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Category:Letter type:
MONTHYEAR2CAN012501, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2 Thirtieth Refueling Outage (2R30)2025-01-23023 January 2025 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2 Thirtieth Refueling Outage (2R30) 0CAN012502, Proposed Alternative ANO1-ISI-24-02 and ANO2-ISI-24-02 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2025-01-13013 January 2025 Proposed Alternative ANO1-ISI-24-02 and ANO2-ISI-24-02 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 0CAN012501, CFR 72.48 Summary Report for the Reporting Period January 1, 2023, Through December 31, 20242025-01-0909 January 2025 CFR 72.48 Summary Report for the Reporting Period January 1, 2023, Through December 31, 2024 2CAN122402, Status of Actions to Return Arkansas Nuclear One, Unit 2 to Compliance2024-12-0404 December 2024 Status of Actions to Return Arkansas Nuclear One, Unit 2 to Compliance 1CAN112401, Safety Analysis Report (SAR) Amendment 32, Technical Requirements Manual (Trm), Technical Specifications (TS) Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2024-11-11011 November 2024 Safety Analysis Report (SAR) Amendment 32, Technical Requirements Manual (Trm), Technical Specifications (TS) Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 0CAN102401, Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzle2024-10-16016 October 2024 Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 2CAN102401, Cycle 31 Core Operating Limits Report (COLR)2024-10-14014 October 2024 Cycle 31 Core Operating Limits Report (COLR) 1CAN082401, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirty-First Refueling Outage (1R312024-08-13013 August 2024 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirty-First Refueling Outage (1R31 2CAN072401, Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02)2024-07-19019 July 2024 Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) 0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply 0CAN062403, Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels2024-06-25025 June 2024 Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels 0CAN062402, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-06-0606 June 2024 Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 0CAN052401, – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 20232024-05-13013 May 2024 – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 2023 1CAN052401, Cycle 32 Core Operating Limits Report2024-05-0404 May 2024 Cycle 32 Core Operating Limits Report 2CAN042403, Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C2024-04-24024 April 2024 Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C 0CAN042402, Annual Occupational Radiation Exposure Report for 20232024-04-23023 April 2024 Annual Occupational Radiation Exposure Report for 2023 0CAN042401, Radioactive Effluent Release Report for the 2023 Calendar Year2024-04-15015 April 2024 Radioactive Effluent Release Report for the 2023 Calendar Year 2CAN042402, Special Report of Non-functional Main Steam Line Radiation Monitor2024-04-11011 April 2024 Special Report of Non-functional Main Steam Line Radiation Monitor 2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications2024-04-0404 April 2024 Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications 2CAN012401, 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) 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 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 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 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 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 2025-01-09
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEAR2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 ML20239B0482020-07-31031 July 2020 RSP_IA-20-028_Johnson ML20239B0472020-07-31031 July 2020 RSP_IA-20-029_Spivey 2CAN031703, Reply to a Notice of Violation; EA-16-2472017-03-29029 March 2017 Reply to a Notice of Violation; EA-16-247 0CAN091501, Units 1 and 2, Response to Non-cited Violation in NRC Integrated Inspection Report 05000313/2015002 and 05000368/20150022015-09-0303 September 2015 Units 1 and 2, Response to Non-cited Violation in NRC Integrated Inspection Report 05000313/2015002 and 05000368/2015002 0CAN021504, Reply to Notice of Violation; EA-14-0882015-02-23023 February 2015 Reply to Notice of Violation; EA-14-088 0CAN071402, Units 1 and 2, Reply to Notice of Violation; EA-14-0082014-07-18018 July 2014 Units 1 and 2, Reply to Notice of Violation; EA-14-008 0CAN041301, Units 1 and 2: Response to an Apparent Violation in Inspection Report Nos. 05000313-13-503 and 05000368-13-503; EA-12-2752013-04-10010 April 2013 Units 1 and 2: Response to an Apparent Violation in Inspection Report Nos. 05000313-13-503 and 05000368-13-503; EA-12-275 0CAN011101, Reply to Notice of Violation, EA-10-2332011-01-10010 January 2011 Reply to Notice of Violation, EA-10-233 2023-09-08
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- ) entergy 2CAN092301 September 8, 2023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Reply to a Notice of Violation Arkansas Nuclear One, Unit 2 NRC Docket No. 50-368 Renewed Facility Operating License No. NPF-6 Riley D. Keele, Jr.
