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Status of the CRAFT Project Working Groups: RADON Facilities IAEA Technical Meeting 17-21 June, 2013, IAEA Technical Meeting of the Complimentary Safety Reports: Development and Application to Waste Management Facilities

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Status of the CRAFT Project

Working Groups:

RADON Facilities

IAEA Technical Meeting

17-21 June, 2013, IAEA

Technical Meeting of the Complimentary Safety Reports:

Development and Application to Waste Management Facilities

12 ОJune, 2007 2

Content

Object (Radon-type facilities)

Group objectives

Scope

Input

Work Plan and Status

12 ОJune, 2007 3

RADON facilities

The system of RADON enterprises was

established the USSR in early sixties of the XXth

century

collection, transportation, processing and

disposal of LILW wastes and DSRS,

generated or used in medicine, research

institutions, various branches of industry

35 “Radon” facilities in the Soviet Union

16 of them in the Russian Federation

12 ОJune, 2007 4

RADON facilities

1 - Moscow «Radon» Facility

2 - Leningrad «Radon» Facility

3 - Volgograd «Radon» Facility

4 - Nizhny Novgorod «Radon» Facility

5 - Grozny «Radon» Facility

6 - Irkutsk «Radon» Facility

7 - Kazan «Radon» Facility

8 - Samara «Radon» Facility

9 - Murmansk «Radon» Facility

10 - Novosibirsk «Radon» Facility

11 - Rostov «Radon» Facility

12 - Saratov «Radon» Facility

13 - Sverdlovsk «Radon» Facility

14 - Bashkirskiy «Radon» Facility

15 - Chelyabinsk «Radon» Facility

16 - Khabarovsk «Radon» Facility

12 ОJune, 2007 5

RADON facilities

Typical historical repositories are vaults below the ground level with the volume from 200 to 9000 m3,

basement made of concrete plates,

walls made of monolithic reinforced concrete or concrete blocks,

divided with concrete or wooden walls into cells (sections),

the top is covered with reinforced concrete plates, sand and waterproof asphalt layer

12 ОJune, 2007 6

RADON facilities

depth –3-6 m, width – 5,5 up to 32 m length – 16 up to 100 m.

Disposal/Storage

Radon facilities evolution Load hatches

Layer-on layer cementation

Container use Above ground facility

8

Radon facilities

Radon facilities

9

Designed and operated as disposal facilities for

institutional LILW without intention of the waste

retrieval

Don’t fit with the safety requirement for near

surface disposal (long lived alpha emitters, high

active DSRS etc.)

Don’t fit with the safety requirements for long term

storage (waste package inspection, retrievability

etc.)

Radon facilities

10

Operators of RADON type facilities are obliged to

perform safety assessment and upgrade safety

Decision making depends not only from the safety

issues but from socio-political, technical and

economic aspects

Most common decisions include:

decommissioning of facility

upgraded storage facility

upgraded disposal facility

Measures are often considered:

partial or complete RW retrieval and conditioning

reconstruction

11

Basic terms definition

RAW classification

special RAW and Retrievable (disposable) RAW

classes of Retrievable RAW (based on disposal option)

For Special (nonretrievable) RAW:

emplacement site and

site for conservation

Deep well injection of liquid LLW and ILW on operating

sites

Main statements of Federal Law «On Radioactive Waste Management»

12

Initial RAW Registration

Initial RAW registration is provisioned in the Article 23 of the Federal Law “On

Radioactive Waste Management” and will be implemented during the first phase of

development of the a unified state system of radioactive waste management starting

from the January 15, 2013 till December 31, 2014 inclusively.

The surveys will be carried out in all facilities having radioactive waste that are subject

for the initial registration.

Based on the survey results special commissions will draw up the acts of initial

registration, on the basis of which proposals will be developed to classify radioactive

waste storage facility into a particular category of radioactive waste storage facilities.

The State Corporation "Rosatom" has confirmed the schedule for survey and initial

registration of the storage facilities (sites) for radioactive waste generated before

15.07.2011.

The schedule was developed in accordance with the Governmental Resolution from

25.07.2012 № 767 "On carrying out the initial registration of radioactive waste"

13

Initial RAW Registration

Initial RAW registration will provide the necessary information to form a

registry of radioactive waste and the inventory of the radioactive waste

storage facilities (sites).

From a legal point of view, the initial RAW registration will allow:

• To assign the status of “accumulated waste” to the waste generated before

the Federal Law “On Radioactive Waste Management” has entered into

force

• To define the categories and types of storage facilities and of the

accumulated RAW according to the new Russian legal framework

(retrievable and special waste, the temporary and long-term storage, sites

of emplacement and sites of conservation of special waste).

