ML20245E689
| ML20245E689 | |
| Person / Time | |
|---|---|
| Issue date: | 06/15/1989 |
| From: | Boyle R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Bernero R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-WM-3 NUDOCS 8906270384 | |
| Download: ML20245E689 (55) | |
Text
~ . -
r i 9
~
g ,
. s JUN I 51989 RB/ BOOK 1,-
MEMORANDUM FOR: Robert M. Bernero, Director Office of Nuclear Material Safety and Safeguards FROM: Regis R. Boyle, Section Leader Regulatory Branch Division of Low-Level Waste Management and Decommissioning Office of Nuclear Material Safety j and Safeguards
SUBJECT:
TRIP REPORT ON IAEA MEETING ON TRANSBOUNDARY MOVEMENT OF RADI0 ACTIVE WASTES - MAY 22-26, 1989 i
The International Atomic Energy Agency (IAEA) convened the first meeting of a Technical Working Group of Experts to develop a " Code of Practice" for international transactions involving radioactive wastes. The meeting was held at the IAEA facilities in Vienna, Austria from May 22 to May 26,1989. It was attended by experts from 18 Member States and observers from one Member State
- and three international organizations. A list of attendees ic attached l (Enclosure 1).
The U.S. participants at the meeting were: Fred McGoldrick, U.S. Mission Counsellor; Barbara Thomas, DOE; Joanna Becker, NRC/0GC; Mary Peterson, NRC/GPA and Regis Boyle, NRC/NMSS. Mr. McGoldrick represented the U.S. at all sessions of the meeting except for a technical session on Wednesday, May 24, that addressed the definition of radioactive waste. The U.S. representative at that session was Regis Boyle.
In its staff requirements memorandum dated April 13, 1989, the Commission directed the NRC staff to actively participate in the IAEA meeting. The Commission indicated that the staff should prepare a detailed report on (1) the results of the meeting; (2) the progress towards an international policy; (3) ro p(4) posed plans for future staff activities regarding this subject; andany additional c contained in SECY-89-063. This trip report contains information requested by the Commission.
Dr. Hans Blix, Director General of IAEA, provided opening remarks to the i Working Group. Dr. Blix indicated that IAEA is unaware of any illicit dumping of radioactive wastes and that the likelihood of it occurring is extremely small. Nevertheless, Dr. Blix endorsed the concept of developing a " Code of Practice" for international radioactive waste transactions, because radioactive wastes were excluded from the scope of the Basel Convention on the control of transboundary movements of hazardous wastes and their disposal. He indicated that the purpose of this first meeting would be limited to providing comments to 8906270384 890615 3 FDC s Mb b@l _ _ _ b
1 -1 9
g ,
e t RB/ BOOK the IAEA Secretariat for the preparation of a subsequent draft " Code of Practice" that would be considered at a follow-up meeting to be held in early 1990.
Objectives of the Working Group Mr. M. El Baradei, Director of the. Legal Division of IAEA, provided initial guidance to the Working Group. He described the difference between a
" Code of Practice" and a " Convention". A " Code of Practice" is not binding on countries and not as detailed as a " Convention", but it generally includes all of the pertinent elements. Existing international and national laws and regulations should be used in developing a " Code of Practice".
Mr. El Baradei set forth the objectives of the Working Group. The objectives were to:
(1) discuss the basic principles which could be included in a " Code of Practice'_' for international transactions involving radioactive wastes; (2) define what wastes should be subject to the " Code of Practice";
(3) examine current national and international laws and regulations on waste disposal in the context of the Working Group's task-l (4) advise the IAEA Secretariat on the preparation of a working document on a draft " Code of Practice" for consideration at the next meeting of the Working Group.
Issues Prior to the May 22-26, 1989 meeting, the IAEA Secretariat drafted " Elements i for Consideration" in a " Code of Practice" on International Radioactive Waste Transactions (Enclosure 2) and a technical background paper entitled " Technical Paper in Support of the Code of Practice on Transboundary Movements of Radioactive Wastes" (Enclosure 3). The draft " Elements for Consideration" was the principal document considered by the Working Group at the meeting.
Each of the 13 elements of the " Code of Practice" were discussed in detail.
Some members of the Working Group suggested that additional elements be added. Based on the connents received, the IAEA Secretariat intends to develop new elements and submit them to the members of the Working Group for their review and comment at a later date. Some of the more significant issues raised by the Working Group at the meeting concerning the " Elements for Consideration" were the following. -
- 1. Regulatory Responsibilities. There was general agreement that each country should oe responsible for determining the adequacy of its own waste management technology and disposal sites. That is, if a country
g- .t ;
. 1 RB/ BOOK .l l
i 4
accepts radioactive waste for disposal, it is the responsibility of 'I the receiving country to judge the adequacy of. its disposal system.
However, some members of the Working Group expressed an interest in i receiving technical support from developed countries to. develop a i regulatory program to assure that waste disposal does not result in adverse effects on public health and safety.
- 2. - Separate trans) ort and disposal requirements. The Working !
Group agreed taat regulatory requirements for the transport of radioactive waste are not necessarily applicable to the disposal of ;
that waste. For example, for purposes of transportation, radioactive :l material is aefined as any material for which the specific activity is greater than 0.002uCi/g. While this may be acceptable for transport, the-same standards might not apply for the disposal of that material.. l
- 3. Definition of Radioactive Waste. The Working Group agreed'to use the existing definition of radioactive waste as contained,in the
" Radioactive Waste Management Glossary" (IAEA-TECDOC-447).
Radioactive waste is defined as "any material that contains or:is.
contaminated with radionuclides at concentrations or radioactivity' levels greater than the ' exempt quantities' established b competent authorities and f or which no use is foreseen" .(y the emphasis added). The two critical parts of this definition are the " exempt quantities" and "no use is foreseen" phrases. The Working Group was in general agreement that the phrase "for which no use is foreseen" is ;
appropriate and r.ecessary for the definition to be meaningful for !
transboundary movement of waste and ultimately their disposal. The
" exempt quantities" phrase was not clearly resolved at the meeting.
Unanswered questions were (1) who is the competent authority to make an exempt quantity determ' nation (i.e., the exporting or importing authority); (2) how is a level for exempt quantities established; and (3) how does one treat differing " exempt quantities" established by various countries' competent authorities. There was a general consensus that a specific numerical standard should not be established by this Working Group for transboundary movement of radioactive wastes.
4 Liability and Compensation. There was considerable discussion on-We issue of liability. Some members of the Working Group (most notably the Egyptian representative) felt that the exporting country l should be held financially liable for any damages that might result j- from the transboundary movement of radioactive wastes and their j disposal. Other members of the Working Group Lelieved that the country receiving the wastes and disposing of them should be 1
i
I +
r o
~
,.. g I
~RB/ BOOK responsible .for assuring that no adverse impacts result from.their i disposal. The Working Group was unable to agree'if the element on liability should remain in the'" Code of Prr *lce" or be deleted.
L 5. Notification and Consent. The " Code of Practice" reviewed by the. !
Working Group-is essentially a " notification and consent" process.
(See Element #5 of the " Code of Practice"). However, the.. Code does not preclude the establishment of more restrictive measures on-radioactive waste shipments by individual countries. The Code-(see i Element #4) mentions the.right of each country.to-ban imports of.
j radioactive wastes if it desires to do so.
l
- 6. Right of innocent passage. There was considerable discus u .. on the right of innocent passage of radioactive wastes over. waterways L versus the rights of transit countries. The debate on rights of innocent passage. expressly addressed transit of radioactive wastes l through the Suez Canal.
I 7. Readmission of wastes for failed transactions. Some representatives l at the meeting expressed the view that the, government of the j l exporting country should be held responsible for the radioactive i
! waste if the transaction should' fail for'any reason.- The.U.S. .
i representative, with support from the U.K representative,-indicated i l
that the government should not necessarily be held responsible for a failed trans6ction because many of these transactions could involve private corporations who should be held responsible for any .l failed transaction, rather than the government.
Schedule q 1
Most of the above issues were not. resolved at the May 22-26 meeting. It is the intent of the IAEA Secretariat to take the comments received from the 3 Working Group at'the May 22-26 meeting and re-draft the " Elements for Consideration". Sometime prior to the next meeting, a draft " Code of-Practice" will be distributed by the IAEA Secretariat to the Working Group for !
their review and comment. The next meeting of the Working Group;is. tentatively i l scheduled for January 29- to February 2,1990. This schedule would permit a j l- final " Code"of Practice" to be completed in~ time for the September, 1990, ;
i 1AEA's General Conference. :
l i Recommendations l Based on the' May ?2-26 meeting and the draft ." Elements for Consideration" discussed at the meeting,.thelfollowing actions ~are recommended:
l
- 1) The NRC staff should proceed directly to a proposed rule that would . l amend the existing regulations on import and export of radioactive i I l l
4 s Rd/800K
- Distribution: NMSS # 8900146 % ..aoi-File # NMSS r/f LLR8 r/f LLRB t/f RBoyle, LLRB JAustin, LLRB MBell, LLWM JGreeves, LLWM ,
ED0 Directors r/f RCunningham, IMNS JBecker, OGC MPeterson, GPA Security BFMcGoldrick, US Mission GPA JDeThomas, State Dept BThomas, DOE CJenkins, NMSS LLWM ticket file JGorn wastes to require a notification and consent procedure. Comments on the other three options presented SECY-89-063 could be solicited when the public has the opportunity to comment on the proposed rule, This recommendation would eliminate the need for an Advance Notice of Proposed Rulemaking as called for in the Staff Requirements Memorandum dated April 13, 1989.
- 2) The staff should continue to participate in the development of the ,
IAEA " Code of Practice". This would permit the staff to (1) be I
fully aware of the development of international standards on this matter; (2) become familiar with the laws and regulations of other j countries on the import end export of wastes; and (3) keep abreast '
of any international transactions or incidents relating to i radioactive waste disposal if they should occur. l Coordination This trip report was coordinated with M. Peterson, GPA and has his concurrence.
Joanna Becker, 0GC, has not had the opportunity to review this report because she has been on official travel and annual leave. I will provide her with a copy when she returns on June 26, 1989.
