1. 1/2000
Hot tests at Temelin completed
František Heczko, Temelín Nuclear Power Plant
Inactive testing of reactor unit 1 is an important step in the
commissioning and start-up of the Temelín Nuclear Po-
wer Plant. Decree of the Czech State Office for Nuclear
Safety no. 106/1998 on nuclear safety and radiation pro-
tection in the course of the commissioning, start-up and
operation of nuclear facilities, defines this stage of com-
missioning activities as „complex performance testing of
the nuclear facility and reviewing of this facility prior to
reactor core fuel loading“.
Inactive testing comprises two major parts, Hot Hydraulic
Tests (HHT) within the Integrated Hydro Testing (IHT),
and the unit review period. The plant operator, ČEZ a. s. –
Temelín NPP, along with the contractor checked the pre-
paredness of the systems and equipment of Unit 1 for the
IHT/HHT hot testing, and, based
on this check, documented the
preparedness by developing the
Complex Protocol.
The preparedness was examined
and checked by personnel of the
state supervision body (SÚJB),
and based on that, the State Offi-
ce for Nuclear Safety issued on
25 February 2000 its permission
to start the IHT/HHT and the in-
active testing phase of the reac-
tor Unit 1. All the necessary ac-
tivities related to the start of pri-
mary circuit coolant heatup by
means of the reactor coolant
pumps work were promptly initi-
ated.
The preparedness for hot testing as documented by the
plant management encompassed the following items:
s primary circuit systems and equipment
s safety systems
s primary circuit auxiliary systems within the reactor bu-
ilding
s process systems within the auxiliary building
s fuel transport and review systems
s secondary section systems and equipment
s process systems of the balance of plant
s ventilation and air conditioning systems
s electrical systems
s instrumentation & control systems
s in-service diagnostics systems
s radiation control systems (partially)
s civil engineering section
s laboratories
s fire protection and safety systems
s communications systems
2. s personnel preparedness
s documentation preparedness (start-up procedures, ope-
rating procedures, quality assurance programmes)
Objectives of reactor unit hot testing
The objectives of the hot testing were as follows:
s Final cleaning of the internal surfaces of the primary
circuit equipment and piping so as to achieve the requ-
ired degree of cleanliness, by circulation flushing with
demineralized water by means of the reactor coolant
pumps; suitable chemicals were added to obtain a pas-
sivating layer on the internal surfaces.
s Attaining and maintaining the required primary and se-
condary circuit water chemistry. Water quality com-
plying with the water chemistry requirements is achie-
ved by water replacement by means of the makeup cir-
cuit (draining) combined with purification by means of
industrial filters.
s Testing of the process systems of the primary part and
the auxiliary systems of the secondary part at zero po-
wer conditions (substitute energy sources include the
pumping work of the reactor coolant pumps, heat supp-
lied by the electric heaters of the pressurizer, and ste-
am from the auxiliary boiler for heating demineralized
water supplied as makeup to the primary circuit and for
heating the feedwater for the steam generators).
s Running-in of the reactor coolant pumps at parameters
close to normal operation conditions.
s Testing of the thermal hydraulic characteristics of the
primary circuit.
s Testing of the instrumentation & control facilities at
parameters close to normal operation conditions.
s Training of the control and operating personnel.