Manager Regulatory Assurance Arkansas Nuclear One Tel 479-858-7826 10 CFR 2.201
Reference:
NRC letter to Entergy, "Arkansas Nuclear One - Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation,"
(0CNA082301) (ML23221A301), dated August 11, 2023 By the reference above, the NRC issued Entergy Operations, Inc. (Entergy) a green Notice of Violation (NOV) for Arkansas Nuclear One, Unit 2 (ANO-2) for failure to promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to correct in a timely manner the deficient system design of the check valves admitting steam to the emergency feedwater turbine. The NOV requires a written response within 30 days addressing the following: reason for the violation, corrective steps that have been taken and results achieved, corrective steps that will be taken, and date when full compliance will be achieved. Enclosure 1 provides Entergy's reply to the NOV.
The new commitments contained in this submittal are provided in Enclosure 2.
Should you have any questions, please contact Mr. Riley Keele at 479-858-7826.
Respectfully, f!:t~-
Entergy Operations, Inc. 1448 SR 333, Russellville, AR 72802
2CAN092301 Page 2 of 2
Enclosures:
- 1. Reply to a Notice of Violation
- 2. List of Regulatory Commitments cc:
NRC Region IV Regional Administrator NRC Senior Resident Inspector - Arkansas Nuclear One NRC Project Manager - Arkansas Nuclear One R4Enforcement@nrc.gov 2CAN092301 Reply to a Notice of Violation
2CAN092301 Page 1 of 3 Reply to a Notice of Violation Description of Violation:
Entergy documented the violation in its Corrective Action Program and a causal analysis was performed to identify and correct the underlying causes for this failure.
Reason for the violation:
Arkansas Nuclear One, Unit 1 (ANO-1) and Unit 2 (ANO-2) were issued a Green Non-Cited Violation (NCV) in 2018 (NCV 05000313/2018011-02 and 05000368/20187011-02).
The inspectors identified a Green non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Actions," was identified for failure to establish an adequate corrective action program and the resulting inability to correct a deficient system design which resulted in damaged and broken internals of the check valves admitting steam to the emergency feedwater pump turbine. Specifically, attempts to correct conditions adverse to quality were unsuccessful when the internals of the safety-related emergency feedwater steam admission check valves were found damaged or broken resulting in the system experiencing multiple and extended periods of degraded and nonconforming conditions.
In 2019, an Engineering Change was approved to change the previous check valve design to a new design check valve. This change was implemented for ANO-2 in 2020 during refueling outage 2R27. During each subsequent ANO-2 refueling outage, missing parts were discovered for the check valves as part of normally scheduled inspections.
In 2022, it was determined the missing parts issue was caused by vendor manufacturing deficiencies; specifically, failure to adequately stake the stem nut and failure to install both halves of a required washer. Due to these failures, ANO-2 has been unable to determine if the check valve design installed in 2020 has been satisfactory and the effectiveness review for this change remains indeterminate. During the check valve replacements in 2023, proper stem nut staking and assembly was verified. The inspections in Fall 2024 refueling outage (2R29) will be used to validate the assembly issues have been addressed.
As part of the causal evaluation performed for this Notice of Violation, a causal factor for the failure to reach an adequate solution to the original Non-Cited Violation was identified as a lack Failure to Establish Adequate Corrective Actions Resulting in Excessive Instances of Damaged and Broken Internals of the Emergency Feedwater Pump Turbine Steam Admission Check Valves Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green
[H.6] - Design 71152A Systems NOV 05000368/2023002-03 Margins Open The inspectors identified a Unit 2 Green finding and associated Notice of Violation of 1 O CFR Part 50, Appendix B, Criterion XVI, "Corrective Action," for the failure to promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to correct in a timely manner the deficient system design of the check valves admitting steam to the emergency feedwater turbine.
2CAN092301 Page 2 of 3 of organizational oversight and engagement with the issue. Visibility of this issue has not been maintained adequately so that the organization could collectively drive resolution.
During this time, the check valve inspection results have not impacted the operability of 2P-7A Emergency Feedwater (EFW) Pump or resulted in any components not able to fulfill their credited functions.
Corrective steps that have been taken and results achieved:
Since the Green Non-cited Violation (NCV) issued in 2018 for ANO-1 and ANO-2, ANO has changed the design of the EFW Pump Turbine Steam Admission Check Valves to a design better suited for the application. However, since the EFW Pump Turbine Steam Admission Check Valves are only available for internal inspection during refueling outages, there have been delays in determining the effectiveness of the current design, complicated by the vendor manufacturing issues discussed previously.
