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Category:Letter
MONTHYEARIR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000334/20230052023-08-31031 August 2023 Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005) ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000334/20230022023-08-0909 August 2023 Integrated Inspection Report 05000334/2023002 and 05000412/2023002 L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23219A0592023-08-0707 August 2023 Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time 2024-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23019A0032023-03-16016 March 2023 Issuance of Amendment Nos. 320 and 210 Adoption of Technical Specifications Task Force (Tstf) Traveler Tstf-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23062A5212023-03-0606 March 2023 Issuance of Amendment No. 319 Revise Technical Specification (TS) 3.5.2, ECCS Operating, Limiting Condition for Operation (LCO) 3.5.2, ML22277A8142022-10-0707 October 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22235A7672022-09-0101 September 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22222A0862022-09-0101 September 2022 Issuance of Amendment Nos. 317 and 208 Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22140A2092022-06-28028 June 2022 Issuance of Amendment No. 207 Correct TS 3.1.7 Change Made by TSTF-547 ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21286A7822022-05-0606 May 2022 Issuance of Amendment Nos. 315 and 205 Regarding Changes to the Emergency Plan ML22077A1342022-05-0202 May 2022 Issuance of Amendment Nos. 314 and 204 Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves ML21153A1762021-06-30030 June 2021 Issuance of Amendment No. 201 Revision of Technical Specifications Related to Steam Generator Tube Inspection, and Repair Methods ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor ML20335A0522021-02-18018 February 2021 Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition ML20345A2362021-01-28028 January 2021 Issuance of Amendment Nos. 307 and 197 to Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20335A0232020-12-28028 December 2020 Issuance of Amendment Nos. 306 and 196 to Remove License Conditions B and C Related to the Irradiated Fuel Management Plans ML20285A2662020-10-21021 October 2020 Correction to Safety Evaluation for Amendment Nos. 305 and 195 Issued September 23, 2020, Modify Primary and Secondary Coolant Activity Technical Specifications ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications ML20223A0142020-08-20020 August 2020 Issuance of Relief Request SSR-1, Revision 0, from the Requirements of the ASME Code (EPID L-2020-LLR-0050 (COVID-19)) ML20206K8652020-08-0707 August 2020 Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 (COVID-19)) ML20153A0142020-07-16016 July 2020 Relief from the Requirements of the American Society of Mechanical Engineers Code Regarding Request VRR4 (EPID L-2020-LLR-0052 (COVID-19)) ML20145A0002020-06-0303 June 2020 Relief from the Requirements of the ASME Code for Requests VRR6 and VRR5 (EPID L-2020-LLR-0049 and EPID L-2020-LLR-0051 (COVID-19)) ML20080J7892020-04-28028 April 2020 Relief Requests 2 TYP-3-B3.110-1, 2-TYP-3-C2.21-1, 2-TYP-3-C1.30-1, and 2-TYP-3-RA-1 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20079F8162020-03-26026 March 2020 Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval ML19336A0282019-12-18018 December 2019 Safety Evaluation Irradiated Fuel Management Plans ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19275E2942019-10-16016 October 2019 Issuance of Relief Request Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in Lieu of Specific ASME Code Requirements ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML18348B2062019-02-25025 February 2019 Issuance of Amendment No. 193 Revise Steam Generator Technical Specifications ML18249A1692018-09-0707 September 2018 Seismic Hazard Mitigation Strategies Assessment (CAC Nos. MF7800 and MF7801; EPID L-2016-JLD-0006) ML18227A7332018-08-27027 August 2018 Request for Relief from the Requirements of the ASME Code ML18205A2922018-08-10010 August 2018 Correction of Errors in Safety Evaluation Associated with Relief Request 2-TYP-4-RV-02 ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18178A1122018-07-0202 July 2018 Relief Request No. 2-TYP-4-RV-02 Regarding the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements ML18065A4032018-04-0505 April 2018 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 301 and 190 ML18073A1062018-03-28028 March 2018 Safety Evaluation of Proposed Alternatives 1-TYP-4-BA-01 and TYP-4-BN-01 Regarding the Fourth 10- Year Interval of the Inservice Inspection Program 2024-07-16
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Text
July 16, 2024
Barry N. Blair Vistra Operations Company LLC Beaver Valley Power Station Mail Stop P-BV-SSB P.O. Box 4, Route 168 Shippingport, PA 15077-0004
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (EPID L-2024-LRQ-0004)
Dear Barry Blair:
By letter dated June 24, 2024 (Agencywide Documents Access and Management System Accession No. ML24176A114), Vistra Operations Company LLC (VistraOps, the licensee) requested revision of the reactor vessel material surveillance capsule withdrawal schedule for the Beaver Valley Power Station (BVPS or Beaver Valley), Units 1 and 2, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix H, Reactor Vessel Material Surveillance Program Requirements,Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation.