The following systems were in the operating conditions in
the course of the hot tests:
VF – essential service water, including the pum-
ping station and cooling ponds with the spray
system
VB – non-essential service water, including the pum-
ps in the pumping station
TP 10, 20, 60, UG, WL – nitrogen system used in the re-
actor hall and in the machine hall
UT – high-pressure air for fast acting valves inclu-
ding the high-pressure compressor station
TF – intermediate cooling circuit
TB30 – contaminated condensate tanks and pumps
TB40, TN pure condensate
TV – sampling in the reactor hall
UJ – stationary fire fighting system including the fire
water pumps
TZ – special sewage system in the reactor hall
TL – VAC systems of the containment and of the
controlled and free zones
UX and UM – cooled and heating water
FC55 – condensate collecting and draining tanks
Chemical water treatment station
Auxiliary boiler
Gas management system
Power station’s house consumption supply systems and
instrumentation & control systems
The following systems were prepared for operation and
testing:
YA – main coolant piping
YB – steam generators
YC – reactor
YP – pressurizer and pressurizer relief tank
YT – safety injection tanks
YR – emergency primary circuit deaeration system
YD50, 60 – reactor coolant pump oil management sys-
tem
YD10, 20, 30, 40 – reactor coolant pumps
TC, TE – primary coolant purification systems
TK – primary system makeup, including the lubricati-
on system
TY – system of organized leakages, primary circuit
draining and deaeration
RY – steam generator blowdown
TH – washing of the end segments of the reactor coo-
lant pump seals
TB10 – boric acid production and distribution manage-
ment system
TB20 – reagent solutions for the primary circuit water
chemistry
TS10 – hydrogen combustion system
TS20 – gaseous releases purification
UR – collection of boric acid leaks
Reactor Unit Main Control Room
3. TX50, 60, 70, 80 – live steam, steam dump station to the
atmosphere, steam generator safety valves, ste-
am line quick acting valves
TX41–44 – steam generator feedwater
FC12d– water removal from the turbo-generator and ste-
am lines
FC32 – auxiliary makeup pumps
FC42 – feedwater tank including heating and reduction
stations
FC54 – auxiliary feedwater pumps
FC55 – auxiliary condenser
FC56 – steam generator feedwater
FC61 – systems of non-essential service water and of
the intermediate machine hall cooling circuit
In the course of the period from 9 October to 20 October
1999, tests of the first sub-stage of the integrated hydro
test were carried out, in particular circulation flushing and
pressure tests. Based on the results of the tests, decision
was made that the first sub-stage of the IHT would go on.
Primary and secondary circuit leak tests at pressures of
3.43 MPa and 1.8 MPa, respectively, were repeated, and
tests with the primary circuit coolant heated to 120 °C we-
re resumed on 30 January 2000. The heatup of the reactor
unit was terminated on 1 February 2000, and primary and
secondary circuit leak tests were performed at pressures
of 17.65 MPa and 8.6 MPa, respectively. The results of
the leak tests were unsatisfactory, leaks were detected,
and so the primary circuit pressure and temperature had to
be reduced in order to enable the identified leaks to be re-
moved. After the repair, the final tests of sub-stage 1 we-
re resumed on 2 February. On 9 February, the tests were
discontinued because of repeated failures of the Instru-
mentation & Control System. Work on the I&C system
was finalized 14 February, and based on evaluation of the
system performance, order was issued to start the reactor
coolant pumps up again and to finalize the tests. The pri-
mary and secondary circuit leak tests were repeated on 15
and 16 February, and satisfactory results were achieved.
The technology testing process was discontinued again on
18 and 19 February for urgent work on the Instrumentati-
on & Control System. The tests within sub-stage 1 of the
integrated hydro testing were completed by 20 February.
Further activities on reactor Unit 1 were controlled so as
to achieve the prescribed preparedness to the extent ne-
cessary for starting the IHT/HHT sub-stage 2.
Hot tests – IHT/HHT sub-stage
The order to start the IHT/HHT sub-stage was issued on
25 February 2000 based on the permission issued by the
State Office for Nuclear Safety. The primary circuit hea-
tup to 150 °C started, and the tests were commenced. The
desired temperature was attained on 26 February. After
accomplishing the full range of tests, the primary circuit
was heated up to 180 °C on 27 February, and additional
tests were carried out. A higher temperature level, 220 °C,
was reached the same day. After completing the tests at
that temperature, the temperature was further increased to
Reactor Coolant
Pump Motor
Coupling of the
reactor coolant
pump motor to
the pump body
4. 260 °C. These conditions were reached on 29 February,
and the next day, 1 March, the temperature was increased
to the final 280 °C. The testing at the rated thermal pro-
cess parameters was thereby started up.
