|
THE MINISTRY
OF SCIENCE AND TECHNOLOGY
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|
SOCIALIST
REPUBLIC OF VIETNAM
Independence - Freedom - Happiness
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|
No.
29/2012/TT-BKHCN
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Hanoi,
December 19th 2012
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CIRCULAR
SPECIFYING THE CONTENTS OF THE PRELIMINARY SAFETY ANALYSIS
REPORT IN THE APPLICATION FOR THE APPROVAL FOR THE NUCLEAR POWER PLANT SITE
Pursuant to the Law on Atomic Energy dated
June 03rd 2008;
Pursuant to the Government's Decree No.
28/2008/NĐ-CP dated March 14th 2008, defining the functions, tasks,
powers and organizational structure of the Ministry of Science and Technology;
Pursuant to the Government's Decree No. 70/2010/NĐ-CP dated June
22nd 2010, detailing and guiding the implementation of a number of
articles of the Law on Atomic
Energy applicable to nuclear power
plants
At the proposal of the Director of the
Vietnam Agency for radiation and nuclear safety;
The Minister of Science and Technology issues
a Circular specifying the
contents of the preliminary safety analysis report in the application for the
approval for the nuclear power plant site as
follows:
Article 1. Scope of
regulation
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Article 2. Subjects of
application
This Circular is applicable to the investors and
organization participating in the formulation, verification, and approval of
the preliminary safety analysis reports; and the relevant advisory
organizations.
Article 3. Interpretation of
terms
In the Circular, the terms below are construed
as follows:
1. Nuclear power plant site include the entire area
that have the containment buildings, the turbine buildings, the important
safety systems, and some other ancillary constructions. The usual area is 01 –
02 km2, surrounded by security fences.
2. The vicinity of the nuclear power plant is
the area around the nuclear power plant, usually a circle of which the radius
is 08 km from the containment building; the vicinity of the nuclear power plant
may be expanded where necessary in order to cover all the phenomena and
processes that need surveying and researching for the purpose of serving the
assessment of the site safety.
3. Sub-region is the area around the nuclear power plant,
usually a circle of which the radius is 40 km from the containment building;
the vicinity of the nuclear power plant may be expanded where necessary in
order to cover all the phenomena and processes that need surveying and
researching for the purpose of serving the assessment
of the site safety.
4. Inter-regional area is the area surrounding a
sub-region, usually a circle having a radius of 320 km from the containment
building; the size of the inter-regional are may be changed depending on the
geological and tectonic characteristics; the shape of the inter-regional area
may not be symmetrical in order to cover all the earthquake sources that need
considering.
Article 4. Contents of the
preliminary safety analysis report
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2. The contents of the preliminary safety
analysis report are specified in the Annex enclosed with this Circular.
Article 5. The documents, order, procedure, time limit for verifying
and reporting the result of the verification of the preliminary safety analysis report
1. The investor shall submit 05 dossiers in
Vietnamese (01 original, 05 photocopies) and 05 dossiers translated into
English of the preliminary safety analysis report, and a written request for
the verification, to the Vietnam Agency for radiation and nuclear safety – the
Ministry of Science and Technology.
The investor shall make a written commitment and
take responsibility before the law for the accuracy of the English
translations.
2. The Vietnam Agency for radiation and nuclear
safety shall examine the validity of the dossiers within 15 days from the date
the dossiers are received, and may request the investors to provide necessary
documents.
3. The Vietnam Agency for radiation and nuclear
safety shall verify the preliminary safety analysis report within 06 months
from the date on which the complete and valid dossiers or additional documents
are received as prescribed in Clause 2 of this Article.
4. Where necessary, the Vietnam Agency for
radiation and nuclear safety shall make a plan for hiring Vietnamese or foreign
independent advisory organizations or experts to assist in the verification,
then send that plant to the Minister of Science and Technology for considering
and sending reports to the Prime Minister.
5. The Vietnam Agency for radiation and nuclear
safety shall report the result of the verification of the preliminary safety
analysis report to the National Nuclear Safety Council, request the Minister of
Science and Technology to approve the result of the preliminary safety analysis
report verification, and notify the verification result to the investor.