ORIGINALSIGNED BY Regis R. Boyle, Section Leader Regulatory Branch Division of Low-Level Waste Management and Decommissioning Office of Nuclear Material Safety and Safeguards
Enclosures:
As stated cc: M. Peterson, GPA W. Parler, 0GC PDR Yes /K/ No / / Proprietary or CF Only / /
ACNW Yes /'/ No /%/ T3 c/379 SUBJECT ABSTRACT: IAEA TRIP REPORT IN RESPONSE TO SRM; NMSS #8900146 l
l uM OFC :LLR :LL :GPA :LLg :LLW :
pg .....h .,........................
NAME:RBoyle/es :JA tin :MPe erson:MIie71 :JG eyes :
DATE p /89 / > /h9 //'b9 )8 // 8 OfflCIAL RECORD COPY
- g. 8 i
% B h d
l l
1 I
ENCLOSURE 1 I
- 1 i
e 9
m___________
R
$ E 4 P
. E t H y 22 x T a 2 e .
M o'.
N5
,20 m. )
R O 2 0
36 a 6 F 2 62 5 e - 7 0 3 u9 2 .
s8 0 1 s9
- A t : 5 I 1 s x 0 6 t r ,e 1 2 x eh 1 e cc ,
i s5 : . ,
f t 7 g t g f i6 n an S O w2 i ei S oA t E ek e ,te R l n , e : ne D l b a e M yam D d i JD s g rm A n n . . ad g a n t on Y W oOP p
i e oi R n rG r A l s . . e c u R e e s r p e .d O t .
RMM o SJ( P o M H E
T S
T a N c A 1 i P 5 m I
C 3 6 1 t I
T S A s E R n A
S a P o .
S f i t E g F
t x R r O
c e D S e 1 a D S n a 1 s ,
A E E n T
S n V R n 0i n/
I a D o 1 e5 t o4 I
L er m D i / d2 n i -
cT o A s 2 8 e s s2 i
o i e l g s L
t e ct R G
'M ss arr i e A N noA M s as e I od s N r a c L t aa i a ,
O PW n n gn t a a e
I e d n ct s n r n I
S f r r A
H n ee ar e et n I oa e a ii N er n s e bi aii V e f L m mV niA ml V O el n A r h 6L rl R
y d c o I e cD i s ee0 P ou C C P s- s .o Pi4 t CN I d- i an e , F o l3 t 0 f al s / o . md e ot 1 a a r F
O c C3 ovu CAB
/ a -
S nn e cMA d
oo 9 t i 8 r n pt 9 a a e ua 1 u n yc l
on q r r y d o gy Ge a a i
rC t M e t e t n H S i a nl rI 6 E n r E e e 2 A i u pr T t
s rF x o
- E A v n i a Ef 2 A T a o 2 I S F e s n er d i l a R z i
r m c e : :
ES el a r d ul g e A H c n v DB N nac a n n u i NMO ini H o f o f N i
AEI t om yi t s MT ri6 .rs oi o e u S A act L as s f e t i t o M l
TGZ M N aA t i nv c NNI k eM n n AI N A e a r r ei e n f N A mD mo o i
PTA I gni I act t t i I AG r6 g L M en rl r s e CNR R o1 r A S e aa s e I GO I J s e R . n ai l e c TI E pg pv t a G i n T Gt a ee ei t
a RSD .mE S sm DL DD i
T D l
P AEN R ro U . rr PDA A DC A ri e MFP l
li ,l ,)
~
- ~
~
y a . .
D M O
I 8 R 2 E
P -
E y H a _
T M R 2 O 2 F
l e
t S o S H E
R f D o D h A s Y m R e A h l
R i
~ O W P
M E
T s n
o i
t a
i
- d S a E r 7 S t 6 S s e 9 n E e 4 o R l e 0 9 D u t 1 s i D e q a 2 5 t c
A r i t l E t
d p e n b X r i t
o u A a k o S c l F o r 2 S P P E e7 m ,
B a
- R n 6 d2 ub d n D o t l a o aa c D i n e3 gt i
o n 6 n -
A t a v/l s r a9 8 i im c S t C1 t hp a e i2 ei n 0 a Ci G t 6 5 n0 N t o l a ae Bd a C o
o
,11 75 i
d ,h c o4 I
r rl ,R a i i L t t as i579 R x5 se I P senssl , y6 r939 g4 a9 - n9 ssa A et edeiee6 r0t f0 a0 isn d neni mnV s9s3 M 3) o 2 h2 Man e1 n)53 n 1 S1 ge aromru5 E x O301 L e 1 t f i A es&rd er6 ,1 6 t x , noV I
C citiAiB i nsv t x c Bo aw (6 :
( uon tB a:
eh nl 0 I
voin6r0e i x ux F
F rinE e i t a1l iu0 e m.a: tllX e: i t .ye ae3 mm1 O S M '1 C Q 1 T to O. t eeA s O.ae n il rm1 ei -
APOt tF IPTT PHA e
e l rs c t e y z S nt C n e E on o n T. ca li et i _
_ r s t -
T ni ua n r S on Fl e a _
io u M R e ti f g i ES D BN r
e c
es oeR t a n l l i a N M0 t n e m n A E1 c e
oo eas h rl i d
a z yo MT ri x R uri S A L Pt t ea g Gas T GZ a yni N Nl t ei mer n f n oei t s A I H r dd SGe M i ooi d rM P TA er a t nc I AG C NR M
U b eer oec
.ra aot r er t. aet nS n l
I GO I R nis A D
D. tom Msue r e T I G Wcd stt R SD L .ive grl A N
en A N .eio ed n F na A EN PDA E
B rne MES A .ra ri I ff t r oosP A B
om C MD H rrn .cr C PPI U C
ree MSP lllI[l !';l1 ;ll!
H a T M R 2 O 2 F
e r
e d
S e
S l v
E e R B D
D l l n A a a a r r m Y i i l R m l A m R
d d u A A P O
P l l l M e e e E t t t T o o o H H H S
E S
S E
R D
D A
n S o S i E n t R n a D o o r 2
4 i i 6 D s s d5
- A n2 n d1 8 o o i s5 s 6 2 3 G i e i i F x s s s M M N s s a - - e e 6
- I ia n i t s a t ad 5 L Mgn ns n n l e I M e a n - c 0 A r e ngc e e 4 M t ei t n d s /
nt V n a ri a e s e meV m i 1 L
n u0 n r y r er A ar9 a e e0 e ua 3 I
mb1 m P m9 P rP 3 C r m1 r l 1
. e I 32 c F er -
PAA P e ol 1
/a - /
o A.3 5 n:
F O cCA c E./957real C27FT .
y
_ t l i
. l a r l n o A o h s i t S ut u e C E oa A r i
_ T b n i L A A r d i
s a B T e . f U S rt t e t f P
_ k anp i n yuA E a a a R r ,
cd n wI e R
_ n a n S nl r
_ ES j o s o n ,D aP
_ DBN ayi i yi A l m ed s C
- NMO A K rs C rs r s E rr N ge I AEI I as as d on e i e rd T
_ MT K vt i rt i et oc i aw ea A
_ S A A aeM i eM ycii mh o dht R TGZ V l r - mr - a er f hCP C ns C NNI O sct i ct S r af a - d . ee r ,mu O AI N L oe n d en i zO F er M
_ PTA S rS e . Di .va areq E I AG aS e r nut i D CNR O i n l n n n yi e rerd H Md a Vd a D ya g l t l
_ E et ai N I GO TI C E .i r rm .i r rm T P
t gi o
. pOurri er A uc cu C B cpr A RSD Z Y N e6 u M AEN rh e rh e G E. e . eN A . rDJ oa
- R PDA C MTP MTP E HD r x R ri E FC DE F MD G
P 2 2 3
- 2 3 E - 2 H y y -
T a -
a y R M M y O a F 2 2 M a 2 2 M 2
2 2 2
e k
c u5 r7 b2 r0 S e7 S n3 E a2 9 R B r e - 2 g 1 D ,
6 4 D s43 a5 h A s1 8 K9 h8 a 7 c1 c Y G 5 2
a a r1 0 t 5 t R o3 u31 t A t N4 Z21 t 0 e A5 A R
O r . l m l P a g: e: o l e
' M E
T zdl al e LBT t l o oeR HT e:
t l oe t
o HT H S
E S
S E
R e y D r c D t n A n e e g C A a
- S i S h y s 4 E c g e R r a r m n D a i n o e
h e h o i n1 n D d n k d s o2 o A s n E o n i i e I 7 R yI s s e s R i 6 G 1 c b M2 s s s N ,0 i l K , i s i I c 51 m u 0 t ea M ar M L i 87 o d51 I m 01 t b87 n s n t t a t A o 01 A A e s n a e n sn n M t 00 s1 2 n e r n e a gi L
A y
4 l a)
. o msV n aii e e n a
A A l
ay:
ib ax nN H. P ta r e e nO mnV m I
oAKk r P nl ri r C B ub e i T aa a0 et 0 e I A oml t A .t k oh1 P n4 P F H r oe aB1 oa e0 F BTBT /o - o g1 o O N(JKJ cJA /r - /
cAA c e
r t
n I s e e c S t C t ni E n e s A os T e h ot d u a T iy A m e
c r
jsy or W S sh T d at mo - i P S g a rWi e ,
v a e i l hl v u i i h R n s d ei al ei a r Dt ES a e ovc Me st e i l
_ DB N M R s ocer g l a a nia an NMO r e c ot F z u racu a oe AEI R c r o i oiB t rrH MT mt i ag Hif aet S A us m oon eC df y K gnf TGZ K a n o t ii H i aOg aoo NNI W ot A od s c hR r i nC ri AI N . iA I r as c ,tnne h a t
. PTA I AG S. oiA f s S E
eR e o c of ri i
k r eE o sMnn oe CNR A I
M vH N S ,o ut S n nom rl i m)
I GO .diB O r Q e et ec i at t I TI D aD A D .daP A N K c gi HrarR RSD N r e MH H N re R
.i r c A P .rnoeam eiaE AEN I B I MH I MS A
. nd pA PDA ri at r eae J MDMA M G R D (J
!l llll li
' Ib g
, .- y s
D a y O M a y I
R 3 M a E 2 8 M
P 2
- 6 E 2 H y -
T a y -
M a y R
O 2 M a F 2 2 M
2 2 2
1 9
e S s S s E a R r D e n t
D h S A h c a0 n Y a b0 e t d3 R t r1 l
A A o1 h
R N2 u
O l m P e l f
M t e: f E o i tl T H oe h HT c
S a
i r
t S s E u o S nf d s S 6 n i E i I p R c D a g
e .
