Ill III I IIIIII liii II

P8241 -065 NT

lnfamation is ow business.

ENVIRONMENTAL SURVEY OF TRANSPORTATION OF

RADIOACTIVE MATERIALS TO AND FROM NUCLEAR

POWER PLANTS SUPPLEMENT I

U.S. NUCLEAR REGULATORY COMMISSION

WASHINGTON, DC

APR 75

U.S. DEPARTMENT OF COMMERCE

National Technical Information Service

PB241 -065

BIBLIOGRAPHIC DATA 1. Report No, [2. tlluIHIlHlJIIIIItllh11IllfHIi

SHEET NUREG-75/038 I

4. Title and Subtitle

_____________________

5. Report Date

ENVIRONMENTAL SURVEY OF TRANSPORTATION OF RADIOACTIVE MATERIALS April 1975

TO AND FROM NUCLEAR POWER PLANTS SUPPLEMENT I 6.

7. Author(s) 8. Performing Organization Rept,

No. NUREG75/038

9. Performing Organization Name and Address 10. Project/Task/Work Unit No.

U.S. Nuc lear Regulatory Commi ssion 11. Contract/Grant No.

Office of Standards Development

Washington, D.C. 20555

12. Sponsoring Organization Name and Address 13. Type of Report & Period

Same as 9 above. Covered Environmental

Survey Supplement I

to Wadi 1238

14.

15. Supplementary Notes

Supplement I to Wash - 1238

16. Abstracts

Supplement I to WASH-l238, "Environmental Survey of Transportation of Radioactive

Materials to and from Nuclear Power Plants," has been prepared by the Office of

Standards Development, U.S. Nuclear Regulatory Commission. This supplement presents

data and identifies methods used to derive the environmental impact and risk values

in Summary Table S-k, "Environmental Impact of Transportation of Fuel and Waste to

and from One Light-Water-Cooled Nuclear Power Reactor." Summary Table s-4 is

referred to and set out following section 51.20(g) of the Commission's regulation,

"Licensing and Regulatory Policy and Procedures for Environmental Protection,"

10 CFR Part 51.

17. Key Words and Document Analysis. 17o. Descriptors

1 lb. Identifiers/Open-Ended Terms

llc. COSATI Field/Group

18. Availability Statement Releasable to the public. Avail- 119. Security Class (This J21.No. of Pages

able at NTIS. UNCLASSIFIED

20. Security Class (This

Page

UNCLASSIFIED

FORM NTIS-35 REV. 10.73) ENDORSED BY ANSI AND UNESCO. THIS 1flRM MAY RF RPPODUCED IJSCOMM.OC 828374

REPRODUCED BY

U.S. DEPARTMENT OF COMMERCE

NATIONAL TECHNICAL

1NJIZC1RMATICIN SIRVICE

SUPPLEMENT I

To

WASH-1238

Introduction

This supplement to WASH-1238, "Environmental Survey of Transportation

of Radioactive Materials to and from Nuclear Power Plants," December 1972,

has been prepared to present the data and identify the methods used in

deriving the values in Summary Table S-4, "Environmental Impact of Transportation of Fuel and Waste To and From One Light-Water-Cooled Nuclear

Power Reactor," referred to in and set out following 10 CFR 51.20 (g)''

of the Commission's regulations. Summary Table S-4 was published in

Part 51 for use by power reactor license applicants in their environmental

reports and by the Nuclear Regulatory Commission in its detailed statements to account for the environmental effects of transportation of fuel

and waste to and from nuclear power reactors within the scope of that

paragraph.

