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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23108A1362023-04-24024 April 2023 Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 2024-01-24
[Table view] Category:Safety Evaluation
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B1602023-01-10010 January 2023 Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027) ML22263A1912022-12-0909 December 2022 Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary ML22236A5452022-08-26026 August 2022 Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22138A4312022-06-23023 June 2022 Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22039A2822022-03-15015 March 2022 Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21225A0552021-12-17017 December 2021 Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program ML21341B2262021-12-13013 December 2021 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21132A2792021-05-19019 May 2021 Request for Approval of Change to the Entergy Quality Assurance Program Manual ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent ML21040A5132021-03-10010 March 2021 Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations ML20288A8242020-11-16016 November 2020 Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020 Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432 ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20107J3172020-04-23023 April 2020 Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20087L8032020-04-0808 April 2020 Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19231A2972020-01-29029 January 2020 Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump ML19220A9382019-09-27027 September 2019 Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code ML19098A9552019-05-22022 May 2019 Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 ML19063B9482019-04-23023 April 2019 Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18337A2472019-01-17017 January 2019 Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme ML18346A3142019-01-0707 January 2019 Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067) ML18317A3822018-12-19019 December 2018 Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation ML18298A0122018-11-27027 November 2018 Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits ML18260A3392018-10-24024 October 2018 Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML18192A1042018-08-15015 August 2018 Alternative to Examination of Reactor Pressure Vessel Flange Threads ML18173A0192018-06-27027 June 2018 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule (CAC MG0244; EPID L-2017-LLL-0020) ML18115A2822018-06-19019 June 2018 Issuance of Amendment No. 260 Technical Specification Changes Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-412 Revision 3 (CAC No. MG0009; EPID L-2017-LLA-0267) ML18134A2532018-06-19019 June 2018 Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268) ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 2024-01-24
[Table view] |
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ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc. N-TSB-58 1448 S.R. 333 Russellville, AR 72802 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 27',, 201
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 -REVISION TO THE REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE {CAC NO. MG0244; EPID L-2017-LLL-0020)
Dear Sir or Madam:
By letter dated September 14, 2017 {Agencywide Documents Access and Management System {ADAMS) Accession No. ML 17257A121
), as supplemented by letters dated November 1, 2017, and March 13, 2018 (ADAMS Accession Nos. ML 17305B616 and ML 18072A229, respectively), Entergy Operations, Inc. {the licensee) submitted a request for U.S. Nuclear Regulatory Commission
{NRC) staff review and approval to revise the reactor vessel surveillance capsule withdrawal schedule for Arkansas Nuclear One, Unit 2 {AN0-2). Specifically, the licensee requested NRC approval to revise the removal intervals for capsule number 4 {W-284) and capsule number 6 {W-277). The NRC staff has reviewed the licensee's submittals and concludes that it is acceptable because it will continue to meet the surveillance capsule withdrawal schedule criteria in the American Society for Testing and Materials Standard Practice E185-82 and Appendix H to Title 10 of the Code of Federal Regulations Part 50 for the period of extended operation.
If you have any questions, please contact Thomas Wengert at (301) 415-4037 or by e-mail at Thomas.Wengert@nrc.gov.
Docket No. 50-368
Enclosure:
Safety Evaluation cc: Listserv Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING CHANGES TO THE REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM ENTERGY NUCLEAR OPERATIONS, INC. ARKANSAS NUCLEAR ONE. UNIT 2 DOCKET NO. 50-368
1.0 INTRODUCTION
By letter dated September 14, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17257A121), as supplemented by letters dated November 1, 2017, and March 13, 2018 (ADAMS Accession Nos. ML 173056616 and ML 18072A229, respectively), Entergy Operations, Inc. (Entergy, the licensee) submitted a request to revise the surveillance capsule withdrawal schedule for the reactor vessel (RV) material surveillance program for Arkansas Nuclear One, Unit 2 (AN0-2). The submittal proposed to make two changes to the capsule removal schedule: ( 1) revise the "Removal Interval" of the previously pulled surveillance capsule from the estimated 30 effective full power years (EFPY) to the actual measured interval, and (2) revise the withdrawal schedule of capsule number 6 from its status as standby capsule to one being withdrawn and tested at a minimum of 40 EFPY, to support the additional 20-year period of extended operation (PEO). 2.0 REGULA TORY EVALUATION Title 10 of the Code of Federal Regulations ( 10 CFR) Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements," requires that RVs that will exceed a neutron fluence of 1 x 10 17 neutrons per square centimeter (n/cm 2) (E > 1.0 MeV) at the end of their design life must have their beltline materials monitored by a surveillance program complying with American Society for Testing and Materials (ASTM) E185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." Specifically, Appendix H to 10 CFR Part 50 requires that the design of the surveillance program and the withdrawal schedule meets the requirements of the edition of ASTM E185 that was current on the issue date of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code to which the RV was purchased.
However, later editions, up to and including the 1982 Edition of ASTM E185 (ASTM E185-82), may be used instead. Section 111(8)(3) of 10 CFR Part 50, Appendix H requires that surveillance capsule withdrawal schedules be submitted to and approved by the NRC staff prior to implementation.
Enclosure In 2003, pursuant to NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," the licensee applied for an additional 20-year period of extended operation beginning on July 17, 2018. The NRC reviewed the submittal and issued the renewed license in June 2005. Revision 2 of the GALL Report states, in part: The plant-specific or integrated surveillance program shall have at least one capsule with a projected neutron fluence equal to or exceeding the 60-year peak reactor vessel wall neutron fluence prior to the end of the period of extended operation.
