Document: NUREG-0800
Document ID: 97b8d603-4b3f-40a3-9dbb-e89b68e654c6
Document Type: srp
Title: ANTICIPATED TRANSIENTS WITHOUT SCRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350327.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.8
CFR Part: 
CFR Title: 

Content:
o assure that under postulated accident conditions and with appropriate margin for stuck rods the core can be cooled. e. Criterion 29, which requires that the protection and reactivity control systems shall be designed to assure an extremely high probability of accomplishing their safety functions in the event of anticipated opera- tional occurrences. f. The BWR recirculation pump trip is acceptable if it meets the criteria provided in Section IV-4 of Volume 2 of NUREG-0460 (Ref. 2). III. REVIEW PROCEDURES The reviewer confirms that the reliability and performance of the reactor protection and reactivity control systems during normal operation, including anticipated transients, meets the requirements of the referenced GOC. The review procedures described below are used during the operating license (OL) review. The review procedure during a construction permit (CP) review is limited to assuring that the applicant commits to meeting the acceptance criteria. The reviewer verifies that a recirculation pump trip that is initiated by high pressure or low level in the reactor pressure vessel is provided on boiling water reactor. The reviewer verifies that emergency procedures are provided for a failure to scram after the following transients: Loss of feedwater Loss of load Turbine trip Loss of condenser vacuum Loss of offsite power Closure of main steamline isolation valves Inadvertent control rod withdrawal The reviewer verifies that the emergency operating procedures for an anticipated transient without scram event consider indicators of a failure to scram, including rod position, neutron flux, reactor coolant pressure and level, relief and safety valve position, turbine stop and main steamline isolation valve position, and feedwater and steam flow. 15.8-2 Rev. 1 - July 1981 The reviewer verifies that the emergency procedures for ATWS events describe the-actions to be taken including manually scramming the reactor, prompt actuation of the turbine trip (PWRs), the