Document: NUREG-0800
Document ID: fde4aca8-91fc-456b-a158-beaedf808cb2
Document Type: srp
Title: STEAM GENERATOR PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380194.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.2.2
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Content:
ications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced regulatory guides contain implementation schedules for conformance to the parts of the method discussed herein. VI. REFERENCES 1. 10 CFR 50.36, “Technical Specifications.” 2. 10 CFR 50.55a, “Codes and Standards.” 3. 10 CFR Part 50, Appendix A, General Design Criterion 32, “Inspection of Reactor Coolant Pressure Boundary.” 4. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 5. 10 CFR 50.65, “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.” 6. Regulatory Guide 1.121, “Bases for Plugging Degraded PWR Steam Generator Tubes.” 7. NUREG-1430, “Standard Technical Specifications for Babcock and Wilcox Pressurized Water Reactors.” 5.4.2.2-11 Revision 2 - March 2007 8. NUREG-1431, “Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors.” 9. NUREG-1432, “Standard Technical Specifications for Westinghouse Pressurized Water Reactors.” 10. “Notice of Availability of Model Application Concerning Technical Specification Improvement To Modify Requirements Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process,” ADAMS Accession No. ML051160106, May 2, 2005. 11. “Notice of Opportunity To Comment on Model Safety Evaluation on Technical Specification Improvement To Modify Requirements Regarding the Addition of LCO 3.4.[17] on Steam Generator