ND 30660496 Approved Order Of The Ministry For Environment

nd 306.604-96 approved order of the ministry for environment protection of ukraine no.114 dated 24 september 1996 radioact

ND 306.604-96
Approved
Order of the Ministry for
Environment Protection
of Ukraine No.114
dated 24 September 1996
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE DISPOSAL
IN NEAR-SURFACE STORAGE FACILITIES
General radiation safety requirements
(regulatory document ND 306.604-96)
This regulatory document covers enterprises, organizations and
institutions (hereinafter – Licensees) dealing with design,
construction, operation, decommissioning and preservation of
radioactive waste near-surface storage facilities except Licensees
dealing with management of waste resulted from uranium mining and
milling industry and spent nuclear fuel.
This document establishes radiation safety requirements for the
activities identified.
Terms and definitions
Terms and definitions being used in this regulation are as follows:
Closure – a state of a storage facility when no activities with
radioactive waste facilities are performed except those which are
required to keep safety.
Final disposal - isolation of radioactive waste from human and the
environment by placing them into a storage facility with no intention
of using it further.
Institutional control – actions carried out by authorized body or
organization after closure of storage facility to prevent
radionuclides removal and unauthorized intervention. This control can
be either active (monitoring, surveillance, remedial work) or passive
(land use control and archives keeping).
License – a special written permission granted by the Ministry for
Environment Protection of Ukraine to carry out any activity related to
radioactive waste management.
Near-surface storage facility – a site final disposal modules and
equipment needed to dispose radioactive waste at depth of not more
than 30 m.
Storage modules – a part of a facility, which consists of engineering
structures destined for radioactive waste location for their final
disposal.
Waste package - containers together with waste located within it that
meet the requirements for final waste disposal.
1. General provisions
1.1 Final disposal is considered safe provided the requirements
described in items 1.2-1.5 of this section are met.
1.2 Radiation exposure of staff under operation of a storage facility
shall not lead to exceeding of the dose limits established in NRB
76/87, item 3.2.
Radiation exposure of staff shall be reduced as low as possible taking
into account economical and social factors.
1.3 Exposure of certain persons from the public (category B in
accordance with NRBU 76/87) due to removal of radioactive substances
outside a storage facility by underground or surface water, by air or
by digestion chains in any period of storage facility lifetime shall
not exceed the dose limit established in NRB 76/87, item 3.2 taking
into account other ionizing radiation sources.
Release of radioactive waste into the environment shall be reduced as
much as possible considering economical factors.
1.4 It is necessary to provide for such a state of a storage facility
under which human being and the environment protection after its
closure does not require permanent active institutional control.
1.5 Protection of a storage facility shall be provided against
accidental intervention after completion of active institutional
control.
1.6 A storage facility shall be registered in the State Cadastre of
storage facilities and sites of radioactive waste temporary storage in
accordance with the Provision on the State Cadastre of storage
facilities and sites of radioactive waste temporary storage.
2. Requirements to waste subjected to final disposal
2.1 Radionuclide content, physical and chemical composition of waste
or their packages shall meet the requirements of storage facility
design where their final disposal is planned.
2.2 Only solid radioactive waste are subject to final disposal.
2.3 Radioactive waste acceptance criteria shall be developed and
agreed upon with the State Sanitary Supervision authorities and the
Ministry for Environment Protection of Ukraine. These criteria shall
cove:
a) list and maximum specific activity of radionuclides;
b) requirements for physical state of waste;
c) list and boundary permissible content of toxic and other dangerous
non-radioactive substances;
d) requirements for waste packages properties;
e) requirements for marking of packages;
f) requirements for supporting documents.
The list of criteria can be supplemented both by the Licensee and the
regulatory authority.
2.4 Numerical values of waste properties shall be determined with the
accuracy sufficient enough to ensure compliance with the requirements
established according to item 2.3 of this document.
2.5 Radioactive contamination of external surfaces of waste packages
shall not exceed the levels established in NRB 76/87, Table 8.5.
2.6 Radioactive waste having other dangerous properties must be
located in a storage facility within special containers and using
additional engineering barriers that ensure fulfillment of the
requirements established in items 1.2-1.5.
2.7 Waste shall be of no fire danger. Waste packages shall keep their
integrity under maximum predicted accident.
2.8 Waste containing alpha-active radionuclides and spent ionizing
radiation sources shall be received for disposal within separate
containers.
2.9 It is necessary to ensure structural stability of waste that is
achieved by the physical as-state of waste, their placing within
containers and engineering structures retaining their protecting
properties during a period of time necessary for waste transfer into a
safe state.
2.10 Each waste package shall have its own marking that shall be
retained up to the moment of the storage facility preservation.
2.11 Supplier shall compose a certificate for each waste package where
waste properties shall be indicated in accordance with SPORO-85.
