state regulation of nuclear and radiation safety in the ... · pdf file1,2,3... 1 state...

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State Regulation of Nuclear and Radiation Safety in

the Russian Federation

2011

Federal Environmental, Industrial and Nuclear Supervision Service (Russian Federation)

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Main objectives of nuclear and radiation safety regulation are:

Establishment and maintenance of conditions of

comprehensive protection of the society and state from

inadmissible radiation impact;

Prevention of uncontrolled propagation and use of

nuclear material and radioactive substance.


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Status and Authorities of Rostechnadzor


Rostechnadzor is subordinated to the

Government of the Russian Federation and

entrusted with the functions of elaboration and

implementation of the state policy and development

and enactment of regulations in the sphere of

nuclear and radiation supervision (civil atomic

energy use area).

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Status and Authorities of Rostechnadzor


Rostechnadzor is:

- a body of state safety regulation in the civil atomic

energy use;

- a regulatory body in accordance with the Convention

on Nuclear Safety and the Joint Convention on the

Safety of Spent Fuel Management and on the Safety of

Radioactive Waste Management, as well as a

competent body of the Russian Federation in

accordance with the Amendment to the Convention on

the Physical Protection of Nuclear Material.

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Main Nuclear and Radiation Safety

Regulatory Functions

1. Development and enactment of safety regulations in the field of atomic energy use

2. Licensing of activities in the field of atomic energy use

3. Supervision of nuclear and radiation safety of nuclear and radiation hazardous installations, including supervision of nuclear materials accounting, control and physical protection


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Organizational Structure of Rostechnadzor

Interregional Territorial Departments for Nuclear and Radiation Safety Supervision

Technical Support Organizations

(2 in the field of nuclear supervision)

HEADQUARTERS

Interregional Territorial Departments for

Nuclear and Radiation Safety

Supervision

(7→6)

Departments for Industrial Supervision

(31)

Analytical laboratories

ORGANIZATIONS

Functional

Departments

(7)

Nuclear

Supervision

Departments

(2)

Industrial and

Energy Supervision

Departments

(6)


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Organizational Structure of Rostechnadzor (NRS)

Interregional Territorial Departments for Nuclear

and Radiation Safety Supervision (ITDs)

North-

European ITD

Siberian and

Far East ITD

HEADQUARTERS

Department for Safety

Regulation of Nuclear

Power Plants and

Research Nuclear

Installations

Department for Safety Regulation of Nuclear

Fuel Cycle Facilities, Nuclear Energy

Installations of Ships and Radiation

Hazardous Facilities, Supervision of

Account and Control of Nuclear Material and

Radioactive Substances and Physical Protection

Central ITD Don ITD Volga ITD Ural ITD

Far East ITD


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FEITD

Khabarovsk

SITD

Novosibirsk

UITD

Ekaterinburg

NEITD

Saint Petersburg

DITD

Novovoronezh

CITD

Moscow

Balakovo

VITD

CITD - Central Interregional Territorial Department DITD - Don Interregional Territorial Department NEITD - North-European Interregional Territorial Department UITD - Ural Interregional Territorial Department VITD – Volga Interregional Territorial Department SITD - Siberian Interregional Territorial Department FEITD - Far-East Interregional Territorial Department (SITD and FEITD were joined in 2011)


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Leg

isla

tive A

cts

(no

rma

tive

le

ga

l a

cts

of

the R

ussia

n F

ed

era

tio

n)

Rec

om

-m

en

- d

ato

ry

Do

cu

-m

en

ts

Federal Norms and Rules

in the Field of Atomic Energy Use

Consti-

tution

International Agreements,

Federal Laws

Decrees of the President Government

Regulations

National Standards, Standards of Enterprise

Guiding Documents

Administrative Regulations

Technical Regulations

Safety Guides (Statutes)

Reg

ula

tory

D

ocu

men

ts

of

Ro

ste

ch

nad

zo

r Structure of the Russian Legislative

and Regulatory Documents in the Field of Atomic Energy Use


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INTERNATIONAL CONVENTIONS

Convention on Nuclear Safety (Adopted by RF Government Regulation No. 377 dated 03.04.1996)

Joint Convention on Safe Management of Spent Nuclear Fuel and

Safe Management of Radioactive Waste (Ratified by Federal Law No. 139-FZ dated 04.11.1995)

Convention on Physical Protection of Nuclear Material (Ratified by Decree of the USSR Supreme Soviet Presidium No. 9236-X dated

04.05.1983)

Convention on Civil Liability for Nuclear Damage (Ratified by Federal Law No. 23-FZ dated 21.03.2005)

