Safety Regulation andActivity of NSC for
Disposal of Radioactive Waste

Kunihisa Soda, Deputy Chair
Nuclear Safety Commission

The Nuclear Safety Research Forum (NSRF) 2010
February 23, 2010 At Toyo University, Tokyo, Japan

Contents
 Utilization of nuclear energy andradioactive waste Safety regulation for disposal ofradioactive waste
 Activity of Nuclear Safety Commission

 Safety research for disposal ofradioactive waste International coordination for nuclear
safetyNSRF2010/NSC(KS)2

Utilization of Nuclear Energy and Radioactive Waste
Sources and Characteristics of Radioactive Waste
Nuclear
Nuclear Reactor
Reactor Facilities
Facilities

U-Enrichment/
Fuel Fabrication

ResearchResearch Reactors/Reactors/
Facilities
Facilities using
using
Nuclear
Nuclear Fuel
Fuel materials
materials

Facilities
Facilities using
using
Radioisotopes
Radioisotopes

NuclearPower Plant
Note: Regulated by MEXT

Characteristics
Characteristics ofof Radioactive
Radioactive
Waste
Waste

MOX Fuel
MOX Fuel
Fabrication

 Various
Various physicalphysical statesstates¾¾ Gas,
Gas, Solid,Solid, Liquid
LiquidNuclear Fuel
Reprocessing
Note: Regulated by METI

Decommissioning
Decommissioning ofof Nuclear
Nuclear Facilities
FacilitiesNSRF2010/NSC(KS) WideWide range
range ofof radioactivity
radioactivity¾¾ Low
Low toto HighHigh levellevel Institutional
Institutional Control
Control¾¾ Short
Short toto LongLong lived
lived radioactivity
radioactivity
level
level
¾
¾ Step-wise
Step-wise approach,approach, Termination
Termination
oftheinstitutionalcontrolof the institutional control

Note:
Note: Waste
Waste below
below thethe clearance
clearance level
level isis notnottreatedtreated as
as radioactive
radioactive waste
waste byby thethe rule.
rule.

3

Utilization of Nuclear Energy and Radioactive Waste
Categorization of Waste and Disposal
Nuclear Facilities

Examples of Waste

Category of Waste by Levelof Radioactivity

Nuclear Power
Plant

Liquid waste, filters,
used equipment, otherused material
Control rods, coreinternals

LowLevelRadioactive
Waste

NPP Waste

Concrete, metal

Method ofDisposal

Very Low-level

Near-Surface（Trench）

Low-Level

Near-Surface（Pit）

Relatively
High-Level

Sub-Surface（１）Uranium Waste

Near-Surface(Trench, Pit),
Sub-Surface,
Geological（２）Waste including
TRU

Near-Surface (Pit),
Sub-Surface,
Geological

U-Enrichment/Fuel Fabrication
Plant

Used material, sludge,
used equipment

Reprocessing/
MOX FuelFabrication Plant

Parts of fuel elements,
filters, liquid waste

Reprocessing
Plant

Vitrified waste

High-Level Radioactive Waste

GeologicalAll Plants

Most of waste fromdecommission

Level below the Clearance
Level

Recycle, Dispose as
industrial waste

Regulation is enforced.
NSRF2010/NSC(KS)

Note: (1) 50 to 100m deep (2) 300m deep or more

4

Utilization of Nuclear Energy and Radioactive Waste
Basic Policy of Safety Regulations（Concept）
Consideration of radioactivity level, Rational and effective
management approach taking into account of risk, Long-term
safety strategy based on effect of physical barriers andisolation, decay of radioactivity etc.
Radioactivity Level
Very Low

Disposal
Near-Surface Disposal

Relatively Low

Trench（without engineeredbarrier), Concrete Pit

Relatively HighSub-Surface Disposal

Depth (m)0 (Surface）

50～100

Disposal at a depth with sufficientmargin for conventional
underground use (50 to 100m)
Extremely High

Geological Disposal

300 or more

Geological layer deeper
than 300m

NSRF2010/NSC(KS)5Safety Regulations for Disposal of Radioactive WasteActivity of Nuclear Safety Commission

Nuclear
Nuclear Safety
Safety Commission
Commission
Regulatory
Regulatory
BodiesBodies①① To
To Develop
Develop Basic
Basic Policy
Policy②② To
To Set
Set thethe Standard
Standard

PrivatePrivateEnterprises
Enterprises
forfor Disposal
Disposal（METI,（METI, MEXT）
MEXT）

Legislation
Legislation

Regulation

waste
waste
disposaldisposal③③ To
To Establish
Establish Safety
SafetyExamination
Examination Guides
GuidesThe
The PrioritizedPrioritized Safety
Safety Research
ResearchProgram
Program (Phase(Phase II）
II）

Research Organizations,
Universities etc.

