6285 U-003-307 . I 7

PENNAK, A.F., FEED MATERIALS PRODUCTION CENTER

REFERENCE IN O U I RI) RADIOACTIVE WASTE MANAGMENT PLAN; - (USED AS A

J

06/20/73

NLCO-I 100 NLO DOE-FN 50 REPORT

FEED MATERIALS PRODUCTION CENTER

RADIOACTIVE WASTE MANAGEMENT PLAN

P r e p a r e d by

A. F. Pennak 7

APPROVED

NATIONAL LEAD COMPANY OF OHIO P. 0. Box 3 9 1 5 8

C i n c i n n a t i , Ohio 45239

C o n t r a c t No. AT- ( 3 0 - 1 ) - 1 1 5 6

R e v f s e d : June 20, 1 9 7 3

UNITED STATES ATOMIC ENERGY COMMISSION CINCINNATI AREA

000001

6285

TABLE OF CONTENTS

Page No.

d u c t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . 1 I 1.0 Program Administration . . . . . . . . . . . . . . . . . . . 1

1.1 S i t e . . . . . . . . . . . . . . . . . . . . . . . . 1.3 AEC Contractors . . . . . . . . . . . . . . . . . . 1.2 Responsible AEC Area Office . . . . . . . . . . . . 1 . 4 Responsible AEC S t a f f Member. . . . . . . . . . . . 1 . 5 Funding o f Waste Management A c t i v i t i e s . . . . . . .

3 2.0 Description of Waste Generating Processes. . . . . . . . 2.1 Brief Description of Process. . . . . . . . . . . . 3

3 . 0 Waste Management F a c i l i t i e s . . . . . . . . . . . . . . . 5 3 . 1 I d e n t i f i c a t i o n and Location of F a c i l i t i e s . . . . . 3 . 2 Description o f Waste Treatment F a c i l i t i e s . . . . .

3 . 2 . 1 Solid Wastes . . . . . . . . . . . . . . . . 3 . 2 . 2 Liquid Wastes. . . . . . . . . . . . . . . .

5 5

9 9

3 . 3 Waste Storage F a c i l i t i e s . . . . . . . . . . . . . . 18 3.3.1 K-65 and Metal Oxide Tanks . . . . . . . . . 18 3.3.2 Chemical Waste Pits. . . . . . . . . . . . . 1 9

3.4 Eff luent Control Systems. . . . . . . . . . . . . . 21 3.4.1 Liquid Waste Control . . . . . . . . . . . . 21 3.4.2 Airborne Radioactive Wastes. . . . . . . . . 3 2

3 . 5 S i t e Administrative Limits for Radioactivity 33 h E f f l u e n t s . . . . . . . . . . . . . . . . . . .

4.0 Radioactive Wastes Stored. . . . . . . . . . . . . . . . 36 4.1 High-level Waste. . . . . . . . . . . . . . . . . . 36 4.2 Solid Radioactive Waste . . . . . . . . . . . . . . 36 4.3 Other Radioactive Wastes. . . . . . . . . . . . . . 40

4.3.1 K-65Tanks. . . . . . . . . . . . . . . . . 40 4.3.2 Metal Oxide Tanks. . . . . . . . . . . . . . 4 1 4.3.3 Wet Chemical Waste P i t s . . . . . . . . . . . 4 1

TABLE OF CONTENTS (Cont'd)

5.0 Plans and Budget Projections . . . . . . . . . . . . 5 . 1 Interim Storage of High-level Liquid Waste

Generated by AEC Reprocessing Plants . . . . . 5 . 2 Long-Term Storage of High-level Liquid Waste. . 5 . 3 Management of Low-Level Liquid Waste, . . . . .

5 . 3 . 1 Summary and Milestone Charts . . . . . . 5 . 3 . 2 Accomplishments in FY 1974 . . . . . . . 5 . 3 . 3 Program and Accomplishments in FY 1975 . 5.3.4 Program and Accomplishments, FY 1976 -

1980. . . . . . . , . . . . . . . . . . . 5 . 4 Management of S o l i d Waste Contaminated

with Radioactivity . . . . . . . . . . . . . . 5 . 5 Management of Airborne Radioactive Waste. . . . 5.6 Summary Tabulation of Budget Projections for

Radioactive Waste Management A c t i v i t i e s , . . , 6.0 Description of Decontamination and Decommissioning .

6 . 1 Radioactively Contaminated F a c i l i t i e s . . . . . 6.2 Degree of Radioactive Contamination . . . . . . 6.3 Recommendations for Conversion, . . . . . . . . 6.4 Other Radioactive Materials . . . . . . . . . .

Page NO.

43

43

43

43

43 47 49

50

50

5 1

52

53

53 54 54 54

-

Bibliography . . . , . . . . . . . e . . , . . . . .e. . . . 56

6285 . TABLE OF CONTENTS (Cont'd)

F i g . 1 2

3

4

5

6

7

8

9

Table I

Page NO . FIGURES AND TABLES

. Area Map Showing Relative Locations . . . . . . . . . 2

. Schematic Diagram of the FMPC Process . . . . . . . . 6 Perimeter Air Sampler Locations . . . . . . . . . . 7

. Production Area Waste Treatment Locations . . . . . . 8

. Liquid Waste Flow Diagram . . . . . . . . . . . . . . 10

. General Sump Flow Diagram . . . . . . . . . . . . . . 1 3

. Test Well Locations . . . . . . . . . . . . . . . . . 22

. Water Sampling Locations . . . . . . . . . . . . .' . 30

. Waste Water Q u a l i t y Report . . . . . . . . . . . . . 3 1

. AEC Solid Waste Management Questionnaire . . . . . . 38 Liquid Wastes . . . . . . . . . . . . . . . . . . . . 48

. Waste Treatment and Storage Locations

. Target Date for Management of Radioactive

......

O O O U ~ 4

. . . . .......... ...., 7 ._-.- ---.--- _I__- -.. ..

INTRODUCTION

This document presents the s i t e waste management plan of the Feed

Materials Production Center. It s e t s f o r t h the s i t e plans for con-

t r o l l i n g releases of radioactivity and ensuring the safe storage of

radioactive wastes generated by past, present and future s i t e

operations.

1.0 Program Administration

1.1 S i t e

The Feed Materials Production Center (FMPC) is located

near Fernald in the Great M i a m i River Valley in south-

western Ohio, approximately 10 miles northwest of

Cinc inna ti .

1.2

The plant proper occupies 136 acres in the center of a

1,050 acre s i t e .

production plant area, i s located within Hamilton County,

Ohio, b u t approximately 200 acres are i n southern Butler

County. The v i l l a g e s of Fernald, New Baltimore, Ross,

and Shandon are a l l located w i t h i n a few miles of the

plant.

Most of the s i t e , including a l l of the

Hamilton, Ohio is approximately 10 miles northeast.

Figure 1 shows the r e l a t i v e location of these populated

areas t o the E'MPC.

Responsible AEC Area Office

Oak Ridge Operations Office

FIGURE 1 Area Map Showing Relative Locations

- 2 -

DWG. 15-61

CINCINNATI

1 . 4

1.5

AEC Contractors

The National Lead

AT- (30-1)-1156 i s

Company of Ohio under Contract No.

responsible for a l l operations,

including waste management a c t i v i t i e s , a t FMPC.

Responsible AEC S t a f f Meniber

J. J. Schreiber, Chief, Waste Management Branch, ORO

Funding of Waste Management A c t i v i t i e s

Waste management a c t i v i t i e s a t FMPC are c o l l e c t i v e l y

funded w i t h a l l other operations under the control of

the Uranium Enrichment Operations Division, Oak Ridge

Operations O f f i c e .