Article 6. Effects
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2. Organizations
and individuals are recommended to send feedbacks on the difficulties arising
during the course of implementation to the
Ministry of Science and Technology for
amendment and supplementation./.
FOR THE
MINISTER
DEPUTY MINISTER
Le Dinh Tien
ANNEX
CONTENTS OF THE PRELIMINARY SAFETY ANALYSIS REPORT
(Enclosed with
the Circular No. 29/2012/TT-BKHCN dated December 19th 2012 of the Minister of
Science and Technology)
1. General
introduction
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1.1. Primary objectives of the PSAR
The objectives of the formulation of the PSAR
during the approval of the nuclear power plant site.
1.2. The legal basis for making the PSAR
The legal basis for making the PSAR serving the
approval for the nuclear power plant site include the brief information about
the official decisions made by competent State agencies and local authorities.
1.3. The information about the investor, the
contractors, the organizations that survey and assess the site
The information about the investor, the contractors,
the organizations carry out the surveys and
assessment serving the selection of the nuclear power plant site.
1.4. General information about the nuclear
power plant project
The general
information about the nuclear power plant project includes:
- The estimated total power, the number of
generating units, the technologies;
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- The information about similar generating units
verified and licensed by Vietnamese or foreign competent agencies.
1.5. The information about the organizations
that makes the PSAR
The information about the organization in charge
of making the PSAR, about the organizations that compile the chapters of the
PSAR, including the information about the experience in relevant disciplines,
the licenses to do relevant jobs related to the safety analysis.
1.6. The format of the PSAR
The format of the PSAR includes:
- The main parts of the report;
- The purposes and scope of each part;
- The connection among the parts in the report.
1.7. The list of acronyms, terminologies, and
definitions.
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2. General description of the nuclear power
plant
This section of the PSAR includes: the system of
law documents and applicable standards; the fundamental technical specification
of the nuclear power plant; the information about the construction conditions,
the layout, and other aspects, the technical characteristics and operations of
generating units, the characteristics of the power supply system; the
references enclosed;
2.1. The system of law documents and
applicable standards
All law
documents and standards applicable to the
survey and assessment of the site, the determination of technical
characteristics of the nuclear power plant design must be enumerated. If the
application of law documents and standards are not prescribed by competent
agencies, it is necessary to prove the conformity of such documents and
standards with the requirements for safety based on the practical experience,
current international commitments and regulations.
2.2. Fundamental technical specifications.
Briefly present the information about the
nuclear power plant, including the number of generating units, the industrial
type of each generating unit, the cooling system, the type of steam supply
system from the reactor, the structure of the containment building, the thermal
power rate and corresponding electric power rate, the communication system, and
other necessary specifications for understanding the primary technical
processes in the design.
If there is a licensed similar design, the basic
differences and foundations for assessing the safety of the changes in the new
design must be compared.
2.3. The information about the construction
conditions, the layout, and other aspects
2.3.1. Briefly assess the general
characteristics of the site that might affect the safety of the nuclear power
plant, including: earthquake, faults, volcanoes, meteorology, flooding,
tsunami, geotechnical engineering, the human factors, the cooling water
sources, and the power supply for the nuclear power plant.
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2.3.3. Describe the diagrams of the systems of
the nuclear power plant, the connection to the grid, the connection to the
railway system, road traffic system, and waterway system. The diagram must
demonstrate the whole nuclear power plant as well as each generating unit,
together with brief description of the primary system and devices, their
purposes, and the interaction among the systems. The general layout of the
whole nuclear power plant shall be demonstrate on a scale of 1:5,000 or bigger.
2.3.4. The information relevant to the
protection of the nuclear power plant, including:
- The roads, railways, waterways, flight
corridors, and residential areas that possibly affect the operation of the
nuclear power plant;
- Describe the local factories and warehouses in
the area, especially the places posing high risk of fire, explosion, and
release of toxic waste into the environment.
2.4. The technical specification and
operation mode of the nuclear power plant
2.4.1. Present the technical specifications of
the nuclear power plant relevant to the safety analysis during the approval of
the site.
2.4.2. Present the technical specifications of
the nuclear power plant relevant to the safety analysis during the approval of
the site.