Note: Atomic Energy Commission (AEC) has established the basic policy of radioactive waste
management in Japan based on the Basic Nuclear Policy of Japan.
NSRF2010/NSC(KS)6

Safety Regulations for Disposal of Radioactive Waste
Development of Basic Policy by NSC (1/4)
Generic Issues of Importance and Basic Guides for Safety
Review
1.
2.

Basic Guides for Safety Review of Radioactive Waste Burial Facilities, March1988, revised October 2009
Generic Issues of Importance for the Safety Regulation of Radioactive Waste
Disposal, Special Committee on Radioactive Waste and Decommissioning,
June, 2004.

Basic Policy for Safety Regulations et al.
Low-Level Radioactive Waste
1.

2.

Basic Policy of Safety Regulation for Land Disposal of Low-Level Solid
Radioactive Waste, Special Committee on Safety Regulation of Radioactive
Waste, NSC, October 1985.
Reference Values on Radionuclide Concentration for Safety Regulation ofLand Disposal of Low-Level Radioactive Solid Waste (3rd Report), SpecialCommittee on Safety Regulation of Radioactive Waste, NSC September

2000.

NSRF2010/NSC(KS)7

Safety Regulations for Disposal of Radioactive Waste
Development of Basic Policy by NSC (2/4)
Basic Policy for Safety Regulations et al.（continued）
Low-Level Radioactive Waste (continued)
3.
4.

Upper Bounds of Radioactive Concentration for Burial of Low-Level
Radioactive Solid Waste, NSC, May 2007.
Basic Policy for Safety Regulations Concerning Land Disposal of Low-Level
Radioactive Waste (Interim Report), NSC, July 2007

High-Level Radioactive Waste
1.

Basic Policy of Safety Regulation on High-Level Radioactive Waste Disposal(First Report), Special Committee on Safety Regulation of Radioactive Waste,
November 2000.

Waste from Research Reactors, Facilities using Radio Isotopeand others
1.

2.

Basic Policy of Safety Regulation for Near Surface Disposal of SolidRadioactive Waste Generated from Research Laboratories, etc., NSC, April
2006.
Basic Policy of Safety Regulation for Near Surface Disposal of Solid
Radioactive Waste Generated from Radio Isotope Utilization Facilities, etc.
NSC, January 2004.

NSRF2010/NSC(KS)8Safety Regulations for Disposal of Radioactive Waste
Development of Basic Policy by NSC (3/4)
 Decommissioning, Clearance Level
Decommissioning of Nuclear Reactor Facilities andfacilities using Nuclear Fuel Materials
1.
2.

Basic policy on regulatory system after the termination of nuclear
facility operation, Jan 2005.
Basic policy for securing safety for decommissioning nuclear
facilities, Dec 1985, rev. Aug 2001）

Clearance Level
1.

2.

Major Nuclear Facilities, Heavy Water Reactor, Fast Breeder
Reactor, Nuclear Fuel Utilization Facility, Uranium Treatment
Facility（1999.3-2009.10）
Radionuclide Concentrations for Materials not requiring Treatment
as Radioactive Wastes generated from Dismantling etc. of Reactor
Facilities and Nuclear Fuel Use Facilities, Special Committee onRadioactive Waste and Decommissioning, Dec 2004, rev. March2005.

NSRF2010/NSC(KS)9Safety Regulations for Disposal of Radioactive Waste
Development of Basic Policy by NSC (4/4)

 Current activity and future scope on development ofbasic policy for waste disposal, e.g.


Sub-Surface, Geological disposal
TRU, Uranium Waste, High-Level Radioactive Waste, Site
ReleaseRisk management approach (concept)

NSRF2010/NSC(KS)10Safety Regulations for Disposal of Radioactive Waste
Risk management approach (concept)

 Use of risk information for safety management of NPP

Basis of safety objectives and performance objectives
Consideration of residual risk (ref. the Seismic safetyguide)Taking into account of rare event with extremely lowprobability such as airplane crash Issues for risk management for radioactive waste
disposal (concept)
Confinement function of facility, Retardation of nuclide
migration, Effect of decay of radionuclide
Disposal at a depth sufficient to safety margin forconventional use of undergroundTermination after several hundred years of operation underactive institutional control
Treatment of uncertainties

NSRF2010/NSC(KS)11

Safety Regulations for Disposal of Radioactive Waste
Risk management approach (illustration of concept)

Probability of Occurrence (yr-1)

Note: Based on the presentation by Dr. A. Suzuki, Chair, NSC, 2007

(1)
(2)
(3)
(4)
(5)

(a) 50μSv/yr for reactor normal operations(b) 5mSv/yr for the reactor design basis events （DBE)(c) 250mSv/yr for the reactor site evaluation accident
1

Normal Operation

Abnormal Transient
(1)

10-1

10-2

DBE

ReactorRisk Limit(a)

Repository

(3)

