Document: NUREG-0800
Document ID: 7bd74f6c-471d-40b1-9659-6a5e00c5f169
Document Type: srp
Title: MAINTENANCE RULE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1409/ML14099A044.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.6
CFR Part: 
CFR Title: 

Content:
R in Chapter 17 of the Safety Evaluation Report (SER)-approved generic design certification document. Note 3: Submission of actual procedures or software for review is not required or expected for the COL application, but they must be available for NRC inspection by the time the program is required to be implemented (i.e., by the time fuel load is authorized). Note 4: If an applicant proposes to use the existing MR program used for its operating plants for new plants, then applicability to, and adjustments required by, the new plant design must be addressed. A new passive plant (AP1000 or Economic Simplified Boiling-Water Reactor (ESBWR)) may be built next to an active pressurized-water reactor/boiling-water reactor. 1. Scoping in accordance with 10 CFR 50.65(b) The applicant should describe its process for determining which plant SSCs, will be included in the scope of the MR program in accordance with 10 CFR 50.65(b) of the rule and the NRC-endorsed guidance. The program description should indicate that additional SSC functions may be added to or subtracted from the MR scope prior to fuel load, as appropriate, as additional information is developed (e.g., emergency operating procedures (EOPs)) after the license is issued. The description of the MR scoping process should address: A. The criteria for including safety-related SSCs relied upon to remain functional during and following design-basis events in accordance with 10 CFR 50.65(b)(1). B. The criteria for including nonsafety-related SSCs in accordance with 10 CFR 50.65(b)(2). Specifically, the criteria are: i. Nonsafety-related SSCs that are relied upon to mitigate accidents or transients or are used in plant EOPs; or ii. Nonsafety-related SSCs whose failures could prevent safety-related SSCs from fulfilling their safety function; or iii. Nonsafety-related SSCs whose failure could cause a reactor scram or actuation of a safety-related system. Related to Item 1.B.i, nonsafety-related SSCs that are necessary to be