The information about the safety system of
generating units relevant to the site, especially under the impacts form the
outside of which the frequency exceeds once every 100 years, or under the
impact of earthquake, tsunami, plane crash.
2.5. The characteristics of the power supply
system of the nuclear power plant
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2.6. Enclosed documents
The separate reports are considered part of the
PSAR, including the reports on the site survey result, the quality assessment,
analysis, and inspection.
3. Assessment of the site
This section of the PSAR includes the detailed
info about the site; the general rules for assessing the hazards at the site;
the activities of humans in the vicinity of the nuclear power plant, the
tsunami, meteorological, hydrographical, geological, tectonic conditions, and
other natural conditions that possibly affect the safety of the nuclear power
plant; the radioactive sources outside the nuclear power plant; the issues
related to the plan for managing and responding to emergencies; observations of
the measurements related to the site; the site safety analysis.
3.1. Detailed information about the site
3.1.1. Location of the site
Provide the map, diagram of administrative
areas, and specify the following information:
- Name of the locality (commune, district,
province) where the plant is situated;
- Name of the city of town of the administrative
agency of the province where the plant is situated
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- The distance from the site to the nearest
commune or town;
- The distance from the site to the national
border, and names of the adjacent countries.
The relative position of the site and the
following areas:
- Residential areas, rivers, sea, airports,
train stations, river ports, and sea ports;
- The perimeter of the important constructions
relevant to the national security;
- The nearest industrial facility (factory,
industrial chemical complex, oil and gas pipeline, food factories, and other
facilities);
- The nearest military bases.
The distance from the site to the holiday
destinations, wildlife sanctuaries, national historical and cultural remains
The information about the areas under the
management of the investor in the nuclear power plant and the vicinity
(including no-fly zone), the activities that possibly affect the operation of
the nuclear power plant must be controlled.
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The information about the residents must include
the latest population survey result (within 5 years from the date of submission
of the application for the approval for the site), the explanation of the
mechanical growth of population, the feasibility of the emergency response plan
available to local residents and non-local residents. The following information
must be specified:
- The population density in the area within the
radius of 30 km form the nuclear power plant site before commencing the
construction, during the construction, and during the entire operation of the
plant;
- The distance from the cities of which the
population exceed 100,000 people within the radius of 100 km from the nuclear
power plant site;
- The population distribution on the map in the
area around the nuclear power plant site within the radii of 10, 10 – 15, 15 –
20, and 20 – 30 km, in 8 directions;
- The information about the particular groups of
permanent and temporary residents, their ages (children, elders), the people
hard to evacuate (patients, prisoners, and other people);
- The portions of residents, the ratio of local
food and imported food;
- The demand for tap water, the water supply
sources;
- The duration of staying outdoors and indoors
(applicable to rural and urban residents) in a day;
- The average number non-local residents in a
day, during holidays, festivals, and other special activities;
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3.1.3. The geotechnical characteristic of the
ground, the hydrography, and underground water, Including:
- The information about the survey for designing
the foundation of the nuclear power plant, and the assessment of the
interaction between the constructions and the ground;
- The plan for building the overground and
underground constructions, the solutions for the weakness of the ground at the
site.
3.1.4. Information about the site, the
tolerances calculated in the fundamental design, and the possibility of
radioactive dispersion, including:
- Reports on the historical data sources;
technical reports on the detailed description of the survey, research, and data
collected;
- The
designs of the constructions (if any) and the measures for ensuring the safety
of relevant constructions;
- The documents forecasting the changes related
to the information above, the possibility of affecting the safety of the
nuclear power plant over a period equal to at least the anticipated operating
time of the plant.
3.1.5. Information about the topographical
conditions of the inter-regional areas, sub-regions, vicinity of the nuclear
power plant and the nuclear power plant site, including:
- The points marking the maximum and minimum
altitudes of the areas where the generating units of the nuclear power plant
are located;
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- The special topographical features (cracks,
cliffs, depressions, karst funnels, and other forms);
- Swamps;
- Forests, farmland, and other types of land.