Convention on Early Notification of a Nuclear Accident (Ratified by Decree of the USSR Supreme Soviet Presidium No. 6035-XI dated

14.11.1986)


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Legislative basis in the field

of nuclear energy use

Federal Law “On the Use of Atomic Energy”

No. 170-FZ dated 21.11.1995

Federal Law “On Radiation Safety of

Population” No. 3-FZ

dated 09.01.1996


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Federal Law «On Sanitary and Epidemiological Well-Being of the Population» (No.52-FZ, dated 30.03.1999)

Federal Law «On Environmental Protection» (No. 7-FZ, dated 10.01. 2002)

Federal Law «On Environmental Review» (No. 174-FZ, dated 23.11.1995)

Federal Law «On Radioactive Waste Management» (No. 190-FZ, dated 11.07.2011)

Water Code of the RF (No. 74-FZ, dated 03.06.2006)

Federal Law «On Mineral Resources» (No. 2395-1, dated 21.02.1992)


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Normative Documents used for the State Regulation of Nuclear and Radiation Safety

Technical Regulations– include obligatory requirements to product characteristics applied by nuclear industry. Approved as Federal Law or RF Government Regulations

Federal Norms and Rules – include obligatory requirements to nuclear facilities and types of activities

Administrative Regulations – define a procedure for fulfilment of state functions on regulation of nuclear and radiation safety of nuclear facilities (obligatory to specialists of regulatory body)

Guiding Documents – specify a procedure for implementation of of state regulation (obligatory or advisory documents for regulatory body specialists)

Safety Guides (Statutes) – explain the implementation of obligatory requirements of technical regulations and Federal Norms and Rules (advisory)


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Federal Law of 21.11.1995, No. 170-FZ «On the

Use of Atomic Energy»

Federal norms and rules in the field

of nuclear energy use

The procedure for

development and

approval of federal

norms and rules as

well as their list is

established by the

Russian Government

Are obligatory for

all the legal entities

and individuals on

the territory of the

Russian Federation

Are approved and

implemented by the

state safety regulatory

bodies within their

competence


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STRUCTURE

OF THE LIST OF FEDERAL NORMS AND RULES

IN THE FIELD OF NUCLEAR ENERGY USE

Federal norms and rules in the field of nuclear

energy use

Rostechnadzor Ministry of the Russian

Federation for Civil

Defense, Emergencies

and Elimination of

Disaster Consequences

Ministry of

Health of the

Russian

Federation

Fire safety of

nuclear

facilities

Technical safety

of nuclear

facilities

Nuclear and

radiation safety

of nuclear

facilities

Radiation safety

of population


Rostechnadzor

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Federal norms and rules

in the field of the nuclear energy use

21

2210

7

15

7

4

General (21)

Nuclear Power Plants (22)

Research Installations (10)

Nuclear installations of ships (7)

Nuclear fuel cycle facilities (15)

Radoactive waste (7)

Radiation sources (4)

TOTAL: 86


NPP

General

RI NI of ships

NFC

facilities

RW

RS

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Main Areas of Federal Norms and Rules on Nuclear and Radiation Safety

• Objectives, principles, criteria External impacts Layout, design Nuclear safety Radiation safety Operation Radioactive waste management Decommissioning Transportation (shipment) Accounting and control Physical protection Emergency preparedness


Predisposal Management of Radwaste

Predisposal Management of Low and Intermediate

Level Radioactive Waste Safety Guide. WS-G-2.5.

Predisposal Management of High Level Radioactive

Waste Safety Guide. WS-G-2.6.

Predisposal Management of Radioactive Waste,

Including Decommissioning Safety Requirements.

WS-R-2. Radwaste disposal. Principles,

Criteria and basic safety

requirements.

NP-055-04.

Near Surface Disposal of Radioactive

Waste. Safety Requirements. NP-

069-06.

GRW

Management.

Safety

requirements

. NP-021-

2000.

Collection,

reprocessing ,

storage and

conditioning

of LRW.

Safety

requirements.

NP-019-2000.

Collection,

reprocessing ,

storage and

conditioning

of SRW.

Safety

requirements.

NP-020-2000.

Safety Principles and Technical

Criteria for the Underground Disposal

of High Level Radioactive Wastes.

Safety Series No. 99. Geological

Disposal of Radioactive Waste Safety

Requirements.No. WS-R-4

Near Surface Disposal of Radioactive

Waste Safety Requirements. WS-R-1.

Principles of Radioactive Waste

Management Safety

Fundamentals

No. 111-F

Safety in Radioactive Waste

Management. General Provisions.

