Document: NUREG-0800
Document ID: 0dcda381-7ccf-499e-b926-b844f97fc4cf
Document Type: srp
Title: MAIN CONDENSERS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070586.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.1
CFR Part: 
CFR Title: 

Content:
ser system design is acceptable and meets the requirements of GDC 60 with respect to failures in the design of the system which do not result in excessive releases of radioactivity to the environment. The applicant has met this requirement by providing radioactiveradioactivity monitors in the 31 system to detect leakage into and out of the main condenser. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.32 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 33 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.34 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criterion 60, "Control of Releases of Radioactive Materials to the Environment." 2. Regulatory Guide 1.68, "Initial Test Programs for Water-Cooled Reactor Power Plants." 3. Regulatory Guide 1.96, "Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants."35 4. SECY-93-087, "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (AWLR) Designs,"