The tests at the rated parameters were completed on
13 March. Partial protocol from the inspection of the HHT
tests was prepared, and cooling down commenced for sub-
sequent work to eliminate the defects which had been
identified during the tests. In the course of the cooling,
hold-up was accomplished at the various temperature le-
vels to implement the planned tests. The reactor unit cool-
down for repair work was completed 18 March, and the re-
pair work was done on 20 March. The next day, the prima-
ry and secondary circuits started to be filled with coolant
again and reheated for repeated leak tests. On 22 March,
a repeated leak test with a favourable result was performed
on the secondary coolant circuit; the leak test result on the
primary circuit was unsatisfactory, and therefore the pri-
mary circuit was cooled down once again. Simultaneous-
ly, preparations followed by hydraulic parameters testing
were performed on the 1TK80W01 heat exchanger, where
insufficient efficiency had been found in the course of the
tests. The tests were completed and the primary circuit was
heated again on 24 March; leak testing followed, a minor
leak on the non-standard measuring sampling on the
1TK80W01 was eliminated, and the reactor unit started to
be heated again on 26 March for completing the remaining
and repeated tests of the IHT/HHT programme.
After heatup the primary circuit and performing a repea-
ted test of the 1YP21S01 pressurizer relief valve, the tem-
perature of 280 °C was reached again on 27 March, and
the programme of the remaining and repeated tests, inclu-
ding tests of the heat generator safety valves, was started.
Final cooling down of the primary coolant circuit was
commenced 28 March. Planned tests were carried out in
the course of the gradual cooling down of the reactor unit.
The cool down was completed at 59 °C on 1 April. Rehe-
ating to 150 °C followed for the cooling down tests with
the reactor coolant pumps in service and out of service,
respectively. The cooling down tests were completed by
attaining a primary circuit temperature below 50 °C on
2 April. The hot tests were thereby finalized, although the
remaining tests of the IHT programme at the cold prima-
ry coolant circuit continued till 6 April. Thereby, the pro-
gramme of IHT/HHT sub-stage 2 was completed.
Performance of the Westinghouse Instrumentation &
Control system in the course of the hot tests
Modifications of the backup software (SW) for the DHG
racks had been accomplished before starting the hot tests.
The racks, through their electronics, provide for communi-
cation between the buses of the individual control levels,
including the flow of information required. After the men-
tioned modifications, the control system, including the
communication of the UIS information system to the vari-
ous subsystems, performed reliably. This means that the
system ensured functions which were required by the ope-
ration and testing of the individual process systems and
equipment for the relevant stage of commissioning work.
None of the subsystems suffered spontaneous loss of in-
ternal communication such as would cause loss of integ-
rity and performance in the course of the hot tests. Tran-
sient losses of communication of some parts on the UIS
were due to partial or complete failures of electricity
supply to the Instrumentation & Control (I&C) systems.
As far as the hardware (HW) is concerned, the Westing-
house control system exhibited a high reliability. Owing
to this reliability, there was a minimal need for replace-
ment of the HW modules of the racks.
Main observations regarding the I&C system
Due to high turbulences, the flow rate measurement on the
primary circuit by means of Pitot tubes has to be replaced
with pressure difference measurement on the steam gene-
rator. This replacement will be complete before the reac-
tor unit is fuelled.
Poor performance of the spent fuel pool level indication.
The sensors will be readjusted and recalibrated within the
reviewing work. The readjustment and recalibration will
be completed before the reactor unit is fuelled.
Poor performance of the measurement of the steam flow
from the steam generator. The measurement was distorted
at a low steam output. A modification of the design has
been proposed. The modification, including its testing, is
planned for the zero and low power and power ascension
start-up periods.