D r A i s e t a 3 s n - o S e ,i 2 S v M 0 c 8 6i
- E n n 1 x 1 5 D R o I a
e e i
e .M E ns D s i o M
- A s d g)N , A os i a i rP . I G M l eI U sr N
r a nMez F. 3 D st eo EEuD1 I
t 6 iS L n S q 9 / M -
I e nl e( r ,16 1 a l
A n eld so95 t r a M a Go lMc 7 / n 1 n nan m raa i37 2 e eK n e L r nrit ox51 i n
A e 6 arac 6 a gi I
P icet s si at sM5 eV moV C :
l i0 rz I
o cD eec0 x e9 e r0 F l e ran4 : e P e2 F rycra1ll z1 h2 O
c i f1 oz1 D ear 6 ee o- /r -
SPF0TT HA cEA n
oe i d sa e i r e
_ vT t
- S i o t a u E Dl l g t
- T a l e i A yn o l t
T ro al r e s S t i ne r D n a st ud L
ea d s B I R t ua uOt r
D BN ES b
a d n nr oo la De gG n AS e vum N MO i I e jt ec ry m oi A EI h r t .rn sd MT S oyn l e e t a l s nn or eR S
T GZ A )
t i cr t gI y aire 6 C. t e n N NI k eef r VD aG1 Ncv zn'
'n e eo ui A I N P TA o ar not uiE .s e ,l grc6 g n ac nrG oi K p I AG c sD yu reui i sD n od a
C NR ( A n .l
- I GO T I N t
ayat n Kt esI rrd O C
oeN ct Jn c s I R
eri a h r V. K g R SD I B er Y n A EN A
P .ul pcnd i
X .iae ger v e" E C
me
. r g R .i PDA A r euin E rnrin I S n M MEADI roi S r. C. e J MDNMa N DFN U MVL
E P
E H
T R
O F
k t t r n n S a e e S s p m m E e t e e R m r d t t D a e a r8 r D J n t a a A e S pe p
. i ps p Y t W m A s A R S a a A n ng n R l o n or o O e i o i e i P t s t sm s M o n l ne n E H e i ei e T P H PR P S
E S
S E n R o D i D t A u l
- l 6 S o S P d
E n
- R a D
f l n 1 n n n n D
o g o/ o o o o A e n i 1 i i i i tE s 1 s s s s G
t a
e s e s s s s N r eY i i i i i I rP M ss M M M M L o t3 I
t eS t aa t t t t A c e
s P n rgnn n n n n M umI e e e e e pP 6 oaW n eeni a n n n n L sI 1 HhS a a a a A nM5 s miV m r m m m I IH A y r n r e r r r C ./ mnMdeao et 0 e e e e I P s9 P P P P S om n r1 F
F M.Aoo3 4 o o e1 o o o l
l LRR4L / b - / / o O / /
COA c c c c l n n n eo o o si i , i S ns s l s E us s a s T ,
k oi i i i A c Cm l m rs m T i r m na m S ra l o s s on o ed m d e ~
aC ry t r o l l ~ r a s o C aaC R w. i g ri M u E S oc ey o ar y DB N n
G u cN rnr eeo h f e et t a r rer gy NMO T f n en o af o AE M a M kGt MT I
e c r c a . ,AE P r e
t a
eeat D n S k o e el H sl f l l S a S A G E . t l yc l TGZ u T cf Bh u ma o R n u o ud u NNI N D i t g aan g BN ng AI N I A rr a e rr ot n I
s e PTA K . T eo nf R a gi n a e S dl y no if mR sf R I AG CNR D C. el c a r b ot e voa i oy E A D rei oea r r a m r r r g t r I GO E F sl aP nt a ega e eea TI T J ce B r r RSD AEN I
N U
r D
. T I
N
.no r o uP .f sf u il c
A ea
.E t p M co e irl
.f P c R cf e i al
.f S c PDA U MC sA ne rf u rf u MON MI I D MO N MO N I
1J g -
1
. . D -
O -
I R -
E P
E H
T -
R O
'F 1
S 1 e S / f s E 4 a os R / n h a D 5 n r g D 1 e eg A i sr Y eV i e z
l ab R l 0 K n A e9 e R r1 l k O f1 en P o - t a M or E
T HA HF _
e #
eu uq qi . s _
i m t e S mo ot n i E e t S t A m i S A n n E e oy u 7
R D
D A
ei ig gr re en nE rt i e vf na ES C
m m
o _
n S ga E 'l er a S
E n e
'l a' h a t e e
p m u
R n l o i D l a a o rc r g D l i 4 ou u l A Kl a s1 fN E e ar e s 9G B are8 r i e G y&2R ei N wen 6i ne8 a Mss r t n6 F h o ,
I ueG Z taa tLs L so02 l I lG a tl ,
e n rn ii f ae A MeaaI et e nS n nt2 n ol s M ritX i ia1 n s .
a 'l v o neu rmem0rV L .i rs rxB odr A f aaoa l eo i B ossP s e asB0 se I
C rss a Pa2 rn 0 su9 I Pii eh r2 eo 3 i r4 F _mmt s og1 m 0 F o
/mmin /a - de C O. 5- m01 O cCCBK oooi CWA F PD o0 -
C2B e
l Y n c ,
N o ye S A i C c E M et n T R ha l et E t v ein A e G r S uce T d rey E S F ost I FS m p t O R n f ne T &l o ES en C of I al D BN mo yC a EN er e ke r HU I
N MO A EI aei bt t L t ,S T6 9 iosne nt ev B l S
S MT mrc aae U eina st r N F0 0 kiaeD ssWG A Tpt P i nee O OC vi -
T GZ N NI iDr eo S R
S E
E R
M Mnc iml I T NN ovee&
li vt h A I N .
ou A OA rDiac p E P TA I AG d
nuo V I
R L
A G. l rN Z IE SP O t rr H ai .foatcoa I
C NR odi R T R N SO I GO E K d E N E rvd e R enn A IR S ocs T I R SD I .feR a S B
U O
D E r.dE e a G R
t 9 U E .di adrR ee A EN A rh O C F MF O 0
0 PDA Z MC reai C MHRD f ,
I Il! jlJ e yy n r r D u d a
- O J t t I ee R 2 rr E cc P - ee SS y
E a cc H M ii T f f R 2 ii 2 t t O nn F ee ii cc sS a
S n i
S
^
t E s R i D r D h A C Y n R o h A i c R s s O n t P e i M
E P w o ~
T k n
ae JD i
t s
e OP
~ -
S E
S i
n MM sr - -
u -
S m E m ~
R o D C D
A n -
a
- e -
S p 8 S o d rt E r n an
- R u a A ee -
D E l E l m D
A ys t g nn eE t
ee h c N
/
N ce ug N a h o m, cn n G
N I
L tL s f ae ol s l
k nR aS ua S r 0 F 68-E A
nom o
f a b7 d i ne I
A s m r ,66 - 6 sot M
neu E1 as 90 ii s od r E vi 3 vsa i
B I
L A
se su9 tS r
en er46 l a2 uP 5 iiW D v i -
C i r4 n bo o : l D 0 ld b6 x a e I
F n01 i
OAn O D 1 : e g ,l F
o0 - M o M C ,0 ll ed c C2B I4L E85 ee L ay O I O37 TT eC
,H -
r l -
one -
t ou -
- n ciF o et nn n r c' oo o i T i e ri i s N DS S it s i CE E rvc i v I M T one E v i MP A
T tEt a o M
I n
onD i
r o
D DR NI s -
S rl r T d o t s OE r -
t aP y I ) nit c n CV si -
R sr t R O ot n ee o EE ra ES iere A M I ne rcdi D ef .
DBN nnef M I em ii nt R nf NMO iema ( evn iDf aa O&
F yA AEI G uS L hno l f l e MT - s A N e t or r yO s e N Rl S A ) enr N O k Ci et rR NO a
- TGZ t t oa O I u r v mul i mpaal OI I T kg NNI AI N 'n ar aC e I T a ogn i e gl a TA ce -
l T A N f nE AR iL -
P TA o Po , c A Z i ZD ef n r I AG c k tt u N I . ,epe LA r S F. tf i C NR ( cnN R N Mf cmn . r - e I P ao e I GO nee E A eiui C o ,l t NO P d T I C k rm& T G .ifDr id ux A- a R SD E ri N R rhf a .nagE GO .da re A EN C D O MCO reee RC re _
M I ar PDA MSHL O MM Bi l a j ; l {l'lb ES
i i
.i G j.
a I
5 0 e . .I 1
l 1
1 l
i j
)
i i
i 1
I a
e l
l ENCLOSURE 2 l l
I i
1 1
l l
l
. i 1
Code of Practice on -
International Radioactive Waste Transactions ;
1 i
Elements for Consideration by the Group of Experts I l
i l
- 1. Each country engaged in nuclear energy activities is itself i responsible for ensuring the nuclear and. radioactive safety, physical security and environmental compatibility of its nuclear facilities and activities.
- 2. The foreseeable growth in the generation of electrical energy by nuclear means and the increased utilization of isotopes in industry, agriculture, medicine and research during the coming decade will involve corresponding generation of wastes. Every effort should be made to minimize such generation of waste and to reduce its volume.
3.
Countries should ensure that radioactive wastes under their jurisdiction are managed.and disposed of in such a way as to protect !
human health and the environment. I 4.
It is the sovereign right of every State to regulate the' import to its territory of any radioactive wastes; this may include imposition of a ban on such imports .
i
. 3.. .
9 B g
')s
- 5. All international radioactive waste transactions should take place ' with the express consent of the- exporting, importing . and transit country, in accordance with their laws and regulations,' and
{
in conformity with acceptable safety standards. Definitions of )
terms and classifications of radioactive vastert should be agreed' upon. Appropriate mechanisms and procedures including a focal point
]
should also be established for this purpose. 4
- 6. No radioactive wastes should be exported to any country _that
' lacks. the technical and/or administrative capacity to safely manage !
and dispose of such wastes.
- l
- 7. Wastes that are to be the subject of a transboundary movement should be packaged, labelled, and transported in conformity with generally accepted international rules and standards in the field of packaging, labelling, and transport.
i
- 8. Countries should co-ope ra te in the control of all radioactive wastes that are subject to transboundary movements from the place of generation to the place of disposal.