2 . 0 Description of Waste Generating Processes

2.1 Brief Description of Process

The primary function of the FMPC as designed was the

production of metal l ic uranium fuel cores for the AEC's

production reactors . Production requirements i n recent years have brought about many changes, and the principal

products a t present are uranium trioxide a s feed for the

gaseous diffusion plants and depleted uranium metal f u e l

cores. Low-enriched uranium ingots and thorium compounds

are a l s o produced, but on a much smaller s c a l e .

4.

The feed materials are uranium ore concentrates and

various uranium recycle compounds and metals. Depleted

uranium tetrafluoride i s shipped i n t o FMPC for the

production of the metal f u e l cores.

The basic processes include n i t r i c a c i d digestion of the

concentrates and recycle compounds, organic phase extraction

of the uranyl nitrate, scrubbing and aqueous phase

re-extraction cf the purified uranyl n i t r a t e , and denitration

of the uranyl nitrate to uranium trioxide.

Depleted uranium tetrafluoride feed stock i s reduced t o

uranium metal by a thermite reaction with ground metal l ic

magnesium. The s l a g generated in the reaction i s processed

to reduce the uranium and magnesium content and a portion

thereafter is used for refractory l i n e r i n the thermite

reduction vessels. The remainder of the processed depleted

s l a g i s discarded d i r e c t l y as a s o l i d waste t o a storage p i t .

The primary uranium i s remelted with recycle uranium metal

in vacuum i d u c t i o n furnaces for p u r i f i c a t i o n and a l l o y i n g .

The resultant uranium ingots are extruded o f f s i t e t o various

hollow tube geometries which, upon return t o FMPC, are c u t

t o desired s i z e s and machined t o s p e c i f i c a t i o n tolerances

and finish.

F a c i l i t i e s e x i s t for the r o l l i n g o f the ingots t o various

bar s i z e s preparatory t o core machining, but these are not

i n a c t i v e use.

6285 5. Available, b u t used sparingly, p r i n c i p a l l y i n production of

low-enriched uranium products, i s a p l a n t for conversion

of the uranium oxide t o uranium t e t r a f l u o r i d e .

mere are a l s o f a c i l i t i e s for tihe sampling of concentrates

and for the hydrometallurgical recovery of uranium from

various process residues, These f a c i l i t i e s , too, have

limited use under present operations and schedules.

A flow chart of the FMPC production processes and the major

waste streams is shown in Figure 2. From the flow chart

it i s obvious t h a t production program changes a t FMFT can

and do influence process waste streams, changing both the

composition and tihe characterist ics of the streams. Waste

Q 0

management f a c i l i % i e s must be and are f l e x i b l e , capable of

responding quickly and e a s i l y to changing needs. 1 8

I 3.0 Waste Manaqement F a c i l i t i e s 3.1 Identif ication and Location of F a c i l i t i e s

The location sf waste treatment and waste storage f a c i l i t i e s

a t FMPC i s shown in Figure 3. Figure 4 i s a plan of the

production area, an aid in locating various production

plants and waa&e treatment f a c i l i t i e s w i t h i n the area.

3.2 DescriPtisn of Waste Treatment F a c i l i t i e s

Solid and l i q u i d radioactive wastes are generated a t FMPC.

The f a c i l i t i e s for handling each type of waste are discussed

separately hereafter,

NLO Nuclear Material Management Manual, Sect IV - "Plant Processes and Flow Sheets"

NLO Accounting Manual, Sect, 304-04

000G09

6285

) WOY f\

- 6 -

I

c I - CRUDE SOLVENT

INUWOUAL PLANT SUMP

SOLVENT RECOVERY EXTRACTION

RAFFINATE TAIL GAS

(NO. t H , O ) F

NH

LEACHED MgF? CAKE SLURRY

>TO WET -d U CHEMKAL

w3

1 L -___--- - r--------

ANHYDROUS HF

HF RECOVERY

L ---- I

METAL REDUCTION SCRAP RECOVERY

TO DRY CHEMICAL

RESIDUES

REMELT METAL

FINIWED FUEL CORES BILLETS TO REACTOR SITES

FIGURE 2 Schematic Diagram of the FMPC Process

- - - - AIR SAMPLING STA. NO. 10 ---\ - -

CHEMICAL WASTE PITS

L

t

I T

i r- - I

I

AIR SAMPLING STA. NO. 3

O1 I

I

SEWAGE

TO RIVER

Id ' AIR SAMPLING. STA. NO. 4

TO RIVER

FIGURE 3 Waste Treatment, Storage Locations, and Perimeter Air Sampling Locations

I

' 0 1

1 1 I i i

i I "i 3 I 1

. . - 8 -

e-.-.- _.-.-

B

I ! ! i !

I I

i

I

I I

FIGURE 4 Production Area Waste Treatment Locations

000012

. a . 3 . 2 . 1 Solid Wastes

No f a c i l i t i e s e x i s t a t FMPC for treatment of s o l i d

radioactive wastes as such.

a t FMPC are discarded without treatment t o a storage

p i t .

of these wastes is regarded as insoluble, and below

economic recovery levels.

feasible without f i r e hazard, water pollution, or

Solid wastes generated

The uranium or thorium content or contamination

Direct p i t storage i s

other incidental problems . Contaminated combustible residues , sewage sludge ,

graphite, and o i l s are treated as process residues

and incinerated i n various f a c i l i t i e s .

values are recovered from the generated ash i n the

Recovery Plant or the Refinery.

The uranium

3 . 2 . 2 Liquid Wastes

Liquid wastes are generated t o some degree i n every

operation a t FMPC.

waste stream are: process waste, sanitary sewage, and

storm water. The system t o control the discharge of

radioactive wastes t o the environment through any of

the branches of the l iquid waste system i s shown i n

The three branches of the l iquid

3 . 2 . 2 . 1 Process waste

3 . 2 . 2 . 1 . 1 Plant Treatment F a c i l i t i e s

A l l of the major process areas

have individual treatment f a c i l i t i e s

REFINERY - -H

GREEN SALT (PLANT 4)

METAL REDUCTION & CASTING

(PLANT 5) il METAL FABRICATION

(PLANT 6) --h

RECOVERY (PLANT a)

(PLANT 9) 6 PILOT PLANT LABORATORY

BOILER PLANT

1

c--

1 GENERAL ~ - p SUMP

:PPLER r+

SAMPLER - SANITARY SEWAGE

FROM PLANTS

TREATMENT

P.2 I ' IMANHO/LE 175 I

I /

f

4 DIVERSION VALVE

t v 1- SAMPLER i o e GREAT MIAMI RIVER

STORM WATER FLOW I TO RIVER

I I= STORM WATER

L I F T STA.

OVERFLOW

WATER TREATMENT I PLANT

LEGEND: 1 -SLAG LEACH SLURRY 2-HEAT-TREAT QUENCH WATER 3- ZIRNLO SLURRY 4-GENERAL PROCESS WASTES

TREATMENT SUMP COLLECTION SUMP

0- SAMPLER

TO PADDY'S RUN

CREEK

FIGURE 5 Liquid Waste Flow Diagram

- . . -. 000014

~ _.. ._-- _- - .- -____ __.__ .- - -.I_ - .

ii

I 1 I 1 1 1

1 1

capable of pretreating the

l iquid wastes that are peculiar

t o that particular process step,

v i r t u a l l y a l l of the radioactive

materials in the wastes are

removed i n these f a c i l i t i e s .

Generally these plant treatment

f a c i l i t i e s are simple instal-

lations which provide equipment

and tankage t o c o l l e c t waste

liquors, adjust the pH for

precipitation of uranium values,

and t o f i l t e r the resultant slurry,

Where o i l s are present, preliminary

1 1 1 il

000015

steps are taken t o break out the

o i l s by a c i d i f i c a t i o n and decant

before neutralization and pre-

c i p i t a t i o n , . The f i l t e r cake con-

taining the radioactive materials

is sent to the Refinery or the

Recovery Plant as a process residue,

After sampling and analysis i s

performed t o ascertain that uranium

content is w i t h i n pre-set allowable

discard l i m i t s , the f i l t r a t e i s

pumped t o the General Sump.

