|
---|
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 Richard L. Anderson ANO Site Vice President 0CAN021801 February 6, 2018 Mr. Kriss Kennedy Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511
SUBJECT:
Notification of Confirmatory Action Letter Focus Area Inspection Readiness Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6
REFERENCES:
- 1. Entergy Letter to NRC, ANO Comprehensive Recovery Plan, dated May 17, 2016 (0CAN051602) (ML16139A059)
- 2. NRC Letter to Entergy, NRC Supplemental Inspection Report 05000313/2016007 and 05000368/2016007, dated June 9, 2016 (0CNA061602) (ML16161B279)
- 3. NRC Letter to Entergy, Confirmatory Action Letter, dated June 17, 2016 (0CNA061604) (ML16169A193)
- 4. NRC Letter to Entergy, NRC Problem Identification and Resolution Inspection Report 05000313/2017015 and 05000368/2017015, dated January 9, 2018 (0CNA011804) (ML18009A878)
Dear Mr. Kennedy:
On May 17, 2016, Entergy Operations, Inc. (Entergy) transmitted a Comprehensive Recovery Plan (CRP) to address the issues that led to the decline in performance at Arkansas Nuclear One (ANO), Units 1 and 2 (Reference 1). The CRP, comprised of 14 Area Action Plans, was based upon a thorough evaluation of related weaknesses, causes, and associated safety culture aspects, as well as insights gained from the NRC 95003 Inspection (Reference 2). The CRP included measures to ensure rigorous implementation and close monitoring of effectiveness and also contains elements designed to achieve sustainable improvement over the long term.
On June 17, 2016, NRC issued a Confirmatory Action Letter (CAL) for ANO (Reference 3). The CAL specified CRP actions needed to resolve the problems identified within the following six inspection focus areas in order to improve safety performance:
0CAN021801 Page 2 of 4
- 1. Significant Performance Deficiencies (SPD)
- 2. Identification, Assessment, and Correction of Performance Deficiencies (IACPD)
- 3. Human Performance
- 4. Equipment Reliability and Engineering Programs
- 5. Safety Culture
- 6. Service Water System Self-Assessment As outlined in Reference 3, the CAL remains in effect until Entergy notifies the NRC that the lists of CRP actions are complete, and NRC follow-up inspections are likewise completed.
The purpose of this correspondence is to notify the NRC of Entergys readiness for NRC inspection and possible closure of the SPD and IACPD focus areas. Entergy has successfully completed actions outlined in Reference 3 for these two areas and determined that they have been completed with quality and were effective in correcting the identified performance issues.
The actions have been reviewed by Action Closure Review Boards to confirm that the steps implemented met the intent and purpose of the associated actions. Metrics and/or other effectiveness measures have been used to verify that the actions have achieved intended results. Effectiveness Review Challenge Boards, comprised of senior station leaders, Entergy fleet representatives, and external representatives, have also determined that intended results have been achieved and are sustainable. For the remaining focus areas, actions remain open or are in review for area closure; Entergy anticipates reporting inspection readiness and requesting NRC inspection for these areas in separate correspondence.
An overall effectiveness review was recently conducted by a team of Entergy fleet and external representatives to determine whether the actions taken have been effective to ensure sustained performance improvement. The emphasis of the assessment was on the inspection focus areas identified by the NRC which encompass the 14 Area Action Plans develop by the site.
Overall, the assessment verified that 1) actions contained in the inspection focus areas and Area Actions Plans were substantially complete or are following the established work-off plan;
- 2) performance improvement occurred in the areas addressed by the Area Action Plans; and
- 3) progress achieved and steps to ensure continuous improvement are sustainable. The measure of success was determined based on the effectiveness and sustainability of actions directly related to the CAL and Area Action Plans recognizing that, in some cases, there may still be gaps to industry-leading performance.
The independent effectiveness review concluded that the focus areas of SPD and IACPD were ready for inspection. The focus area of SPD was rated as effective and concluded that the desired behaviors and outcomes associated with the key actions were addressed. This assessment in conjunction with the sites Closure Readiness Evaluation for SPD confirmed:
- Sustained improvements in vendor oversight are being demonstrated as station leaders continue to reinforce correct behaviors, and the knowledge of individuals responsible for vendor oversight is being demonstrated in the metrics.
- Degraded or non-conforming flooding design features have been corrected and sustained improvements in flood protection is being demonstrated through the establishment of a thorough, documented design basis for the ANO Flood Protection Program such that personnel understand the significance of properly maintaining flood protection features.
0CAN021801 Page 3 of 4
- Leaders are now consistently reinforcing expectations that nuclear safety is the overriding priority in making decisions and use decision making tools that emphasize prudent choices.
- Workers are preventing errors and identify problems by not proceeding in the face of uncertainty as demonstrated by declining error rates.
The focus area of IACPD was rated as effective with comment and confirmed that overall:
- As supported by improving metrics, apparent and root cause evaluations are now identifying underlying causes, are correctly scoped for extent-of-condition and extent-of-cause and are defining specific, measurable, achievable, realistic, and timely corrective actions.
- Effectiveness reviews and performance indicators have shown that ANO personnel are now consistently using operating experience to improve performance with a bias for sustainable actions.
- Leaders are now supporting continuous improvement and driving excellence in processes and procedures through Department Performance Review Meetings (DPRMs) and Aggregate Performance Review Meetings (APRMs).
- ANO performance indicator data is available and used to consistently compare to top industry performance.
- Corrective action and continuous training processes effectively verify that training is used as appropriate to address performance issues.
The assessment team also recommended areas in which adjustment or supplemental action is warranted regarding specific desired behaviors and outcomes. These recommendations are considered gaps to industry standards and have been entered into the Corrective Action Program (CAP), and prompt action has been taken to address the concerns.
Additionally, on September 28, 2017, the NRC completed a Problem Identification and Resolution inspection at ANO (Reference 4). The NRC inspection team reviewed the stations CAP and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for CAP. Based upon the inspection sample, the team determined that the CAP, and ANOs implementation of the CAP, supports nuclear safety.
Similar to the recent conclusion by the effectiveness review team, the NRC inspection team concluded that ANO maintained a CAP in which individuals identified issues at an appropriately low threshold, evaluated and addressed these issues appropriately, timely, and in a matter commensurate with their safety significance, and that the corrective actions were effective in addressing the causes and extent-of-conditions of problems.
In conclusion, Entergy has determined that committed actions have been completed to address performance issues in the focus areas of SPD and IACPD. The actions were also determined to be effective in improving safety performance issues in these areas. Entergy requests that the NRC inspect these two focus areas for closure.
0CAN021801 Page 4 of 4 This letter contains no new regulatory commitments. Should you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.
Sincerely, ORIGINAL SIGNED BY RICHARD L. ANDERSON RLA/nbm cc: U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-8B1A One White Flint North 11555 Rockville Pike Rockville, MD 20852