Derivation of Values in Summary Table S-4

With the exception of the values used for cumulative doses to the

exposed population, the values in Summary Table S-4 are those derived for

the "typical" nuclear power reactor in WASH-1238. The calculative methods,

assumptions, and parameters used in deriving the values in WASH-l238 are

described in detail in that report. The results of individual analyses

-'The amendments to 10 CFR Part 51 ( 51.20 (g), Summary Table S-4, and

§ 51.23 (a) became effective February 5, 1975 (40 FR 1005 - 1009,

January 6, 1975). In the Statement of Considerations accompanying the

Notice of Rule Making, it was stated that the Regulatory staff intended

to issue a supplement to WASH-1238 showing how the impact values in the

Summary Table S-4 were derived (40 FR 1007 and 1008, January 6, 1975).
-2-

by the Commission during the period January 1972 through March 1973 of

the environmental impact of such transportation for 84 individual

nuclear power reactors at 53 different sites are given in Table S-l,

"Summary of Transportation Data for Nuclear Power Reactor Sites."

The values used for cumulative doses are based on data tabulated in

Table S-i.

The value of 250,000 Btu/hr for the heat output from an irradiated

fuel cask in transit is based on an actual design of a shipping cask

for LWR fuel. Shipments of unirradiated fuel and solid radioactive

waste release negligible amounts of heat (see pages 5, 27, 38, and 50

of WASH-l238). As indicated in the table, the gross weights of trucks

are limited by state restrictions to about 73,000 pounds, which limit

the cask weight to about 50,000 pounds. The weight of a cask for routine

shipment by rail or barge in most cases will not exceed about 100 tons

(see pages 7, 20, 39, and 40 of WASH-i238).. Shipments of unirradiated

fuel and solid radioactive waste, although made up of several packages,

are subject to the same weight restrictions.

The estimated numbers of shipments per year of fuel and waste and

return of empty containers that were used to estimate the traffic

densities for truck and rail were derived in WASH-1238 (see pages 20,

22, 23, 27, 34, 39, and 50 of WASH-1238). Those "typical" numbers are

compared, in Table S-5, to the numbers of shipments estimated for the

individual reactors tabulated in Table S-l.
-3-

Data in Table S-i were analyzed to determine the values for average

estimated annual doses to transport workers and the general public from

the transportation of fuel and waste for the operation of a single

reactor for one year. Those values, along with other average values for

numbers of shipments and shipping distances, are given in Tables S-2

through S-5. As can be seen from these data, there is a considerable

range of estimated values for distances, numbers of shipments, and doses

to people, but the average values did not differ greatly from the "typical"

numbers derived in WASH-1238.

As shown in Table S-2 and Figures 1, 2, and 3, the values for

cumulative doses to transport workers and the gen.ral public given in

Sunmary Table S-4 exceed the doses calculated for 90% of the more

than 80 reactors for which specific analysis of the environmental

impact of transportation has been made.