1
- 9. Countries should co-operate, notably with developing countries, to improve and achieve environmentally safe management and disposal of radioactive wastes. Such co-operation should include exchange of information on institutional structures, laws and . regulations, as well as technology transfer.
t , ..
,4 4- I i
+
j
- 10. Countries should co-operate and' take the necessary measures to suppress illicit transfer and disposal of radioactive wastes. ;
- 11. The exporting country-should readmit any shipment of radioactive wastes illicitly exported, or where the transaction could no t . ' be completed for any reason.
)
i
- 12. Appropriate rules and procedures should be adopted in the field of liability and compensation for damage resulting from the.
transboundary movement of radioactive wastes.
- 13. The IAEA shall give priority consideration to requests by developing countries for technical assistance in' the field of nuclear waste management.
_ _ - _ _ - _ . - ._ . - _ _ - . _ - . = - _ _ _ - _ _ .
- t. 4
' B 4
' n ENCLOSURE 3 I
I 1
]
If 2802y 1929y e
TE3ENICAL PAPER In SUPPORT W TEE. CX3DE N PRACTICE CBI I TRANSBOUNDARY SEIP95ItFS w
RADIOACTIVE WASTES -
i
)
l unste management sectice Division of nuclear Fuel Cycle International Atomic Energy Agency April 1989 O
. ., .i n
Technical Paper in support of the Code of Practice on Transboundary Shipments,of Radioactive Waste Foreword The issue of transboundary shipment of radioactive wastes, principally for the purpose of disposal, has attracted public concern in the recent past, following various reports of Illicit exports and dumping of toxic and hazardous wastes in developing countries. The subject was discussed at the 32nd Session of the IAEA General Conference in 1988 and, by consensus, a resolution (GC/XXXII/RES/490) was adopted to develop an internationally agreed
" code of practice" for international transactions involving radioactive wastes. As a follow-up to this resolution, a meeting is planned for 22-26 May 1989 of a " representative technical working group of experts to elaborate the code of practice".
The objective of this Technical Paper is to provide the meeting participants with some " background" information of a scientific, technical and regulatory nature on relevant issues in Member States, and the principles, guidelines and provisions for safe management of radioactive waste. The Technical Paper is, therefore, not intended to be a part of the Code of Practice.
I l
4 1
. i
- '
- Technical Paper 19 support of
. . Code of Practice on Transboundary Shipments of Radioactive Westes Table of Contents
- 1. Introduction
- 2. Some aspects of Radioactive Wastes 2.1 Types 2.2 Sources 2.3 Generation rates
- 3. Disposal options for radioactive wastes
- 4. International standards and procedures for radioactive waste disposal 4.1 International guidance on safe handling and disposal 4.2 Agency's future plans S. Aress of potential future international'co-operation in radioactive waste management
- 6. Overview of Agency assistance to Member States related to radioactive waste management 6.1 WAMAP service 6.2 Management and control of radiation sources 6.3 WATRP service 6.4 WPSF service
- 7. Issues associated with transboundary shipments of radioactive wastes
7.1 Background
7.2 Elements of the waste management system 7.3 Technical issues l 7.3.1 Issues associated with notifications and approvals to l transport waste for disposal ;
7.3.2 Issues associated with the safe transport and handling of the j waste 7.3.3 Issues associated with the safe disposal of the waste 7.3.4 Issues associated with long-term surveillance of the disposal facility i
References Appendix At Relevant IAEA publications on management of radioactive wastes Appendix B Glossary of radioactive waste management terms
. , i e
59k9y 1989-04-13 1_
- 1. INTRODUCTION In common with other industrial activities, the generation of electricity by nuclear fission produces waste products,. Wastes are also produced from the application of radionuclides in medicine, research, induistry and other institutional uses. Wastes that contain radioactive material are termed radioactive wastes. Very many countries produce some amount of radioactive wastes.
The primary objective of radioactive waste management and disposal is the effective protection of man and his environment, now and in the future, from the radiological hazard of nuclear waste material. This objective is achieved through the planning and implementation of national radioactive waste management programmes which follow a systematic integrated approach to the management of radioactive wastes, including steps:
o to minimize the amount of radioactive waste generated; o to treat the wastes generated so as to reduce the volumes; o to condition (immobilize) and pack the waste to render it chemically and physically stable ; and o to dispose of the waste at carefully selected sites using technologies and multiple barriers to effectively isolate the waste from man and his environment.
In considering the radioactive wastes that are generated from nuclear programmes, it is important to recognize that:
The radioactivity and therefore the hazards associated with radioactive wastes declines with time.
1 There are large volumes of waste that contain very low levels of radioactivity and can therefore be safely disposed of as non-radioactive industrial waste. This very low level of radioactivity, sometimes referred to as an " exempt quantity" or a "de minimis level" is usually established by the competent authority in each country.
a , .
1939y o 1989-04-13 .
The radiological hazard associated with radioactive wastes varies considerably with vaste types.
Waste management practices are based on an assessment of the risk and consequences of radionuclides released from the waste reaching man and his environment.
Different radioactive wastes will therefore be managed and disposed of according to the potential hazards associated with them.
Technologies necessary for the safe management and disposal of radioactive wastes have been developed, No new technology breakthrough is required for the safe disposal of any type of radioactive waste .
Countries may adopt different strategies for managing their wastes, but they are based on established concepts and technologies and are ect subj to strict regulatory controls.
2.
SOME ASPECTS OF RADIOACTIVE WASTE 2.1 Types Radioactive waste can take many forms, but since this paper is oncerned c with transportation and disposal, consideration is limited to solid w aste.
The shipment of radioactive waste in gaseous or liquid forms is neither prohibited nor inconceivable, but it is sufficiently unusual not to be worthy of further consideration here.
Radioactive categorized. wastes are very diverse in nature and can only be broadly This can be done in several ways, but the approach more commonly used is based on a classification that characterizes the radioactive wa with regard to their potential hazards and the handling and disposal o s.meth d High-level wastes are those vastes of high specific activity arisingmfro the reprocessing of spent fuel, or any other waste with a comparable specifi activity. c These wastes generate significant quantities of heat. Spent fuel, if declared a waste, falls in this category.
More than 99% of all radioactivity in wastes from the nuclear fuel cycle are contained in HLW. The
_ _ _ , - - - - ^ - - ' ' -
. , i 1929y. 1989-04-12 volumes are, however, small, typically less than 0.5% of the total volume of radioactive wastes from the nuclear fuel cycle. ,
Intermediate-level wastes are of lower specific activity and heat output j than HLW. Usually decay heat generation can be ignored in the design of transport containers and of facilities for storage and disposal. They require shleiding during handli'ng and transportation.
i I
Low-level wastes are those which do not require shielding during normal )
handling and transportation. They occupy the largest proportion by volume, accounting for about 80% of the wastes from the nuclear fuel cycle. ]
Alpha-bearing wastes are those which are contaminated with significant amounts of long-lived, alpha-emitting radionuclides. l l
I A complete listing of radioactive waste management terms is provided in the Appendix. l 1
2.2 Sources The sources of radioactive wastes include all facilities in the nuclear fuel cycle. Wastes are generated during the normal operation of nuclear power plants, fuel fabrication plants, reprocessing facilities, uranium mining and !
milling facilities, the decommissioning of these facilities and from the use of radioactive materials in hospitals. industry, research and educational establishments. The nuclear fuel cycle is by far the largest source of radioactive waste.
2.3 Generation rates The quantities of radioactive waste produced vary greatly from country to country depending on the level of nuclear power production. The current situation, together with the anticipated arisings of waste to the end of the century are summarized in Tables 2.1 and 2.2. Radioactive wastes from non-power applications such as medical, industrial and research facilities account for around 10% of the total arisings. Overall quantities of LLW and ILW are predicted to almost double between now and the end of the century.
i 4
- of = 4 0
, e , , .
e l
C O O u O O O O
'O O O es be tw m M C N
.= __
. e
- O e U O O O e C O O 3 e O et eJ e.e N en M E a.e .e
=
E O O a
== O O O e O O O O tp O O O O 3 O O .Ce a are w og m u M
e e e m ,a O @
4 m N @ a=
- e
= = = = - - . - -.
9g C O u arl e O O O O D o O O O e
g O U O C
O O O O O O O N O g O = N 3 e=0 m W be 3 e u +4 8"1 e 3 w e h M E N e ek 04 me .en 4 e M ^ a.4 e=0 *w ese M U
__- 3 O y
_ . - _ _ _ _ _ en O O C
. O O O
_ __ _ _ g. O en .O, O
a . e n H e4 e .*
O O O O a
O o o u
% O O O O O e O O O O O O b W w ett O te C h we =*
to e en N oJ e6 * * **
s.e M e e4 N 'O
.- s4 M.* 9 m x s.e O e
== e en eO e D O *** 00 y
) O O O O 8'* O O 6e N
= O en N O O G g M o M e "" O O O O C 8 kn O W 89 e "8 e e . -
m
- _ _ _ _ .- _ _ _ _ _ _ ._ _ en e-e gp g
w e O O O O O O O e4 &
O O O O f Qs O O w O O 3
O O ne me oJ e N m O 'e m e.e O
- mo n J e m # E* ** *'* **
e.e .O M
$ e e #
S e h!\
l C .$a O %
_ _ .= =. .- _ = O O O O O O eC O 4 O O 6. e
.e N O et W @ e e O O O 3
O O 4 w e O es O O O M N W eO O O O *4 e O "* O
.* O O O ON
- e w 0 O e 3 ,.4 3 .e4 me - e ~
O C
O O O wC e 4 . O O O ==
p O' 3 e
. - . - - - e eh
- M " " ^
ein e4 e
pe N m Ae
- og N O.e s ww m .,
.a. 6
% O O O O w O O O O b N O e D e e a w
'e w**
En w w en O *t C D a O O O O
- .-.=-- e %- O e N O C
- e en 3 to to e en e es en me w e es U O e se en 3 O O O b O O N >e e4 X N O me e
M eew O O O O e ==
C 4 me & ** a o O w e w es e W N M # e*
_ _ . - _ ae3 E ee e
3w 4 4 3-e m
== e e me me 3
.eg aw 3 e ==>3 ce en e
m O O O O ** Q O O O > M O O O O 3 O O O e .ee me e 3 O e e O en a m O O -e se eu me = O ee M e est e > e eAe N e em
> N w eb M me
.o e .==
.. E =* u en
_ . - - - - . . - - == 0 ee 3 O O O O w O O O O O O O O E 3s=
O O O O e O O O O ea q C O O O 3 P **
3 O ea es m en w tr U 4 m m e e4 N N e e e4 m 4 8'l og me e Q.
e4 .O* =
- 33* &W
________ _____________ 3= I' U
-Jb . e
_____-. ___ e,U, O
, .e c e e
A tm es a
- e. es .t.e e .U. A t>
ne Oe & =*
- w
.C M A .U. RU 5 he tee en *ee u u se me .Ooeas M 3 U O & == *=
e e se ec e Me R O to 3 9 TU > M se Q he me e M
- L. E G e e Q ec
- 9 e en Q On U e e '
>D M
- De 4 9k On
& Qw U
o
'1929y 1989-04-12 However, with changes in. waste management practices currently being implemented in many countries, future arisings of waste, particularly LLW, are ,
expected to be generally lower than currently forecast.
