ML19269E999

Environ Survey of Transportation of Radioactive Matls to & from Nuclear Power Plants:Suppl 1 to WASH-1238

ML19269E999
Person / Time
Issue date:	04/30/1975
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
NUREG-75-038, NUREG-75-038-S01, NUREG-75-38, NUREG-75-38-S1, NUDOCS 7911140420
Download: ML19269E999 (16)

Text

SUPP E NT I T WASH-1238 ENVIRONMENTAL SURVEY OF TRANSPORTATION OF RADIOACTIVE MATERIALS TO AND FROM NUCLEAR POWER PLANTS SUPPLEMENT I 2185 001 O

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OFSTANDARDS DEVELOPMEAT 7011140QR$

Available from National Technical Information Service Springfield, Virginia 22161 Price: Printed COPY $3.25 ; Microfiche $'_.25 2185 002

SIBLIOGRAPHIC DATA

3. Report No.

2.

3. Recipient's Accession No.

5HEET NUR1rs-75/038

4. Title and Subtitle

5. Report Date ENVIRONMENTAL SURVEY OF TRANSPORTATION OF RADIOACTIVE MATER!AIS April 1975 TO AND FL M NUCLEAR POWER PLANTS SUPPLEMENT I 6.

7. Author (s)

8. Performing Organization Rept.

"' NURM-75/038

9. Performing Organization Name and Address

10. Project / Task /#ork Unit No.

U.S. Nuclear Regulatory Commission

11. Contract / Grant No.

Office of Standards Deielopment 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 Wash 1238 14,

15. Supplementary Notes Supplement I to Wash - 1238

16. Abstracts

~

Supplement I to WASH-1238, " 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-4, " Environmental Impact of Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor." Suu.ary 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 lords and Document Analysis. 17o. Descriptors 2185 003 17b. Identifiers /Open-Ended Terms 17c. COSATI Field / Group

18. Availability Statement Releasable to the public. Avail-

19. Security Class (This

21. No. of Pages R eport) able at NTIS.

Unci m fFIFD lb

20. Security Class (Ibis

22. Price

' UNCI. A SSIFIE D

$3.25 PO Ru N TIS-Ss I R E Y.

t o.7 M ENDORSED BY ANSI AND UNESCD.

THIS FORM MAY BE REPRODUCED usceuw.oc ones-Pye 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 Trans-portation 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)1/

of the Commission's regulations. Summary Table S-4 was published in Part 51 for use by power reactor license applicants in their environnental reports and by the Nuclear kegulatory Commission in its detailed state-ments 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 h WASH-1238. The calculative methods, assumptions, and parameters used in deriving the values in WASH-1238 are described in detail in that report. The results of individual analyses The amendments to 10 CFR Part 51 (5 51.20 (g), Summary Table S-4, and 5 51.23 (a) became effective February 5,1975 (40 FR 1005 - 1009, January 6,,1975)4,In the Statement of Considerations accompanying the Notice of Rul'e Eikin'g', it was sta*.ed 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).

2185 004 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-1,

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

The values used for cumulative doses are based on data tabulated in Table S-1.

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 LUR fuel. Shipments of unirradiated fuel and solid radioactive waste release negligible amounts of heat (see pages 5, 27, 38, and 50 of WASH-1238). 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 nest cases will not exceed about 100 tons (see pages 7, 20, 39, and 40 of WASH-1238). 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-1.

2186 005 gi, Data in Table S-1 were analyzed to determine the values for average estimated annual doses to transpo:n e rkers 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 general public given in Summary 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 environmentti 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 common 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-1238).

2185 006 4

v 1

TABI.E S-1 SUMART OF TRANSPORTATION DATA F0t NUC1. EAR F0WER REACTOR SITRS t

satinated Accussulated

(' :-

RadiationDoogo TData from Unitradiated Fuel Irradiated Fuel Fackazed Waste man-res/ year Combined Final pet General Public Transport Workers Environmental Number of Fouer Number of Shipping psseber of Number of Shipping Number of Shipping Along 6 General Public.

$ tatemant Reactors Type of Rating.

Truck

Distance, TrucA I*AI Distance.

Truck

Distance, Transport the man-rom / year g

2 2

Site egDeted At Site Reactor We Shipmente Miles Shipments Shipmente Miles Shipmente Miles Workers Onlookers Route For reactor Midland 1. 2