The fluence value for capsule W-284, the most recently pulled capsule at AN0-2, is below the predicted fluence for 60 years of operation.
Therefore, the licensee proposes to adjust the withdrawal schedule to remove a standby surveillance capsule during the PEO and testing it in accordance with the guidance in the GALL Report. 3.0 TECHNICAL EVALUATION AN0-2 is following the requirements of ASTM E185-82 to comply with the surveillance capsule withdrawal requirements of 10 CFR Part 50, Appendix H. Table 1 of ASTM E185-82 defines the minimum number of capsules required to be withdrawn and tested, based on the predicted transition temperature shift at the inner surface of the RV. The withdrawal schedule initially assumed a design life of 40 EFPY and was developed using the column for 3 specimen capsules with the following requirements:
- 1. The first capsule must be withdrawn either at 6 EFPY or at the time when the accumulated neutron fluence of the capsule exceeds 5x10 18 n/cm 2 , or at the time when the highest predicted
~RT NDT (the shift in the reference temperature nil ductility transition) of all encapsulated materials is approximately 50 degrees Fahrenheit
(°F), whichever comes first. 2. The second capsule must be withdrawn either at 15 EFPY or at the time when the accumulated neutron fluence of the capsule corresponds to the approximate end of life (EOL) fluence at the reactor vessel inner wall location, whichever comes first. 3. The third capsule must be withdrawn at a time where the accumulated neutron fluence exceeds the limiting fluence of the reactor vessel at the EOL but not exceeding twice the peak EOL vessel fluence. Table 1, "Current Capsule Removal Schedule," of the licensee's submittal provides the current RV surveillance capsule withdrawal schedule, as well as the removal intervals (EFPY) and location of the capsules that were previously removed and tested. Capsules W-97, W-104 and W-284 were removed at 1.69 EFPY, 15. 7 EFPY, and 30 EFPY, respectively with corresponding fluence values of 3.4x10 18 n/cm 2 , 2.937x10 19 n/cm 2 , and 3.67x10 19 n/cm 2 , respectively.
Three other capsules were designated as STANDBY for future testing. The NRC staff reviewed the licensee's previous capsule withdrawal schedule and determined that it complies with the withdrawal schedule set forth in ASTM E185-82 for 40 years of operation. In its submittal, the licensee proposed three modifications to the previously approved withdrawal schedule, which are listed in Table 2, "Proposed Revision to Capsule Removal Schedule," as discussed below: (1) The licensee proposed to change the removal interval for capsule W-284 from 30 to 29.24 EFPY, which represents the measured interval from the capsule summary report. The NRC staff determined that this is solely an editorial change and is, therefore, acceptable.
(2) The licensee proposed to revise the interval of capsule W-277 from STANDBY to a minimum of 40.00 EFPY. AN0-2 is currently licensed to operate for 60 years (approximately 54 EFPY) and revised pressure-temperature (P-T) limits are being developed from the results of capsule W-284 to cover the PEO. The fluence value measured from that surveillance capsule is less than the predicted value at 60 years of operation and, as a result, is not valid for the current life of the plant. Therefore, the withdrawal and testing of capsule W-277 is in accordance with the guidance in the GALL report. All three capsules have the same lead factor of 1.35, however only capsule W-263 contains Standard Reference Materials in place of AN0-2 specific RV material, as contained in both capsules W-83 and W-277. Capsule W-277 was chosen to be withdrawn and tested arbitrarily.
The NRC staff concludes that the choice of withdrawing this capsule is acceptable because the two remaining capsules provide a wider array of materials to be irradiated for further testing. At 40 EFPY, Capsule W-277 will accumulate the projected 60-year peak vessel fluence of 4.98 x 10 19 n/cm 2. (3) As a result of the above discussion, the licensee revised Note (a) at the bottom of Table 2 of the licensee's submittal dated September 14, 2017, from 48 EFPY to 54 EFPY to accurately represent 60 calendar years of operation.
The NRC staff concludes that this change is consistent with the currently-licensed PEO and therefore is acceptable.
The NRC staff concludes that the proposed changes to the AN0-2 withdrawal schedule for: (1) capsule W-277 from STANDBY to 40 EFPY, (2) capsule W-284 from 30 to 29.24 EFPY, and (3) Table 2 Note (a) from 48 to 54 EFPY are acceptable for continued operation, do not result in a decrease in safety or security, and are consistent with ASTM E185-82, as supplemented by the GALL Report guidance.
4.0 CONCLUSION
The NRC staff reviewed Entergy's proposed withdrawal schedules for AN0-2 and determined that the changes to the schedule will continue to meet the RV surveillance capsule withdrawal schedule criteria in ASTM E185-82, as supplemented by the GALL Report guidance, and 10 CFR Part 50, Appendix H for AN0-2's period of extended operation.
The staff, therefore, concludes that the RV withdrawal schedule, as proposed in the licensee's letter dated September 14, 2017, is acceptable for implementation.
Principal Contributor:
A. Young Date: June 27, 2018
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 -REVISION TO THE REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (CAC MG0244; EPID L-2017-LLL-0020)
DATED JUNE 27, 2018 DISTRIBUTION:
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