1
- 3. DISPOSAL OPTIONS FOR RADIOACTIVE WASTES Not all disposal options are suitable for all types of radioactive waste. In regard to disposal, the longevity of the radionuclides becomes the controlling characteristic and it is essential that the planned duration of the isolation is matched with the time for which the radioactive wastes remain a significant hazard.
Authorized waste disposal practices are designed to ensure that there will be no significant impacts on man and his environment, now or in the future. Such practices use a multi-barrier concept (a systet : ne t wo or more independent barriers to isolate radioactive waste from the bicsphere).
The radioactivity of low- and intermediate-level wastes becomes negligible through natural decay cfter a few hundred years. These wastes are usually disposed of by burial close to the surface (shallow land burial) -
from a simple trench to an artificial engineered underground structure. Deep burial in disused mines is also a common practice.
Shallow-land burial facilities for low-level wastes have been in operation for many years in France, USA and the UK. Deep cavern under seabed is in practice in Sweden for low-level wastes. Some developing countries have disposal facilities for low-level wastes, while many of them have plans for selecting such facilities.
High-level and alpha-bearing wastes remain radioactive for several thousand years. For disposal of thase wastes, deep geological repositories (several hundred metres below the ground) in granite, clay, salt or other host rock formations are being actively investigated by many countries.
Ocean disposal of certain packaged radioactive wastes has been studied since 1949 and has been regularly practiced by several European countries in
s 1929y 1989 04-12 ,
the past. Technically it is easy to implement with little environmental impact, in part because of the sea's enormous dilution effect. Dispesal is '
also being considered within deep ocean sediments in stable regions of the earth's crust that are unlikely to be disturbed by natural events or by drilling or other commercial operations.
l l
Since 1983, there has been a non-binding moratorium on the sea-dumping of radioactive wastes (unkt the " Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matters" - known as LDC or London Dumping Convention) while certain issues raised by LDC parties are resolved.
The Agency is assisting by providing answers to questions of a scientific and technical nature, 4.
INTERNATIONAL STANDARDS AND PROCEDURES FOR RADIOACTIVE WASTE DISPOS 4.1 International cuidance on safe handlino and disoosal Internationally agreed guides and recommendations exist for the management and disposal of low- and intermediate-level wastes. Considerable progress has been made in achieving international consensus on principles and technical criteria for the safe underground disposal of high-level waste.
While the IAEA is not an international regulatory body, it publishes standards, guides, and recommendations that many countries use as the basis for planning and regulating their waste management programmes. The documents are based on international consensus achieved as a result of meetings held by the IAEA and by consultations with its Member States. The IAEA publications on radioactive waste management provide guidance for the safe management and I disposal of radioactive wastes produced in the nuclear industry. These publications are issued as Safety Series, Technical Reports Series or Technical Documents.
The intents and hierarchies of the various Agency l
publications are summarized in Appendix A.
Many standards, guides and recommendations have been developed and published by the IAEA on various aspects of waste management. Topics include:
Radioactive waste handling, processing and storage
i t
+
Ib29y
< . 1989-04-12
.y-Environmental dispersion and behaviour of radionuclides Underground disposal in shallow ground, rock cavity and deep geological ,
repositories
. Sea disposal of radioactive wastes Disposal of wastes from uranium and thorium mining and milling l . Decommissioning of nuclear facilities Management of wastes produced by radioisotope uses.
Relevant documents prepared and published by the IAEA under the Safety Series only are listed in tables A-1 to A-7 in Appendix A.
An important Agency Safety Standards document for underground disposal of high level waste is in final review. This document calls for independence of the safety of the HLW repositories from institutional control. This means that monitoring, surveillance, or other control or remedial actions may be carried out, as required by national authorities, but the safety of the waste repository must not rely on these measures.
International recommendations on radiation protection from nuclear power and associated radioactive wastes are built on the principles set out by the International Commission on Radiological Protection (ICRP). They serve as the basis for the IAEA's guidelines on radiation protection and related subjects, such as the Basic Safety Standards for Radiation Protection [2] and Regulations for the Safe Transport of Radioactive Material [3].
Some radioactive wastes may need little or no regulation in the interests of public safety.
One recent achievement'of international consensus is likely to influence the national regulation of certain low-level radioactive wastes
[4). At a meeting in 1988, an advisory body to the IAEA agreed upon the principles by which certain radiation sources and practices can be exempted from regulatory control. This consensus is an important outcome of discussions over many years involving experts from the IAEA, NEA/OECD, World Health Organization (WHO) and Commission of European Communities (CEC).
4.2 Agenev's future plans:
The demands on the Agency from Member States to provide harmonized international standards and criteria in the waste management area seem to be
i .
2 s
1939y ,
1989-04-13 , \
increasing. Such standards and criteria, agreed at an international level, are seen as one way of improving confidence in Member States that radioactive wastes can be managed safely. The Agency plans to review these documents and where necessary, to update them to make them compatible with the current knowledge and experience of waste management in Member States. Thus, while j there is an ongoing and active Agency programme aimed at producing such safety standards, criteria and guides it can be argued that more can be done to improve its visibility and effectiveness.
In 1989, the IAEA established a standing committee called the International Radioactive Waste Management Advisory Committee (INWAC) to a review and recommend the Agency's future (1991 onwards) waste management I programme.
In view of the importance of the radioactive waste managsment issue, the Agency requested participation in this Committee by experts at a senior level familiar with the broad issues of radioactive waste management !
policy in their own countries and in the international community. I l
5.
AREAS OF POTENTIAL FUTURE INTERNATIONAL COOPERATION IN RADIOACTIVE WAS MANAGEMENT The concept of an international or regional disposal sites for radioactive wastes is one that continues to be pursued and has been strongly advocated by countries having limited land resources (5, 6]. Large, well-organized, well-located, and well-equipped sites are considered to be preferable to a host of smaller sites. Besides, there are and will be countries with very small nuclear programmes and countries without geologically ideal disposal sites.
These approaches were considered as part of regional or international plannin) of the nuclear fuel cycle by IAEA study and working groups in 1977 and 1982 (7). A report by the CEC in the 1980s has argued for a regional solution to the problem of waste disposal (6]. Preliminary study of the feasibility of an international waste repository system was organized by the Nuclear Energy Agency of the OECD (NEA). This study, completed in 1986, concluded that, on the basis of international studies carried out so far, there are no apparent insurmountable safety, technical, economical or institutional reasons why such a project could not be seriously considered [8].
l' t
o l
. *1929y 1989-04-12
.9- !
i 1
A few countries could join together on a regional basis to establish and share repositories as individual repositories in these countries may not be i' technologically and economira?ly justifiable. To share waste disposal sites on a regional basis, countries, however, should have commonality ins l
1 national legislation covering nuclear activities including radiation protection and waste management; regulations for waste management and disposal; i
criteria for radiological protection, waste package form and its I
acceptance for disposal. 1 l
i l
l l
6.
OVERVIEW OF AGENCY ASSISTANCE TO MEMBER STATES RELATED TO RADIOACTIVE l WASTE MANAGEMENT l The IAEA's various programmes in radioactive waste management are especially designed to anticipate developments in nuclear energy's uses and the needs of developing as well as developed countries. For decades, the Agency has assisted its developing Member States through training, technical a
co-operation, by providing assistance in starting and building necessary infrastructures, providing fellowships and financial support through research contracts for carrying out basic research in nuclear energy and its applications in other fields. Emphasis is now being placed on helping i countries to develop long-term, integrated waste management programmes and to use recent technology that can be transferred to them. By this means, the i countries are able to gain the benefits of international experience in l
implementing their own waste management programmes, particularly when they are in the early stages of nuclear energy development.
6.1 WAMAP Service In late 1986, the IAEA decided to augment its waste management efforts by starting an advisory programme to provide greater assistance to its develeping Member States. WAMAP - the acronym for @ te _ Management Advisory Programme
- is helping countries by assessing their needs for waste management and l related areas; reviewing operational and planned programmes; and evaluating
I 1 2
1 , .
t 1939y . , , ,
1989-04-12 , .
available expertise and manpower, laboratories, equipment, and services.
Teams of experts in various waste management disciplines visit a Member State, .
upon its request, for a comprehensive overview of waste management needs, pr'actices, procedures, and institutions. Teams directly assist in the development and implementation of waste management options, plans and methods l {
for waste segregation, treatment, conditioning, storage, and disposal, all a within the context of the country's policies, programmes, and financial situation.
'l
]
Countries have also benefitted from the programme's assistance in establishing regulations, analysing problems, and selecting solutions for the j design, construction, and operation of waste disposal facilities. WAMAP specialists typically explore ways to best share expertise, engineering !
know-how, and laboratory facilities, for example, within a region. The
{ l intention is to make regional co-cperation more efficient and fruitful in this field.
WAMAP missions began in 1987, building upon the traditional base of information and expertise established at the.IAEA over the past 30 years.
Sixteen missions have been conducted so far (Table 6.1). WAMAP has prepared a report on model laws, regulations, and guides for the implementation of I legislative controls.