I L . When thorium is processed i n the

P i l o t Plant, a f t e r neutralization

the waste liquors are treated with

barium carbonate and aluminum

s u l f a t e before f i l t r a t i o n i n order

t o reduce 228Ra a c t i v i t y in the - f i l t r a t e . Because of i t s higher

228Ra content, raf f inate from

the thorium extraction process i s

' segregated from other thorium

l iquid wastes and subjected t o a

double BaC03-A12(S04)3 treatment

and f i l t r a t i o n before the resultant

f i l t r a t e i s pumped t o the General

sump . 3 . 2 . 2 . 1 . 2 General Sump

A simplified flow diagram of the

General Sump is shown in Figure 6.

Physically the General Sump i s a

c o l l e c t i o n of v e r t i c a l tanks of

various s i z e s , pumps, piping, and

valves established on a controlled

pad. It i s designed to f a c i l i t a t e

the storage and transfer of l iquid

wastes w i t h i n the tankage complex

and the discharge therefrom, and

o o o o i.6 . . . . . . .

J'

c a W

K P

I- z F

6286 - 3 - 13 -

L I

t, a a

LL

14.

the addition of various reagents

and coagulation aids. Provisions

have been made for ease of sampling,

both grab and continuous, Controls

are simple b u t adequate. The pad

i s equipped with i t s own sump and

drainage trenches t o handle any

leaks or accidental s p i l l s . /’

The process wastes from the various

production plants and service

f a c i l i t i e s are received a t the

General Sump, checked for SS content,

and segregated or s e l e c t i v e l y com-

bined as required. I f a certain

waste exceeds discard specifications

it i s sent t o the Recovery Plant

(Plant 8 ) or the Refinery for

recovery of SS values.

Thorium wastes are segregated, again

co-precipitated w i t h barium carbonate

and aluminum s u l f a t e t o further

reduce 228Ra a c t i v i t y , and then

pumped t o the Wet Chemical Waste

P i t ( P i t 5 ) .

O O O G 1 8

1 5 .

A l l acidic uranium-bearing wastes

are adjusted for pH w i t h calcium

oxide t o obtain a m a x i m u m pre-

c i p i t a t i o n of radioactive material . Thereafter, these wastes are

similarly given a Bas04 treatment,

b u t for the reduction of 226Ra

a c t i v i t y , and pumped t o P i t 5.

Other wastes are s e t t l e d and

decanted in successive steps prior

t o discharge of the supernatant

liquor t o the r i v e r . The s e t t l e d

sludges are a l s o transferred t o

P i t 5.

A l l l iquid wastes, before discharge

from the General Sump t o the Wet

Chemical Waste P i t or t o the Miami

r i v e r are sampled. The samples

are analyzed t o ascertain con-

centrations and t o t a l content of

radioactive materials.

3 . 2 . 2 . 1 . 3 Wet Chemical waste P i t

The Wet Chemical Waste P i t ( P i t 5 )

i s a large rubber l ined s e t t l i n g

basin located northwest of the

Production area. It is roughly

rectangular i n shape, w i t h a surface

1 P 1 1 0 1

d 1 1 d

area of approximately 3 . 6 acres . Capacity i s approximately 21,000,000

gallons. 3

A l l l i q u i d wastes discharged t o

the wet Chemical Waste P i t enter

a t the eastern or smaller end of

the basin. The huge volume of the

p i t , i n addition t o providing

s e t t l i n g time for sol ids i n the

e f f l u e n t as received, a l s o allows

time for slow interreaction of

e f f l u e n t s and resultant additional

precipitation of radioactive s o l i d s .

The s o l i d s , which contain almost

a l l of the uranium, thorium, and

r a d i o a c t i v i t y remaining i n the

waste, s e t t l e out and remain in

the p i t for long term storage.

The supernatant liquor, p r a c t i c a l l y

s o l i d s free, overflows through an

e f f l u e n t control tower near the

western end of the p i t into a

c learwell from which it i s pumped

t o the M i a m i River.

The major portion of FMPC's l iquid

process wastes i s routed through

NLO Drawing No. 2100-X-5500-G-00196

d 000020

'0 1

3 . 2 . 2 . 2

the General Sump t o the Wet Chemical

waste P i t : however, there are three

process waste streams which are

routed d i r e c t l y t o the P i t . They

are: Zirnlo Slurry, Heat-Treat

Quench Water, and Slag Leach Slurry.

The f i r s t two streams are produced

i n very minor quantities. The

t h i r d i s not generated under

present production programs . Radioactivity in a l l three streams

i s e f f e c t i v e l y controlled by

s e t t l i n g i n the P i t without

processing a t the General Sump,

Sanitary Sewage

The sanitary waste c o l l e c t i o n and treatment

system i s a completely separate system from

the process waste system. These wastes by

virtue of t h e i r natural separation from the

a c t u a l production e f f o r t do not nurmally

contain s i g n i f i c a n t amounts of uranium.

However, uranium contamination does occur

through the plant laundry and showers,

Normal treatment of the sanitary sewage in

the Sewage Treatment Plant removes , *- much of

the uranium which i s captured i n the sewage

sludge. The sludge i s incinerated and the

6285 - . 18 ,

'. I

uranium recovered from the ash in the

Recovery Plant or Refinery.

3 . 2 . 2 . 3 Storm Water

The storm water system i s b a s i c a l l y designed

t o be uranium-free: however, it i s possible

for uranium t o enter the Storm Sewer System

through accidental s p i l l s and r a i n water

washing of the plant area. No-treatment

f a c i l i t y as such i s provided for the storm

water, b u t control and recovery of uranium

washed or s p i l l e d into the Storm Sewer System

i s possible t o a major degree through diversion

f a c i l i t i e s described in Section 3 . 4. 3 . 3 Waste Storage F a c i l i t i e s

The three f a c i l i t i e s a t FMPC used for the long term storage

of wastes are the Chemical Waste P i t s , the K-65 Tanks, and

the Metal Oxide Tanks,

3 . 3 . 1 K-65 and Metal Oxide Tanks

There are two K-65 tanks and two metal oxide tanks.

These tanks are of c y l i n d r i c a l concrete construction,

80 f e e t in diameter and approximately 27 f e e t high,

The capacity of the individual tanks i s 125,000

cubic feet . The tank walls are of concrete 8 inches

thick, The walls were post-stressed w i t h high t e n s i l e

s t e e l wire and the wires protected by a 3/4 inch grout

coating. I n 1964, the two K-65 tanks were protected by

enclosing them w i t h an earth embankment.

tanks were used for the storage of Refinery residues

that resulted from the processing of pitchblende ores.

These residues or t a i l i n g s contain 226Ra. Pitchblende

ore processing a t the FMPC was discontinued in 1959;

however, the residues r e s u l t i n g from t h i s work remain

i n storage, Other similar residues were sent t o FMPC

from other s i t e s and are stored in the K-65 tanks,

The K-65

The K-65 wastes are the property of the African Metals

Corporation and are stored a t FMPC under a lease

contract which expires June 30, 1983, and which pro-

h i b i t s abandonment by the lessee.

these wastes i s included herein t o provide a complete

review of a l l radioactive wastes stored a t FMPC,

Discussion of

One of the metal oxide tanks contains similar t a i l i n g s

or residues from Refinery operations a t FMPC; however,

these residues are the r e s u l t of processing of ore

concentrates other than pitchblende and contain no

radium.

The other metal oxide tank i s empty.