3. Requirements for storage facility site
3.1 The objective of this section is to identify the requirements for
properties of storage facility site that can influence upon safety of
final disposal.
3.2 Geological structure of the site shall be simple enough to have a
possibility to perform its modeling and monitoring.
3.3 Geological stability of the site shall be assessed with time till
the waste subjected to disposal will is dangerous.
3.4 Siting shall be performed considering future population upsurge
and prospects as to development of territories adjacent to site.
3.5 The territories with deposits of useful minerals shall be avoided.
3.6. The territories shall be avoided where complete of partial
flooding or underflooding is possible.
3.7 The depth down to ground water mirror shall be sufficient enough
to prevent continuous or other storage facility inundation. Waste must
not be located within area where deviations of ground water level are
possible.
It is necessary to assess possible changing in ground water level.
3.8 Relief of the site territory shall be such to provide for minimum
surface outflow that prevents from erosion and flooding of waste
storage facility.
3.9 Geochemical and hydrogeological properties of the site shall
promote delaying of radionuclides migration and shall not impact
considerably on the engineering barriers efficiency.
3.10 The territories shall be avoided where the expression of cavity
formation and slump processes is possible that can influence upon a
storage facility capability to isolate radioactive waste from the
environment.
3.11 The site shall not be located within the territory where
near-surface geological processes are expressed or can be actuated
such as erosion, landslides, landslips and weathering that can
influence upon a storage facility ability to isolate radioactive waste
from the environment.
3.12 The storage facility site shall be located in such a way that
entering paths allow transporting radioactive waste without
unacceptable risk for the public.
3.13 The storage facility site shall not be located near enterprises
and productions that can influence upon a storage facility capability
to isolate radioactive waste from the environment or violate the
environmental monitoring program.
4. Storage facility designing
4.1 Radioactive waste storage facility shall be designed considering
its operation lifetime along with quantity and properties of
radioactive waste subjected to final disposal at the territory to be
served by this facility. In designing the following radioactive waste
shall be taken into account:
1) available during designing;
2) being generated in future under operation of nuclear facilities and
as a result of radioactive substances using in industry, medicine and
research;
3) being produced under decommissioning of nuclear facilities.
It is necessary to envisage the reserve in a case of final disposal of
radioactive waste generated in elimination of radiation accidents.
4.2 Under designing the following items shall be identified:
1) type of a storage facility;
2) technology, structures, premises and equipment necessary to receive
waste;
3) technology, structures, premises and equipment necessary for waste
interim storage;
4) method of waste packages location within a storage facility;
5) types of protecting barriers;
6) drainage systems within a storage facility;
7) internal transporting system;
8) technology, structures, premises and equipment necessary for
decontamination of transport and equipment;
9) methods to monitor on-site ground water level within the storage
facility site;
10) radiation monitoring program in compliance with the requirements
of Section 9;
11) environment monitoring program in accordance with the requirements
of Section 10;
12) scenarios of progression of possible emergencies, their
consequences and comparison of the analysis results with safety
criteria.
4.3 The storage facility shall be designed in a way to exclude water
intrusion inside it and reduce water infiltration. The storage
facility design shall envisage removal of infiltration water and
near-surface drainage from waste and reduction of unfavorable
geological processes impact.
Structures, premises and equipment necessary for sorting, intermediate
storage and final disposal of waste shall be located separately from
other structures and premises not destined for radioactive waste
management. Also, arrangement of changing room mode shall be planned.
4.4 A physical protection system for radioactive materials being
stored or disposed yet has to be developed.
4.5 It is necessary to envisage a sanitary and protecting area around
a storage facility. Its size should be determined in compliance with
the requirements of OSP 72/87 item 2.5.
4.6 Under designing of a storage facility it is necessary to develop a
facility preservation plan. This plan shall describe sequence and
contents of measures on:
1) ceiling of storage facility modules;
2) decontamination and dismantling of equipment and structures
unnecessary for subsequent maintenance;
3) archives storage;
4) establishing of a post-operational monitoring and institutional
control system.
4.7 The efforts on designing of storage facilities can perform only
those organizations that have the license to perform appropriate
design activities. Licensing procedure is established by the Ministry
for Environment Protection of Ukraine.
5. Storage facility construction
5.1 Construction of a storage facility includes preparation of a site,
construction of production premises and modules for final disposal of
waste, laying of engineering communications, structures, assembling
and tuning of technological equipment and monitoring system.
5.2 Construction activities can be started only after regulatory
approval of the site selected, design development, issuing of permits
(licenses) provided for by the legislation and development of the
quality assurance program.
5.3 Construction activities shall be performed under strict compliance
with the design and terms of the licenses obtained.