This report will be distributed to national authorities during future WAMAP missions.
l 1
Table 6.1: WAMAP Missions Completed and Planned i
1987 l Hungary, Portugal, Bulgaria, Turkey l
1988 j Bangladesh, Brazil, People's Republic of China, l
Colombia, Indonesia, Republic of Korea, Malaysia, l Mexico, Morocco, Peru, Thailand, Zimbabwe 1
I l 1989 l Chile, Egypt, Iran, Jordan, Kenya, Pakistan, l Philippines, Poland, Zaire, Zambia l
1 i
. .s1929y 1989-04-12
. . 1 l
6.2 Management and Control of Radiation Sources j l
A common problem, most evident in developing countries, concerns regulation and control of radiation sources and equipment. Accidents occurred in Mexico in 1983, Morocco in 1984, and, in Brazil in 1987, that involved abandoned or discarded radiation equipment and sources that caused exposures to people, sometimes with fatal results. Such incidents have led to renewed efforts at the IAEA to assure that Member Sta.es possess the necessary requirements for the control, safe use, and disposal of radiation sources.
In many countries, control is not being achieved for a variety of reasons. Many lack the appropriate legal and regulatory framework or an adequate system of notification, registration and licensing by a competent authority. Many lack training in the control and safe use of radioactive materials and lack the facilities or arrangements for the collection, conditioning, storage, and final disposal of radiation sources that are no j longer useful. l l
The incident in Goiania, Brazil, in September 1987, involved the removal of abandoned radiotherapy equipment with a caesium-137 radiation source, which subsequently was deliberately broken open. This incident caused extensive j environmental contamination, human injuries, and four deaths. The incident pointed to the value of international co-operation, as national authorities I
and international organizations, including the IAEA (under the ' Convention on Emergency Assistance in the Case of a Nuclear Accident or Radiological Emergency'), sent experts and equipment in response to the incident.
The IAEA's waste management programme addresses these issues in a variety of ways:
Infrastructure: Particular attention is being placed upon helping ,
countries to develop the proper framework of laws and regulations to control sources in use and after disposal. Regulatory documents and codes of practice have been provided so far to 25 Member States.
Standards, Guidance, Recommendations: In conjunction with its radiological protection activities, the IAEA provides technical guidance to Member States on the protection of workers, patients and the public from the use of radioisotopes in industries, medical centres, and nuclear research and Mdhan thvaM AMm. _ -_.
t 1939y 1989-04-12 ' '
Training: Training courses are being conducted to promote greater "
awareness among users, regulators, and safety officers of the radiation hazards and procedures for protection of workers and the public. Topic areas include safety in the handling, treatment, and disposal of radiation sources.
Practical Assistance: To enhance national waste management capabilities,
+he IAEA is providing guidance on the standardization of the design and procedures for waste management systems. In 1988, a video flim illustrating techniques for the safe immobilization and storage of used radiation sources was prepared for use in training and future WAMAP missions.
6.3 WATRP Service The IAEA has increased its emphasis on country specific assistance not only to developing but also to industrialized countries by providing a service in which national plans for radioactive waste management can be assessed and reviewed by an international panel of experts. IAEA convened a number of panels at the request of the Swedish Government in May 1978, November 1979 and November-December 1983 to evaluate the KBS reports entitled
" Handling of Spent Nuclear Fuel and Final Storage of Vitrified High-level Reprocessing Waste",
" Handling and Final Storage of Unreprocessed Spent Nuclear Fuel" and
" Final Storage of Spent Nuclear Fuel,- KBS-3".
Since early 1987, consideration has been given to the development of a programme that would provide such an assessment service entitled " Waste Management _Aasessment and Technical Review Programme' (WATRP).
Available experience and the results of informal contacts with nuclear experts and waste management organizations in some Member States give strong evidence that developed and lesser developed Member States are keenly interested in the Agency's WATRP service from both the peer review and public acceptance standpoints.
, J 1929y 1989-04-32 A new panel was convened by the IAEA at'the request of the Government of a Sweden. The panel members, serving'in their individual capacities, met in .
1987 and evaluated the planned research and development and other activities
~
required to safely handle and finally dispose of the radioactive waste from
. Sweden's nuclear power plants.
Recently, the Agency has received a request from the United Kingdom Atomic Energy Authority to assist them in reviewing the UK Nirex Ltd. R&D programme on deep repository post-closure safety and site assessment. The Agency has agreed to arrange for an experts' meeting to evaluate the proposed methodology and programme. Although Nirex programmes are well-established, and Nirex has confidence.in them, it seeks the additional' confidence which can come from a review by international experts. The company looks for views on the completeness of the safety analysis, and how convincing is the resulting assessment to scientists and to the layman at a Public. Inquiry, considering the judgements and uncertainties involved.
6.4 WPSF Service l
One important area of the Agency's technical co-operation programme is to 1 provide assistance to Member States that generate radioactive wastes from the i use of isotopes in nuclear research, hospitals, industry and other institutional activities rather than from a nuclear power programme.
Many of the requests for technical assistance in the field of waste 1 management are similar in project objectives and scope. The volumes, characteristics and activity levels of the wastes generated, or expected to be i generated, by these Member States are also often quite siellar. Taking this into account, the Agency decided to develop new strategy for providing technical assistance including preparation of' design package for a reference i Neste Processing and gtorage Facility (WPSF). The design package for the WPSF would be engineered so that the basic waste management needs for Member States without nuclear power plants could be met.
The proposal for the development of a design package for a reference WPSF to handle LLW generated within Member States without a nuclear power programme presents a new dimension to the standard technical co-operation projects
l' , .
s 1929y 1989-04-12 . -
offered by the Agency. In simple terms, the design package would be a complete Architectural-Engineering (A-E) service such that the package could
- be used to proceed directly into the construction phase of a waste processing and storage facility.
7.
ISSUES ASSOCIATED WITH TRANSBOUNDARY SHIPMENTS OF RADIOACTIVE WASTE 7.1. Background The IAEA Regulations for the Safe Transport of Radioactive Materials, which include technical and administrative requirements, specifically govern the transboundary movements of radioactive materials. Transport of radioactive material has an outstanding record. In the past 35 years, it is estimated that more than 200 million packages have been transported, yet there has been no accident with serious radiological consequences to the public.
l International transport of spent fuel takes place routinely from reactors l to reprocessing plants. There are two large reprocessing plants that l
commercially reprocess spent fuel in Western Europe, they are in France and in the UK. In addition, the Soviet Union carries out spent fuel reprocessing for the fuel of Soviet origin used in reactors outside the Soviet Union.
The large reprocessing plants are centres where both national and international transport routes meet. The most important international transport route is the one used to bring spent fuel by sea from Japan to Europe. Eventually the return voyages will tranuport the equivalent waste back to Japan. The Japan-Europe route is well. established with five ships continuously transporting spent fuel.
Another form of transboundary movement of radioactive waste is the return of sealed radiation sources, after use in medicine and industry, to the supplier country.
If in the future international repositories for radioactive waste were to become a reality, either land-based or seabed facilities, then transfrontier movements of radioactive waste would increase significantly. This section'of
. , i o j 4 f s J 1929y 1989-04-12 1 I
l the report attempts to identify the technical issues associated with ensuring ]
that transboundary shipments of radioactive wastes are conducted in a safe and .l environmentally acceptable manner.
7.2 Elements of the waste management system In order to understand the issues, one must first understand the system under which wastes are (or et least should be) managed. The waste management system consists in essence, of two functional components: operational activities and surveillance or regulatory activities. Although many different organizations or groups within organizations may be responsible for specific actions, these actions are either operations related or surveillance related.
In order for the waste management system to exist, an organization must exist which addresses these two functions, and in which the operator's and regulator's roles and responsibilities are clear, distinct, and well-defined.
a While the operator could be a government, private, or other type of I i
organization, the government usually fills the role of regulator. The rolt. of l 1
the operator is "to do" while the role of the regulator is "to make sure it's l
1 done right." j The operating steps in waste management from generation to disposal are shown in Figure 7.1. The first step in waste management is to characterize and classify the waste. The waste is characterized using standard chemical or instrumental techniques or both in order to determine its chemical and radioactive constituents. Once characterized, the waste is classified as to type using the appropriate waste classification system and segregated accordingly. At this point, appropriate handling, treatment, storage, and/or disposal requirements can be identified.
The next component of the system relates to treatment, storage, and disposal of the waste. Once classified, treatment, storage, and disposal options are identified and evaluated. These evaluations often include engineering assessments and feasibility studies, facility performance assessments, safety assessments, environmental evaluations, and systems optimization studies. These studies define the performance objectives and j design and operating requirements for the waste management facilities and also evaluate and compare the impacts of the activity. Operating procedures are 1
- e.
. y, ,
1939y _,
_. 1989-03-28
. Figure 7.1 l
l' PRODUCTION OF WASTE i,
WASTE CHARACTDIZATION-AND CLASSIFICATION 1P WASTE SEGREGATION
<r ir '
q, j STORACE !
PRE-TREATMENT s RECYCLE, REUSE I o
TREATMENT FOR TRANSPORT STORAGE OR DISPOSAL 3
i l
., 1 e DISPOSAL :
)
l l l 1
l i
i l
._.______:__________----i
,- t i
.,41929y 1989-04-13 developed and implemented to provide for the safe management of the waste on a j i
day-to-day basis. The operator is also responsible for training personnel *j widh regard to all aspects of his operations (health, safety, environment, etc.). 1 i
From an operations, standpoint, activities are monitored to verify that I the waste management facility is operating as intended and licensed.
Environmental monitoring quantifies the impact of releases on the ambient -
environment while routine monitoring of the workplace protects the workers from an industrial hygiene and health physics standpoint.
A key component in the waste management system is record-keeping. It is essential that records be kept of wastes generated indicating the types, characteristics, volumes, and ultimate disposition. Normally this is accomplished through a vaste manifest system linked to package labels and a (computerized) data base. Thus, a record of the waste can be kept from the point of generation to the point of disposal. If the generator and disposal i site operator are different, duplicate records are often kept.
Built into waste management system is a quality assurance program to assure that actions which should be done are, in fact, done in the specified manner. For example, standard analytical methods are used for waste characterization and classification. Audits are routinely conducted to ensure operating procedures are implemented.
In addition to this rigorous programme put in place by the operator, independent oversight or surveillance of waste management activities are provided by the appropriate regulatory agency. In addition to often defined standardized waste characterization and classification techniques, treatment, storage, and disposal requirements are often specified as part of a permit or licence. Separate, independent monitoring programmes are often implemented to verify or confirm facility performance. Finally, periodic site inspection or audits are conducted to ensure compliance with regulatory or permits requirements.