These metal oxides are owned by the AEC,

3 . 3 . 2 Chemical Waste P i t s

Five chemical waste p i t s have been constructed a t FMPc.

These p i t s are identif ied by nuniber based on a chrono-

l o g i c a l sequence of t h e i r construction.

further identified as Iadrya8 or aawet" p i t s .

t i n c t i o n i s made on the b a s i s of the physical s t a t e of

the material as it i s placed i n the p i t .

They are

This dis-

If the material

. . . .

O O O G 2 3

I

L

k I

i s placed as a slurry, the p i t i s known as a wet p i t .

I f the material i s placed as a dry s o l i d , the p i t i s

known as a dry p i t .

Pits No. 1 through No. 4 vary in depth from approxi-

mately 12 f e e t t o 27 feet .

these p i t s were lined with 1 . 5 t o 2 f e e t of impervious

blue c l a y . P i t No. 5 i s 29 f e e t deep and has a rubber

medrane l i n e r .

The wall and bottoms of

When a p i t i s f i l l e d w i t h waste it i s covered w i t h

earth as soon as the contained material has stabil ized

and i s capable o f supporting the earth burden.

The following table gives a description and status

of each of the chemical waste p i t s .

P i t No. P i t Type P i t Volume (C.Y.) Status

1 Dry 40,000 F i l l e d and covered

2* D r y 1 3 8 000 F i l l e d and covered

3** Wet 226,500 F i l l e d - being covered 4 Dry 53 , 000 8077 f i l l e d 5 Wet 115,000 40% f i l l e d

* P i t No. 2 was b u i l t for a dry p i t and primarily used

as such: however, some wet materials were introduced

into this p i t j u s t prior t o the completion of P i t No. 3 .

21. 6285 - 9 * * P i t No. 3 is f i l l e d t o capacity when considered as

a wet p i t , since it i s no longer a useful s e t t l i n g

basin,

s o l i d (dry) wastes while the covering process i s being

This p i t i s being used for storage of additional

carried out.

Test wells have been d r i l l e d around the Waste Pits

t o permit monitoring of ground water in the area.

The location of these wells is shown in Figure 7 ,

Sampling of these w e l l s , performed on a monthly b a s i s ,

furnishes an indication of the condition of the p i t l iners.

Nitrates and chlorides found in well samples in amounts

s l i g h t l y higher than background tend t o indicate that

the natural c l a y l i n e r s used i n Pits No. 1 through No. 4

are not completely impervious; however, no increase i n

uranium or r a d i o a c t i v i t y has ever been detected in the

t e s t wells.

3 , 4 Eff luent Control Systems

3 - 4 . 1 Liquid Waste control

Liquid e f f l u e n t streams from FMPC are released to

the environment a t two locations. These are:

1. The conibined sewer o u t f a l l which discharges

into the Great Miami River a t a point ahnost

d i r e c t l y e a s t of the plant s i t e , This point

i s 3% r i v e r miles upstream from the v i l l a g e of

New Baltimore.

e3 PROD. WELL NO. 3 5 23 t 62.34 E 33 t 48.28 EL. 579.84'

FIGURE 7 Test Well Locations

I 1

2. The storm sewer o u t f a l l which discharges into a

branch of Paddy's Run Creek on s i t e . Paddy's Run

Creek joins the Great M i a m i River approximately 2

miles south of the FMPC s i t e and 1% r i v e r miles

downstream from New Baltimore. The flow of these

streams i s the only property t h a t influences the

dispersion of radionuclides from FMPC.

A 20-year study of the Great Miami River by the Miami

Conservancy D i s t r i c t Shows the r i v e r flow t o be as follows:

January through March - 8,000 t o 14,000 c f s (Avg. 10,000 c f s )

April through August - 600 t o 4,000 c f s (Avg. 2,000 c f s )

September through Decerrber - 100 t o 6,000 c f s (Avg. 5,000 c f s )

These flows are normally adequate t o provide very

substantial d i l u t i o n of the FMPC discharge. 'Any

unusual periods of extremely low r i v e r flow can be

compensated for by the reduction of process waste

pumping rates, with retention of the excess liquids in

the Wet Chemical Waste P i t .

Paddy's Run creek, on the other hand, i s a small stream

in which a flow generally only e x i s t s during the period

January to May.

The balance of the year it may be considered as a dry

bed stream w i t h occasional f l a s h flows of a few hours

duration following heavy rains.

'

This flow ranges from 0.2 t o 4.0 c f s .

6285 - -cp 24. To control the l i q u i d e f f l u e n t streams r e l a t i v e t o

these receiving stream conditions, a system of dis-

charge piping and a l i f t station was designed and

installed, The system is shown schematically on

Figure 5. The function o f this system i s t o combine

process waste and sanitary sewage flows, and storm

water flows t o the maximum degree possible, in a single

eff luent stream discharging t o the Great Miami River

through Manhole 175. Complete monitoring of the r i v e r

discharge i s thus possible a t one point,

The flows from the branches of the e f f l u e n t stream

may be shut o f f or modified i n quantity as desired.

Thus, w i t h knowledge of the characterist ics and

radioactive material content of each stream furnished

by a widespread sampling system, s t r i c t control can be

maintained over the e n t i r e . eff luent system.

3.4.1.1 Process Waste

The greatest potential for discharge of

radioactive materials i s through the process

waste stream, Therefore, most of the e f f o r t

to achieve control of the radionuclide dis-

charge Inthe environment through the l iquid

e f f l u e n t streams i s concentrated i n this area,

The i n i t i a l emphasis i s placed upon the m a x i m u m

removal o f the radioactive materials from

the process waste eff luent a t the generating

000028

! -

!

plant or area, Thereafter, successive

processing steps are taken t o reduce

s t i l l further the remaining radionuclides ,

The treatment steps are described i n

Section 3 . 2 . 2 . 1 .

Control of the treatment of the process waste

stream i s achieved through sampling, discussed

i n Section 3.4.4.

each treatment s t e p specify that no waste

material i s t o be released before analysis

i s received showing the waste t o be below

Operating procedures a t

pre-set discard limits . /

3.4.1.2 Storm Water

A key component of the l iquid e f f l u e n t system

i s the Storm Sewer L i f t Station. The storm

water system c o n s i s t s of a grid work o f catch

basins and connecting pipe l ines t o c o l l e c t

precipitation t h a t f a l l s in the immediate

v i c i n i t y of the manufacturing and service

f a c i l i t i e s . The Storm Sewer L i f t Station,

located near t h e s u t h e r n terminus of the

system, i s a f a c i l i t y designed t o d i v e r t and

pump t o the extent o f i t s pumping capacity

(approximately 600 g p m ) flows from the

storm sewer system t o the process waste

discharge l i n e t o the M i a m i River,

6285 26. During periods of heavy r a i n f a l l when the

capacity of the L i f t Station pumps i s

exceeded, the excess flow proceeds towards

Paddy's Run Creek. A t such times however,

the creek flow i s heavy with runoff from

other areas along i t s course.

A special diversion capacity i s provided

adjacent t o the Storm Sewer L i f t Station

for use in the event of an accidental s p i l l

or release of radioactive materials into the

storm sewer system. A valve, located in the

process waste discharge l i n e immediately

a f t e r the junction with the Storm Sewer L i f t

Station diversion discharge pipe, may be

closed and the L i f t Station pumps used t o

pump the radioactive materials t o the General

Sump or t o the Chemical Waste P i t .

for detection of such releases or s p i l l s i s

provided through the use of a pH meter

instal led i n the L i f t Station. Earlier

notice of possible releases i s obtainable

from three similar pH alarms located

s t r a t e g i c a l l y in manholes upstream i n the

Storm Sewer System from the L i f t Station.