Provide the following documents about
sub-regions:
- The above-water topographic map on the scale
of 1:5,000 or larger;
- The bathymetric map on the scale of 1:10,000,
together with the diagram of the cross-section of the continental shelve and
the topographical map of the vicinity of the nuclear power plant;
- The list of the instruments for observing the
movements of the earth's crust, together with a diagram showing the observation
results.
Provide the following documents about nuclear power plant site:
- The above-water and underwater topographic maps map on the scale of 1:1,000 or larger;
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3.2. The general rules for assessing the
hazards at the site
3.2.1. The assessment of the hazards from
natural and human factors at the site.
When taking administrative measures for
minimizing the hazard, especially the hazards caused by human factors, it is
necessary to provide information about the implementation, the roles, and
responsibility of each person and organization for the implementation of such
measures.
3.2.2. The criteria
for filtering the hazards, including the thresholds of the probability of
events, together with the possible impacts of each hazard, including the
sources, the transmission mechanism, and possible impacts at the site.
3.2.3. The target probabilities that the design
must reach in order to prevent the external hazards, and the conformity with
the acceptable limits.
3.2.4. The information about the periodic update
of the hazard assessment according to the measuring instruments and the
observations.
3.3. Activities of humans in the vicinity of
nuclear power plant
3.3.1. Information about the activities of
humans that possibly affect the operation of the nuclear power plant,
including:
- The method and data for quantitative
determination of the characteristics and measurements of the factors that may
have an impact on the nuclear power plant from the outside;
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3.3.2. The result of the detailed assessment of
the impacts of the emergencies that might arise at the industrial facilities,
traffic facilities, other existing facilities and future facilities in the vicinity
of the nuclear power plant.
The risks that might affect the safety of the
nuclear power plant must be included in the list of events as the basis for
diminishing the impacts of the possible emergencies, and forecasting the
changes relevant to the events that might lead to hazards.
3.4. Activities at the site
3.4.1. The activities at the site that might
affect the safety of the nuclear power plant, including the activities of the
vehicles in the plant perimeter, the storage and transport of fuel, gases, and
other chemicals that might cause fire, explosion or contamination, the
ventilation capacity.
3.4.2. The protective constructions include
dykes, dams, drainage system, and other factors that might affect the site such
as: replacing the ground, changing the altitude of the site, and other
activities. Assessment of the efficiency of these constructions, factors,
and activities in relation with the fundamental design
3.5. The hydrography
Assessment of the hydrographic features of the site
relevant to the selection of that location, and the technical protective
measures against the hazards, including the following information:
3.5.1. The impacts of the hydrographic
conditions at the site on the nuclear power plant (on the design and safe
operation of the plant).
The analysis of the impacts of unusual phenomena
such as monsoons, flooding, (on account of the rivers, reservoirs, provisionary
drainage area, and drainage system as the site); especially the negative
phenomena that affect the cooling water sources.
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If the site is near the coast or estuary, it is
required to examine the possibility of tsunami, assess the overall impacts upon
the occurrence of earthquake and tsunami, or high tide and strong wind.
3.5.3. The impacts of the hydrographic
conditions on the possibility of radioactive dispersion to the site and from
the site into the environment.
3.6. The meteorology
Assessment of the meteorological features of
the site relevant to the selection of that location, and the technical protective
measures against the hazards, including the following information:
3.6.1. The impacts of the meteorological
conditions at the site on the nuclear power plant (on the design and safe
operation of the plant).
3.6.2. The description of the meteorological
features relevant to the site and vicinity of the nuclear power plant,
considering the regional and local climatic impacts.
Reports on the results of the meteorological
observation at the site.
Assessment of the peak values of the
meteorological measurements such as temperature, humidity, rainfall, wind speed
and wind direction, especially the extrema of storms and tornados.
3.6.3. Analysis of the impact of meteorological
conditions on the possibility of radioactive dispersion to the site and from
the site into the environment.
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3.7.1. Assessment of the geological and tectonic
features relevant to the location of the nuclear power plant, and the technical
protective measures against the hazards.
The scale (sizes and shapes) of the research
areas must be founded on the subjects of research and the specific features
relevant to the site.
