Document: NUREG-0800
Document ID: bcfc82c4-2420-4dbd-9351-ac433c1d2309
Document Type: srp
Title: CONDENSATE CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070599.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.6
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CFR Title: 

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rational occurrences by reducing corrosion of BWR reactor system components and of PWR steam generator tubes and materials, thereby reducing the likelihood and magnitude of reactor piping failures and of primary-to-secondary coolant leakage. This requirement has been met by the applicant's design of the CCS meeting the regulatory positions of Regulatory Guide 1.56 for BWRs and meeting the Branch Technical Position MTEB 5-3 for PWRs. 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.34 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan 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 35 cases in which the applicant proposes an acceptable alternative method for complying with DRAFT Rev. 3 - April 1996 10.4.6-6 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.36 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 2. Regulatory Guide 1.56, "Maintenance of Water Purity in Boiling Water Reactors." 3. Branch Technical Positions ASB 3-1, "Protection Against Postulated Piping Failures in Fluid Systems Outside Containment," attached to SRP Section 3.6.1, "Plant Design for Protection Against