The quantity pumped and samples of the storm

sewer e f f l u e n t during such an episode are

provided through flow meters and sampling

equipment in the L i f t Station discussed i n

Section 3.4.4.

Capability

000030 - - . - _ _ _ - - _. - - - __I-- - _- - __I_ - ---

6285 - 27 . 3 . 4 . 1 . 3 Sanitary Sewaqe

Effluent from the Sanitary Sewage Plant

joins the other e f f l u e n t streams a t Manhole 1 7 5 .

Since the radionuclide concentrations in the

sanitary sewage eff luent are of a very

minimal nature, no sampling and analysis

s p e c i f i c a l l y for radionuclides i s performed.

Adequate sampling and analysis is of course

performed for control of normal sanitary

sewage plant operations.

3.4.1.4 Sampling and Analysis

To e f f e c t i v e l y control the entire e f f o r t ,

repeated sampling and sample analysis is

employed a t each treatment step or junction

of l iquid waste streams. Before discharge

of the treated e f f l u e n t from the generating

plant t o the General Sump, samples must be

taken and analyzed t o establish that the

e f f l u e n t meets the pre-set discard. l i m i t s . The process waste effluents are again sampled

and checked on r e c e i p t a t the General Sump.

The sampling and analysis is repeated before

discharge of the e f f l u e n t from the General

Sump and again upon discharge from the Cleai-well

a t the Chemical Waste P i t .

Samples of other waste streams are similarly

taken and analyzed before the wastes are sent

d i r e c t l y to the Chemical Waste P i t ,

28.

The Storm Sewer L i f t Station i s equipped

with recording f lowmeters and automatic

proportional samplers t o provide data on

storm sewer system flow. One u n i t measures

and samples the flow being pumped t o the

M i a m i River through Manhole 175. The second

u n i t i s automatically activated whenever

there i s an overflow t o Paddy's Run Creek,

and provides samples and measurement of

these flows. From the sample analyses and

flow data, the losses of radioactive materials

through the storm sewer system can be controlled

and measured.

Manhole 1 7 5 - i s the f i n a l junction point of

the major waste streams. This f a c i l i t y is

equipped with a recording pH meter, a flow-

meter u t i l i z i n g a Parshall flume, a temperature

recorder, and an automatic proportional sampler.

A t t h i s location, the discharge flow t o the

M i a m i River i s continuously measured and a

composite sample c o l l e c t e d and analyzed on a

d a i l y basis. The effectiveness of the

entire eff luent control program i s demonstrated

i n the analyses of the Manhole 1 7 5 samples.

I n addition t o t h i s on-site monitoring, an

of f -s i te monitoring program i s conducted t o

0000.32

determine t h e , e f f e c t of FMPC releases on the

quality of the M i a m i River.

locations t h a t are used i n implementing t h i s

program are shown in Figure 8. Point A i s

located upstream from the point of the FMPC

discharge into the M i a m i River. Weekly

samples are taken& t h i s point t o give an

I

The sampling

indication of the q u a l i t y of the water

approaching the FMPC discharge.

the continuous sampler a t Manhole 1 7 5 .

Point C i s located downstream from the FMPC

discharge point.

withdrawn from the r i v e r a t this point and

analyzed no l e s s frequently than once a week.

A sample comparison provides an e f f e c t i v e

means o f noting the e f f e c t of FMPC discharge

on the r i v e r .

Point B is

A continuous sample i s

A l l data compiled with respect t o discharge

of radionuclides from Manhole 1 7 5 t o the M i a m i

River i s tabulated as p a r t of the Waste Water

Q u a l i t y Report, issued each month. The Report

form i s shown on Figure 9.

3.4.1 .5 Testinq Procedures

All instrumentation, alarms, and sampling

equipment are routinely tested, as dictated

by the requirements of the particular equip-

ment item.

BUTLER HAMILTOH

6285 - 4 - 30-

co. co. -

FIGURE 8 Water Sampling Locations

0000 3 4

FIGURE 9 Waste Water Quality Report 000035

6285 - -s

v v v v \

FIGURE 9 (Continued) 000036

6285 -31b-

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FIGURE 9 (Continued) . - _-._ . ._ 000G37 - - -

3.4.2 Airborne Radioactive Wastes

'a 1 i 1

B im n

a

A l l radioactive dusts, fumes, mists, e t c , emanating

from production processes a t FMPC are vented t o the

atmosphere only a f t e r passing through c o l l e c t i o n

devices such as bag c o l l e c t o r s , e l e c t r o s t a t i c pre-

c i p i t a t o r s , and scrubbing towers. I n general, bag-

type c o l l e c t o r s are used on operations producing

dry dusts, scrubbers are used on furnace off-gases,

and e l e c t r o s t a t i c precipitators are used t o control

releases from machining operations.

are used t o reduce N% content from Refinery stack

gases.

from the off-gas of the hydrofluorination process,

Each i n s t a l l a t i o n i s s p e c i a l l y designed for the

operation it serves,

Water scrubbers

Similar scrubbing i s applied t o remove HF

Cpntinuous stack samplers monitor the performance

of the dry dust col lectors and precipitators and

measure the quantities of material not being c o l l e c t e d

by the system.

tinuously sampling wet exhaust gases, the stack

e f f l u e n t from scrubbers i s periodical ly grab-

sampled t o evaluate c o l l e c t i o n e f f i c i e n c i e s .

Since no method is known for con-

I n addition t o these controls, an environmental a i r

sampling program i s employed t o determine the amount

of radioactive material in the a i r surrounding the

project . Six permanent a i r sampling stations are

.--I-- _ _ _ _ --.-- -. - . . - - _.___-._-__. ..-_. -.

33. 6285

1. li

operated around the perimeter of FMPC, located as

shown on Figure 3 . These samplers are in continuous

operation.

each week. Results show t h a t the average concen-

tration of radioactive materials i n the a i r surrounding

FMPC i s l e s s than 1% of the MPC for uncontrolled areas.

The samples are c o l l e c t e d and analyzed

3.5 S i t e Administrative Limits for Radioactivity i n Effluents

Numerical administrative limits for a l l radioactive com-

ponents of l iquid and gaseous e f f l u e n t s have not been

established for this s i t e . Process l imits have been

established for uranium and thorium in discard liquors

and the policy has been t o keep r a d i o a c t i v i t y in eff luents

t o the minimum achievable.

While the e f f o r t expended t o meet this goal is dependent

on economic and technical considerations, it has been

established t h a t no radionuclide which i s present in the

eff luent i s t o exceed the concentration guide in Table I1

of AEC Appendix 0524.

measurement of the radioactivity i s made a t the point the

eff luent passes beyond the s i t e boundary.

For compliance w i t h t h i s requirement,

The major components of radioactivity i n our e f f l u e n t a i r

and water and t h e i r concentration guides are given in the

following table :

I 3 D t

6285 - - 34- Radionuclide Concentration Guide - uc/ml

A i r Water - N a t u r a l Uranium 3 x 10'12 . 2 10-5

Thorium 234 1 10-9 2 10-5

Natural Thorium 1 x 10'12 1 x 10-6

R a d i u m 226 2 x 10'12 3 x 10-8

Radium 228

*Technetium 99

*Ruthenium 106

1 x 10-12 3 x 10'8

*Technetium and ruthenium occur only when recycled uranium

o r thorium w h i c h has been i n nuclear reactors is processed.

They are present then only i n l i qu id eff luents and are not

found i n s ign i f icant concentrations i n a i r .

Discard limits for discharge of uranium and thorium i n l iqu id

w a s t e s and t h e i r radiometric equivalents from individual

processing areas are :

uranium

Thorium

20 mg/l

50 mg/l

6 x 10-6 yc/ml

5.5 x 10-6 pc/ml

The discard l i m i t w i t h respect t o allowable quantity of

u r a n i G in the ef f luent is more r e s t r i c t ive than the

concentration guide.

greater than the concentration guide, thorium discard

l iquors are about 5% of the t o t a l process waste.

d i lu t ion of approximately 20 i n the thorium concentration i s

achieved merely by mixing these wastes.