10μSv

10-4
10-5
10-6

B

A: allowance forreactor safety
B: additional allowance
for repository safety
10-3

10-2

（BDBE）

A

(2)
10-3

Controllability
Engineering design life
Uncertainties
Safety requirements
Hypotheses

(b)
(4)
(5)

300μSv

(c)
10mSv

10-1

100

10100

Radiological Consequences (mSv)
NSRF2010/NSC(KS)12Safety Research for RW Disposal

Prioritized Safety Research: Key Area(*)
 Radioactive Waste High-Level radioactive waste Sub-Surface disposal waste among Low-Level
radioactive waste Long-lived/Low heat generating radioactive waste Uranium waste Decommissioning Processing, Disposal and reuse of waste resulting
form dismantling Radiation measurement technology( *)NSC, ”Prioritized Safety Research Program on the Nuclear Safety（Phase II）”,August, 2009

NSRF2010/NSC(KS)13

Safety Research for RW Disposal
Prioritized Safety Research: Topics(*)
 Geological Disposal

Investigation and evaluation methodology for sitecharacterization, engineering technologies for EBS, safetyassessment research for pre- and post-closure period

 Sub-Surface, Near-Surface Disposal

Investigation and evaluation methodologies for geologicalenvironment, engineering technologies, safety assessment,
evaluation of institutional control, long term safetyassessment, data to be obtained for safety assessment,
data-base development Decommissioning( *)Development of the standard for clearance R&D ofradioactivity measurement for clearance

NSC, ”Prioritized Safety Research Program on the Nuclear Safety（Phase II）”,
August, 2009

NSRF2010/NSC(KS)14

International Coordination for Nuclear Safety
International Organization & Safety Conventions
 International Organization
 IAEA¾ Basic Guides for Licensing Review, Peer Review
among the Contracting Parties, support etc.
 NEA
¾ CSNI、CNRA、RWMC、CRPPH etc.
 Regional Cooperation¾ FNCA、ASEAN+3、IAEA/ANSN etc.

 Safety Convention
 Convention on Nuclear Safety Joint Convention on the Safety of Spent FuelManagement and on the Safety of Radioactive Waste
Management
NSRF2010/NSC(KS)15

International Coordination for Nuclear Safety
International Organization & Safety Convention(*)
Objectives of JC
 To achieve and maintain a highlevel of safety
 To ensure effective defences
against potential hazards
 To prevent accidents withradiological consequences and to
mitigate their consequences

Contracting Parties
CPnon CP

Review meeting Mutual review among thecontracting parties
 General meeting of JC is held
every 3years (2003, 2006,2009)Entered into force in June 2001,
Contracting Parties : 25
Contracting Parties : 51 (in Feb. 2010)

Ref. IAEA(*) Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste
Management
NSRF2010/NSC(KS)16Over View of Policy and Practice on Spent Fuel Managementand Radio-active Waste Management in Japan (*)
Type ofLiability

Long-term
management
policyFunding

Current
practice /Facilities

PlannedFacilities

Spent fuelReprocessing

Utility pays
fund forreprocessing

Domestic
reprocessing
plantsInterim storage
facility

Nuclear fuelcycle waste

Geological,
intermediate
depth or nearsurface disposal

Utility pays
fund fordisposal ofwaste

HLW Storage
Facility / LLW
Disposal Facility

Geological,
intermediate
depth or nearsurface disposal
facilities

Non-power
waste

Geological,
intermediate
depth or nearsurface disposal

Underdiscussion

On site storage

Underdiscussion

Operators
pays into
reserve fundDecommissionin－g underway

Decommission- Immediate
decommissioning
ing liabilities
of NPP

Return to
Disused Sealed manufacture /UserSourceLong-term storage

Return to
manufactures /Storage insidefacilities－(*) National report of Japan for the 3rd review meeting of JC, Oct 2008
NSRF2010/NSC(KS)17International Coordination for Nuclear Safety
The 3rd Joint Convention (May 2009) Common Observation-Challenges (Third Review Meeting, May2009）






The implementation of national policies for the long-term
management of SF, including disposal of high level waste
and/or SF
Siting, construction and operation of SF and RW disposal
facilities
Management of legacy wastes
Monitoring of disused sealed sources and recovery oforphan sources
Knowledge management and human resources
Financial resources for liabilities.

 The Fourth Review Meeting is to be held in May 2012
Actions to increase the contracting partiesNSRF2010/NSC(KS)18NSRF2010：Program
Session 1 Status of Safety Regulation
International activities (IAEA etc.)
Safety regulation in Japan (NSC etc.)

Session 2 Current Technology and theRegulatory Safety Research for
Geological Disposal
Session 3 Regulatory Safety Research for
Sub-Surface and Near-Surface
Disposal
NSRF2010/NSC(KS)19Thank you for your attention

NSRF2010/NSC(KS)20