Unwanted affecting of the measuring circuits for some
shared PRPS/DPS sensors during failures of electricity
supply to the DPS racks. HW modifications will be made
to eliminate this deficiency. These will be accomplished
before the reactor unit is fuelled.
Spontaneous failures of bitbus communication between
the divisions of the PRPS and RCLS systems. SW modifi-
cations will be effected to eliminate this deficiency. These
will be accomplished before the reactor unit is fuelled.
Transition of working DHGs to standby ones due to tran-
sient disconnection of one of the two concentrator racks.
5. Currently it seems optimal to complete the UPS facility to
one of the two supplies for the concentrator racks. The
modification will be accomplished before the reactor unit
is fuelled.
Unreliable performance of the LOG server and of all the
related printer types (including printers for the printout of
events). This problem will be eliminated by installation of
a new UIS operating system. This modification will be
accomplished before the reactor unit is fuelled.
Autonomous tests of the I&C system were deliberately li-
mited to a minimum in the course of the IHT. In some in-
stances, the test processes were governed by the require-
ments of the technology testing programmes (such as the
tests of the input, output, and MMI interfaces).
The following parts of the I&C systems were unavailable
in the course of the HHT:
s Computation server (sequential automata)
s Diversion protection system (DPS)
s INCORE (in-core measuring system)
s Unit and Non-Unit Datalink server (communication
links for the Non-WELCO systems, OLM, RMS, etc.)
Circulation flushing and pressure tests
The circulation flushing and pressure tests encompassed
the following:
s Normal operating mode tests in the course of the inte-
grated hydro testing; primary coolant circuit and pres-
surizer heatup to temperatures of 120 °C to 130 °C by
means of the reactor coolant pumps work (RCPs) and
pressurizer heaters; pressurizer filling testing; RCP in-
terlocks’ testing; oil pump testing and examination of
the oil management parameters in the course of the
running-in of the RCPs; examination of the parameters
of the RCPs and their auxiliary systems; measurements
of RCP vibrations; hydrocyclone performance testing;
testing of the antireversing function of the RCPs by
tripping a RCP while running the remaining three
RCPs; measurement of the time of RCP run-up to the
rated rpm and of the time of RCP coast-down; measu-
rements of parameters of the RCP electric motors in
various modes; RCP strength and leak testing; measu-
rements of leaks from the terminal sections of the RCP
seals; measurements of RCP displacements; measure-
ments of the acoustic background level with the RCPs
running and idle.
s Strength and leak tests of the primary circuit and rela-
ted systems; acoustic emission testing in the course of
the primary circuit pressure tests; strength and leak tes-
ts of the secondary side of the SG including the steam
lines and related piping.
s Circulation flushing of the primary circuit with water
makeup and draining and coolant purification by the
TE, TC filters; dispensing solutions into the primary
circuit; adjustment and maintenance of the primary and
secondary circuits and auxiliary circuits following the
E038 programme.
s Primary circuit cooling down by means of the TQ12,
22, 32 systems; heatup mode testing for the TQ lines in
the course of the preparation of the cooldown.
s Connecting the linear step drives (LSDs) at the reactor;
connecting the LSD position sensor at the reactor.
s Tests of the automatic switching sequence facility; ot-
her tests of the electrical systems.
Some tests of the circulation flushing and pressure testing
sub-stage were transferred to the hot testing sub-stage.
These included tests that could not be implemented to the
full extent or had been accomplished with outstanding
items.
Repeated pressurized leak tests of the primary and secon-
dary coolant circuits were performed prior to the inactive
testing stage ( HHT sub-stages of the integrated hydro
test). The hot testing processes then were controlled based
on approved programmes and schedules. Nearly 250 ma-
in tests were accomplished in the course of the gradual
temperature and pressure increase in the primary and se-
condary circuits, in the course of their stabilization, or in
the course of the reactor unit cooldown. The mutual logic
and time links between the various activities, i.e. their ac-
tual sequence and course, were refined in weekly plans
and schedules in dependence on the actually attained pre-
paredness, on the actual operating conditions of the reac-
tor unit, as well as on the status of the commissioning
work. The weekly plans and schedules were also submit-
ted to the SÚJB inspectors.