The environmental risks from accidents due to radiological effects

were evaluated in WASH-1238 based on probabilities of a wide spectrum of

accidents and estimates of a range of consequences from each category of

accidents, taking into account such variables as weather conditions,

population density, type of shipment involved, and effect of the accident

conditions on the package (see Appendixes A and B of WASH-1238). The

risks from conmon causes were extrapolated from data provided by the

Department of Transportation on reportable accidents of all types of

hazardous material (see Appendix C of WASH-l238).
TABLE S-i

SUMMARY OF TRANSPORTATION DATA FOR NUCLEAR POWER REACTOR SITES

ite

Data from

Final

Environmental

Statement

Dated

umber of

Reactors

At Site

et

Power

Type of Rating,

Reactor MWe

Unirradiated Fuel

Number of Shipping

Truck Distance,

Shipments Miles

Irradiated Fuel

Number of Number of

Truck 2 Rail

2

Shipments Shipments

hipping

Distance,

Miles

Packaged

Number of

Truck

Shipments

Waste

Shipping

Distance,

Miles

Estimated Accumulated

Radiation Doss

man-rem/year

General Public

Along

Transport the

Workers Onlookers Route

Combined

Transport Workers

S General Public,

man-rem/year

per reactor

Midland 1, 2 03/29/72 2 PWR 500/850 5 650 20 400 12-15 400 1.51 .51 .4T 1.2

.13R .37R .258

Oconee 1 03/27/72 1 PWR 885 3 30 15 1,2 .5 .4 2.1

Pilgrim 05/09/72 1 BWR 655 5 850 80 (8) 700 45 200 6.41 1.6T .231 8.23

Point Beach 1, 2 05/18/72 2 PWR 28 497 12 1000 12 200 12 200

l.SR

2.7

.78

.2

.058

.12 1.51

Surry 1*5 05/25/72 1 PWR 20 800 8 400 104 500 60 500 7.8 2.2 2.1 4.05

Surry 2 06/30/72 1

Farley 06/23/72 2 PWR 20 840 10 500 20 500 30 500 1 .7 .1 0.9

Palisades 06/28/72 1 PWR 700 5 850 20 (10) 700 6-9 500 1.31 .41 .6T 2.

Vermont Yankee 07/06/72 1 BWR 513 3 700 15 (5) 900 12 500 1.41 .4 .3 2.1

Fermi 2 07/07/72 1 BWR 1150 6 900 8 900 12 500

.SR

.5 .3 .1

Turkey Point 07/14/72 2 PWR 28 740 tO 700 30 (12) 700 45 1000 3.4 1 .2 2. 3

Maine Yankee 07/19/72 1 PWR 792 5 27-40 (8-10) 16 500 2.9 .7 .2 3,8

Fort St. Vram 08/04/72 1 BTGR 330 4 1200 40 700 1 900 .3 .3

Fort Calhoun 08/30/72 1 PWR 457 5 1000 25 (6) 1000 40 1000 2.7 .8 1.6 5.1

Zier 09/07/72 1 BWR 840 4 700 5-8 300 40-55 300 2.4 .8 .1 :1.3

Quad Cities 09/08/72 2 BWR 29 809 5 850 7 700 45 500 1.5 .6 .7 1,4

Indian Point2 09/29/72 1 P'WR 873 5 800 22 (10) 1000 5-10 600 1.4 .7 1.1 3.2

Arkansas 2 09/29/72 1 PWR 925 5 10 750 12 750 . .2

Shoreham 10/02/72 1 BWR 820 5 700 70 (6) 900 40 500 1T 8.1

McGutre 1, 2 10/26/72 2 PWR 20 1100 11 100 144 (24) 150 33 400 2:11 3.25 :
TABLE S-i (Continued)

SUMMARY OF TRANSPORTATION DATA FOR NUCLEAR POWER REACTOR SITES

Estimated Accumulated

Radiation 0099

Data from Unirradiated Fuel Irradiated Fuel Packaged Waste em ea Combined

Final Net General Pub1 Transport Workers

Environmental Number of Power Number of Shipping Number of Number of Shipping Number of Shipping 1°E 4 General Public,

Statement Reactors Type of Rating, Truck DIstanceS Truck Rail Distance, Truck Distance Transport the man-rem/year

Site Dated At Site

1

Reactor 8e Shipments Miles Shipments 2 Shipments2 Miles Shipments

,

Miles Workers Onlookers F ute per reactor

Batch 10/30/72 2 BWR 28 790 10 10-16 800 55-70 BOO 2.2 .5 1.2 1.95

Monticello 11/22/72 1 BWR 545 4 1400 20 (6) 500 40 500 .8 .1 2.5

Zion 12/06/72 2 PWR 28 1100 6 (40) (10) 900 40 500 l.3R .6k .7k 3.0

3.6T l.T 1.4T

Three Mile Island 12/06/72 2 PWR 850/930 10 15 800 50200 600 1,66.1 .8-2.8 1.- 6.1

