Document: NUREG-0800
Document ID: ba447c99-c09a-4d8c-84cd-804a2261f17c
Document Type: srp
Title: MAINTENANCE RULE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0729/ML072920088.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.6
CFR Part: 
CFR Title: 

Content:
ety-related functions in accordance with 50.65(b)(2)(ii). The applicant | should describe how the process considers system interdependencies, | including failure modes and effects of nonsafety-related SSCs (e.g., | support systems) that could directly affect safety-related functions. | (iv) SSCs whose failure could cause scrams or unwanted engineered | safeguard feature actuations and those whose failure caused a reactor SCRAM or actuation of safety-related systems at the applicant’s plant or plants of similar design in accordance with 50.65(b)(2)(iii). The applicant | should describe the process for identifying and using relevant utility- | specific and industry-wide operating experience. NOTE: If at the time of the COL application, the Commission has approved the | applicant’s program for implementing 10 CFR 50.69 for its new reactor plant, the | requirements of 50.69 may be followed instead of those of 50.65 for risk- | informed safety classification (RISC)-3 and RISC-4 SSCs in the scope of the MR | except for the purposes of 50.65(a)(4). In this case, the applicant should | describe its process for identifying RISC-3 SSCs among those in MR scope | 17.6-6 Revision 1 - August 2007 under 50.65(b)(1), and RISC-4 SSCs among those in MR scope under | 50.65(b)(2) and for treatment under 50.69 of those RISC-3 and RISC-4 SSCs | that would otherwise be treated in accordance with 50.65. Deviations in this | process from SSC risk classification and treatment in accordance with NUMARC | 93-01, as endorsed by RG 1.160, where it would result in classifying as RISC-3 | or RISC-4 an SCC that otherwise would be classified as high-safety-significant | (HSS) under NUMARC 93-01, as endorsed by RG 1.160, or would otherwise be | classified as HSS consistent with a new reactor design, should be identified and | explained. | C. Specific information on the actual SSCs within the scope of the MR program will | be reviewed as part of the operational program implementation inspection by