Document: NUREG-0800
Document ID: d4d35b7c-b4e5-4cb4-8dd9-1b7edddf0ad6
Document Type: srp
Title: CHEMICAL AND VOLUME CONTROL SYSTEM (PWR) (INCLUDING BORON
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070537.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.4
CFR Part: 
CFR Title: 

Content:
that contain (or may contain) radioactive material following an accident (OL) or NUREG-0718 (CP) as it relates to establishing a leak reduction program ; and (9) the relevant requirements of 10 69 CFR 50.63(a)(2) and the guidance of Regulatory Guide 1.155 positions C.3.2, C.3.3.4, and C.3.5 by demonstrating the capability of the CVCS to support the plant's ability to withstand or cope with, and recover from a station blackout. Conformance with 10 CFR 50.63 requirements for station blackout is discussed in further detail in Section 8.4 of this report.70 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.71 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 72 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 guidelines for primary water chemistry described in subsection III.A.5 are used for the evaluation of new applications. Also, pending further regulatory action (e.g., issuance of an approved Regulatory 73 Guide) to resolve Generic Safety Issues with respect to the integrity of reactor coolant pump seals, the method for review of the adequacy of the reactor coolant pump seal integrity for station blackout described in subsection III.E is used for