While the thorium discard l i m i t is

Thus a

Additional treatment

0285 - 35.

. . -

of a l l process waste a f t e r discard but pr ior t o discharge

f u r t h e r reduces the concentration of both uranium and

thorium i n the eff luent discharged from the s i t e .

Use of the concentration guides for boundary limits is

very conservative w i t h respect t o rad ia t ion protection of

the public.

River.

the discharge concentrations. An added protection factor

is that no drinking water is taken from this stream below

the o u t f a l l before it discharges into the Ohio River.

Liquid wastes are discharged in to the M i a m i

This stream provides a minimum di lu t ion of 300 for

There

is very limited use of the stream fo r recreat ional purposes.

Also, in consideration of airborne radioact ivi ty , the plant

is located i n a r u r a l area.

hundred f e e t from the plant boundary. The t o t a l population

of the area w i t h i n a 3.0 mile radius of the plant , i n w h i c h

there are four small communities, is estimated t o be about

four thousand people.

miles or more from the plant.

The nearest houses are a few

Larger population centers are ten

These practices for limiting the concentrations of radio-

nuclides i n eff luents also enable us t o meet State standards.

36.

4.0 Radioactive wastes Stored

The radionuclides encountered a t FMPC are b a s i c a l l y uranium,

thorium, and the radioactive daughters of each.

small quantities of recycle compounds does introduce other radio-

nuclides such as plutonium, neptunium, ruthenium, technetium, etc.

Technetium and ruthenium are present in FMPC e f f l u e n t in detectable

The processing of

quantities but always below AEX concentration guides for water in

uncontrolled areas.

only trace quantities and therefore do not cause any problems or

require any additional treatment i n the handling of wastes,

The other TRU radionuclides are present in

4.1

4-2

Hiqh-level Waste

No high l e v e l wastes are stored a t FMPC.

Solid Radioactive Waste

There are four principal types of s o l i d wastes generated

a t the present time a t FMPC which are discarded without

treatment to Chemical Pit No. 4. They are:

(a) Depleted Uranium Residues - Process residues of depleted uranium (0.142 - 0.40"A 235W) t h a t are not suitable for remelt or containing uranium values i n

amounts not economical for recovery,

(b) Low Grade Thorium Residues - Process residues t h a t similarly cannot be economically processed for

recovery of thorium values.

000042

6385 - 37. contaminated Ceramics - S l i g h t l y contaminated refractories from production e l e c t r i c furnaces

discarded during repairs,

General Refuse - Various types of trash, generally noncombustible, which have become s l i g h t l y con-

taminated through incidental contact w i t h radioactive

substances.

Although the process is not in use a t the present time,

the hydrometallurgical system in the Recovery Plant produces

a uranium-barren f i l t e r cake as a by-product.

this waste i s a l s o discarded d i r e c t l y t o the storage pit.

This waste from past years forms a substantial proportion

of the s o l i d waste stored a t FMPC.

When generated,

Before discard a l l of these wastes are reviewed t o determine

t h a t they (1) are insoluble, ( 2 ) do not present a f i r e hazard, and ( 3 ) do not include organic l iquids which possibly present

a water pollution problem.

Existing s o l i d waste storage and estimated future generation

is tabulated i n Table I, representing Part I of the AEC

Solid Waste Management Questionnaire,

Solid Waste Management Questionnaire i s not included a s

not being applicable t o FMPC.

P a r t I1 of the AEC

000043

6285 38.

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I

4.3 Other Radioactive Wastes

The major radioactive wastes other than s o l i d wastes stored

or accumulated a t FMPC are the residues of ore concentrate

processing. Most of these residues were originally discharged

as a l iquid waste, and the materials stored are the s e t t l e d

s o l i d s contained therein. These wastes are stored i n the

K-65 tanks, the metal oxide tanks, and the wet chemical waste

p i t s . 4.3.1 K-65 Tanks

The two K-65 tanks contain residues principally

resulting from the processing of pitchblende ores.

In addition to uranium, t h i s material contains radium

i n an amount averaging 311 milligrams per ton. The t o t a l radioactivity is estimated t o be 2.0 x l o 3

)ICi/Kg*

A l l of t h i s material i s the property of the African

Metals Corporation and i s being stored a t FMPC under an

agreement w i t h the Atomic Energy Commission. The

material must be removed by the Owner by June 30, 1983.

The inventory of material stored in the K-65 tanks is

as follows: Total Waste S.S. Content

Description (LbS. 1 (Lbs. 1

Australian Ra Cake 380,451 606

K-65 (Radium bearing from pitchblende ores) 19,004,675 24, 121

Total 19,385,126 24,727

Estimated volume of material stored i n the K-65 tanks

i s 195,000 ' c . f .

41.

1. I I 1 I 1

4.3.2 Metal Oxide Tanks

The metal oxides are stored in one of two tanks

north of the K-65 tanks. The second tank i s empty.

The metal oxides are a l s o the residues o f ore con-

centrate processing: however, they do not contain

radium. The metal oxides are the property of the

Atomic Energy Commission.

The t o t a l radioactivity i s estimated t o be

-013 x l o 3 pCi/Kg.

The inventory of material stored i n the Metal Oxide

Tanks i s as follows:

Description

Metallic Oxides (Residues from ore concentrates)

Total Waste ( I b S . 1

3,898,288

S.S. Content (Lbs. 1

39,627

Estimated volume of material stored i n Metal Oxide

Tanks i s 125,000 c . f .

4 . 3 . 3 Wet Chemical Waste P i t s

Chemical Waste P i t No. 3 was used for a retention or

s e t t l i n g basin for liquid e f f l u e n t and slurries, and

contains the sol ids dropped out i n the s e t t l i n g process.

The solids contained are mostly the residues from the

extraction o f uranium from ore concentrates plus minor

amounts of other s lurries generated on s i t e . The

useful l i f e of t h i s P i t has been exhausted and it i s

being covered w i t h earth.

I 6285 42. chemical Waste Pit No, 2 , although used primarily

as a dry p i t for storage of s o l i d wastes, a l s o

contains a small amount of s e t t l e d solids from

liquid residues, similar t o the material i n P i t

No, 3 ,

chemical Waste Pit No. 5 i s now being used as a

s e t t l i n g basin and is accumulating similar materials.

A tabulation o f sludges and s e t t l e d s o l i d s i n s e t t l i n g

basins a t FMPC i s as follows:

Total Est. volume ( c . Y . ) S.S. Content ( K g 1 Radioactivity

247 , 500 197 , 200 65.7 C i

43 . 6285

1 1 1 1 I 1

There are no operating funds s p e c i f i c a l l y designated for waste

management a c t i v i t i e s a t FMPC. Wastes are handled as part of the

normal operations incidental to the production program a t FMPC.

5 . 1 Interim Storage of High-level Liquid Waste Generated by AEC Reprocessinq Plants

This section i s not applicable t o FMPC.

5.2 Long-Term Storaqe of High-level Liquid Waste

No high-level l iquid wastes are generated or stored a t FMPC.

5.3 Management of Low-Level Liquid Waste

5 . 3 . 1 Summary and Milestone charts

The "PLANNING GUIDE FOR MANAGEMENT OF RADIOACTIVE

L I Q U I D WASTES" included in the "PLAN FOR THE MANAGEMENT

OF AEC-GENERATED RADIOACTIVE WASTES'' indicates under

Milestone 21 that by FY 1976 a l l s i t e s should have

"Systems available for ( a ) monitoring and diverting

waste streams released d i r e c t l y t o man's environment,

and (b) eliminating the routine use of s o i l columns

t o remove radioactivity from l iquid waste."

