Document: NUREG-0800
Document ID: 2349ea77-1f6e-45e4-a2df-f56249a774f1
Document Type: srp
Title: CONTROL ROD DRIVE SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070364.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.4
CFR Part: 
CFR Title: 

Content:
s. For BWRs only, the CRDS is reviewed to verify that the system is capable of withstanding adverse dynamic loads such as water hammer. The response to each set of combined loads has a selected stress or deformation limit. The selection of a specific limit is influenced by the probability of the postulated event occurring and the need to assure operation during and after the event. 4. The portion of the SAR is reviewed that describes plans for the conduct of an operability assurance program or that references previous test programs or standard industry procedures for similar apparatus. For example, the life cycle test program for the CRDS is reviewed. The operability assurance program is reviewed to ascertain coverage of the following: a. Life cycle test program. b. Proper service environment imposed during test, including appropriate conditions for normal operation, anticipated normal operational occurrences, seismic, and 7 postulated accident conditions. c. Mechanism functional tests. d. Program results. Review Interfaces:8 The EMEB also performs the following reviews under the SRP sections indicated:9 1. Verifies that CRDS pressure-retaining components are acceptably classified and that corresponding appropriate quality standards are applied, as part of its primary review responsibility for SRP Sections 3.2.2 and/or 5.2.1.1.10 2. Evaluates BWR CRDS piping with respect to locations and effects of postulated piping failures under SRP Section 3.6.2.11 In addition, the EMEB will coordinate other branches' evaluations that interface with the 12 overall review of the CRDS as follows: 1. The Core Performance Branch (CPB)Reactor Systems Branch (SRXB) will 13 14 verifyevaluates the adequacy of the fuel system design, including effects of the CRDS 15 on fuel behavior in meeting the requirements of the reactor core design under various DRAFT Rev. 3 - April 1996 3.9.4-4 normal operating and accident operating conditions in SRP Section 4.2. The SRXB 16 also reviews the