institute 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents.
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Site Vice President Arkansas Nuclear One 0CAN121502 December 22, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Commitment to Maintain Severe Accident Management Guidelines Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6
Dear Sir or Madam:
The Nuclear Energy Institute Nuclear Strategic Issues Advisory Committee recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for Arkansas Nuclear One.
These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures.
SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments are listed in the enclosed attachment.
It is expected that NRC staff personnel will conduct periodic inspection of the SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to NRC review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
Should you have any questions regarding this submittal, please contact Stephenie Pyle at 479.858.4704.
Sincerely, ORIGINAL SIGNED BY JEREMY G. BROWNING JGB/nbm
Attachment:
List of Regulatory Commitments
0CAN121502 Page 2 of 2 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: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 0CAN121502 List of Regulatory Commitments
Attachment to 0CAN121502 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy Operations, Inc. (Entergy) 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 Entergy will consider the site Severe X October 31, 2016 Accident Management Guidelines (SAMGs) within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.
Entergy will update the site SAMGs to X Within two refueling future revisions of the Pressurized Water outages or three Reactor Owners Group generic severe years of the accident technical guidelines, and the publication date of SAMGs will be integrated with other the guidelines, emergency response guideline sets and whichever is greater.
symptom-based Emergency Operating Procedures, and validated, using the guidance in Nuclear Energy Institute 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents.
