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
CFR Part: 
CFR Title: 

Content:
management systems under SRP Sections 11.2, 11.3, and 11.4. 10.4.6-5 DRAFT Rev. 3 - April 1996 4. RABPERB determines the adequacy of the shielding design of the condensate 32 demineralizers under SRP Section 12.2. For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.33 IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided to support conclusions of the following type, to be included in the staff's safety evaluation report: The condensate cleanup system includes all components and equipment necessary for the removal of dissolved and suspended impurities which may be present in the condensate. Based on the staff's review of the applicant's proposed design criteria and design bases for the condensate cleanup system and the requirements for operation of the system, the staff concludes that the design of the condensate cleanup system and supporting systems is acceptable and meets the primary boundary integrity requirements of General Design Criterion 14. This conclusion is based on the applicant having met the requirements of GDC 14 as it relates to maintaining acceptable chemistry control for BWR reactor coolant and for PWR secondary coolant during normal operation and anticipated operational 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