Document: NUREG-0800
Document ID: 81a2e18b-7311-4c4e-822e-8dfe1b0ba7aa
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230009.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
oustic resonances or cause flow-induced vibration that can damage associated components (valves, steam dryer, or pipes). The applicant/licensee is expected to make any necessary modifications to plant piping or components based on the results of this evaluation, as necessary, to increase the structural capability of that equipment, or to reduce the pressure fluctuation and vibration levels. 6. Power Ascension Data. An applicant for the construction and operation of a BWR or PWR nuclear power plant and a licensee of an operating BWR or PWR nuclear power plant proposing a power uprate license amendment or a major plant modification is expected to develop a program to confirm its evaluation of the potential adverse flow effects on plant systems and components during power ascension and operation at full licensed power conditions. For example, the applicant/licensee is expected to establish a power ascension program that includes, as applicable, (a) specific hold points and their durations during power ascension; (b) activities accomplished during the hold points; (c) plant parameters monitored and applicable limit curves; (d) inspections and walkdowns of steam, feedwater, and condensate systems and components during the hold points; (e) methods for trending plant parameters; (f) acceptance criteria for monitoring and trending plant parameters and conducting walkdowns and inspections; (g) actions taken if acceptance criteria are not satisfied; and (h) provisions for informing the staff about plant data, evaluations, walkdowns, inspections, and procedures prior to and during power ascension, including interactions during hold points and any instance where acceptance criteria are not satisfied, and resolution of safety concerns during the 3.9.5-15 Revision 3 - March 2007 staff review of that information prior to further power ascension or continued full power operation. For a BWR plant with an instrumented steam dryer, the steam dryer stresses are determined from the