5.4 Amendments in and deviations from design or terms of licenses are
possible provided that they will not impact on safety and a written
permit of the Ministry for Environment Protection will be obtained.
5.5 Reconstruction activities and construction of additional modules
can be performed under storage facility operation provided that this
will not impact upon the existing storage facility safety, and a
written permit of the Ministry for Environment Protection of Ukraine
will be obtained.
5.6 It is necessary to identify accurately and indicate at the map the
storage facility boundaries and location of its each module. At least,
one permanent point for plane and height basis of geodesic network of
Ukraine shall be laid on-site.
5.7 The guarding system shall be used at the storage facility
territory that prevents unauthorized intervention of strange people,
vehicles and animals. Radiation safety signs shall be installed prior
to starting operation.
6. Storage facility operation
6.1 Operation of a storage facility covers its commissioning, receipt
and location of waste inside, storage facility maintenance,
intermediate storage and other measures in compliance with the license
terms.
6.2 The Licensee is of complete responsibility for safe operation of a
storage facility, radioactive waste accounting and keeping of
documentation.
6.3 There shall be a changing room mode in a storage facility for
transport and staff.
6.4 All the persons involved into the activities related to
transportation, acceptance, storage, sorting and final disposal of
radwaste, decontamination of equipment and radiation control refer to
the category A – staff in accordance with NRB 76/87, item 26.
6.5 Prior to operation instructions and storage facility technical
specifications reflecting the following main aspects shall be
developed and approved by the Licensee:
1) personnel qualification, duties and responsibilities;
2) radioactive waste monitoring and acceptance procedure;
3) procedure for internal transportation, temporary storing and
sorting of waste in a storage facility;
4) radioactive waste disposal procedure;
5) decontamination procedure;
6) procedure for ensuring sanitary and changing mode;
7) procedure and forms for accounting waste received and disposed at
the storage facility.
6.6 “Instruction to prevent accidents and fires and to mitigate their
consequences” and “Plan of measures on personnel protection and in the
event of accidents” shall be developed, approved by the Licensee and
agreed with the State Sanitary Supervision and State Fire Supervision
authorities in accordance with the requirements of OSP 72/87 items
14.11 and 14.12 and other instructions in the event of accidents
pursuant to the requirements of the regulatory authorities.
6.7 Radiation monitoring and the environment monitoring programs shall
be developed, approved by the Licensee and agreed with the State
Sanitary Supervision authorities and the Ministry for Environment
Protection of Ukraine in accordance with sections 9 and 10 of this
document.
6.8 Prior to start receiving radioactive waste it is necessary to get
the sanitary certificate for the storage facility from the State
Sanitary Supervision authorities of Ukraine in accordance with the
requirements of OSP 72/87 item 3.3.
6.9 Waste received for disposal shall meet the requirements stated in
items 2.1-2.11 of this document. The Licensee shall be able to check
radioactive waste being received.
6.10 When radioactive wastes do not meet these requirements they are
not being received. At that time an appropriate act is being compiled
describing the refusal reasons.
6.11 Radioactive waste entering a storage facility are subject to
account. Account documentation shall be kept during the whole period
of storage facility operation.
6.12 Radioactive waste packages located in a storage facility module
are subject to account indicating a package number along with that of
module where it is located, as well as each package in-module location
place. During one month since the end of each quarter it is necessary
to submit a report to the Ministry for Environment Protection of
Ukraine on received and disposed waste.
6.13 Only radioactive waste shall be disposed at the storage facility.
7. Storage facility decommissioning and preservation
7.1 Storage facility can be decommissioned both under planned order
after filling of all its modules and resulted from the state
regulatory authorities decision. In the latter case repeated
commissioning is possible only if repeated permission from appropriate
regulatory authority is available.
7.2 The storage facility preservation plan shall be developed based on
the previous decommissioning and preservation plan in accordance with
item 4.7 of this document considering the storage facility
construction and operation experience. The plan shall be agreed upon
with the State Sanitary Supervision authorities.
7.3 Storage facility can be preserved only after the Ministry for
Environment Protection of Ukraine issues the appropriate permit
(license).
7.4 There shall be permanent signs installed at the territory of
storage facility that warn on danger of intervention.
7.5 After completion of preservation efforts a storage facility can be
transferred to the organization responsible for its post-operational
maintenance only on a basis of a written permission of the Ministry
for Environment Protection of Ukraine.
8. Post-operational maintenance of a storage facility
8.1 Post-operational maintenance is aimed at preventing inadvertent
intervention and removing radionuclides off-site.
8.2 Post-operational maintenance of a storage facility is performed as
active and passive institutional control.