FMPC i n FY 1 9 7 3 already meets these goals. S o i l columns

have never been used a t FMPC. Monitoring of l iquid

e f f l u e n t s a t FMPC i s e f f i c i e n t and leaves l i t t l e t o be __-- -- ---- - desired.' Diversion capacity e x i s t s .

6285 Currently, e f f o r t s are under way to find methods t o

reduce radium and uranium in the l i q u i d e f f l u e n t

although concentrations of both in the receiving

stream meet AEC concentration guides for waters in

uncontrolled areas.

Through process and equipment modifications and

improvements as outlined hereafter it i s anticipated

that by E Y 1976

uranium losses through the l i q u i d e f f l u e n t

streams w i l l be reduced by a minimum of 50%

from those recorded i n FY 1972, and

t o t a l 228Ra and 2 2 6 ~ a discharges in the

Manhole 1 7 5 eff luent t o the Great Miami

River w i l l be well within the 0.066 d/m/ml

concentrations usually accepted a s "drinking

water" l imits . The major source of uranium i n the combined liquid

e f f l u e n t stream i s the storm sewer system, which

contributes more than 60% of the t o t a l l iquid e f f l u e n t

uranium loss, Because of the large drainage area

covered, it i s d i f f i c u l t t o pinpoint the sources,

Some of the uranium i s that which f a l l s out from the

plant stacks.

where s p i l l s and leaks can occur, a l s o adds t o the loss.

Undoubtedly some uranium i s leached from the earth

surfaces in the production area.

Drainage from concrete storage pads,

S i g n i f i c a n t e f f o r t s

$%85 45 .

3, Reverse osmosis u s h g duPont Permaset Permeators

i s being examined t o ascertain f e a s i b i l i t y of the

process for removal of uranium from intercepted

storm water flows, i n the event neither of the

previously mentioned alternates appearsusable and

e f f e c t i v e .

have been and are being made to reduce t h i s ground

contamination; however, u n t i l the sources and t h e i r

degree of contribution t o the overal l storm sewer

contamination problem are determined, a l l o c a t i o n

of e f f o r t s and funds in the most e f f e c t i v e way i s

d i f f i c u l t .

The adopted course of action i s three-pronged:

1.

2.

Conduct a systematic sampling program of

the entire storm sewer system. The data

cbtained would be used to i s o l a t e and

eliminate, i f possible, the uranium sources.

If uranium source elimination does not or

cannot provide s a t i s f a c t o r y reduction in the

storm sewer uranium losses, areas of the

storm sewer system which are the greatest

contributors of uranium contamination would

be %solated from the remainder of the storm

sewer system, Through the construction of a

new l i f t s t a t i o n , the e f f l u e n t from these areas

would be pumped through the Wet Chemical P i t

for precipitation and reduction of uranium content.

For immediate improvement of the capabil i ty of pre-

venting uranium losses from accidental s p i l l s , the storm

sewer diversion system w i l l be modified by the use of

b e t t e r detection instrumentation and by automation of

the divers ion valve operation.

To reduce uranium losses through the process e f f l u e n t

stream (from the Wet Chemical Waste P i t , Clearwell) it

i s necessary t o reduce uranium i n solution, presently

a t 1-3 ppm concentrations.

determine the e f f e c t s of operation variables on this U

concentration. For example, the e f f e c t of processing

various sump cakec, some containing oxalates, requires

examination as t o result ing increased uranium s o l u b i l i t y

in the process eff luents.

A study i s under way t o

The b e s t available and acceptable e f f l u e n t treatment process

for removal of soluble uranium in the concentrations

present’appeass t o be reverse osmosis.

of R/O t o process e f f l u e n t treatment i s under review.

The a p p l i c a b i l i t y

Several studies of radium removal systems are under way.

Radium-228 from thorium wastes i s being successfully

removed by the barium s u l f a t e ,coprecipitation method and

the concentration of t h i s nuclide in the f i n a l e f f l u e n t i s

l e s s than the limit for water in uncontrolled areas.

Removal of Radium-226 by use of the barium sulfate

coprecipitation method has not been as successful:

however, improvements in the process, presently under

t e s t , appear t o y i e l d much b e t t e r 226- removal r e s u l t s .

47 . 628%

I

sewer discharge l ine t o Manhole 175 and return the

diverted storm sewer flow t o the General Sump or

the Wet chemical P i t .

Reference: (1) Section 5 . 3 . 1 , Summary and Milestone Charts FMPC Radioactive Waste Management Plan, 1973

( 2 ) NLO CP-73-14, "Storm Sewer Effluent Control"

The barium s u l f a t e process, however, i s expensive

and i t s effectiveness appears t o be variable. Reverse

osmosis again appears t o o f f e r a viable substitute.

It i s under study for 226Ra removal.

(See Table I1 for summary of t a r g e t dates for Management of Low-Level Liquid Wastes on Page 48.)

5 . 3 . 2 Accomplishments i n E Y 1974

1. Two portable flow proportional samplers w i l l be

purchased and used for a survey of the entire

storm sewer system. The entire sampling program

should be completed within the f i r s t h a l f of FY 1974.

Reference: Section 5 . 3 . 1 , Summary and Milestone Charts FMPC Radioactive Waste Management Plan, 1973

2 . Uranium analysis instrumentation w i l l be i n s t a l l e d a t the Storm Sewer L i f t Station, capable of detecting

minute increases i n uranium concentration. This

instrumentation w i l l supplement the e x i s t i n g pH

alarm system,

close the diversion block valve i n the process

I n addition it w i l l automatically

TABLE I1 Target Dates for Management of Radioactive Liquid Wastes

FY - 1973 FY -1974 F Y - 1975 FY - 1976 F Y - 1977 AEC

PLANNING GUIDE

REDUCTION OF URANIUM I N

L IQUID E F F L U E N T

REDUCTION OF RADIUM IN

L IQUID E F F L U E N T I Systems available for (a) monitoring and diverting waste streams released directly to man's environment, and (b) eliminating the routine use of soil columns to remove radioactivity from liquid waste.

(1) Start: Storm Sewer Effluent Control (2) Complete: National Lead Company of Ohio

Ref: CP - 73 - 14

(3) Start: Prevention of Uranium Loss Through Storm Sewer (4) Complete: Ref: National Lead Company of Ohio

F Y - 1975 Budget Project No.: 02 - 74 - 1

(5) Start: Wet Chemical P i t . (6) Complete: Ref: National Lead Company of Ohio

FY - 1975 Budget Project No: 02 - 75 - 1

(7) Start: Facility for Reduction of Radionuclides (8) Complete: Ref: National Lead Company of Ohio

FY - 1975 Budget Project No.: 02 - 74 - 1 .

3 . u t i l i z i n g data from the storm sewer sampling

program, portions of the storm sewer system w i l l

be selected for i s o l a t i o n and connection into a new

l i f t station. Construction should be started in

the l a t t e r part of EY 1974.

Reference: (1) Section 5 - 3 - 1 8 summary and Milestone Charts FMPC Radioactive Waste Management Plan, 1973

( 2 ) NLO EY 1975 Budget, Proj. No. 02-74-1 NPrevention of Uranium Loss Through Storm Sewers"

4. The study of available processes for removal of

radionuclides from the process eff luent stream w i l l

be completed.

construction should be i n i t i a t e d l a t e in Fy 1974 on

a f a c i l i t y for reduction of both uranium and radium

Based upon r e s i l t s of the study,

concentrations i n the process eff luent stream.

