ML20126G189

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Amend to Effluent & Waste Disposal Semiannual Rept for 910701-1231
ML20126G189
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1992
From: Fey F
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9301040103
Download: ML20126G189 (12)
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Text

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4 TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT

_MONTICELLO NUCLEAR GENERATING PLANT Amendment to the Effluent and Waste Disposal Semlannual Report for July 1.1991 throuch December 31,1991 Manifest Date: December 22, 1992 USNRC 4

Regional Admin lli ANI Library 1

NRR Project Manager General Electric 2

Document Control Desk San Jose Cust. Serv.

Resident inspector San Josa Fuel Proj. Manager K M Beadell 1

Shaw Pittman Potts & Trowbridge 1

K P Jepson 1

J Silberg P H Kamman 1

Safety Audit Committee 13 J E Windschill 1

A B Cutter Monti Site General Manager 1

R L Hannen ERAD Department 1

W J Hill Attn: Reccrds Clerk F W Hartley Communications Department 1

D D Lanning NRS File 1

D S Mendele NSS File 1

D M Musolf MDH 1

G H Neils Attn: Comm. of Health T M Parker M B Sellman C R Steinhardt J A Thie Secretary Manifest Binder 9301040103 921231 PDR ADOCK 05000263 R

pon

,7

.,y..

7:

4 Nottimn States Power Company 414 Nconc+ Mall

- Minneapes; Minnetota 55401 1927.

- Telephone (612) M0-5500_ -

December 22,1992 Monticdio Technical' Specification TSB.7 4A' U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 1

Monticello Nuclear Generating Plant Docket No. 50-623 Licenso No. DPR :

Amendment to the Effluent and Waste Disposal Semlar:nual Report for July 1.1991 throuah December 31.jR11.

in accordance with the Monticoilo Technical Specifications, Appendix A to Operating License

. DPR-22, we are submitting an amended Semiannual Radioactive Effluent Releace Report -

~

covering the last half year of 1991.- The Stront!um values for the fourth quarter have beenL added following offsite analysis.

f,d W

Fred L. Fey, Jr., Manager Nuclear Radiological Services Attachment fh 310025

..,1

NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 Supplemental Information

1. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A.

Noble Gases :

5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation B.

Long Lived Iodines, Particulates, and Tritium 7.5 mrem / quarter dose to any organ C.

Liquid Effluents :

1.5 mrem / quarter dose to the total body 5.0 mrem / quarter dose to any organ

2. Maximum Permissible Concentrations A.

Noble Gases :

10 CFR Part 20, Appendix B, Table II, Column 1 B.

Long Lived Iodines, Particulates, and Tritium :

10 CFR Part 20, Appendix B, Table II, Column 1 C.

Liquid Effluents :

10 CFR Part 20, Appendix B, Table II, Column 2 2.0 E-4 uci/ml for dissolved and entrained gases

3. Average Energy (Not Applicable) 0

..__.m.

_Paget '2

?-

9 W

EFFLUENT AND: WASTE DISPOSAL SEMIANNUAL REPORT Period-: Jul - Dec 1991

-Supplemental-'Information (continued)-

4.-Measurements and Approximations of Total Radioactivty

- A.

Noble-Gases :

Continuous gross activity monitors in Reactor Building Vent-and' Plant.

Stack exhaust streams.

Weekly isotopic analysis of exhaust streams, B.

Iodines in Gaseous-Effluent Continuous monitoring with charcoal cartridges in Reactor Building Vent-and Plant Stack exhaust streams with weekly analysis.

C.

Particulates in Gaseous Effluent :

Continuous monitoring with particulate filters in Reactor Duilding Vent and Plant Stack exhaust streams with weekly analysis.

D.

Tritium in Gaseous Effluent :

Continous monitoring with silica gel cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.

E.

Liquid Effluents :

Tank sample analyzed prior ~to each planned release and continuous--

monitoring of gross activity during planned' release.

