Reactor coolant pumps

Fig. 1. Pressurized water reactor (PWR) coolant system having U-tube steam generators typical of the 3—4 loops in nuclear power plants. PWR plants having once-through steam generators contain two reactor coolant pump-steam generator loops. CVCS = chemical and volume-control system.

Reactor coolant pump (RCP) seal failures that lead to a loss of coolant accident (LOCA)... [Pg.394]

ATWS A Reappraisal, Part 3 Frequency of Unanticipated Transients Nuclear 200 pump failure events from Arkansas Nuclear Unit 1, Calvert Cliff Unit 1, and Indian Point Unit 3 nuclear plants Nuclear reactor coolant pump seals 102. [Pg.91]

DATA BOUNDARY Nuclear reactor coolant pump seals... [Pg.102]

Reactor trip signal reactor coolant pumps tripped 4,685... [Pg.323]

Reactor Coolant Pumps. As indicated by Fig. 8, four reactor coolant pumps are used, two for each steam generator, The pumps are vertical, single-bottom-suction, horizontal-discharge, motor-driven centrifugal units. The pump impeller is keyed and locked to its shaft, A complex system of... [Pg.1106]

Fuel Handling Area 11. Reactor Coolant Pumps (4) 21. High Pressure Feedwater Heaters... [Pg.1120]

Verify actuation of safety systems Trip reactor coolant pumps (0 04)... [Pg.1030]

Summary of Design and Analysis of the SNAP-50/SPUR Reactor Coolant Pump. PW AC-467. August 10, 1965. [Pg.75]

Reactor was critical at a temperature of 195°C The reactor coolant pumps were operating on the mam motor on 110 rpm... [Pg.79]

At 23 01 05, reactor coolant pumps RCP C and D went into reverse rotation as a result of the loss of inertia This loss of inertia is due to opening of the self-exciting circuit breaker 03 JA of the vanable speed alternators supplying the motors of these two pumps... [Pg.79]

Closure of the obturators on the two reactor coolant pumps C and D took place at 23 28... [Pg.79]

Manual coupling of diesel LHPE led to re-powermg of the reactor coolant pump E although this was m reverse rotation as a result of failure of a rotation sensor on this pump... [Pg.92]

FIG. 2. "Arctica "-type icebreaker s nuclear power plant configuration 1-reactor, 2-steam generator, 3-reactor coolant pump, 4-auxiliary turbine generator (ATG),... [Pg.16]

Thermocyclic cracks were revealed in pipes connecting a reactor with pressurizers, in internal headers for water supply from purification system to reactor coolant pumps, in internal shells of pumps flow chambers, etc. The indicated defects became the reason for in-depth analytical and experimental studies of equipment operating conditions in the propulsion and test reactor plants, particularly thermal and strain parameters monitoring. [Pg.18]

Ihe operating ejqjerience has shown that abnqit changes in a primary pressure can be the reason of damages in internal structures made as semi-closed plena which walls were not designed for the primary coolant pressure. That was the reason of feilure of a partition in the reactor coolant pump of icebreaker "Arctica". [Pg.18]

Dismantling of the remainder of the small primary components and all the large components (reactor coolant pumps and intermediate exchangers). [Pg.186]

The first observation we can make on examination of this table is that the sodium coating will be completely eliminated during the carbonation operation, provided that the carbonation fluid is circulated uniformly in the vessel. Removing the reactor coolant pumps provides the opportunity for treating certain retentions that would not be accessible otherwise. If we only treat the retentions that are directly accessible after withdrawal of the reactor coolant pumps, it is estimated that a further 600 L of sodium could be eliminated. This would leave only approximately 700 L of sodium in retentions in the vessel (before carbonation). [Pg.200]

AR309 1.14 Reactor coolant pump fl5rwheel integrity (for comment) (Rev. 1, ML003739936) October... [Pg.263]

Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break... [Pg.400]

Many other components of reactor plant V-320 are upgraded in V-392 design with the aim to enhance the station safety and efficiency and improve the conditions for operation and maintenance. In particular, for reactor plant V-392 the reactor coolant pump MCP-1391 is used. This pump is the upgraded MCP-195M, which is used for the operating reactor plants V-320. In MCP-1391 pump water is applied as the lubricant and cooler of the main bearing in combination with the improvements in the system of motor lubrication this allows to give up the outside oil system and exclude possible fire. [Pg.147]

The nuclear steam supply system of the KNGR is designed to operate at rated output of 4000 MWth to produce an electric power output of around 1450 MWe. The major components of the primary circuit are the reactor vessel, two coolant loops, each containing one hot leg, two cold legs, one steam generator (SG), and two reactor coolant pumps (RCPs), and one pressurizer (PZR) connected to one of the hot legs. Two SGs and four RCPs are arranged symmetrically. [Pg.157]

Operating Conditions In-service Surveillance COMPONENT AND SUBSYSTEM DESIGN REACTOR COOLANT PUMPS... [Pg.16]

Reactor Coolant Pump Piping and Instrumentation Diagram... [Pg.22]

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