Document: NUREG-0800
Document ID: 21b88814-85a2-4153-982a-8f00240a5d45
Document Type: srp
Title: GENERIC GUIDELINES FOR EXTENDED POWER UPRATE TESTING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0300/ML030080406.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2.1
CFR Part: 
CFR Title: 

Content:
dividual jet pump flow variation from average pump flow Is limited Dynamic response of the RG 1.68, App A 90% of RTP performance In accordance with design 15.1.1 Decrease In Feedwater plant to loss of feedwater 5k k Temperature heaters that results In most severe feedwater temperature reduction DRAFT Rev. 0 - December 2002 ATTACHMENT 2 14.2.1-16 C C DRAFT Rev. 0 - December 2002 C Transient Test Reference Typical Reactor Plant Initial Typical Transient Test Acceptance Criteria and Applicable Accident Analyses Conditions Associated Functions Important to Safety (SRP Section) Dynamic response of plant RG 1 68, Appendix plant performance In accordance with design 15 2.7 Loss of Normal Feedwater to loss of feedwater flow A, Section 5 Flow (Introduction) Dynamic response of plant RG 1.68, App A 100% of RTP with electrical system aligned Performance In accordance with design, Including* 15.2.6 Loss of Nonemergency AC for full load rejection 5 n n for normal full-power operation and load Power to the Station rejection method should subject turbine to Automatic transfer of plant loads as designed, automatic start of Auxiliaries (Loss of OffsIte Power IP 72517 maximum credible overspeed condition diesel generators, automatic load of diesel generators In the Testing) specified sequence IP 72582 steady-state plant operations with greater than 10% generator output (IP 72517 & Reactor pressure remains below the first safety valve setting 72582). Pressurizer safety valves do not lift trip of the plant with breakers In specified All safety systems such as RPS, HPCI, diesel generators, and positions so that plant loads will be RCIC function without manual assistance transferred directly to the diesel generators following loss of house power Normal reactor cooling systems should maintain adequate core temperatures, and prevent actuation of the Automatic recirculation system flow control mode Depressurization System; however selected relief valves may specified function to control