PRHRS

Fig. 6J-3 The In-Containment Passive Safi System IRWST, PRHR HX ami the...

Fig. 37. Schematic representation of the in-containment passive safety injection system (PS1S). 1RWST = in-containment refueling water storage tank. PRHR-HX = passive residual heat removal heat exchanger. ADS = automatic depressurization system (four stages). (Westinghouse)...

PRHR Rent- 17R258 nosft l rCnnf r.nr used as a... [Pg.392]

Passive Residual Heat Removal System (PRHRS)... [Pg.81]

Passive residual heat removal (PRHR) system ... [Pg.70]

If feed water systems or steam generator heat removal is not available, two PRHR heat exchangers provide decay heat removal. The system is located above the Reactor Coolant System (RCS) and forms a closed loop at full system pressure using natural convection circulation. The... [Pg.70]

Decay heat removal Passive Residual Heat Removal System (PRHR) Passive Non-LOCA heat removal... [Pg.76]

Passive residual heat removal system (PRHRS) X 3 channels 1 channel on the reactor, 2 channels to the secondary circuit 1 loops... [Pg.133]

Decay heat removal PRHRS Passive 72 h capacity... [Pg.135]

Primary circuit pressure control PRHRS, RCPC,DRPS Passive Without discharge of primary coolant... [Pg.135]

Decay Heat Removal Passive heat removal system, PRHRS Passive Self-actuates at P = 0 6 MPa, 2x2 5 m ... [Pg.310]

Heat Removal EWIS/ARHRS/PRHRS Active/Passive Fmal heat removal is completely passive... [Pg.310]

A 3-3 Primary pressure control Implemented system (Name) - ARHRS, PRHRS... [Pg.313]

Strong negative reactivity coefficients L Pnmary Transients - Great primary mertia, CPS actuation, PRHR actuation L Secondary Transients - Great primaiy mertia, CPS and PRHR actuation L Loss of Electric Sources - Implementation of passive systems (battery power sources) Total Loss of heat sink not cntical ... [Pg.462]

Decay heat removal PRHRS/AHRS Passive Natural circulation of water/jur AHRS is permanently connected... [Pg.512]

Primary circuit pressure control CPS/PRHRS Active/ Passive No safety valves and prim, coolant discharge for overpressure protection... [Pg.512]

Severe Accidents Containment temperature and pressure control CPS/PRHRS Passive/ Active ... [Pg.512]

Debris cooling system (name) PRHRS, AHRS... [Pg.516]

Self sufficiency (h) 24 through each train Safety graded Yes A3 3 Primary pressure control Implemented system (Name) PCPS, PRHRS a Actuation mode (manual/automatic) Automatic... [Pg.578]

A passive residual heat removal (PRHR) nozzle attaches to the bottom of the channel head of the loop-1 steam generator on the cold-leg portion of the head. This nozzle provides recirculated flow from the PRHR heat exchanger to cool the primary side under emergency conditions. A separate nozzle on one of the steam generator channel heads is connected to a line from the CVCS. The nozzle provides for purification flow and makeup flow from the CVCS to the RCS. [Pg.70]

If the duty systems are unavailable, or are imable to control the ult, passive residual heat removal (PRHR) is initiated and the CMTs actuated to inject borated water into the reactor coolant system (RCS). In most cases this will be sufficient to manage the fault for at least 72 hours. [Pg.118]

Operator action is not generally required for operation oftiie safety measures claimed in the DBA. For events where the PRHR heat exchanger is actuated, the plant automatically cools down to the... [Pg.127]

Inadvertent operation of the PRHR heat exchanger (inadvertent opening of one of a PRHR isolation valve). This fault models the failure of one protection division as the limiting single failure. This is fault 4.2.6 in the fault schedule. [Pg.130]

Results of the analysis for the postulated feedwater line rupture show that the capacity of the PRHR heat exchanger is adequate to remove decay heat, to prevent overpressurising the reactor coolant system, and to maintain the core cooling capability. Radioactivity doses from mptures of the postulated feedwater lines are less than those presented for the postulated main steam line break and meet US regulatory criteria. Fiuther consequence analysis will be conducted to demonstrate that the results meet the relevant UK criteria. [Pg.132]

The results of this analysis show that inadvertent operation of the core makeup tanks or CVS during power operation does not adversely affect the core, the reactor coolant system, or the steam system. The PRHR heat removal capacity is such that reactor coolant water is not relieved from the pressuriser safety valves. DNBR always remains above the design limit values, and reactor coolant system and steam generator pressures remain below 110 percent of their design values. [Pg.138]

The plant response following an SGTR until the primary-to-secondary break flow is terminated is analyzed with the LOFTTR2 program. The LOFTTR2 program is modified to model the PRHR system, core makeup tanks, and protection system actions appropriate for the APIOOO. [Pg.139]

The ADS and PRHR system are design features that can be used to prevent high-pressure core melt in a severe accident. [Pg.166]

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