Upper block of the reactor lid with non-standard start-up
measurement during the primary circuit pressure tests
6. s Start-up of the auxiliary condenser, bringing the sen-
sors to the operating state, testing of the auxiliary con-
denser pumps, testing of non-essential service water at
the auxiliary condenser
The following tests were performed in the course of the
primary circuit heatup to parameters close to the operating
values:
s Tests of the pressurizer level, pressure and temperatu-
re controllers in the course of heatup and at the rated
parameters
s Thermal hydraulic tests of the reactor shaft
s Formation of a passivation layer on the internal surfa-
ces of the primary circuit pipes and equipment, main-
taining of the primary and secondary circuit water che-
mistry
s Tests of the feedwater tank level and temperature con-
trollers
s Tensometric and temperature measurements on the re-
actor pressure vessel, reactor internals, main coolant
piping, SG, pressurizer, pressurizer relief tank
s Tests of the movable biological protection at 280 °C
s Tests of the reactor coolant pumps run-up and coast-
down; measurements of vibrations and displace-
ments; running-in of the reactor coolant pump in the
hot state
s Tests of the pressurizer; measurements of the heatup
trends of the various groups of pressurizer electrical
heaters; measurements of the effectiveness of injection
into the pressurizer; determination of the pressurizer
thermal losses
s Leak tests of the non-return flap valves between the sa-
fety injection tank and reactor; measurements of dila-
tations, displacements and vibrations of the safety in-
jection tank–reactor piping; determination of the pres-
sure gradient for opening the non-return flap valves
between the safety injection tank and reactor
s Tests of the diagnostics subsystems for monitoring of
impact shocks, leaks, vibrations, stresses, fatigue; mo-
nitoring of the linear step drives
s Test of the gas exhaust from the TK10 degasser to the
hydrogen combustion
s Tests of the steam generator blowdown and of the ste-
am generator blowdown treatment station
s Measurements of the start-up currents and voltage
drops at high-power electric drives
B. Hot tests of the primary circuit
s Maintaining the primary circuit in the hot state by fee-
ding steam to the auxiliary condenser
s Maintaining the primary and secondary circuit water
chemistry, formation of a passivation layer on the in-
ternal surfaces of the primary circuit
Contents of the hot tests
A. Primary circuit heatup to parameters close to the ope-
rating ones
s Tests of the linear step drives (LSDs) under cold con-
ditions and at 150 °C and 260 °C
s Measurement of the dynamic parameters of the reactor
and primary circuit loops at 50 °C, 120 °C, and 260 °C
s Primary circuit filling and venting and pressure increa-
se to 2 MPa
s Creating a nitrogen blanket inside the pressurizer, pres-
surizer level reduction to 1170 cm
s Tests of the collective automatic backup, testing of the
automatic switching sequence of systems 1 through 3
s Start-up of the reactor coolant pumps, heatup of the
primary circuit and pressurizer to 120 °C, heatup of the
bubbler feeding tank in parallel to the primary circuit
heatup, running of the auxiliary makeup pumps and au-
xiliary feedwater pumps, heatup of the steam generator
and steam line blowdown
s Maintaining the primary and secondary circuit water
chemistry in the course of heatup process
s Tests of the TX10, 20, 30D01 steam generator emer-
gency feedwater pumps
s Tests of the TQ low-pressure and high-pressure emer-
gency pumps into the sealed primary circuit
s Measurements of the hydraulic parameters of the pri-
mary circuit, reactor coolant pumps, reactor and reac-
tor internals; measurements of the cold pressure pulsa-
tions at approx. 120 °C
s Displacement measurements of the viscous dampers at
120 °C, 190 °C, and 260 °C
s Continued heatup of the primary circuit to 150 °C,
190 °C, 220 °C, and to the rated parameters
s Calibration of the temperature measurement at the re-
actor core outlet at 150 °C, 190 °C, 220 °C, and 260 °C
s Dispensing of KOH into the primary circuit coolant,
formation of a passivation layer
s Replacement of the nitrogen blanket in the pressurizer
by a steam blanket; performance tests of the sequential
switching facility and of the pressurizer relief tank; tes-
ts of the pressurizer relief valve
s Tests of the YR emergency venting system
s Preliminary tests of the thermal capacity and losses of
the primary circuit at 220 °C, measurement of the ther-
mal capacity and losses at 285 °C
s Connecting the non-return flap valves to the reactor,