NP-058-04.


Evolution of the system of federal norms and rules with account of IAEA standards

Harmonization of federal

norms and rules with

IAEA standards’

provisions

Improvement of the

structure of federal

norms and rules


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32 nuclear fuel cycle plants (312 facilities):

15 production reactors, 30 nuclear material processing facilities,

12 SNF storage facilities, 44 nuclear material storage facilities,

190 solid RW storage facilities, 21 liquid RW storage facilities.

75 research nuclear installations; 6,176 radiation-hazardous facilities of national economy.

28 nuclear fleet facilities: 10 nuclear ice breakers, 5 nuclear service vessels, 2 nuclear material storage locations,

2 RW storage locations, 1 floating liquid RW processing plant,

1 floating power unit (under construction), 6 prototype benches.

32 operating NPP units;

4 NPP units under preparation for decommissioning;

9 NPP units under construction;

904 manufacturing plants;

540 facilities and organizations providing activities and services.

Nuclear Facilities under Supervision


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Fuel Cycle Facilities


МСЗ

СХК

НЗХК

УЭХК

АЭХК

ГХК

ПО «Маяк»

ПО «ЭХЗ»

ВНИИНМ

ВНИИХТ

РНЦ «КИ»

ГНЦ ФЭИ

НПО Луч

РИ

Далур

ППГХО

Хиагда

ЧМЗ

НИИАР

ХМЗ

ОКБМ

ВНИПИЭ

Т

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Common situation in the Russian Federation regarding the civil nuclear and radiation hazardous facilities

decommissioning

More then 120 nuclear and radiation hazardous facilities (installations) are

shutdown (but not decommissioned) in the Russian Federation.

Among them:

4 NPP units;

13 Uranium-graphite production reactors;

11 Research nuclear reactors.


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Decommissioning of Fuel Cycle Facilities

Urgent decisions should be elaborated regarding to the 20 open liquid RW storage

pools, including decommissioning of those located at FGUP “PO “Mayak” site as

containing the highest concentration and amount of liquid radioactive waste.

The decommissioning activities for fuel cycle facilities are foreseen (financially) by

the Federal Target Program on Nuclear and radiation safety in the Russian Federation.


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JSC «Hydrometallurgical Enterprise»

(mines № 1, 2; dumps, slag-heaps )


• Mines isolation

• Decontamination and

decommissioning of buildings,

rehabilitation of the site territory

(physical and protection barriers for

the slag accumulators)

• Radioactive waste disposal on

special areas

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Kirovo-Chepetsky Chemical Combine

(territory rehabilitation)


• Slag accumulators isolation

• Protection barriers creation

• Decontamination and

decommissioning of the buildings

on the site

• Special area creation for the

radioactive waste temporary storage

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Chemical-Metallurgical Enterprise


• Buildings decontamination and decommissioning on

the site

• Transportation of the dismantled and decontaminated

equipment to MCC

• Creation “brown” site.

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Uranium Graphite Production reactors decommissioning at

MCC, SCC and PO Mayak sites

(13 reactors)


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Categorization of radiation facilities according to their potential hazards. * (Principal Sanitary Rules on the Radiation Safety Ensuring, OSPORB-99/2010)

Category I. Radiation facilities where an accident can cause radiological impact on population. Population protection measures may be required.

Category II. Radiation facilities where accident radiological impact is restricted by the sanitary protected zone.

Category III. Radiation facilities where accident radiological impact is restricted by the site boundaries.

Category IV. Radiation facilities where accident radiological impact is restricted by the premises where the work with the radiation sources are conducted.

* Categorization should be developed at the design stage in coordination with

radiation safety supervision authorities. The operator is responsible for the categorization of

the already existing facilities. He should do this work in coordination with the state sanitary

and epidemiological supervision authority.

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Decommissioning of Fuel Cycle Facilities (Cont. 1)


Development of decommissioning design for radiation facilities (radiation sources). * (Principal Sanitary Rules on the Radiation Safety Ensuring, OSPORB-99/2010)

Category I. not less than 5 years before A detailed decommissioning design should be developed not less than 5 years before a facility or its part operational life-time expiration. The design should be coordinated with the state radiation safety supervision authority.

Category II. not less than 3 years before A detailed decommissioning design should be developed not less than 3 years before a facility or its part operational life-time expiration. The design should be coordinated with the state radiation safety supervision authority.

Category III. not less than 1 years before A detailed decommissioning design should be developed not less than 1 years before a facility or its part operational life-time expiration. The design should be coordinated with the state radiation safety supervision authority.