3,3

Hanford 2 12/07/72 1 BWR 1100 15 10 10 3000 50 10 1.1 .1 .15 1.35

Kewaunee 12/20/72 1 PWR 540 4 10-40 700 82.65 .6 .8 4.05

Virgil C. Summer 01/12/73 1 PWR 900 6 40 28 (6) 100 21 500 .66k .28k .2k lU

1.2T .671 .241

$

La Salle 02/10/73 2 BWR 28 1100 10 14 800 40 600 1.3 0.7 0.9 1.45

Arkansas 1 02/09/73 2 PWR 820/902 10 20 870 24 0.82 0.7 0.7 1.11

790

Bailly 02/12/73 1 BWR 660 4 6 40 1.2 0.58 0.2 1.98

Cooper 02/21/73 1 BWR 778 5 6-13 68 2.2 .98 1.2 4.38

Forked River 02/16/73 1 PWR 1093 SR 140 72 (12) 600 37 600 3,421 1.41 l.21T 6,03

12T 1.2R O.7R 0.538

Duane Arnold 03/12/ 73 1 BWR S69 4 6 500 25 500 0.84 0,4 0.28 1.52

Davis Besse 03/12/73 1 PWR 872 5 6 700 9 300 .26 .18 .06 .48

R8ncho Seco 03/13/73 1 PWR 913 5 2800 4(5,6) 2600 14 (15,35) 650 1.44 0.6 0.64 2.68

Waterford 03/21/73 1 PWR 1165 5 50-72 5-7 700 IS 900 2.75 l.2T l.lT 5,05

.6R .3R .3R

FitzPatrick 1 BWR 821 5 800 70 1000 20 10)0 2.7 .4 1.7 4.8

San Onofre 2, 3 03/21/73 2 PWR 281140 11 3000 145 26 2000 50 soo 12.5T 2.6T 2 T 8,55
TABLE S-i (Continumi)

SUMMARY OF TRAN5POKTAflON DATA FOR NUCLEAR POWER REACTOR SITES

Eatimated Accumulated

Data from

Draft

Unirradjated Fuel Irradiated Fuel Packaged Waste

Radiation Dosa

man-rem/Year Combined

Environmental Number of

Net

Power Number of Shipping Number of Number of Shipping Number of Ship7ing

General Public

Along

Transport Workers

6 General Public

Site

Statement

Dated

Reactors

A Si

Type of1 Rating, Truck Distance, Truck 2 Rail

2

Distance, Truck Distance, Transport the

,

aan-rsm/year t te Reactor 8e Shipments Mile. Shipments Shipments Miles Shipments Miles Workers Onlookers Route per reactor

Calvert Cliffs 01/20/72 2 PWR 28 910 12 144 4(Barge) 550 12 600 9.4T 2.6T 2.2T 7 1 1, 2 ,

.SBarge .2Iarge .2Barge

Hutchison Island 09/13/72 1 PWR 850 s 1400 36 500 15-20 800 1.3 .8 . 2.7

Peach Bottom 2,3 10/06/72 2 BWR 281065 12 460 200 (16) 650 164 600 11 T 4.4T 3.21 9.3

Salem 1,2 10/31/72 2 PWR 281090 11 250 130-150 775 40 500

5.1K

4.2

2.2K

2.4

2 R

2.5 4.55

Shearon Harris 1-4 11/22/72 4 PWR 49 900 18 31 300 180 400 5.2 2.7 1.5 2.35

Limerick 1, 2 12/06/72 2 BWR 281055 12 500 200 (16) 775 70 500 5 T 3.lT 3.11 5.6

.7K .2K

North Anna 1-4 12/11/72 4 PWR 49 900 18 300 200 (20) 500 200 500 8T 5.2T 3.61 4.2

4.1K 2,9K 2K

Crystal River 3 09/11/72 1 PWR 830 5 10 350 18 85) .6 .3 .4 1.3

Diablo Canyon 1,2 12/12/72 2 PWR 291150 10-14 3000 10-18 3000 9 1003 1.4 .8 . 7 1 . 45 *