measurement of the pressure drop for opening the non-
return flap valves between the safety injection tank and
the reactor
s Tests of the spring adjustment of the pressurizer im-
pulse safety valve, leak testing of the pressurizer safe-
ty valve at rated parameters
s Tests of the SG blowdown system
7. s Measurements of the hydraulic characteristics of the
primary circuit, reactor coolant pumps, reactor, and re-
actor internals at the rated parameters; measurements
of pressure pulsations at the rated parameters
s Adjustment of the SG level indicators at the rated pa-
rameters
The following tests were performed in the course of the
HHT:
s Test of the pressurizer level and pressure controllers
s Measurement of the coolant flow mixing in the reac-
tor core
s Thermal hydraulic tests of the reactor shaft
s Tests of the feedwater tank level and pressure control-
lers
s Tests of the auxiliary condenser controllers
s Measurements of the dynamic characteristics of the re-
actor and primary circuit loops
s Tests of the TF system in the course of normal operati-
on and with failures of pumps and essential service wa-
ter cooling
s Tensometric and temperature measurements on the re-
actor pressure vessel, reactor internals, main coolant
piping, SG, pressurizer, pressurizer relief tank
s Tests of the normal modes and failure situations of the
reactor coolant pumps
s Leak tests of valves of the YR primary circuit emer-
gency venting system
s Measurements of the pressurizer thermal losses, test of
the injection efficiency into the pressurizer, test of the
accumulating performance of the pressurizer relief
tank, leak test of the pressurizer safety valve
s Leak tests of the non-return flap valves between the sa-
fety injection tank and reactor
s Tests of the diagnostic subsystems for monitoring im-
pact shocks, leaks, vibrations, stresses, and fatigue;
monitoring of the linear step drives
s Tests of the primary circuit makeup system (inter-
locks, controllers, pump parameter measurement;
tests of the automatic backup of the standby equip-
ment and pumps; failures of cooling; major and mi-
nor boron regulation modes; operation of two make-
up pumps)
s Flow rate measurements for the throttle diaphragms of
the TY system of primary circuit venting
s Tests of the SG blowdown system and of the blow-
down treatment plant
s Tests of the TC primary coolant purification system
s Test of the automation of the start-up, shut-down, and
transition to the standby line of the TE system
s Tests of the gas purification system
s Pump tests of the TQ 14, 24, 34D01 system of emer-
gency high-pressure makeup injection into the sealed
primary circuit
s Leak tests of non-return flap valves in the discharge li-
nes of the TQ systems pumps
s Tests of the essential service water rated mode and fa-
ilure of essential service water pumps
s Tests of the synchronization of inverters and output
voltage stability, measurements of the harmonic com-
ponents of the inverter voltage and current, measure-
ments of the start-up currents and voltage drop at the
high-power drives, monitoring of overvoltage in the
plant house consumption distribution system
C. Primary circuit cooldown after HHT
s Preparatory activities for cooldown, increasing the le-
vels in the pressurizer and SG
s Shutting down the auxiliary condenser
s Cooldown by one steam dump to atmosphere station
(PSA) (4 reactor coolant pumps in operation) to 250 °C
– 160 °C at a rate of 60 °C/h, to 190 °C at 30 °C/h, co-
oldown by means of 1 – 4 PSAs to really attainable
temperature
s Pressurizer cooldown by injection from the reactor co-
olant pumps, creation of a nitrogen blanket in the pres-
surizer
s Tests of the SG safety valves
s Feedwater tank cooldown
s Test of the pressurizer main safety valve
s Primary coolant circuit cooldown to 150 °C
s Preparation of the primary circuit for cooldown by the
TQ system, heating of the TQ system lines
s Trip of the reactor coolant pumps,. pressurizer cool-
down from the TK system (system of normal primary
circuit makeup)
s Primary circuit cooldown by the TQ system with the
reactor coolant pumps idle, at a rate of 30 °C/h
Tranformer for power supply to meet the house consump-
tion of the plant
8. Published by the Czech Nuclear Forum, Prague, Czech Republic
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s Pressure reduction in the primary circuit to the at-
mospheric pressure, level reduction in the reactor to
250 – 300 mm below the main dividing plane
s Test of the reactor core residual heat removal in the
course of reverse coolant circulation and with the level
in the reactor reduced down to the cold neck level.