Category IV. Is not regulated

* The issue of operational life-time extension of a radioactive source should be considered by an appointed commission. This commission should include the representatives of an operator, using the source, representatives of state radiation safety supervision authority, and the source manufacturer if necessary. The commission should make a decision on the possibility of radioactive source operational life-time extension for a certain period of time and the conditions of its use.

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«Nuclear Fuel Cycle Facilities Decommissioning Safety Rules».

NP-057-04

Safety requirements at

decommissioning

Requirements to the Decommissioning

program (plan)

Requirements to the Comprehensive technical engineering and radiation

investigation (survey)

Requirements to the Decommissioning

design

* This document is valid for the NFC Facilities under the design, operation or

decommissioning, apart from Uranium ore mining facilities.

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Main decommissioning milestones

Shutdown (stop) for decommissioning

Preparation for decommissioning

Decommissioning

Decommissioning design

Putting into the nuclear (criticality) safe condition

Comprehensive engineering and radiation investigation (survey)

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Main milestones for the decommissioning documentation development

Comprehensive engineering and radiation investigation (survey) of the facility and the site

Putting into the nuclear (criticality) safe condition

Precise sanitary

passport

Decommissioning program

Decommissioning project

Safety analysis report on decommissioning

Quality assurance

program

Decommissioning

concept

Technological (operation-technical) documentation

Technological reglament

Dismantling program and schedule

Emergency plan for the workers

protection in the case of accident

Instruction on accident liquidation

Instruction on the equipment and

system operation

Special

program

If the nuclear materials could not be removed using the existing standard technology, the special program is

necessary

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Comprehensive technical engineering and radiation investigation (survey) of a facility and its site.

Radiation conditions (situation) investigation (survey) inside the premises, buildings, and on the site. Developing the maps of radioactive contaminated zones and (or) dose rates.

Tests, including probing and sampling with its subsequent analysis with the view to finding long-lived fission products activities, their location in the graphite stack of the reactor where there were operational incidents with the fuel.

Evaluation of radiation characteristics of spills and parts (fragments) of nuclear fuel inside the graphite stack originated from accidents, which were kept in the core.

Review of radionuclide composition, physical and chemical condition of radioactive materials, its activity, zones of its location, its origin (activation, coolant transfer, accidents, and so on).

Investigation (survey) of equipment, constructions, systems necessary for decommissioning in order to understand how reliable and operable they are for using them in the frame of the decommissioning activity.

Investigation (survey) of constructions, systems, equipment, and buildings planned for decommissioning in order to understand how robust they are, to evaluate their residual operational life-time taking into consideration data on the observed long-term environmental impact on the basements of these facilities including hydrological conditions on the site.

Performing the investigations on mass and location of nuclear fuel spills, to compile a written report on results and a conclusion on nuclear safety.

Conducting, if necessary, other testing and computation of nuclear, physical and radiation characteristics of equipment, materials, radioactive and non-radioactive wastes located within the reactor.

Inventory of mass, content and condition of fissile materials with the view to regulating nuclear safety of spent nuclear fuel pools and storage facilities, equipment with sediment of fissile materials, storage and disposal facilities for radioactive waste containing fissile materials different from the design.

Evaluation of volumes (mass) and radiation characteristics of radioactive and non-radioactive wastes.

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Программа вывода из эксплуатации

Decommissioning Program

Brief description and justification of the decommissioning option chosen by the

operator.

Criteria on the required safety level achievement (for the facility) after implementation of each

decommissioning stage.

Main stages of decommissioning and

their time-frames.

Brief description of end-states of a facility under decommissioning

when every stage is finished.

Brief description and justification of safety measures at each decommissioning stage, including brief description and justification of the sequence of protective barriers integrity destruction. краткое описание и обоснование мер безопасности на каждом из этапов вывода из эксплуатации ПР, включая краткое описание и обоснование

Safety ensurance principles at each decommissioning

stage.

Brief characteristics of decommissioning process at each

stage.

Decommissioning concept

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Quality Assurance Program

Work performance in compliance with the general plan and general procedures of organizational and technical activity (implemented on a planning base).

Quality control system including: creation and certification of divisions (organizations),

responsible for quality control of work performance, items and services;

work performance controle procedures at every stage of decommissioning, quality control of items and services;

reporting procedures on the results of the control implementation;

measuring devices and metrological ensuring; data collection and evaluation system for accidents

(deviations) and their causes (reasons); other issues related to the organization and quality

assurance of the performing works. система контроля качества, включающая:

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THANK YOU

FOR

THE ATTENTION