The NRC staff has reviewed the submittal and concludes that the proposed changes are acceptable and consistent with the intent and requirements of the applicable regulations and guidance found in Appendix H to 10 CFR Part 50, as well as American Society for Testing and Materials Standard E 185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, dated July 1, 1982. Furthermore, the proposed change meets the guidance in NUREG-1801, Revision 2, Generic Aging Lessons Learned (GALL) Report, dated December 2010. The NRC staffs related safety evaluation is enclosed.
B. Blair
If you have any questions, please contact V Sreenivas, Project Manager at 301-415-2597 or by email to V.Sreenivas@nrc.gov
Sincerely,
Hipólito González, Branch Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-334 and 50-412
Enclosure:
Safety Evaluation
cc: Listserv SAFETY ASSESSMENT BY THE OFFICE OF NUCLEAR REACTOR REGULATION
REQUEST FOR REVISION TO
REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM
WITHDRAWAL SCHEDULE
VISTRA OPERATIONS COMPANY LLC
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2
DOCKET NOS. 50-334 AND 50-412
EPID L-2024-LLQ-0004
1.0 INTRODUCTION
By letter dated June 24, 2024 (Agencywide Documents Access and Management System Accession No. ML24176A114), Vistra Operations Company LLC (VistraOps, the licensee) requested revision of the reactor vessel material surveillance capsule withdrawal schedule for the Beaver Valley Power Station (BVPS or Beaver Valley), Units 1 and 2, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix H, Reactor Vessel Material Surveillance Program Requirements,Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation.
Specifically, the licensee proposed to revise the reactor vessel material surveillance capsule withdrawal schedule at Beaver Valley so that supplemental Surveillance capsule A, which is comprised of previously irradiated BVPS-1 surveillance materials, unirradiated BVPS-1 surveillance materials, and materials from the Fort Calhoun and St. Lucie surveillance programs, and footnote 3 is removed from BVPS-2 Updated Final Safety Analysis Report (UFSAR) Table 5.3-6, Reactor Vessel Material Irradiated Surveillance Schedule.
2.0 REGULATORY EVALUATION
The regulations and guidance relevant to this request are the following.
Section I of Appendix H to 10 CFR Part 50, which states, in part:
The purpose of the [reactor vessel] material surveillance program required by this appendix is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of light water nuclear power reactors which result from exposure of these materials to neutron irradiation and the thermal environment.
Under the program, fracture toughness test data are obtained from material specimens exposed in surveillance capsules, which are withdrawn periodically from the reactor vessel.
Section III.B.1 of Appendix H to 10 CFR Part 50, which states, in part:
The design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of ASTM E185 [an industry standard by ASTM International, formerly known as American Society for Testing and Materials] that is current on the issue date of the ASME code [American Society of Mechanical Engineers Boiler and Pressure Vessel Code] to which the reactor vessel was purchased; . later editions of ASTM E185 may be used, but including only those editions through 1982.
Section III.B.3 of Appendix H to 10 CFR Part 50, which states:
A proposed withdrawal schedule must be submitted with a technical justification as specified in [10 CFR] 50.4. The proposed schedule must be approved prior to implementation.