1
'l 1 ,
9 1929y 1989-04-12 '
- The roles and responsibilities of the operator and regulator are '
summarized below:
Within its overall responsibility, an implementing organization normally assumes the following functions:
Performance of safety analysis of waste management activities; Develors.ent and submission of proposals to the regulatory authority regarding the quantities of radionuclides to be discharged as effluents and the methods and procedures for monitoring and controlling such discharges; Provision to the regulatory authority of such documentation on siting, design, construction, operation and shutdown of facilities for the handling, treatment, conditioning, transportation, storage and disposal of radioactive wastes as is required for demonstration of compliance with its regulations; Preparation and updating of operating and maintenance instructions and training of the operating and maintenance personnel in their duties; Operating the waste management systems in accordance with requirements and technical specifications approved by the regulatory authority.
Monitoring and maintaining records of all waste management activities and provision to the appropriate regulatory authority of' periodic reports at such intervals as are required; in the event of an accident or unplanned event, making a prompt report specifying the extent and nature of the occurrence and the remedial actions undertaken.
Maintaining records of waste inventories for storage, transport and disposal and providing such information to the regulatory authority as required; Retaining such samples of effluents as may be specified by the regulatory authority.
U
,,1929y 1989-04-12
- 19 It is the responsibility of the regulatory authority tos Develop regulations, requirements and criteria for waste management; Assess .snd review in the light of operational experience, and in the context of the regulations, the, requirements and criteria for safety analyses of the waste management systems and facilities; Specify limits for the discharge of radionuclides to the environment and' the conditions relating to those discharges on a site-specific basis; Verify compliance with regulations, requirements and criteria (e.g. on design, construction, operation, operator qualification and records by inspection of the radioactive waste management facilities);
Enforce necessary remedial and corrective actions in the event of non-compliance with regulations, requirements and criteria; Provide a format for the records and reports that it requires; Establish an appropriate independent sampling and analysis programme to verify compliance with the specified discharge limits and criteria.
This brief overview of the waste management system indicates that waste management should not be viewed as a series of ad hoc actions but rather a well planned and coordinated effort from start to finish.
7.3 Technical issues In this sub-section, major technical issues associated with transboundary shipments of radioactive wastes are identified.
7.3.1 Issues Associated with Notifications and Approvals to Transport Waste for Disposal These issues focus on concerns related to the importing or exporting country, or country through which the waste would be shipped:
o 1929y . . . . ,
~
1989-04-12 ,' .
not knowing waste was being shipped in or through it; .
not having sufficient time or technical expertise to evaluate the acceptability of a proposed waste shipment; I not having the administrative capability to process notification and apptoval; and 5
insufficient information being provided to technically evaluate the proposal.
7.3.2 Issues Associated with the Safe Transport and Handling of the Waste These issues focus on concerns related to:
i
)
The accurate and complete radiological and chemical characteristic of the waste; The accuracy and completeness of waste shipping manifests; The acceptability of waste packages for shipment; The acceptability of the transportation methods. I 7.3.3 Issues Associated with the Safe Disposal of the Waste These issues focus on concerns related to:
The accurate and complete radiological and chemical characteristic of i
the vaste; j
The technical acceptability of the waste form and package for the proposed disposal option; i
- ~
The acceptability of the proposed disposal option; !'
The acceptability of the proposed environmental monitoring program,
, .t.
I
'1929y 1989-04-12 l
.- l 1
+
The technical acceptability of the worker protection plans (e.g., .
industrial hygiene and health physics plans for the proposed facility);
and.
+
.The accuracy and completeness of the proposed waste management information I 1
system. '
7.3.4 Issues Associated with Long-Term Surveillance of'the Disposal ,
. .l Facility l i
i These issues focus on concerns related to:
a 1
+
the accurate and complete radiological and chemical characteristic of '
the waste; i
+
the accuracy and comiletness of records of wastes disposed of in the disposal facility (i.e., the technical acceptability of the waste management record-keeping system);
l
- the acceptability of the overall disposal system (i.e., the waste form, engineered facility, etc.);
f i
I
+
the acceptability of the environmental monitoring programme; 1
l
+
the acceptability of the waste disposal facility closu'e r plans; and j the acceptability of the post-closure plan.
1 j
i l
1
1 i e 1929y
- 1989-04-12
- References
[1] NEA/IAEA, Nuclear Energy and its Fuel Cycle, Prospect to 2025, OECD Paris (1987).
[2] International Atomic Energy Agency, Basic Safety Standards for Radiation Protection, IAEA Safety Series No. 9, 1982 Edition.
[3] International Atomic Energy Agency, Regulations for the Safe Transport of Radioactive Materials, Safety Series No. 6, 1985 Edition.
[4} International Atomic Energy Agency,' Principles for the Exemption of Radiation Sources and Practices from Regulatory Control, Safety Series No. 89 (1988).
[5] GEIZERS, H.G.Y., KORTHOF, R.M., CORNELISSEN, A., VAN DE VATE, L.,
Radioactive Waste Policy of the Netherlands, Proc. of an IAEA/OECD Symposium on Back End of the Nuclear Fuel Cycle, Strategies and Options, Vienna, May 1987.
[6] Director General's speech at the IAEA General Conference, September 1985.
~<
17] RICHTER, D.K.,
The Agency's Activities in Radioactive Waste Management, IAEA Bulletin No. 23 No. 2, 1981.
\
l (8) NEA (OECD), International Approaches in the Use of Waste Disposal l Facilitiest Report on the Preliminary Study, Paris, June 1986. l j
1 I
l i i
i
__- -______ _ Q
6.
. I e
- . ' 1929y 1989-04-12 i
APPENDIX A 1 l
RELEVANT IAEA PUBLICATIONS ON MANAGEMENT OF RADIOACTIVE WASTE !
t
- 1. Safety Series (SS):
1 The various publications in the Safety Series are divided into four categories, as follows:
IAEA Safety Standards: Publications in this category comprise the Agency's f safety standards as defined in "The Agency's Safety Standards and Measures",
approved by the Agency's Board of Governors on 25 February 1976 and set forth in IAEA document INFCIRC/18/Rev.1. They are issued under the authority of~the Board of Governors, and are mandatory for the Agency's own operations and for the Agency's codes of practice.
1 i
l IAEA Safety Guides: As stated in IAEA document INFCIRC/18/Rev.1, referred to above, IAEA Safety Guides supplement IAEA Safety Standards and recommend a ,
procedure or procedures that might be followed in implementing them. They are issued under the authority of the Director General of the Agency.
Recommendations: Publications in this category, containing general i
recommendations on safety practices, are issued under the authority of.the l Director General of the Agency. l l
Procedures and Data Publications in this category contain information on procedures, techniques and criteria pertaining to safety matters. They are issued under the authority of the Director General of the Agency.
- 2. Technical Reports Series (TRS):
l l
It is comprised of reports on the status of technology and practice, but which are not highly oriented to safety.
.n.
s .
4 1929y 1 ,a
- l t
1989-04-13 ,, .
)
1
- 3. Technical Documents (TECDOCs):
These are informal reports that typically present data or information on j a particular subject or summarize the results of a meeting. Special pamphlets are also issued periodically on specific subjects. These usually.contain general information for the layman at the non-technical level.
l l
Tables A-1 to A-7 provide a list of IAEA documents in the Safety Series only. {
There are many relevant reports produced'in the Technical Reports Series and Technical Documents Series, which are not listed in these tables for the sake of brevity.
i l
1 1
1 i
l I
'b l
!= .
i i
l l
l l
i
. ,, e 1929y 1989-04-12 j
. Table A-1. Radioactive Waste Processing and Storage IAEA Safety Standards -l
- 1. Code of Practice: Management of radioactive Saf.Ser.No.69 wastes from nuclear power plants (STI/ PUB /705) (1985).
IAEA Safety Guides
- 1. Management of radioactive wastes at Saf.Ser.No.28 nuclear power plants (STI/ PUB /208 (1968)
.i
- 2. Design of radioactive waste management Saf.Ser.No.79 systems at nuclear power plants (STI/ PUN /739) (1986) -
i
- 3. Operational management for radioactive Saf.Ser.No.50-SG-011 effluents and wastes arising in nuclear power plants; a safety guide (STI/ PUB /734) (1986)
- 4. Safety consideration in design and (At preparation stage)'
operation of radioactive waste incineration facilities.
I i
i l
l
1929y i ,.
1989-04-12 , .
l j
Table A-23 Underground Disposal- of Radioactive Wastes {
t IAEA Safety Standards .)
- 1. Safety principles and technical criteria for the underground disposal of high-level wastes (At preparation stage) i IAEA Safety Guides
- 1. Radioactive waste disposal into the ground (STI/ PUB /103) (1965) Saf.Ser.No.15 ;
- 2. Guidance for the regulation of underground 'I repositories _t disposal of radioactive wastes (At preparation stage) {
- 3. Qualitative acceptance criteria for radioactive wastes to be disposed of in deep geological formation (At preparation stage)
Recommendations: Procedures and Data I
- 1. Basic factors for the treatment and disposal I of radioactive wastes !
(STI/ PUB /170) (1967) Saf.Ser.No.24
- 2. Development of regulatory procedures to the disposal of solid radioactive waste in deep, 1 continental formations (STI/ PUB /540) (1980)
Saf.Ser.No.51
- 3. Shallow ground disposal for radioactive l wastes: a guidebook I (STI/ PUB /578) (1981)
Saf.Ser.No.53 I
- 4. Underground disposal of radioactive wastes basic guidance (STI/ PUB /579) (1981)
Saf.Ser.No.54-t
- 5. Safety assessment for the underground disposal of radioactive wastes l (STI/ PUB /590) (1981) l Saf.Ser.No.56
- 6. Concepts and examples of safety analyses for radioactive waste repositories in continental geological formations (STI/ PUB /632) (1983)
Saf.Ser.No.58 l
.../
.. j
l/29y 1989-04-12 i
l Table A-2 cont. Underground Disposal of Radioactive Wastes ,
l
- 7. Disposal of low- and intermediate-level solid radioactive wastes in rock cavities:
a guidebook i (STI/ PUB /610) (1983) Saf.Ser.No.59 )
i
- 8. Criteria for underground disposal of solid ]
radioactive wastes '
(STI/ PUB /612) (1983) Saf.Ser.No.60 !
l 9. Site investigations, design, construction, '
l operation, shutdown and surveillance of I repositories for low- and intermediate-level radioactive wastes in rock cavities (STI/ PUB /659) (1984) Saf.Ser.No.62
- 10. Design, construction, operation, shutdown and surveillance of repositories for solid radioactive wastes in shallow ground j (STI/ PUB /652) (1984) Saf.Ser.No.63 i i
- 11. Safety analysis methodologies for radioactive I waste repositories in shallow ground f!
