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:
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 direct instrumentation and compared to the applicable limit curves with appropriate bias errors and random uncertainties. For an operating BWR plant without an instrumented steam dryer, the steam dryer stresses are calculated from data from steam system instrumentation fully accounting for appropriate bias errors and random uncertainties. The applicant/licensee is expected to provide a summary of its evaluation of plant startup and power ascension to the staff within 90 days of reactor criticality. If full licensed power is not achieved in that time period, the applicant/licensee is expected to provide a supplemental report within 30 days of achieving full licensed power. The extent of NRC staff interaction will depend on the evaluation results and plant experience. 7. Monitoring of Potential Adverse Flow Effects. Plant operating experience, such as from the Quad Cities and Dresden nuclear power plants, has shown that adverse flow effects might not appear for an extended period of time following initial startup or power ascension. Therefore, an applicant for the construction and operation of BWR or PWR nuclear power plant and a licensee of an operating BWR or PWR nuclear power plant proposing a power uprate or a major modification is expected to maintain its program for monitoring potential adverse flow effects on plant systems and components for a sufficient time period to verify that adverse flow effects are not occurring. This program is expected to include monitoring plant data with vibration sensors at critical locations, conducting walkdowns, and inspecting components during power ascension and operation at full licensed power conditions to verify whether adverse flow effects occur. The program also is expected to include inspections and walkdowns during