Type of radioactive waste and of the category of radioactive waste storage

facility are crucial for planning of treatment of previously accumulated waste

in accordance with the requirements of the Article 24 of the Federal Law “On

Radioactive Waste Management.”

Initial Registration and Survey of RAW Storage Facilities

Survey

EBS Upgrade,

Additional

Barriers

On Site Disposal

Waste Retrieval

Treatment and

Conditioning

Interim Storage

Transportation

Disposal in Regional

Disposal Facility

Storage Facility

Special

RAW

Retrievable

RAW

Site of sRAW

Emplacement

Site of sRAW

Conservation

If meet safety requirements

15

Regulations of VLLW, LLW, ILW disposal

The criterions for classification of RAW are given in the

Decree №1069 from 19.10.2012 by the Government of the

Russian Federation

«On criteria for classifying solid, liquid or gaseous waste to

radioactive waste, criteria for classifying radioactive waste to

special and removable RAW and criteria for classification of

removable RAW».

Criteria for classifying radioactive waste to special and retrievable RAW

Special RAW

• The collective effective dose for the entire period

of the potential danger

• The risk of potential exposure

Retrievable RAW

RAW, including:

•RAW generated:

•in result of implementation of the state program of armaments and state defense order

•In result of the use of nuclear weapon for peaceful purposes

•In result of nuclear and (or) radiation accident in nuclear facility

•liquid RAW, accumulated in surface water-storage facilities, totaling more than 25000

m3, commissioned before the entry into force of the Federal Law "On the treatment of

waste ...", as well as the sediments of the storage reservoirs meet the following criteria:

• The cost of moving away,

processing, conditioning,

transportation to disposal facility

and disposal of radioactive waste

Moving away On site

disposal

• The size of the possible harm to the environment

• The cost of disposal of radioactive waste, including

conversion Site of sRAW to RAW disposal facility, its

operation and closing, its safety over the period of the

potential danger

RAW storage and its sanitary protection zone located outside the boundaries of settlements, protected areas, coastal protection

strips and water protection zones of water bodies, and other security protection zones

1

2

3

Other RAW that

hasn't been

assigned to

special RAW

>

> On

sit

e

dis

po

sal

Movi

ng a

wa

y

Decree №1069

17

Regulation of RAW Management in Russia

Predisposal RAW management.

General Safety Requirements

GSR, part 5

Disposal of radioactive wastes. Principles,

criteria and general safety requirements.

NP-055-04

Near-surface disposal of radioactive

waste. Safety requirements.

NP-069-06

Collection,

treatment,

storage and

conditioning od

Solid RAW.

Safety

Requirements.

NP-020-2000

Collection,

treatment,

storage and

conditioning od

Liquid RAW.

Safety

Requirements.

NP-019-2000

Gaseous RAW

Management.

Safety

Requirements.

NP-021-2000

Disposal of Radioactive Waste.

Special Safety Requirement

SSR-5

Near-surface disposal. Safety

Requirements

WS-R-1

Safety Fundamentals

SF-1 Safety of Radioactive Waste

Management. General Provisions

NP-058-04

RAW WAC for Disposal

NP-ХХ-ХХХ

12 ОJune, 2007 18

Participant list (as for 2012)

Alexander Smetnik, [email protected], Russia (TSO)

Nikolay Anisimov, [email protected], Russia (TSO)

Andrey Guskov, [email protected], Russia (TSO)

Valery Bochkarev, [email protected], Russia (TSO)

Alexey Tkachenko, [email protected], Russia (Operator)

Merle Lust, [email protected], Estonia (TSO)

Previous meeting – June 2012, IAEA

Working Group Objectives

19

to adopt the safety assessment methodology

presented in the GSG-3 The Safety Case and

Safety Assessment for the Predisposal

Management of Radioactive Waste (former DS284)

for the RADON type facility needs

to develop illustrative test cases for applying this

methodology to RADON type facility using

SAFRAN tool

to provide Member States with the supporting

information for decision making regarding the

future of existing historical RADON type facilities

Scope

20

Typical near surface RADON type long term

storage facility for solid institutional LILW

Waste retrieaval operations during facility

decommissioning

Input

21

Results of the SADRWMS project

SAFRAN tool

GSG-3 (DS284)

Information from existing reports on

Murmansk Facility (“RosRAO”) and similar

Radon-type facilities

Work Plan

22

By the end of 2012 (Working group meeting):

• Drafts of the documents prepared for discussion

in the working group:

• Preliminary results of the safety assessment

(Nikolay Anisimov)

• Historical overview for the Radon-type facilities

(Andrey Guskov)

• Draft interpretation of DS284 into Russian

language (all group participants)

Work Plan

23

By the end of 2012 (Working group meeting):

• Drafts of the documents prepared for discussion

in the working group:

• Preliminary results of the safety assessment

calculations (Nikolay Anisimov)