(STI/ PUB /656) (1984) Saf.Ser.No.64
- 12. Performance assessment for underground radioactive waste disposal systems (STI/ PUB /692) (1985) Saf.Ser.No.68
- 13. Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities (STI/ PUB /710) (1985) Saf.Ser.No.71 l l
i l
l
I 4 , - -
1929y ,
1989-04-12 '
Table A-3: Sea Disposal of Radioactive Wastes IAEA Safety Standards 1.
Definition and recommendations for the convention on the prevention of marine pollution by dumping of l wastes and other matter (1972-1986 edition)
(STI/ PUB /733)-(1986) Saf.Ser.No.78 IAEA Safety Culdes
- 1. Methods of surveying and monitoring marine radioactivity (STI/ PUB /86) (1965) Saf.Ser.No.11 Recommendations Procedures and Data . .
- 1. Environmental assessment methodologies for sea i
dumping of radioactive wastes (STI/ PUB /681) (1984) Saf.Ser.No.65
- 2. Control of radioactive waste disposal into the marine environment (STI/ PUB /609) (1983)
Saf.Ser.No.61
- 3. The oceanographic and radiological basis for the definition of high-level wastes unsultable for dumping at sea (ST1/ PUB /686) (1984)
Saf.Ser.No.66 I
- . _ _ . _ _ _ _ . _ .___mm___.__m -
e ', 1929y 1989-04-12 i
Table A-4: Environmental Dispersion and Behaviour of Ra6ionuclides ,
IAEA Safety Guides
- 1. Disposal of radioactive wastes into fresh water (STI/ PUB /44) (1963) Saf.Ser.No.10
- 2. Disposal of radioactive wastes into lakes and estuaries (STI/ PUB /283) (1972) Saf.5er.No.36
- 3. Principles fer limiting releases of radioactive effluents into the environment (STI/ PUB /728) (1986) Saf.Ser.No.77
- 4. Principles for the exemption of radiation sources and practices from regulatory control Saf. Ser. No. B9
- 5. The establishment of upper bounds to doses to individuals from global and regional sources (At preparation stage)
Recommendations; Procedures and Data
- 1. Generic models and parameters for assessing the environmental transfer of radionuclides from routine releases - exposures of critical groups (STI/ PUB /611) (1982) Saf.Ser.No.57
- 2. Procedures for assessing the reliability of environmental radionuclides transfer model predictions (At preparation stage)
- 3. Application of exemption principles to the disposal of very low level radioactive wastes to municipal landfills or by incineration (At preparation stage)
- 4. Application of exemption principlea to the recycle of materials from nuclear facilities (At preparation stage) 1
l 1
i 1939y . ,.
1989-04-12 , e
~i l
l Table A-5:
Decontamination and Decommissioning of Nuclear Facilities IAEA Safety Guides
- 1. (
Safety in decommissioning of research reactors )
(STI/ PUB /713) (1986)
Saf.Ser.No.74
- 2. -
Planning for the cleanup and control of very 1arge areas after a serious accident at a nuclear
~
facility (At preparation stage)
Recormendationst Procedures and Data 1.
Manual on decontamination of surfaces Saf.Ser.No.48 l 2.
Factors relevant to the decommissioning of 1and-based nuclear reactor plants }
(STI/ PUB /541) (1980)
Saf.Ser.No.52 l
1 2
l l !
l i
I i
i
.l 1
l l
i i
1 i
4
- 1929y 1989-04-12 Table A-6. Management of Wastes from the Mining and Milling of Uranium ,
and Thorium Ores IAEA Safety Standards
]
I
- 1. Safe management of wastes from the mining and )
milling of uranium and thorium pres j (STI/ PUB /772) (1987) Saf.Ser.No.85 IAEA Safety Guides
- 1. Application of the dose limitation system to the mining and milling of radioactive ores (STI/ PUB /737) (1987) Saf.Ser.No.82
)
Table A-7. Management of Waste Produced by Radioisotope Users Recommendations; Procedures and Data
- 1. Management of radioactive wastes produced by users of radioactive materials (STI/ PUB /711) (1985) Saf.Ser.No.70 e
i 1
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ d
1 J-1929y . ,. .
~
1989-04
- l l
l i
APPENDIX B l 1
l CLOSSARY OF RADIOCTIVE WASTE MANAGBIENT TERMS J i
! I A radioactive material is defined as any material for which the specifia j
activity is greater than 70 kBq/kg (0.002 pCi/g). In this context, specific.
I activity means the activity per unit mass of a radionuclides or, for a material in which the radionuclides f per unit mass of the materialis(1).
essentially uniformly distributed, the activity l
4 The following definitions have been extracted from the IAEA Radioactive Waste Management Glossary (2) and have been used in IAEA documents and many1j other non-Agency publications dealing with radioactive waste management.
acceptable limit ,
Limit acceptable to the regulatory body.
(Sees authorized limit).
alpha-bearino waste Waste containing one or more' alpha-emitting radionuclides, usually actinides, release. in quantities above acceptable limits for uncontrolled The limits are established by the national regulatory body.
authorized limit Limit set for a given radionuclides or source or for a given environment by a national or international environmental authority. (Sees acceptable limit.)
1 I
competent authority An authority designated or otherwise recognized by a government for specific safety. purposes in connection with radiation protection and/or nuclear de mAnimis :
Part itselfofwith the maxim trifles),"de minimis non jurat lex" (the law does not concern sometimes used with reference to sources of ;
radiation which a compete... authority may decide to exempt fro defined '
, regulatory requirements because individual and collective effet.sive dose equivalents received from them are both so low that they may k3 ignored, conditioning of waste 1
Those. operations and/or storage thatdisposal.
and/or transform waste into a form suitable for transport the waste to another form, enclosing the waste in containers, andThe opera providing additional packaging. -
(1) gm ww
' Transport of Dangerous United Nations, Goods, Recommendations, Fifth Revised Edition, N.Y. 1988. !
n~on ~~ - .
+
t e , a
- . 1929y 1989-04-12
_33_
l disposal l l
The emplacement of waste in a repository, or at a given location, without ,
the intention of retrieval. Disposal also covers the approved direct discharge of wastes into the environment, with subsequent dispersion.
heat ceneratino waste l Waste which is sufficiently radioactive that the energy of its decay significantly increases the temperature of its surroundings. Spent fuel elements require active cooling, for example in a water-filled basin, for l several years after discharge from the reactor. The hest-generating .f period of ELW in a repository may last several hundred years. j high-level waste j (i) The highly radioactive liquid, containing mainly fission products, as well as some actinides, which is separated during chemical reprocessing of irradiated fuel-(aqueous) waste from the first solvent extraction cycle and those waste streams combined with it. .
)
(11) Spent reactor fuel, if it is declared a waste.
{
(iii) Any other waste with a radioactivity level cccparable to (i) or (ii). g interim storace (storage)
Storage of radioactive materials such that:
(a) isolation, monitoring, environmental protection and human control j are provided; and l (b) subsequent action involving treatment, transport, and disposal or reprocessing is expected.
intermediate-level waste (or medium-level waste)
Waste of a lower activity level and heat output than high-level waste, but which still requires shielding during handling and transportation. The term is used generally to refer to all waste not defined as either high-level or low-level. (Sees alpha-bearing waste and long-lived waste for other possible limitations.)
long-lived waste Waste that will not decay to an acceptable activity level in a period of time during which administrative controls can be expected to last. (See:
short-lived waste.)
low-level waste Waste which, because of its low radionuclides content, does not require shielding during normal handling and transportation. (See: alpha-bearing waste and long-lived waste for other possible limitations.)
l
[ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ -
b e
. , , ,
- i 1929y '
1989-04 ;2 *
\
l mill tallings (tallings) 1 Finely ground residues resulting from the processing of ore for recovery
(1) slimes: the lighter, finer particles in the tailings (including l j
j
! particles in the micron and sub-micro range) made up of the clays -
and other very fine particles;
.1 (ii) sands the heavier, coarser range of particles.
mixed waste Radioactive waste that also contains chemicals that could cause {
undesirable effects in the environment. Such wastes present a number of '
technical and regulatory problems for processing and disposal.
j radioactive waste Any b,'terial that contains or is contaminated with radionuclides at conce.atrations or radioactivity levels greater than the ' exempt quantities' established by the competent authorities and for which no use is foreseen.
l radioactive waste management All activities, administrative and operational, that are involved in the handling, treatment, conditioning, transportation, storage and disposal of waste.
reoository A facility or designated site for storage or disposal of radioactive wastes. f reprocessing, fuel I
~
Recovery of fissile and fertile material from irradiated nuclear fuel by chemical separation from fission products ands other' radionuclides (e.g. j activation products, actinides); selected fission products may also be {
recovered. '
1 shallow-ground disposal (e.g. shallow-ground burial) I i
Disposal of radioactive waste, with or without engineered barriers, above or below the ground surface, where the final protective covering is of the order of a few metres thick. Some Member States consider ' shallow-ground {
disposal' to be a mode of storage rather than a mode of disposal. !
short-lived waste i
Waste which will decay to a level which is considered to be insignificant from a radiological viewpoint, in a time period during which administrative controls can be expected to last. Such waste can be determined by radiological assessment of the storage of disposal system chosen. (Seet long-lived waste.) -
d
, ' ,, ' *192 9y 1989-04-12
- s spent fuel Irradiated fuel units not intended for further reactor service. ,
treatment of waste Operations intended to benefit safety or economy by changing the characteristics of the waste. Three basic treatment concepcs ares (a) volume reduction; (b) removal of radionuclides from the waster (c) change of composition. (See: conditioning of waste).
underground disposal Disposal of waste at an appropriate depth below the ground surface, waste package The waste form and any container (s) as prepared for handling, transport, treatment, conditioning, storage and disposal of waste.
1
_ _ _ _ _ - _ _ _ _ _ _ _