U.S. Nuclear Regulatory Commission (NRC, the Commission) Administrative Letter 97-04, NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules, dated September 30, 1997 (ML031210296), which states, in part:
The Commission found that while 10 CFR Part 50, Appendix H, III.B.3 requires prior NRC approval for all withdrawal schedule c hanges, only certain changes require license amendments as the process to be followed for such approval. Specifically, those changes that do not conform to the ASTM standard referenced in Appendix H (ASTM E-185, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels) will require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance.
NUREG-1801, Revision 2, Generic Aging Lessons Learned (GALL) Report, dated December 2010 (ML103490041), which lists generic aging management reviews of systems, structures, and components (SSCs) that may be in the scope of a license renewal application and identifies aging management programs that are determined to be acceptable to manage aging effects of these SSCs.
3.0 TECHNICAL EVALUATION
3.1 Licensees Proposal for BVPS-1 and BVPS-2
The licensee explained that it is requesting approval of a modified reactor vessel surveillance capsule withdrawal schedule for BVPS-2. Specifically, with respect to surveillance capsule A, which is comprised of previously irradiat ed BVPS-1 surveillance materials, unirradiated BVPS-1 surveillance materials, and materials from the Fort Calhoun and St. Lucie surveillance programs, that was installed in the BVPS-2 so that end of license extension fluence values would be accrued more efficiently. As a result, the withdrawal schedule for BVPS-1 surveillance capsule A is tracked on the BVPS-2 surveillance capsule withdrawal schedule.
The current BVPS-2 Updated Final Safety Analysis Report (UFSAR) Table 5.3-6, Reactor Vessel Material Irradiation Surveillance Schedule, includes, in part, surveillance capsule A to be withdrawn at 32 effective full power years (EFPY). The licensee proposes to remove surveillance capsule A from BVPS-2 UFSAR Table 5.3-6, as well as footnote 3, which states:
Supplemental Capsule A contains Beaver Valley Unit 1 initially unirradiated material specimens, as well as previously irradiat ed material specimens from Beaver Valley Unit 1, St. Lucie, and Fort Calhoun. Supplemental Capsule A was inserted in the vacant Capsule V location at the end of Cycle 8. In order to be consistent with the Materials Reliability Program: Coordinated PWR Reacto r Vessel Surveillance Program (CRVSP)
Guidelines (MRP-326) recommendation, Capsule A is to be removed and tested when it reaches a fluence value equivalent to the peak 80-year vessel fluence for Beaver Valley Unit 1. This is expected to occur at approximately 32 FPY.
3.2 NRC Staff Review
Appendix H to 10 CFR Part 50 requires, in part, that the design of the surveillance program and the withdrawal schedule meet the requirements of ASTM E185, Standard Recommended Practice for Conducting Surveillance Tests for Light-Water Cooled Reactor Vessels. The BVPS-1 operating license is scheduled to expire at midnight January 29, 2036 (i.e., the end of the renewed 60-year operating license). Additionally, the BVPS-2 operating license is scheduled to expire at midnight May 27, 2047 (i.e., the end of the renewed 60-year operating license).
As of July 2024, BVPS-1 has withdrawn and tested a total of five surveillance capsules (i.e., Capsules V, U, W, Y, and X). The test results from the latest surveillance capsule (i.e., Capsule X) are documented in WCAP-17896-NP , Revision 0, Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program, (ML14288A393). Per WCAP-17896-NP, Capsule X received a neutron fluence of 5.07 x 10 19 n/cm2 after an irradiation time of 26.6 EFPY.
Consistent with ASTM E185-82, the withdrawal of Capsule X for a 40-year license was completed at a neutron fluence that was not less than once or greater than twice the peak end-of-life vessel fluence (i.e., 3.54 x 10 19 n/cm2). This peak end-of-life neutron fluence for the 40-year license is provided in WCAP-15571-NP, Revision 1, Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program (ML082740207). Based on the review of the capsules that have already been withdrawn and tested for BVPS-1, the NRC staff notes that no additional surveillance capsules are required to be withdrawn and tested to satisfy Appendix H to 10 CFR Part 50 and ASTM E185-82 for the original 40-year license.