For ANO-1, an additional action to assist in addressing the condition was to change the position of the Motor Operated Valve (MOV), CV-2617, upstream of the EFW Pump Turbine Steam Admission Check Valve (MS-271), from normally open to normally closed. This eliminated the Steam Generator crosstie which causes check valve oscillations. A similar solution is not readily available for ANO-2 because the upstream MOVs do not currently receive an Emergency Feedwater Actuation System (EFAS) signal to open.
Both ANO-2 valves were inspected and replaced during the Fall 2021 refueling outage (2R28).
During this inspection, the 2MS-39B check valve was discovered to have missing parts. A vendor failure analysis report indicated the cause of the missing parts could have been caused by inadequate staking of the valve stem nut. A work order task was planned for the Spring 2023 refueling outage (2R29) to ensure the valves were assembled per the approved design prior to installation. Maintenance procedures were revised to include additional inspections to verify proper assembly prior to installation of this model check valve going forward.
The valve inspection in 2R29 determined the 2MS-39B stem nut was not staked correctly and again resulted in missing parts. ANO-2 implemented the updated maintenance procedures for stem nut staking prior to installing a new valve for 2MS-39B during 2R29. Additionally, 2MS-39A stem nut staking was verified to be correct.
Corrective steps that will be taken:
To restore compliance and resolve this Notice of Violation, ANO-2 will:
- 1. Replace 2MS-39A and 2MS-39B with new or manufacturer refurbished check valves during the Fall 2024 refueling outage (2R30).
- 2. Inspect the removed 2MS-39A and 2MS-39B check valves for wear and degradation. At this point, the effectiveness review for the current plant design will be completed to determine if it is adequate. If the current design is deemed adequate to satisfy the credited design function(s), compliance will be restored.
2CAN092301 Page 3 of 3
- 3. With compliance restored, ANO-2 will continue to replace 2MS-39A and 2MS-39B on an every refueling outage (1R) frequency until an adequate longer-term design solution has been explored and analyzed for possible implementation.
- 4. Prior to the Fall 2024 refueling outage (2R30), ANO-2 will conduct a scoping study to determine if there is another solution the site should be prepared to pursue in the event the current check valve design is determined to be inadequate (i.e., different check valve, orifice, MOV).
- 5. If another solution is determined to be necessary, ANO-2 will implement the selected option during the Spring 2026 refueling outage (2R31).
- 6. An effectiveness review will be completed during the Fall 2027 refueling outage (2R32) to validate the implemented option was effective in addressing the condition.
- 7. Additional corrective actions will be issued as part of the causal evaluation for this Notice of Violation to share the organizational learnings. These actions will also facilitate improvements in the use of available tools (i.e., system health reports, heat maps) so that visibility is maintained in the future for similar issues and the organization can collectively drive the issues to resolution in a timely manner.
Date when full compliance will be achieved:
Based on the actions described above, full compliance will be achieved when:
- 1. Current check valve design is verified to be adequate to satisfy the credited design function(s) following inspection in the Fall 2024 refueling outage (2R30).
Or
- 2. If the adequacy of the current check valve design to satisfy the credited design function(s) is challenged, a new design will be implemented in the Spring 2026 refueling outage (2R31) with an effectiveness review to occur in the Fall 2027 refueling outage (2R32).
2CAN092301 List of Regulatory Commitments
2CAN092301 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.
COMMITMENT TYPE (Check One)
SCHEDULED COMPLETION DATE ONE-TIME ACTION CONTINUING COMPLIANCE Entergy will ensure instructions associated with inspections and replacement of the current design check valves verify proper assembly per approved plant design.
X 12/31/2023 Entergy will complete scoping study to determine alternate plant design to satisfy the credited design function(s).
X 9/10/2024 Entergy will verify current check valve design is adequate, or not, to satisfy the credited design function(s).
X End of Fall 2024 Refueling Outage (2R30)
Entergy will implement alternate plant design, if necessary, to satisfy the credited design function(s).
X End of Spring 2026 Refueling Outage (2R31)
Entergy will verify alternate plant design is adequate, or not, to satisfy the credited design function(s).
X End of Fall 2027 Refueling Outage (2R32)