8.3 Efficient institutional control includes such an activity as
monitoring, periodical inspection of drainage system functioning,
repair of fences and signs of radiation danger, replacement of
equipment for monitoring and vegetation removal that can influence
upon safety of storage facility. Also, the efforts can be performed to
prevent erosion due to sharp worsening of climate conditions.
8.4 Duration of efficient institutional control shall not exceed 100
years.
8.5 Except efficient control, also passive institutional control shall
be performed that is retention of information on the storage facility
location place, as well as restriction of land-tenure for some kinds
of activity.
9. Radiation monitoring
9.1 Under operation of a storage facility the radiation monitoring
program shall be implemented where the following items shall be
identified:
1) kinds, scope, facilities and internal regulations of radiation
control;
2) order of recording, accounting and storing the monitoring results;
3) permissible and reference levels of the parameters being monitored;
4) contingent of persons under individual monitoring;
5) necessary equipment and its location inside a storage facility;
6) necessary staff and its qualification;
7) format and order of reporting to the state regulatory authorities.
The radiation monitoring program shall be agreed upon with the state
regulatory authorities.
9.2 Radiation monitoring under final disposal of radioactive waste is
performed in the scope and by the parameters envisaged in GOST
12.1.048-85.
10. Environment monitoring
10.1 At the stage of storage facility siting it is necessary to
perform the environmental monitoring to obtain background
characteristics and take them into account under designing. It is
necessary to obtain the information on ecological, meteorological,
climatic, hydrological, hydrogeological, geological, geochemical and
seismic properties of the storage facility site. For the properties
that undergone season variations the data shall be generalized, at
least, for a year.
10.2 During construction it is necessary to provide for monitoring
aimed at assessing possible changes in the environment state due to
storage facility construction.
10.3 Prior to storage facility operating it is necessary to develop an
environmental monitoring program for its operation period. Scope, kind
and parameters of monitoring as well as their sufficiency shall be
agreed upon with the state regulatory authorities on nuclear and
radiation safety.
10.4 Environmental monitoring program shall be aimed at:
1) detection of radionuclides migration from storage facility modules;
2) prevention against weather conditions, underground water level and
other properties changing impact upon a storage facility safety.
10.5 The following aspects shall be covered by the program:
1) procedure for recording, accounting and storing the monitoring
results;
2) list of the parameters to be monitored;
3) necessary equipment and its location;
4) necessary staff and its qualification;
5) format and order of reporting to the state regulatory authorities.
10.6 The following kinds of monitoring shall be included into the
environmental monitoring program:
1.
control over contamination levels of near-surface and underground
waters, atmosphere, vegetation and soils within sanitary and
protecting area boundaries;
2.
control over changes in level, physical and chemical properties of
underground and near-surface water;
3.
control over changes in weather conditions.
10.7 It is necessary to develop the monitoring program for
post-operational period. This program shall be aimed at timely
notification on removal of radionuclides from the storage facility
modules, as well as at control over protecting barrier properties.
11. Quality assurance requirements
11.1 Quality assurance is a set of measures on control over
observation of designing, construction, operation and post-operational
maintenance conditions. Quality assurance is aimed at ensuring that
the safety requirements will be met.
11.2 The following items shall be identified in the quality assurance
program:
1) properties of storage facility components quality level;
2) methods to achieve and keep this quality level;
3) control over its achievement and maintaining;
4) analysis and elimination of possible deviations;
5) account of the control results and reporting formats;
6) necessary staff and its qualification;
7) necessary technical means for quality assurance;
8) storage of design, construction, operation documentation, as well
as the one developed during preservation stage.
11.3 The Licensee is of complete responsibility for development and
implementation of the quality assurance program, including the system
to check storage facility, as well as all the activity being
implemented there. The Licensee can charge another organization with
development and implementation of the whole quality assurance program
or its part, but in such a case he also is still responsible for its
general efficiency without transfer of responsibility and commitments
to the Contractor.
11.4 In developing the quality assurance program it is necessary to
take into account that radioactive waste final disposal safety also
depends upon waste producers. It is necessary to request waste
producers to submit the documentation justifying that quality was
ensured during waste sorting and reprocessing, radionuclide content
identification, compiling the documentation for waste packages and
other activities that can influence upon safety.
11.5 It is necessary to check quality of the information submitted by
waste producers to provide for waste compliance with the acceptance
criteria identified in items 2.1-2.11 of this document.
Referenced data
1.
DEVELOPED AND INTRODUCED BY
the State Scientific and Technical Centre for Nuclear and Radiation
Safety
Executors: Dr. M. Korotenko (Task Leader),
O.Davidovs’ky
V.Golubev
2.
APPROVED by Ordinance of the Ministry for Environment Protection
of Ukraine No.114 dated 24 September 1996.
3.
INMPLEMENTED BY THE FIRST TIME
4. THE FIRST CHECKING TERM IS – September 1998.
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