2191 R0 XI.M37

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XI.M37 FLUX THIMBLE TUBE INSPECTION

Program Description

The Flux Thimble Tube Inspection is a condition monitoring program used to inspect for thinning of the flux thimble tube wall, which provides a path for the incore neutron flux monitoring system detectors and forms part of the reactor coolant system (RCS) pressure boundary. Flux thimble tubes are subject to loss of material at certain locations in the reactor vessel where flow-induced fretting causes wear at discontinuities in the path from the reactor vessel instrument nozzle to the fuel assembly instrument guide tube. A periodic nondestructive examination methodology, such as eddy current testing (ECT) or other applicant-justified and the U.S. Nuclear Regulatory Commission (US NRC)-accepted inspection method, is used to monitor for wear of the flux thimble tubes. This program implements the recommendations of US NRC Bulletin 88-09, as described below.

Evaluation and Technical Basis

1. Scope of Program: The flux thimble tube inspection encompasses all of the flux thimble tubes that form part of the RCS pressure boundary. The instrument guide tubes are not in the scope of this program. Within scope are the licensee responses to US NRC Bulletin 88-09, as accepted by the staff in its closure letters on the bulletin, and any amendments to the licensee responses as approved by the staff.

2. Preventive Actions: The program consists of inspection and evaluation and provides no guidance on preventive actions.

3. Parameters Monitored or Inspected: Flux thimble tube wall thickness is monitored to detect loss of material from the flux thimble tubes during the subsequent period of extended operation.

4. Detection of Aging Effects: An inspection methodology (such as ECT) that has been demonstrated to be capable of adequately detecting wear of the flux thimble tubes is used to detect loss of material during the subsequent period of extended operation. Justification for methods other than ECT should be provided unless use of the alternative method has been previously accepted by the US NRC.

Examination frequency is based upon actual plant-specific wear data and wear predictions that have been technically justified as providing conservative estimates of flux thimble tube wear. The interval between inspections is established such that no flux thimble tube is predicted to incur wear that exceeds the established acceptance criteria before the next inspection. The examination frequency may be adjusted based on plant-specific wear projections. Re-baselining of the examination frequency should be justified using plant-specific wear-rate data unless prior plant-specific US NRC acceptance for the re-baselining is received outside the license renewal process. If design changes are made to use more wear-resistant thimble tube materials [e.g., chrome-plated stainless steel (SS)], sufficient inspections are conducted at an adequate inspection frequency, as described above, for the new materials.

5. Monitoring and Trending: Flux thimble tube wall thickness measurements are trended and wear rates are calculated based on plant-specific data using a methodology that includes sufficient conservatism to ensure that wall thickness acceptance criteria continue to be met during plant operation between scheduled inspections. Corrective actions are taken when trending results project that acceptance criteria would not be met prior to the next planned inspection or the end of the subsequent period of extended operation.

6. Acceptance Criteria: Appropriate acceptance criteria, such as percent through-wall wear, are established, and inspection results are evaluated and compared with the acceptance criteria. The acceptance criteria are technically justified to provide an adequate margin of safety to ensure that the integrity of the reactor coolant system pressure boundary is maintained. The acceptance criteria include allowances for factors such as instrument uncertainty, uncertainties in wear scar geometry, and other potential inaccuracies, as applicable, to the inspection methodology chosen for use in the program. Acceptance criteria different from those previously documented in the applicant’s response to Bulletin 88-09 and amendments thereto, as accepted by the US NRC, should be justified.

7. Corrective Actions: Results that do not meet the acceptance criteria are addressed in the applicant’s corrective action program under those specific portions of the quality assurance (QA) program that are used to meet Criterion XVI, “Corrective Action,” of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B. Appendix A of the Generic Aging Lessons Learned for Subsequent Licensing Renewal (GALL-SLR) Report describes how an applicant may apply its 10 CFR Part 50, Appendix B, QA program to fulfill the corrective actions element of this aging management program (AMP) for both safety-related and nonsafety-related structures and components (SCs) within the scope of this program.

Flux thimble tubes with wall thickness that do not meet the established acceptance criteria are isolated, capped, plugged, withdrawn, replaced, or otherwise removed from service in a manner that ensures the integrity of the reactor coolant system pressure boundary is maintained. Analyses may allow repositioning of flux thimble tubes that are approaching the acceptance criteria limit. Repositioning of a tube exposes a different portion of the tube to the discontinuity that is causing the wear.

Flux thimble tubes that cannot be inspected over the tube length, that are subject to wear due to restriction or other defects, and that cannot be shown by analysis to be satisfactory for continued service are removed from service to ensure the integrity of the reactor coolant system pressure boundary.

8. Confirmation Process: The confirmation process is addressed through those specific portions of the QA program that are used to meet Criterion XVI, “Corrective Action,” of 10 CFR Part 50, Appendix B. Appendix A of the GALL-SLR Report describes how an applicant may apply its 10 CFR Part 50, Appendix B, QA program to fulfill the confirmation process element of this AMP for both safety-related and nonsafety-related SCs within the scope of this program.

9. Administrative Controls: Administrative controls are addressed through the QA program that is used to meet the requirements of 10 CFR Part 50, Appendix B, associated with managing the effects of aging. Appendix A of the GALL-SLR Report describes how an applicant may apply its 10 CFR Part 50, Appendix B, QA program to fulfill the administrative controls element of this AMP for both safety-related and nonsafety-related SCs within the scope of this program.

10. Operating Experience: In US NRC Bulletin 88-09 the US NRC requested that licensees implement a flux thimble tube inspection program due to several instances of leaks and due to licensees identifying wear. Utilities established inspection programs in accordance with US NRC Bulletin 88-09, which have shown excellent results in identifying and managing wear of flux thimble tubes. However, leakage events due to accelerated wear have occurred (see US NRC Event Notification Report 42822, dated August 31, 2006).

As discussed in US NRC Bulletin 88-09, the amount of vibration the thimble tubes experience is determined by many plant-specific factors. Therefore, the only effective method for determining thimble tube integrity is through inspections, which are adjusted to account for plant-specific wear patterns and history.

The program is informed and enhanced when necessary through the systematic and ongoing review of both plant-specific and industry operating experience including research and development such that the effectiveness of the AMP is evaluated consistent with the discussion in Appendix B of the GALL-SLR Report.

References

10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” Washington, DC: U.S. Nuclear Regulatory Commission. 2016.

US NRC. Bulletin 88-09, “Thimble Tube Thinning in Westinghouse Reactors.” Washington, DC: U.S. Nuclear Regulatory Commission. July 1988.

_____. Information Notice No. 87-44, “Thimble Tube Thinning in Westinghouse Reactors.” Washington, DC: U.S. Nuclear Regulatory Commission. September 1987.

_____. Information Notice No. 87-44, “Thimble Tube Thinning in Westinghouse Reactors.” Supplement 1. Washington, DC: U.S. Nuclear Regulatory Commission. March 1988.

_____. Licensee Event Notification [EN] 42822, “Technical Specification Required Shutdown Due to Unidentified Reactor Coolant System Leak.” Washington, DC: U.S. Nuclear Regulatory Commission. August 2006.

United States of America

Nuclear Regulatory Commission - The US federal government agency that regulates nuclear power plants

Quality Assurance

Generic Aging Lessons Learned - The US NRC GALL Report is NUREG-1801. The US NRC Subsequent License Renewal GALL is NUREG-2191

Subsequent License Renewal - The extension of the original license from 40 years to 60 years is known as License Renewal. Extensions of the license beyond 60 years are known as Subsequent License Renewal.

Aging Management Program