5.--Batch-Releases AJLiquid :

0

1. Number of-Batch = Releases

~

NA-min l

2. Total Time Period for Batch. Releases
3. Maximum Time Period for.a-Batch Release NA-min-4.~-Average Time Period-for a Batch Release NA
min 5.-Minimum Time Period'for a' Batch Release:

NA lminL

6. Average River _ Flow.During Release NA*

tcf/sec

' B.-Gaseous :

-Ic. - Number: of Batch Rele ases 2-

2. Total Time Period'for: Batch-Releases

'4630.0 min 3". Maximum Time-Period for.a Batch Release 4030.0-min

4. Average Time Period for a Batch Release 2315.0 mi:n

_5. Minimum Time Period for~a: Batch Release 600.0 - min

'I i

.. 7

....y

's

."g.y.e _ -....', - r ;..,-_,

o N

i,57 iPage?"}3; s

a- _.

i

. EFFLUENT-AND WASTE' DISPOSAL SEMIANNUAL REPORTJ Period _:~Jul --Dec

.1991-Supplemental'Information (continued);

6. Abnormal Releases.

.- A ', Liquid :

2. Total Activity Released

_NA_

- Ci,

1. Number of Releases

~0 B. Gaseous':

i

~

1,-Number of Releases 0

2. Total Activity __ Released

-0,0

-Ci i

?

8 5

.7 I. T g

w 5

m k

A

'-r'

+

.7 I

4 a

/

1.-

s w

s-e p--n.

4

.. ~ _ _.. _ _.

-- ~

-C-P a g e _:- 'i EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL' REPORT.

Period : _Jul - Dec-1991 4

Table 1A _ Gaseous Effluents - Summation of all Releases

_- l 1

Units. 1.3rd Qtr I_4th Qtr lEst. Totall l

l l~

-l l Error,=%1 ]

A.

Fission & Activation gases

.l 1.

Total Release i

Ci 1 5.2SE+0f'I 4.63E+02 l 2.00E+01-J

-l 2.

Averace Release Rate I uci/sec l 6.60E+01 l 5.83E+01 1 r

-l.

3. Percent Tech Spec Qtrly I

i l

l-l Reporting Level l

J

_l l-l Gamma Radiation

-l l 1.26E+00 l 6.88E-01-1

l-;_

Beta Radiation I

l 4.18E-01 1 1.50E-01 l-B; Iodines i

.l 1.

Total 1-131 Release Ci i 1.1?E-02 l 7.'03E-03 1 1.00E+01 l l

2.

Average I-131 Release Rate uci/sec i 1.47E-03 1 8.84E-04-l-C.

Particulates

.l 1.

Total Particulates l

Ci l 1.70E-03 l-1.36E-03 l 3.06E+G1-l

.l

2. Average Releaso Rate I uci/sec l 2.14E-04 1 1.72E-04 l l

3.

Gross Alpha Radioactivity 1

Ci I 6.49E-06 1 4.11E-06-l-1 D. Tritium

-l 1.

Total Release l-Ci l 1.46E+01 1~1.9?E+01 l 1.00E+01-l-;

_l

2. Average-Release Rate l uci/sec-I-1.83E+00 1-2.47E+00 t E.

Percent ~Otrly Tech-Spec Reporting Levels-l' 1.

Iodines,-Particulates, j

l

-l l

l

-and Tritium l

l 2.97E+00-l 1.99E+00'l i -

1 e

u

Page-5 1

+

i' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-Period : Jul - Dec 1991-Table 1B Gaseous Effluents - Elevated Releases-l l-l

_ l-Continuous Mode l-Batch Mode-l i Unit i 3rd'Otr I 4th Qtr 1 3rd Otr l'4th Otr l

i Nuclides Released

1. Fission Gases l

KR-85M l

Ci I 5.70E+00 t 5.98E+00 1 0.00E+00 1 0.00E+00 )

0.00E+00 l.

