ML21286A354

Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.3, Emergency Core Cooling Systems Equipment Design Data Summary

ML21286A354
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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Text

BFN-28 Table 6.3-1 EMERGENCY CORE COOLING SYSTEMS EQUIPMENT DESIGN DATA

SUMMARY

Number AC Power Installed- Design Flow Pressure Required Individual (each) Range for Source Backup Function Capacity flow psid* psig Initiation of Water Systems HPCI 1-100% 5000 gpm @ 1120**** to 150 1174**** to 150 None Condensate Auto Depress.

3600 gpm @ 1174 Storage Tank with either Core and Pressure Spray or LPCI Suppression Pool Automatic 6- 25% 865,000 lb/hr @ 1105 1169***** to 50 None N/A Remote-Manual Depressurization Main Steam System Relief Valves Core Spray 2-100%*** 6250 gpm @ 105 289 to 0 Normal Aux. Pressure Suppression LPCI or Standby Pool Diesel Gen.

LPCI 4- 50% 20,000 gpm @ 0 319.5 to 0 Normal Aux. Pressure Suppression Core Spray (2 pumps per loop) or Standby Pool System 10,800 gpm @ 0 Diesel Gen.

(1 pump per loop)

• psid-pounds per square inch differential between reactor vessel and primary containment

• • (Deleted).

• • • 2-100% capacity systems each having 2-50% capacity pumps

• • • • Full rated flow of 5000 gpm is only required between 150 and 1120 psid. See Table 6.5-2 for flow rates credited for LOCA for pressures above 1120 psid.

Otherwise, pressures above 1120 psid are representative of conditions where HPCI is required to serve as backup to RCIC which produces significantly less flow (600 gpm).

• • • • • 1169 is calculated from the lowest MSRV setpoint + 3%.