Document: NUREG-0800
Document ID: 050fa52d-0a13-4146-93e4-0f4659c7d893
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350140.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
regardina the maximum pressure in the reactor coolant and main steam systems. The variations with time during the transient of neutron power, heat fluxes (average and maximum), reactor coolant system pressure, minimum DNBR (PWR) or CPR (BWR); core and recirculation loop coolant flow rates (BWR), coolant conditions (inlet tempera- ture, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions), steam line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor coolant system to the containment system (if applicable) are reviewed. The more important of these parameters for the loss of ac power transient are compared to those predicted for other similar plants to verify that they are within the expected range. IV. EVALUATION FINDINGS The evaluation findings under this SRP section are incorporated In a statement covering all transients of moderate frequency involving a decrease in heat removal by the secondary system. See the findings statement in SRP Section 15.2.1-5 for a typical statement. 15.2.6-5 Rev. 1 - July 1981 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 2. NUREG-0151, Safety Evaluation Report, "GESSAR-251, Nuclear Steam Supply