The tests performed in the course of the cooldown follo-
wing HHT included:
s Testing of pressurizer level and temperature controllers
in the course of cooldown
s Thermal hydraulic tests of the reactor shaft
s Maintaining the primary and secondary circuit water
chemistry in the course of cooldown
s Tests of the feedwater tank level and temperature con-
trollers in the course of cooldown
s Tensometric and temperature measurements on the re-
actor pressure vessel, reactor internals, main coolant
piping, SG, pressurizer, pressurizer relief tank and
1TQ10W01 in the course of cooldown
s Displacement measurements of the viscous dampers at
190 °C
s Measurements of reactor coolant pump displacements
and vibrations
s Tests of the diagnostic subsystems for monitoring impact
shocks, leaks, vibrations, dilatations, stresses, fatigue
s Tests of pressurizer and SG collector cooldown, tests
of the SG draining mode
s Tests of the primary circuit draining into the 1TY20B01
tank, tests of the level control in the tank, test of the
„drain“ mode, test of the safety valve of the TE system
(system of organized primary circuit leakages)
In the second half of March, the integrated hydro test sub-
stage 2 entered its final phase, virtually all tests having be-
en carried out and documented with protocols. Some tes-
ts had to be repeated; in some instances, experts from
Russian or other plants were invited to attend.
The testing ran well and the results were acceptable. No
major problems arose from the mechanical systems, elec-
trical equipment or the instrumentation & control system.
The performance of all the major process and safety sys-
tems of the reactor unit, equipped with the Westinghouse
I&C system, was tested in a complex manner. The hot tes-
ts constituted an important part of the non-active testing
of the reactor unit: the co-operation of the individual sys-
tems was verified under normal operating conditions (alt-
hough without nuclear fuel), and the operating personnel
acquired habits they would need in the course of the com-
mercial operation of the reactor.
All problems and failures detected in the course of the
commissioning and tuning-up work were eliminated
promptly by the relevant suppliers. Based on the results,
some work will be transferred to the reviewing period af-
ter the hot tests (e.g., the 1TK80W01 recuperative heat
exchanger). Since the integrated hydro test (the unit coo-
ling after the hot tests) is followed by a roughly 2-month
period of equipment reviewing which includes a large
volume of work, vigorous organizational activities in
preparation for the future pre-operational inspections and
reviewing and adjustment were started sufficiently ahead
of time. A very detailed schedule was developed as a ba-
sis for work orders to control and inspect all the partial
activities.
The review will include inspection of the facility – especi-
ally the reactor and the primary coolant circuit – after the
hot tests; pre-operational inspections that could not be im-
plemented as yet will be completed, and the initial condi-
tions as are necessary for the reactor fuelling will be secu-
red. As an additional outcome, the review will enable the
operating personnel to acquire experience in repair and
maintenance work.