The NRC staff notes that the projected neutron fluence (E> 1.0 MeV) at the core mid-plane for the BVPS-1 reactor vessel at the end of 60-year renewed license is 5.89 x 10 19 n/cm2 per the current BVPS-1 surveillance capsule withdrawal schedule located in FSAR Table 4.5-3, Reactor Vessel Material Irradiation Surveillance Schedule. This capsule withdrawal schedule was approved by the NRC in a safety eval uation dated July 2, 2018 (ML18164A082). FSAR Table 4.5-3 indicates that Capsule Z will be withdrawn after 39 EFPY, which corresponds to the peak vessel fluence at the end of the 60-year renewed license. Additionally, the NRC concluded, in part, in its safety evaluation dated July 2, 2018, that the surveillance capsule withdrawal schedule for BVPS-1, which includes Capsule Z, meets the requirements in Appendix H to 10 CFR Part 50, is in compliance with ASTM E185-82, and is consistent with the recommendations of GALL Report Section XI.M31.
As discussed above, the licensee has fulfilled its material surveillance requirements for the original 40-year license with the withdrawal and testing of Capsules V, U, W, Y, and X, and the approved BVPS-1 capsule withdrawal schedule includes the withdrawal and testing of Capsule Z. The NRC staff noted that withdrawal and testing of Capsule Z fulfills the
recommendations in GALL Report Section XI.M31 and ensures adequate aging management of the reactor vessel for irradiation embrittlement during the 60-year renewed license. Based on the review of the five capsules that have already been withdrawn and tested for BVPS-1, and with the planned withdrawal and testing of Capsule Z in accordance with its approved capsule withdrawal schedule, the NRC staff notes that no additional surveillance capsules, including the mechanical testing and reporting of results for supplemental surveillance capsule A, are required to satisfy Appendix H to 10 CFR Part 50 and ASTM E185-82 for the original 40-year license or the 60-year renewed license.
The licensee has already fulfilled its reactor vessel material surveillance requirements for BVPS-1 for the original operating license period (i.e., 40 years), and will be withdrawing Capsule Z consistent its approved surveillance capsule withdrawal schedule located in FSAR Table 4.5-3, Reactor Vessel Material Irradiation Surveillance Schedule, which address the recommendations in NUREG-1801, Revision 2, for its current operating license through 60-years of operation. The NRC staff notes that a report containing the test results for supplemental Surveillance capsule Z must be reported to the NRC within 18 months of the capsule withdrawal in accordance with Section IV.A of Appendix H to 10 CFR Part 50.
Based on its review of the capsules that have already been withdrawn and tested for BVPS-1, and with the planned withdrawal and testing of Capsule Z (per UFSAR Table 4.5-3 BVPS-1), the NRC staff finds the proposed withdrawal schedule to remove Surveillance capsule A and footnote 3 from UFSAR Table 5.3-6 for BVPS-2, will not impact the licensees ability:
to address the underlying purpose of Appendix H to 10 CFR Part 50 (i.e., monitor changes in the fracture toughness properties of the reactor pressure vessel) and to demonstrate compliance with Appendix H to 10 CFR Part 50 and ASTM E185-82 for the continued plant operation of BVPS-1 through the 60-year renewed license.
Therefore, the NRC staff finds that the licensees proposed withdrawal schedule for surveillance capsule A and footnote 3 to be removed from UFSAR Table 5.3-6 for BVPS-2 is acceptable.
The NRC staff concludes that the withdrawal and testing of Surveillance capsule A is not necessary for compliance to the requirements of the reactor vessel material surveillance program for the current license period at BVPS-1.
4.0 CONCLUSION
Based on the above evaluation, the NRC staff conc ludes that the proposed surveillance capsule withdrawal schedule for Beaver Valley Power Station to remove surveillance capsule A and foot note 4 from UFSAR Table 5.3-6 for BVPS-2 is acceptable; therefore, the NRC staff approves this surveillance capsule withdrawal schedule.
Principal Contributors: O. Yee, NRR
Date: July 16, 2024
ML24193A291 NRR-106 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DNRL/NVIB/BC NAME VSreenivas KZeleznock ABuford DATE 07/11/2024 07/15/2024 07/10/2024 OFFICE NRR/DORL/LPL1/BC NAME HGonzález DATE 07/16/2024