Standard Review Plan for License Renewal (SRP-LR).

The SRP-LR provides technical guidance for NRC staff reviewers and documents acceptance criteria and review procedures that are acceptable to the NRC staff [7]. The SRP-LR has the purpose of assuring the quality and uniformity of NRC staff reviews and presenting a well-defined base from which to evaluate applicant programs and activities for the period of extended operation. The SRP-LR is also intended to make regulatory information widely available to enhance communication with interested members of the public and the nuclear power industry and to improve their understanding of staff reviews. This report incorporates by reference the GALL Report and Regulatory Guide 1.188.

Each SRP-LR section is organized into subsections, generally consistent with “Standard Review Plan for Review of Safety Analysis Reports for Nuclear Plants [15].” Each of the individual SRP-LR sections address: (1) who performs the review, (2) the matters that are reviewed, (3) the basis for the review, (4) the way the review is accomplished, and (5) the conclusions that are drawn. Chapter 3 of the SRP-LR addresses how the AMRs and AMPs are reviewed.

Section 3.5 of the SRP-LR addresses the AMR and the associated AMPs for containments, structures, and component supports. Section 3.5.2 of the SRP-LR provides acceptance criteria describing methods to determine whether the applicant has met the requirements of 10 CFR Part 54.21. The AMR addresses three areas:

  • (1) AMR results consistent with the GALL Report, (2) AMR results for which further evaluation is recommended in the GALL Report, and (3) AMR results that are not consistent with or not addressed in the GALL Report. For PWR and BWR containments the SRP-LR identifies a number of areas for which further evaluation is required: (1) cracking and distortion due to increased stress levels from settlement, reduction in foundation strength, and cracking due to differential settlement and erosion of porous concrete subfoundations;
  • (2) reduction in concrete strength and modulus of elasticity due to elevated temperatures; (3) loss of material due to general, pitting, and crevice corrosion; (4) loss of prestress due to relaxation, shrinkage, creep, and elevated temperature; (5) cumulative fatigue damage; (6) cracking due to stress corrosion cracking; (7) loss of material (scaling, spalling) and cracking due to freeze-thaw cycles; (8) cracking due to expansion from reaction with aggregates; and (9) increase in porosity and permeability due to leaching of calcium hydroxide and carbonation. The AMR consists of identifying the material, environment, aging effects, and the AMP(s) credited for managing the aging effects.

Review of the AMPs requires assessment of the ten program elements as defined in the SRP-LR to verify their technical adequacy. The staff verifies that the applicant’s programs are consistent with those described in the GALL Report and/or with plant conditions and operating experience during the performance of an AMP audit and review that is conducted at the applicant’s facility to evaluate the AMPs that the applicant claims to be consistent with the GALL Report.

 
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