Document: NUREG-0800
Document ID: b4734a50-4d73-4532-b9ec-2c7890d55a94
Document Type: srp
Title: and are compared by the reviewer with those provided by the applicant.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070364.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
rod drive system to withstand effects of earthquakes and conditions of normal operation, including anticipated normal operational occurrences with adequate margins 66 to assure its reactivity control function and with extremely low probability of leakage or gross rupture of reactor coolant pressure boundary. The CRDS design capabilities include the ability to accommodate water hammer dynamic loads resulting from rapid opening of the scram insert and withdraw valves and closure of the hydraulic buffer under the worst case loading condition without compromising the safety functions of the system. The specified design transients, design and service loadings, combination of 67 loads, and limiting the stresses and deformations under such loading combinations are in conformance with the requirements of appropriate ANSI and ASME Codes and acceptable regulatory positions specified in SRP Section 3.9.3. For BWRs, also include the following: The CRDS design capabilities include the ability to accommodate water 68 hammer dynamic loads resulting from rapid opening of the scram insert and withdraw valves and closure of the hydraulic buffer under the worst case loading condition without compromising the safety functions of the system.69 3. The applicant has met the requirements of GDC 27 and 29 with respect to designing the control rod drive system to assure its capability of controlling reactivity and cooling the reactor core with appropriate margin, in conjunction with either the emergency core cooling system or the reactor protection system. The operability assurance program is acceptable with respect to meeting system design requirements in observed performance as to wear, functioning times, latching, and overcoming a stuck rod. 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),