l KR-87 l

Ci 1 9.22E+00 6.68E+00 1 0.00E+00 t

l-KR-88 i

Ci i 1.36E+01 2.77E+00 1 0.00E+00 0.00E+00 1 l

KR-89 Ci l 8.05E+00 2.26E+00 1 0.00E+00 0.00E+00 1

-l XE-133 I

ci 1.20E+02 9.57E+01 1-4.76E-03 l-0.00E+00 l l-XE-133M l

Ci-1 2.25E+00 2.64E+00 1 0.00E+00 1 0.00E+00-1:

l XE-135 l

Ci 1 5.36E+01 1 6.36E+01 1 4.24E-03 1 0.00E+00 l-

-l XE-135M i

Ci l 2.35E+01 4 2.38E+01-l 0.00E+00 l 0.00E+00

-l-l XE-137 i

Ci i 1.25E+02

-1.29E+02 1 0.00E+00 1 0.00E+00 l-1 l

XE-138 l

Ci 1 6.58E+01-6.58E+01-1-0.00E+00 1 0.00E+00 l_

l AR-41 Ci l 1.97E-01 l 0.00E+00-! 3.50E-03 1 0.00E+00 l l

1 I

i

-l l

Total for Period l Ci l 4.27E+02 1 3.98E+02 1 1.25E-02 1 0.00C+00 l

2. Iodines
l-I-131 l-Ci I 3.35EuG3 1 8.30E-04 l-0.00E+00 1 0.00E+00 l l

I-133 l

Ci l 2.04E-02 1 3.48E-03 1 0.00E+00 1 0.00E+00__l 2.78E-02 l 4.-71E-03 1 0.00E+00 l 0.00E+00 l.

l

'I-135 i

Ci 1

-l l-1 I

l l

Total for Period l Ci j 5.15E-02 I 9.02E-03 1 0.00E+00 l 0.00E+00 l

3. Particulates.

.l CR-51 i

Ci i 2.13E-06 ; 0.00E+00 1-0.00E+00 1 0.00E+00 l

.l MN-54 i

Ci i 1.13E-06-1.1.72E-07 I 0.00E+00 1 0.00E+00-l1 l

Co-60 Ci i 8.19E-06 I 2.53E-06 l 1.82E-08 1 0.00E+00 l

[

l ZN-65 C1 1.49E-06 1 4.84E-07 1 0.00E+00 1 0.00E+00-l-E l<

OR-95 Ci 2.28E-01 1 0.00E+00 1 0.00E+00 1 0.00E+00 l-

-l CS-137 Ci l 1.75E-05 l-9.84E-06:1 0.00E+00-0.00E+00-l-l

-aA-140 i

Ci

! 3.28E-04 i 3.97E-04 1 0.00E+00 0.00E+00 l l

SR-89 i

Ci

'6.29E-04 6 3.38E-04 1 0.00E+00 1 0.00E+00 l I

l SR-90 i

Ci 6.29E-07 I 7.42E-07-l 0.00E+00 1 0.00E+00

[=

l I

i l

1 l

l Total for Period i Ci 9.88E-04 l 7.48E-04 l 1.82E-08 1 0.00E+00 l.

L

Page?

6-a1

]

-EFFLUENT AND WASTE DISPOSAL $EM1 ANNUAL REPORT 1

Period : Jul - Dec 19911 Tab 1'e'1C Gaseous Effluents

_ Building Vent Releases.

q l

l.

l Continuous Mode 1

__ Batch Mode.

l

!'Nuclides Released i Unit 1-3rd Qtr l 4th Otr i 3rd Otr;_l 4th Otr' l 1.-Fission Gases

-l KR-88 l

Ci l 4.57E-01 2.74E+00 0.00E+00

! 0.00E+00 l 1

)

KR-89 i

Ci 1.14E+01 0.00E+00 0.00E+00 + 0.00E+00 l l

XE-133 C1 1.12E+01 1 1.85E-01 0.00E+00 3.14E-03-l l

XE-138 Ci 4.20E+01 1 2.07E+01 0.00E+00 1 3.433-03 1

_i

)

XE-135M i

ci 3.23E+01 l 4.04E+01 0.00E+00 1 0.00E+00 l l-

-XE-138 I

Ci 1 0.00E+00 l

1. lee +00 0.00E+00 l-0.00E+00-l_

-l l

I

-l l

l Total for Period i Ci I 9.73E+01 6.51E+01 l 0.00E+00 1 6:57E-03 1:

