ML21278A115

2 to Updated Final Safety Analysis Report, Chapter 4, Appendix 4A.4, In-Plant Measurements of Reactor Coolant Flow

ML21278A115
Person / Time
Site:	Calvert Cliffs
Issue date:	09/07/2021
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
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References
NEI 99-04
Download: ML21278A115 (1)

Text

CALVERT CLIFFS UFSAR 4A.4-1 Rev. 47 4A.4 IN-PLANT MEASUREMENT OF REACTOR COOLANT FLOW The RCS flow will be measured during pre-core hot functional testing. This measurement will be used to predict the post-core load flow. Flow will be verified during post-core hot functional testing. The method for determining flow has already been outlined in Appendix 4A.2.1. The post-core load hot functional test results are then extrapolated to full power conditions by correcting for reactor coolant density changes.

During hot functional testing, the RCP case P will be measured with a 0-150 psi Barton Model 227 P gauge. The accuracy of this gauge is +/- 0.5% FS. Measurements will also be made of steam generator P and reactor vessel P.

Should a change in plant conditions result in lower than specified flow, the safety analyses can be recalculated at the existing core burnup. To provide Technical Specifications which include flow as a variable would require unnecessary complexity. The effect of flow on the peak linear heat rate permitted by the LOCA analysis can be determined from Figure 5.1-13 of CENPD-106.

This figure shows that a 14% flow increase results in only a 3% increase in allowable peak linear heat rate at beginning-of-life. The impact of changes in flow on this analysis is, therefore, minimal.