Document: NUREG-0800
Document ID: f9ea930a-8e7e-4e1f-b7a5-caeeffb721d5
Document Type: srp
Title: STEAM GENERATOR TUBE INSERVICE INSPECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070447.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.2.2
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CFR Title: 

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criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.43 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 44 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.45 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulations, regulatory guides, and NUREGs and in 10 CFR Part 50, Section 50.36.46 VI. REFERENCES 1. 10 CFR 50.55a, "Codes and Standards."47 1.2. 10 CFR Part 50, Appendix A, General Design Criterion 32, "Inspection of Reactor 48 Coolant Pressure Boundary". 2.3. Regulatory Guide 1.83, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes". 4. Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes".49 3.5. NUREG-0103, "Standard Technical Specifications for Babcock and Wilcox Pressurized Water Reactors". 5.4.2.2-7 DRAFT Rev. 2 - April 1996 4.6. NUREG-0212, "Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors". 5.7. NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors". 8. NUREG-0844, "NRC Integrated Program for the Resolution of Unresolved Safety Issues A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity."50 9. NUREG-1430, "Standard Technical