3

2. Iodines

~l' I-131 l-Ci I 8.35E-03 ! 6.20E-03 l 0.00E+00 1 0.00E+00 l I

I-133 l

Ci l 7.32E-02 1 5.24E-02 1 DIO0E+00 i C 00E+00 l l l I-135 l

Ci l-9.45E-02-l 8.84E-02 l-0.00E+00 l 0.00E+00-l

. l-

-)

i 1-l

-l _-

l Total for Period-Ci l-1.76E-01 1 1.47E-01 1 0.00E+00 1 0.00E+00 l

3. Particulates
l-MN-54 Ci-l 1.48E-05 l 7.10E-06--l 0.00E+00-l 0.00E+00 l=

- l CO-60 Ci 2.58E-04 l 1.12E-04 1 0.00E+00

0. 00E+00- _ l-l ZN-65 l

Ci 4.48E-05 l 1.03E-04 l 0.00E+C0 0.00E+00 l i-- l CS-137 Ci 4.31E-05 l 9.- 5 9E-0 6 1 0.00E+dD-l 0.00E+00 l l-BA-140 Ci l 3.14E-04 1 3.14E-04 1 0.00E+00 l 0.00E+00 l l

CE-141 1

Ci-

'l 3.06E-05 1-2.34E-05=1 0.00E+00 6 0.00E+00 ll

~ j SR-89 l-Ci 1-7.34E-06-l 4.67E-05 I 0.00E+00-1-0.00E+00 !

l

. _ _ i

- l-1 l

la 4

ll Total for Period l-Ci 7.12E-04 l 6.16E-04 i O.00E+00 1 0.00E+00 l m,

e m

v

i

.Page. T

,r;.

EFFLUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT

~

Period 1: Jul - Dec- _1991

-Table 2A -Liquid Effluents - Summation;of all-Releases-

-l i

Units i 3rd:Qtr 1 4th Qtr IEst. Totall-i l

l' I

l l-Error, %

["

.A.

Fission & Activation products'

~

{

El. Total Release (not including!

l

.)

.l.

l l'

tritium, gases, alpha)

Ci I 0.00E+00 1 0.00E+00 1 0.00E+00-1 l

2. Ava Diluted Concentration i uci/ml I 0.00E+00 l 0.00E+00-l B.

Tritium l

1.. Total Release l

Ci

-l 0.00E+00-l 0.00E+00 1 0.00E+00 ll l-

2. Avg Diluted Concentration l-uci/ml l 0.00E+00 1 0.00E+00 l C.-Dissolved and Entrained Gases
- l 1.

Total Release l

Ci 1 0.00E+00 1 0.00E+00 f 0.00E+00 l l

2.-Avg Diluted Concentration l uci/ml 1 0.00E+00 1-0.00E+00 t D. Percent =Qtrly Tech Spec Reporting Level 1

1. Whole Body Dose I

1 0.00E+00 1 0.00E+00 -l

.l 2.

Organ Doso I

t I 0.00E+00 1 0.00E+00 l E.

Cross Alpha Radioactivity

.l 1.

Total Release-l Ci l 0.00E+00 l-0.00E+00 1-0.-00E+00---l-lF. Volume of Waste Released l-Liters 1 0.00E+00 1 0.00E+00-1:0.00E+00 l lF. Volume of Dilution Water Used l-Liters-l 0.00E+00 1 0.00E+00 l 0.00E+00 l t

Table 2B Liquid Effluents l

l l

Continuous Mode:

l Batch Mode

=l

'l Nuclides Released i Unit I-3rd otr i 4th Qtr l 3rd Qtr' 1 4th-Otr

-l-None Released This Period v

~ - ~

~

-s Page _8L u.

3 EFFLUENT-AND-WASTE DISPOSAL SEMIANNUAL' REPORT Period : Jul - Dec L1991 t

Table 3 Solid Waste and Irradiated Fu'el: Shipments

-A.

Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) 1: 1.

Type of Waste l

Units i

6-month (Est..Totall r

-l l

l.