Reference: (1) Section 5 . 3 . 1 , Summary and Milestone charts FMPC Radioactive Waste Management Plan, 1973

( 2 ) NLO Fy 1975 Budget, Proj. No. 02-74-1 " F a c i l i t y for Reduction of Radionuclideso8

5 . 3 . 3 Program and Accomplishments i n Fy 1975

During E'Y 1975 construction would be completed for the

"Prevention of Uranium Loss Through Storm Sewers" and

the " F a c i l i t y for Reduction of Radionuclides, both

started i n FY 1974. I n addition, a new Wet Chemical

Waste P i t would be constructed and available for use

000055

628% 50. by mid-FY 1975. The p i t would be rubber lined and of

similar construction t o the e x i s t i n g Wet Chemical Waste

P i t ( P i t No. 5 ) . *

The study on possible applications of reverse osmosis

treatment for removal of uranium from storm sewer

e f f l u e n t would be continued, and implemented if it

was found t h a t further reduction of uranium concen-

tration was feasible and necessary.

*Reference: (1) Sections 3 . 2 . 2 . 1 . 3 and 4.3.3, FMPC Radioactive Waste Management Plan, 1 9 7 3

( 2 ) NLO FY 1975 Budget, Proj. No. 02-75-1 W e t Chemical P i t "

5.3.4 Program and Accomplishments, FY 1976 - FY 1980 The program for reduction of uranium losses through

the storm sewer system would continue t o be implemented

during this period, consistent with AEC p o l i c i e s and

goals as they are developed and announced.

5.4 Manaqement of Solid Waste Contaminated With Radioactivity

No operational changes in s o l i d waste management a t FMPC are

planned during the period FY 1974 through FY 1980. No solid

waste treatment t o reduce volume generated appears feasible

because of the low l e v e l of radioactive contamination of these

wastes .

6285 51.

I) General Plant Project funds (39-BB-00-00-0) i n the amount of

$50,000 w i l l be required in E T 1977 for the construction of a

new dry Chemical Waste P i t .

a t l e s s than s i x (6) months.

Construction time i s estimated

5.5 Management of Airborne Radioactive Waste

Under present production programs, the exist ing controls on

airborne radioactive releases are considered adequate . Uranium i s the only radionuclide discharged in s i g n i f i c a n t

quantities and these releases usually occur because of the

sudden rupture of a dust c o l l e c t o r bag.

and maintenance w i l l be continuously emphasized t o reduce

losses due to avoidable malfunctions.

Collector inspection

No c a p i t a l equipment fund requirements are anticipated for

reduction of airborne radioactive releases .

6285 52, 5.6 Summary Tabulation of Budqet Projections for Radioactive

Waste Manaqement A c t i v i t i e s

The following i s a summary of Budget Projections for c a p i t a l

equipment and construction funds:

Management of Soljhd Waste

W i t h 1 Contaminated

RadioactiviSy

Management of Aifberse Radioactive 4 waste

m m m

a a

a fll I

1976 -

--

EY Fy EY ET 1978 1979 1980 --- - 1977

NOTES :

(1) High l e v e l l iquid wastes neither generated nor stored a t FMPc.

(2) Storm Sewer Effluent Control ( 3 ) F a c i l i t y for Reduction of Radionuclides - - $ 17,000) 150,000) $167,000 (4) Wet Chemical Waste P i t .

( 5 ) D r y Chemical Waste P i t ,

1 6285 53.

6.0 1 le I

Description of Decontamination and Decommissioning

6 . 1 Radioactively Contaminated F a c i l i t i e s

There are no radioactively contaminated f a c i l i t i e s and/or

adjoining land a t FMPC either (a) excess t o present needs,

or (b) expected t o become excess i n the next f i v e years

under program assumptions used i n preparing EY 1975 budget

submissions . The above accepts the d e f i n i t i o n of 'I f a c i l i t y " as a d i s t i n c t operational unit including building, capable

of being separated from the whole for disposal to others.

Based upon a survey in 1971 by the General Services

Administration, a t a meeting between GSA and AEC on

February 18, 1972, a decision was made t h a t no portion

of the land area included i n FMPC was excess t o present

needs . (4) No f a c i l i t i e s are designated as Ilstandby" although there

are portions of the equipment within c e r t a i n f a c i l i t i e s so

designated. A l l f a c i l i t i e s as such are considered as

currently i n use.

applied t o estimate a date when the status of these f a c i l i t i e s

can or w i l l be changed t o 'lexcesstt or #'expected t o become

excess . I'

There i s no data available which can be

( 4 ) ~ t t e r , D. K. K h s e y (GSA) t o J. A. Erlewine ( A E C ) , February 25, 1 9 7 2 a: li 0

6.2 Deqree of Radioactive Contamination

A survey was made in 1972 of the contamination levels i n

FMPC buildings . ( 5 ) The levels ranged from clean t o moderate, based upon the following table:

Contamination Alpha, dpm/100 cm2 a t 1 cm

Clean L 104 103 L0.4

LOW 104 - 105 103 - l o 4 0.4 - 4.0 Moderate 105 - 107 104 - 106 4 - 400

B + A Category Nat. u & Th Other mr/hr

a s h ? i o 7 7106 7 400

Contamination is due t o natural or low enrichment uranium

with the exception of a few areas where thorium was a l s o a

minor source . 6.3 Recommendations for Conversion

Since there are no excess f a c i l i t i e s , t h i s section i s not

applicable t o FMPC.

6.4 Other Radioactive Materials

Natural s o i l columns or seepage basins have never been used

a t FMPC. Such operations are regarded as completely

unsuitable t o the plant location, s o i l conditions, and the

valuable underground aquifers from which the plant (and

other industry) draws i t s water supply.

(5)Letter, Contamination Levels in FMPC Buildings, M. S. Nelson (NLO) t o c. A. Keller ( O R ~ M C ) , ~ u l y 14, 1972

55. 6285 The eff luent from the combined process sewer i s discharged

into the Waters of the Great M i a m i River through a submerged

o u t l e t t o eliminate p o s s i b i l i t y of s o i l contamination from

this source.

Every e f f o r t has been made during the years of operation a t

FMPC t o clean up immediately s p i l l s , leaks, or other

accidental releases of radioactive materials so as t o

prevent s o i l contamination a t FMPC.

present knowledge, no substantial volume e x i s t s of soil

contaminated through operations or accidental releases .

I n the l i g h t of

I 56. BIBLIOGRAPHY

1.

2.

National Lead Company of Ohio Nuclear Material Management Manual.

National Lead Company of Ohio Accounting Manual. 1 3 . CP-68-13, New Wet Chemical Waste P i t , March 28, 1968 I - National Lead Company of Ohio Construction Proposal. 4. Letter, D. K. Kinsey, GSA, t o J. A. Erlewine, AEC, February 25, 1972. 1 ' 5. Contamination Levels in FMPC B u i l d b q s , M. S. Nelson, NLo t o

C. A. Keller, ORO-AEC, July 14, 1972.

1 I

6. CP-73-14, Storm Sewer Effluent Control, National Lead Company of Ohio Construction Proposal.

3 . National Lead Company of Ohio FY 1975 Budget.

8. FMPC Environmental Monitorinq Annual Report for 1972. NIX10-1098, February 1 6 , 1973.

- 9. FMPC Radioactive Effluent Data Report - 1972, February 27, 1973. 10. Radioactive Effluent Release Monitoring and Control.

M. S. Nelson t o C. L. Karl, February 5, 1971,

ml. The Control and Sampling of AFrborne Contaminants. K. N. Ross and M. W . Boback. November 1 5 , 1971.

I 12. Report on Compaction of Radioactive S o l i d Wastes. J. B.' Stevenson, February 18, 1970. 1 3 . Report on Incineration of Radioactive Wastes.

J. B. Stevenson, February 18, 1970.

Report on Sortinq of Radioactive Wastes. J. B.. Stevenson, February 18, 1970.

14.

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II I 1