• Historical overview for the Radon-type facilities

(Andrey Guskov) – drafted in Russian

• Draft interpretation of DS284 into Russian

language (all group participants)

Work Plan

24

By the CRAFT Plenary meeting (June 2013):

• Draft version of the Safety Case

• Group proposals to improve the methodology

• Group proposals to improve the SAFRAN tool

• Starting version of the methodology for RADON

facilities (in Russian)

Work Plan

25

By the CRAFT Plenary meeting (June 2013):

• Draft version of the Safety Case -

Draft version of the Safety Assessment in Russian

• Group proposals to improve the methodology -

No proposals

• Group proposals to improve the SAFRAN tool

(to be reported and discussed during WG sessions)

• Starting version of the methodology for RADON

facilities (in Russian) - not started

Work Plan

26

By the end of 2013 (Working group meeting):

• Draft Working group report

• Draft methodology for the Radon-type facilities (in

Russian)

By the CRAFT Plenary meeting (June 2014)

• Discussed feedbacks from the other working groups

on the draft report

• Improved version of the Working group report

• Improved version of the methodology for the Radon-

type facilities

Proposed content of the report (as for 2012)

27

• Introduction (related CRAFT information and historical

overview)

• Safety case context

• Safety assessment

• Assessment methodology

• Object and activity description

• Overall description and data of the radioactive waste

in the storage facility.

• Waste inventory

• .

Proposed content of the report (as for 2012)

28

• Scenario generation and justification

• Principles and organization of the work (retrieval

operations).

• Overview of the technical means to be used for the

waste retrieval.

• Description of the waste retrieval stages (working

plan)

• Initiating events to be considered

• Normal operation scenarios

• Abnormal and accidental scenarios

• Assessment models

• Calculation results

• Analysis of the assessment results

• .

Proposed content of the report (as for 2012)

29

• Recommendations for improvement of the technological

rules for waste retrieval procedure and working plans.

• Assessment of the doses to workers based on the

corrected technological rules and working plan.

• Assessment of the discharges to the environment due to

the retrieval activity.

• Possible corrections for the working plan during retrieval

operations.

• Overall conclusions and recommendations from the

safety case.

• Recommendations and conclusions for the methodology

and SAFRAN improvements.

Context

30

The safety case will be developed as the project

progresses and will be used as a basis for

decision making relating to selection of the

decommissioning option.

The purpose of safety assessment to be

performed as the illustrative test case is to test

initial ideas of the waste retrieval and

improvement of technological rules for waste

retrieval procedure and/or decision making related

to the decommissioning options for historical

Radon-type facility

Context

31

Murmansk solid radioactive waste storage facility is

the typical near surface vault constructed from

reinforced concrete below the ground level and

divided into four cells of 200 m3 each.

Context

32

Context

33

Context

34

35

Context

36

Context

Wastes are not conditioned and in most cases are packed

Context

Legend Waste Number.

Б1 – Б10 Cylindrical metal containers 10

К1 – К10 Rectangular metal containers 10

ЯБ1 – ЯБ6 Concreted and partially damaged wooden boxes 6

Ф Box with air filters 1

Шары Blocks of gamma-ray sources ~ 40

- Unidentified objects 6

Vault No1

There are DSRSs in transport containers, few wooden boxes with

unknown cemented waste, packages with ion-exchange resins and

others.

Context

Rectangular metal containers Concreted and partially damaged wooden boxes

Blocks of gamma-ray sources BGI-75 Blocks of gamma-ray sources E-1M

Context

39

The inventory consists mostly from 226Ra, 152Eu, 137Cs, 60Co and 3H

and other radionuclides.

The nearest settlement is in the distances of about

10 km from the facility;

40

Context

Construction of temporary protecting building

Gates

Wells

Storage

vaults

Context

42

The assessment of the future management of

retrieved waste is not part of the current safety

assessment and safety case. This can be covered

by other relevant safety assessments addressing

the management steps for such waste, i.e. its

clearance, discharge, processing, storage, transport

and disposal

Context

43

The endpoint of the safety assessment will be the

doses for the workers as result of external

irradiation and inhalation both for normal and

accidental scenarios

For treating uncertainties in the safety assessment,

cautious assumptions will be used, but, in view of

the intervention situation, these should be as

realistic as possible;

Context

44

Timeframe for safety assessment for dose

calculation is the sum of time required all

considered technological operations. In terms of

possible accidents caused by external events the

timeframe cover all the period of waste retrieval

operations at the site

Safety assessment calculations are performed using

SAFRAN and other tools

Safety Assessment Report is drafted in Russian

This week working plan

45

Look back, discuss and agree on TOR

Discuss the safety assessment results

Discuss and agree on realistic group work plan

WG Report content

Developing other documents

46

Thank you for your attention