Period 1 Error, % 1 "l

a. Spent resins, filter sludges, l Cu. Meter-l 7.34E+01 l-1 l=

evaporator bottoms, etc.

I Ci-l 9.95E+02 l 3.70E+01 l_

'l.

b.

Dry compressible waste, 1 Cu. Meter 1 6.82E+01 I

. :l contaminated equipment, etc.

I Ci l 4.26E+01 I 3.50E+01 l l

l c.

Irradiated components, 1 Cu. Meter 1 0 00E+00.l l

_l control rods, etc.

I Ci-1 0.00E+00 l=0.00E+01 l lt d.

Other (describe) i Cu. Meter 1 0.00E+00 -l l:

I Ci-t 0.00E+00il'0.00E+01 1:

l- - 2. Estimate of major nuclide composition (by type of waste) l l

1 Type A I

Type B 1

Type C-l' Type-D 1.

I Nuclide i

percent i percent I percent I percent =l

" ~ ~

l H-3 l 1.21E-02 1 6.60E+00 l l

l l

-C-14 l-2.48E-01 1 3.45E-02 I

(

l

'l lCr-51 l.2.08E-01 l l

l

_- l _

.l__

Mn-54 l 5.60E+00 l 4.13E+00 1

l_

l l-Fe-55 I 2.94E+01 1 2.40E+01 l l

l I

Co-58 l 5.24E-01'l 1.04E-01 1 I

i

. 1 Fe-59 l 1.89E-01 l 1

-l

[

t L.I Co-60 l 3.07E+01 l 4.26E+01 l l

l Ll' Ni-63 l 1.52E-01 l 2.41E-01 l I

i l

Zn-65 1 2.98E+01 l 1.68E+01 l l

l l~

Sr-89 1 3.18E-01~ 1;9.20E-01 1 I

I l.

Sr-90 1 3.42E-02-l 1.93E-01 1

l-1

'l1

.Tc-99 l 6.81E-05 l 1.12E-05 l l

l-

.l I-129 l 1.34E-04 !.1.91E-04Jl l-

-l

-l:

-I-131 l 4.17E-01 1 l'

I

(-

1l Cs-134 1 7.51E-02--l-1.87E-01 l l

.l:

_l-Cs-137 l 2,13E+00 1 4.07E+00 1

_1

_l_

l

_Ba-140 l 1.72E-01 l __

l l

l I

_La-140 l 5.24E-02 l l

l.

.)

l-

'Ce-141 1 2.69E-02 l 1

1 l

~l*

Pu-238 l 2.56E-04 l 1.15E-02-l-l-

-l

.. l

Pu-239 l'1.36E-04.l 6.53E-03 l-1 I

l:

Am-241 1 3.22E-04 l 4.96E-03'l I

1.

-l:

- Pu-241 l 1.53E-02 jf4.'44E-02_l l

_l

-l-Cm-242 l 2.56E-04 l 1.65E-02 I i

l-

.l

Pu-2 4 2 l 1.77E-08 l'1.46E-04 l l

l

~l

_Cm-243

-l' 7.05E-04 1 2.46E-03:1-

_I l

l' I

J I:

1-l

._.,.y_

I

+

^

~Page

.9-

)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

Period : Jul - Dec 1991 Table 3 Solid Waste and Irradiated Fuel Shipments-

.3.' Solid waste disposal

- l-Number of I Mode of I

-Destination

_l.

l Shipments i Transportation l l

l 7

l Truck-1 Chem-Nuc Inc., Barnwell, SC.

i l-5 1

Truck i

US_ Ecology, Richland,11A.

-]:

_l" 3

i Railway i

US Ecology,

_Richland, WA.

-[J l

24 l

Truck i

US Ecology, Beatty, NV.

-- l

'l!

l I

I i

B.

Irradiated Fuel Shipments

1. Disposition l Number of l Mode of I

Destination l.

l' Shipments l-Transportation l l

None This Period C.

Shipping Container and Solidification Method

~l-No.