Newbold 1,2 12/20/72 2 BWR 281088 6 92 (16) 900 400 3.4 1.4 1.6 3.2

Cook 1.2 11/09/72 2 PWR 291100 10 64 (21) 900 36 50) 3 1,4 1.3 2.85

Millstone 12/30/72 2 BWR/PWK 650/830 4/5 70/72 (6/8) 1000 80 803 6.71 2.81 4 1 6.75

2.SR 1.2K 1,7k

Trojan 01/05/73 1 PWR 1130 5 3100 7 3100 9 250 .3 .2 .2 0.7

Nine Mile Point 01/17/73 1 BWK 1120 6 800 76 (6) 1000 42 1003 3.6T 5.2

Susquehana 1,2 01/19/73 2 BWR 281100 13 21 600 52 400

1.3K

1 1

.7K .9k

. .8 .6 1.25

Prairie Island 1,2 01/22/73 2 PWR 29 540 80 1000 16 1000 6.9 1.2 1.2 4.65

Beaver Valley 03/ /73 1 PWR 852 5 53 (6) 520 22 750 1 . 7 1 .8 3.5

Kaddam Neck 03/26/73 1 PWR 600 4 50 (7) 950 4 800 1 . 6 .7 1. 3,3

FES's for SURRY 1 and SURRY 2 were issued separately, but both FES'. treated both unit..

1 All reactors li sted except Fort St. Vram are light-water-cooled power reactors fueled with pelletizad 1-4% enriched U0 in Zircelloy rods. 2 In most cases, shipment is either by truck or by rail. Where truck and rail are

2

optional, rail is shown in psrentheais.

3 In most cases, two values are give; the dose identified with a T is for truck only and an K is for rail only; if neither T nor K, the transport

is by truck only. For averaging, the higher values were used.
TABLE S-2

ESTIMATED RADIATION DOSES TO TRANSPORT WORKERS AND THE GENERAL PUBLIC

FROM TRANSPORTATION OF FUEL AND WASTE FOR A NUCLEAR POWER REACTOR

Range of Values, Standard 90 Percentile

man-rem/year Average Doses, Deviation, Value,F

Mm Max man-rem/year man-rem/year man-rem/year

Transport Workers ' 0.24 6.4 2.04 1.48 4

General Public$' 0.24 3.8 1.45 0.92 3

Combined: ' 0.48 9.3 3.50 2.26 7

Transport Workers

and General Public

I

Based on data for 83 reactors.

21 Based on data for 84 reactors.

The cumulative doses calculated for 90% of the 83 or 84 reactors are lower than these values.
-8-

20

19

18

17

16

15

14

13

2:12

11

0

E

2

10

9

8

7

6

5

4

3

2

I I

-

10-1.4 1 -

- I FIGURE1 -

1.5-1.9 I

LU

>

LU

- 2 -

LU

0

a:

LU

2.0-2.4

1I3°-33.O341

I I

I I -

0-0.4

-

6.0-6.4

-- I 4.5.9 5,5-5.9 -

-

5.0-5.4] -

I I

4.0-4.4 I _____

1 2 3 4 5 b

Estimated Accumulated Radiation Doses-Transport Workers (man-rem/year per reactor).
-9-

26

24

22

20

FIGURE 2

18

16

14

12

z

10

8

6

4

2

0.5-0.9

1.0-1.4 12.0-2.4

LU

-J

>

LU

-J

z

LU

0

LU

0

C)

1.5-19

-

0

1 2 3 4 5

Estimated Accumulated Radiation Doses General Public (man-rem/year per reactor).