3.7.2. Assessment of the dangerous geological
processes (sliding, avalanche, karst, alluvium, streams, waterfalls, erosion,
slope and river bed, , subduction, collapse, subsidence, abrasion, volcanic
ash, volcanic eruption) and their combinations.
Forecast of the unfavorable changes that possibly
increase the dangerous geological conditions during the construction and
operation.
3.7.3. The assessment of the tectonic features
of the site and vicinity of the nuclear power plant.
The detailed description of the assessment
result used in the design of constructions (anti-earthquake design) of the
nuclear power plant that serve the safety analysis.
3.7.4. The comprehensive and detailed analysis
of the result of construction surveys for setting up the foundation for the
nuclear power plant safety.
3.8. Radioactive sources outside the nuclear
power plant
3.8.1. The description of the radioactivity at
the site, considering the impact of the radioactivity from the existing
generating units and other radioactive sources for assessing the radioactivity
at the site.
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3.9. The issues related to the site in the
plan for emergency response and emergency management
3.9.1. Specify the feasibility of the plan for
emergency response, specifically the access to the nuclear power plant, the
ability to transport, and the traffic assurance upon the occurrence of serious
emergencies.
3.9.2. Prove the suitability of the off-site
infrastructures for the emergency response.
3.9.3. Determine the necessity of administrative
measures and responsibility of other organizations and individuals than the
operators of the nuclear power plant.
3.10. The list of external impacts on the
nuclear power plant site
Enumerate the external impacts on the nuclear power plant site taken into account in the nuclear power plant design.
3.11. Observation of measurements related to
the site
3.11.1.
The plan for the observation of the seismic,
meteorological, hydrographic quantities, the factors of population, production,
trade, and traffic related to the site.
The observation plan must sufficiently provide
necessary information for the response actions outside the plant, assisting in
the periodic assessment of the site safety for the purpose of developing the
dispersion modeling of radioactive releases.
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3.11.2. The long-term observation program,
including the collection of data from the measuring instrument at the site and
the data from the specialized organizations for comparison.
The observation program must be able to detect
the remarkable changes in the design, including the changes caused by the
greenhouse effect.
3.11.3. The observation plan and program must be
founded on the forecast about the impacts of relevant hazards on the site,
assist the operators of the nuclear power plant and relevant organizations in
preventing, minimizing, and managing emergencies.
4. Emergency response
This section of the PSAR includes the basic
contents of the plans for emergency response; the ability to respond upon the
occurrence of emergencies, the necessary actions for protecting the community,
the radiological workers, and the plant.
4.1. The plan for emergency response
4.1.1. The plan for emergency response must have
the following contents:
- The targets and actions for mitigating the
consequences of the emergency, the actions for managing serious emergencies,
the procedure for taking such actions;
- The foundation for the feasibility of those
actions;
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- Taking into account the ability to cooperate
and the coordination of all relevant organizations;
- The establishment of the emergency management
board;
- The determination, classification, and
notification of the emergencies to relevant organizations; the provision of
information for the community, the scenario for responding upon the occurrence
of earthquakes, tsunami, or both;
- The measures for protecting the workers
participating in the emergency response;
- The measures for protecting the people within
the radius of 30 km;
- The specific jobs including: planning the
shelters, the locations, routes, vehicles, measures for ensuring the traffic
during the evacuation, the medical works;
- The cycle of emergency response drills
4.1.2. Refer to other relevant sections of the
PSAR where necessary.
4.2. Response center
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- Making decisions, take and manage all
responding measures of the plant, except for the control of the plan,
transmission of information about the plant condition to the off-site response
center;
- Take appropriate measures for controlling the
primary safety system from the backup control room;
- Forecast the possible emergencies; launch the
plans for mobilizing manpower and vehicles to take the initial measures, help
people, prevent the spread of emergencies, mitigate the consequences, isolate
the hazardous zones, and control the safety and security.
4.2.2. The off-site response center shall direct
the implementation of the provincial and national response plan, including:
- Assessing the information receive from the
emergency response center at the nuclear power plant site; provide
recommendations and assist in controlling the plant and protecting the workers
where necessary, cooperate with all organizations in responding to the
emergency, providing information and protecting the community where necessary;
- Run the off-site observation systems in order
to transmit data and information to the governing body where necessary;
- Anticipate
the possible emergencies; launch the plans for mobilizing manpower and vehicles to
take initial measures, help people, prevent the
emergency from spreading, mitigate the
consequences, isolate the hazardous zones, and control the safety and security.
