Loss of control air at Browns Ferry Unit One: accident sequence analysis

Technical Report · Tue Apr 01 04:00:00 EST 1986

OSTI ID:5763863

Harrington, R M; Hodge, S A

This study describes the predicted response of the Browns Ferry Nuclear Plant to a postulated complete failure of plant control air. The failure of plant control air cascades to include the loss of drywell control air at Units 1 and 2. Nevertheless, this is a benign accident unless compounded by simultaneous failures in the turbine-driven high pressure injection systems. Accident sequence calculations are presented for Loss of Control Air sequences with assumed failure upon demand of the Reactor Core Isolation Cooling (RCIC) and the High Pressure Coolant Injection (HPCI) at Unit 1. Sequences with and without operator action are considered. Results show that the operators can prevent core uncovery if they take action to utilize the Control Rod Drive Hydraulic System as a backup high pressure injection system.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5763863
• Report Number(s): NUREG/CR-4413; ORNL/TM-9826; ON: TI86009102
• Country of Publication: United States
• Language: English

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