I Volume l Activity l-Type of l-Container l_ Solidification l-l-

I M3 l

Ci I

Waste 1

Code I

Code l-

~l 91-63 1 5.61E+00 l-7.54E+01 l

_A-

.l A.

l

.D

_l

-l 91-66-l 2.00E+01 1 1.51E+00 1-A l

L l

D l:

l~91-69-l 5.83E+00 l 5.42E+01 l

'A' l.

A l-D l

l 91-74 1 5.83E+00-l-5.88E+01 l A

I

-A-l D

'l:

ll 91-75 1 5.83E+00 [ 4.53E+01 1 A

l A-l D

-l.

1

.l-91-76 l 3.41E+00 l 3.05E+02 l A

l At i

D l

9 A

l A

l D

l 6

l l 91-77 1 3.41E+00 l 2.39E+02 _l ~

A l-A_

l D

l l

91-79--I 5.83E+00 l 9.26E+01 l L-lJ91-81 l

l 5.83E+00 1.6.60E+01 l A

l-A l

D -

l lL91-84 l 5.83E+00 l 3.92E+01 l

.A 1

A I

D l-l 91-88~1 5.83E+00 l 1.76E+01: 1 A

l A.

l

.D I

d

-l 91-9011.3.81E+01 1 1.67E+00-l B

l' L.

I N

l.

17

-l 91-91_l 5.84E+00 l 3.45E+01 1 B

i

A' i

N

l '

-lD91-92 l 9.09E+00 l 3.80E-0111 B

.I L"

l-N-

l-4

'l-9120a i 1.03E+00-l-1.'46E-02 l B

.I L-ll N

' l-

=h l-9120b l 3.40E-02 l 2.86E-02_l B

1 L-l N

Ll1 1

l: 9120c l 5'.66E-03 l 1.03E-03 l B'

l L

l N~

(;

3

-l 9120d [ 9.63E-02.I 1.11E-02 i B

l L

l

'N 1:

o!: nl.9120e l 1.42E-02 l_3.13E-04 [

B-

- l.

L-l N

l-I 9130a-l 1.74E+00.l ' 4.01E-02-l B

l L.

I N.

l

-l 9130b I.3.13E+00-l 8.70E-02-l B-l L

{

N l.

l '): 9130c l 6.03E-01-l 1.35E-02 l-B

-l L

l N.

l l

l 9130d i 3.40E-02 118;99E-02--l' B

-L l

.N

-l

.l 9130e l:5.95E-01 l'1.69E-02 'l B

l' L.

l N

l-P

-l 9147a I 5.01E-01 l'1.82E-02 l B

.I L

l N

l 1 9147b l 8.21E-01-l 3.18E-02 l-B i

L l

N l

l 9147c-l 9.06E-01 1-: 4.41E-02-l-B l

L j

N l.

l~9147d=l 4;30E-01 l 2.30E-02 l B

l L

l N

l.

'l l

I-1 I

I I

Page 10

+

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 C, Shipping Container and Solidification Method (Cont.)

l No, i

Volume i Activity l Type ot l Container i Solidification l l

l M3 i

Ci l

Waste i

Code i

Code 1

l 9147e 1 4.53E-01 l 2.22E-02 l B

i L

I N

l i 9147f I 1.13E-01 1 2.09E-01 i B

l L

l N

1 l 9157a I 4.76E-01 l 1.06E-02 l B

l L

I N

l 1 9157b i 9.74E-01 1 3.13E-02 l B

1 L

I N

1 1 9157c l 3.60E-01 1 1.40E-02 l B

i L

N I

1 9157d i 5.58E-01 l 1.43E-02 i B

l L

l N

l

[ 9157e l 5.07E-01 l 1.77E-02 I B

i L

I N

l 1 9157f l 6.80E-02 1 1.43E+00 l B

l L

1 N

1 l 91579 l 3.85E-01 l 9.31E-03 I B

l L

l N

1 l 9178a 1 9.63E-01 l 8.56E-03 i B

l L

1 N

I l 9178b l 4.33E-01 1 3.87E+00 l B

i L

I N

I I

I I

I I

I I

Container Codes :

Solidification Codes :

L - LSA C - Cement A - Type A U - Urea Formaldehyde B - Type B D - Dewatering O - Large Quantity N - Not Applicalble 1

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