4.3. The ability to anticipate the
emergencies, radioactive dispersion, and emergency consequences
4.3.1. The foundation for the ability of the
operating organization to anticipate the emergencies, the possibility of
radioactive dispersion, and emergency consequences.
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4.3.3. The assessment prescribed in Clause 4.3.1
in this Annex must be able to:
- Continuously monitor the on-site and off-site
radioactive conditions;
- Anticipate the radioactive dispersion that
exceeds the permissible limits;
- Constantly assess the condition of the plant,
especially the possible damage and plan the next emergency actions.
4.3.4. The foundation for the ability to run
normally of the safety equipment and systems; may be referenced to other relevant
sections of the PSAR.
4.3.5. The forecast of the complete emergency
recovery; the standards of emergency recovery.
The plan and instruments for decontaminating the
radioactively contaminated areas; the standards of emergency recovery, and the
conditions for normal operation.
4.4. Emergency response drill
The program, methodology, method of training and
practicing emergency response, the technical instruments (including practicing
instruments) for the training.
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The measures for treating, controlling, managing
radioactive waste and non-radioactive waste that suit the chemical – physical
properties of the waste and the amount of waste in over various period
(construction, normal conditions, and decommissioning).
5.1. Radiological impacts
5.1.1. The measures for treating and controlling
the radioactive waste before it is discharged into the environment. The
measures for treating and controlling that depend on the state of the waste
(solid, liquid, gas; high, medium, and low activity).
5.1.2. The explanation for the conformity of the
release with ALARA rules, including:
- The reasons and limits on the release of
solid, liquid, and gas waste during the operation, and the measures for
ensuring such limits;
- The plan for monitoring the level of
radioactive contamination and the level of off-site radiation;
- The method for measuring, recording, and
retaining the measurements about radioactive release from the site;
- The plan for monitoring the environment, and
the system for detecting unplanned radioactive release, and the devices for
automatically stopping the release (where necessary);
- The solutions and process of information
provision for the governing body and the public.
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5.1.4. The measures for managing the radioactive
waste at the nuclear power plant site.
5.2. Non-radiological impacts
Description of the measures for treating, controlling,
and managing non-radioactive waste similar to that of radioactive waste
prescribed in Clause 5.1 of this Annex.
5.3. Assessment of the impact of the nuclear
power plant on the agriculture, forestry, aquiculture, and the public
5.3.1. Analyze the sources of radioactive nuclei
that might affect the agricultural, forestry, and aquiculture.
5.3.2. Anticipate the amount radioactive nuclei
that might significantly affect the biological aspect of plants, animals, and
aquatic organisms.
5.3.3. Assess the exposure to radiation of
plants, animals, aquatic organisms, and the public; assess the possible
impacts.
The analyses, forecasts, and assessments
prescribed in Clause 5.3 must cover the usual operation of the nuclear power
plant and the occurrence of emergencies (including the planned and unplanned
emergencies).
5.4. The impacts of the nuclear power plant
on the social environment
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5.4.2. Assess the people's health
5.4.3. Assess the total exposure to radiation.
5.4.4. The positive and negative impacts of the
nuclear power plant on the social environment.
5.4.5. Explain the measures for overcoming the
negative impacts of the nuclear power plant on the everyday social conditions
of the public.
The analyses, assessments, and explanations
prescribed in Clause 5.4 must cover the residents in the vicinity of the
nuclear power plant.
5.5. Assessment of the impacts of the nuclear
power plant on the traffic, the industrial constructions, and civil
constructions
5.5.1. Assess the impacts of the nuclear power
plant on the traffic, the industrial constructions, civil constructions,
architectural, historical, and cultural constructions.
5.5.2. Analyze the possible negative impacts of
the traffic, production, and trade on the nuclear power plant; suggest method
and instruments for diminishing such impacts.
5.5.3. Explain the measures for ensuring the
safety of industrial constructions, civil constructions, and transport.