3.5-3.9

2.9I
It

14

12

U

I

10

E

z

8

6

4

2

0

- 10 -

1.0-1.9

20-2.9

w

-J

>

w

-J

I-.

z

w

C)

I

U)

0

3.0-3.9

4.0-4.9

6.0-6.9 I

FIGURE 3

50-5.9

8.0-8.9

7.0-7.9 9.0-9.9

1 2 3 4 5 6 7 8 9 10 11 12

Estimated Accumulated Radiation Dose - Combined Transport Workers and General Public

(man-rem/year per reactor).
TABLE S-3

ESTIMATED RADIATION DOSES TO INDIVIDUALS

FROM SHIPMENTS OF FUEL AND WASTE FOR A NUCLEAR POWER REACTOR

Range in Numbers of Range in Individual Overall Average

Persons Exposed Doses, millirem/year Individual Doses,

inillirem/year

Transport Workers 20 to 200 5 to 500 i'

General Public

Onlookers 10 to 1100 1.3

Along the route 36,000 to 0 to 0.06 O.0O2'

1,200,000

For 83 reactors

For 84 reactors
- 12 -

SUMMARY TABLE S-4

ENVIRONMENTAL fl{PACT OF TRANSPORTATION OF FUEL AND WASTE

TO AND FROM ONE LIGHT-WATER-COOLED NUCLEAR POWER REACTOR1

Normal Conditions of Transport

Heat (per irradiated fuel cask in transit)

Weight (governed by federal or state restrictions)

Traffic density

Truck

Rail

Exposed

Population

Transportation

workers

General public

Onlookers

Along Route

Estimated

Number of

Persons

Exposed

200

1,100

600,000

Range of Doses

to Exposed 2

Individuals

(per reactor year)

0.0 to 300 millirem

Environmental Impact

250,000 Btu/hr

73,000 lbs. per truck; 100

tons per cask per rail car

less than 1 per day

less than 3 per month

Cumulative Dose to

Exposed Population3

(per reactor year)

4 man-rem

0.003 to 1.3 millirem ) 3 man-rem

0.0001 to 0.06 millirem)

Accidents in Transport

Radiological effects

Common (nonradiological) causes

Environmental Risk

Small4

1 fatal injury in 100

reactor years; 1 nonfatal injury in 10

reactor years; $475

property damage per

reactor year.

1 Data supporting this table are given in the Commission's "Environmental Survey of

Transportation of Radioactive Materials To and From Nuclear Power Plants," WASH-1238,

December 1972.

2 The Federal Radiation Council has recommended that the radiation doses from all sources

of radiation other than natural background and medical exposures should be limited to

5,000 millirem per year for individuals as a result of occupational exposure and should

be limited to 500 millirem per year for individuals in the general population. The dose

to individuals due to average natural background radiation is about 130 millirem per

year.

Man-rem is an expression for the summation of whole body doses to individuals in a group

Thus, if each member of a population group of 1,000 people were to receive a dose of

0.001 rem (1 millirem), or if 2 people were to receive a dose of 0.5 rem (500 millirem)

each, the total of man-rem dose in each case would be 1 man-rem.

4

Although the environmental risk of radiological effects stemming from transportation

accidents is currently incapable of being numerically quantified, the risk remains small

regardless of whether it is being applied to a single reactor or a multi-reactor site.
Unirradiated Fuel

TABLE S-5

NUMBER OF SHIPMENTS AND SHIPPING DISTANCES

FOR FUEL AND WASTE FOR NUCLEAR POWER REACTORS

Number of Shipments "Typical" Number Shipping Distance, "Typical" Distance

Method of Per Year Per Reactor of Shipments miles in WASH-1238,

Shipment Mm Max Average in WASH-1238 Mm Max Average miles

Truck' 3 7 4.9 6* 10 3000 922 1000

Irradiated Fuel Truck' 10 100 48.8 60* 150 2000 739 1000

Rail' 4 13 8.35 10* 300 3100 1102 1000

Packaged Waste Truck' 1 250 34.6 46 10 1000 510 500

1/ For 82 reactors * plus an equal number of shipments for return of empty packagings.

2/ For 53 reactors

3/ For 31 reactors

H

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