• D3[29/72 2

FWR 500/850 5

650 20 400

'2-15 400 1.5T

.5T 4T 1.2

/,

.131

.373

.251 Oconee 1 03/27/72 1

FWR 885 3

30 15 1.*

.5

.4 2.1 Filgria 05/09/72 1

BWR 655 5

850 80 (8) 700 45 200 6.4T 1.67

.237 8.23 1.51

.7R

.05R Foint Beach 1, 2 05/18/72 2

FWR 29 497 12 1000 12 200 12 200 2.7

.2

.12 1.51 Surry 1**

05/25/72 1

FWR 29 POO 8

400 104 500 60 400 7.8 2.2 2.1 6.05 Surry 2 06/30/72 1

Farley 06/23/72 2

FWR 29 840 10 500 20 500 30 500 1

.7

.1 0.9 Fa11sedes 06/28/72 1

FWR 700 5

850 20 (10) 700 6-9 500 1.3T 4T

.6T 2.3 1

Vermont Tankee 07/06/72 1

BWR 513 3

700 15 (5) 900 12 500 1.47 4

.3 2.1 9

.51 g

Forst 2 9 07/07/72 1

BWR 1150 6

900 8

900 12 500

.5

.3

.1 0.9 Turkey Point 07/14/72 2

FWR 20 740 10 700 30 (12) 700 45 1000 3.=

1

.2 2.3 Maine Tankee 07/19/72 1

FWR 792 5

27-40 (8-10) 16 500 2.9

.7

.2 3.8 Fort St. Vrain 08/04/72 1

HTCR 330 4

1200 40 700 1

900

.3

.3 Fort Calhoun 08/30/72 1

FWR 457 5

1000 25 (6) 1000 40 10L 3 2.7

.8 1.6 5.1 21mer 09/07/72 1

BWR 840 4

700 5-8 300 40-55 300 2.4

.8

.1 3.3 Quad Cities 09/08/72 2

BWR 20 809 5

850 7

700 45 500 1.5

.6

.7 1.4 Indian Point 09/29/72 1

FWR 873 5

800 22 (10) 1000 5-10 600 1'

.7 1.1 3.2 N

Arkansas 2 09/29/72 1

FWR 925 5

10 750 12 750

.5

.3

.2 g,o

@ Shoreham 10/02/72 1

BWR 820 5

700 70 (6) 900 40 500 5.2T 1.4T 1.5T g.g 1.3R

.6R

.5R McGuire 1, 2 10/26/72 2

FWR 29 1100 11 100 144 (24) 150 33 400 3.97 2.1T

.5R 3.25 1.1R

.6R

.2R O

CD N

+

TABLE S-1 (Continued)

SIBMART OF TRANSPORTATION DATA FOR NUC1.ZAR F0WER REACTOR SITES Estimated Accumulated Radiation Doege b

Data from Unitradiated Fuel Irradiated Fuel Packmaed Weste Final Net man-ren/ year Combined General Public Transport W sere Environmental Number of Power Mtamber of Shipping Neber of Number of Shipping Number of Shipping Along 6 General Public, Statement Reactors Type of Rating.

Truck

Distance, Truck Rail Distance.

Truck

Distance, Transport the man-ren/ year g

L /*

Site Dated At Site Reactor Mde Shipmente M11ee Shipments Shipmente Miles Shipmente Miles Workers Onlookers Route per reactor Batch tw'30/72 2

BWR 20 790 10 10-16 800 55-7C 800 2.2

.5 1.2 1.95 Monticello 11/22/72 1

BWR 545 4

1400 20 (6) 500 40 500 1.6

.8

.1 2.5 Iton 12/06/72 2

FWR 29 1100 6

(40)

(10) 900 40 500 1.3R

.6R

.7R 3.0 3.6T 1.T 1.4T Three Mile Island 12/06/72 2

FWR 850/930 10 15 800 50-200 600 1.6-6.1

.8-2.8 1.-

4.1 3.3 Ranford 2 12/07/72 1

BWR 1100 15 10 10 3000 50 10 I*I "I

'II I'3I Kewaunee 12/20/72 1

FWR 540 4

10-40 700 8

2.65

.6

.8 4.05 g

Virgil C. Susumer 01/12/73 1

FWR 900 6

40 28 (6) 100 21 500

.66R

.28R

.2R 2.11

\\;)

1.2T

.677

.24T I

La Salle 02/10/73 2

BWR 28 1100 10 14 800 40 600 1.3 0.7 0.9 1.45 Arkaneae 1 02/09/73 2

FWR 820/902 30 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 1.96 Cooper 02/21/73 1

BWR 778 5

6-13 68 2.2

.98 1.2 4.38 Forked River 02/16/73 1

FWR 1093 SR 140 72 (12) 600 37 600 3.42T 1.4T 1.217 6.03 N

12T 2.2R 0.7R 0.53R Duane Arnold 03/12/73 1

BWR 569 4

6 500 25 500 0.84 0.4 0.28 1.52 O

Davie Besse 03/12/73 1

FWR 872 5

6 700 9

300

.24

.18

.06 48 Rancho Seco 03/13/73 1

FWR 913 5

2800 4(5,6) 2600 14(15,35) 6 50 1.44 0.6 0.64 2.68 O Waterford 03/21/73 1

FWR 1165 5

50-72 5-7 700 15 900 2.75 1.2T 1.1T 5.05 Q

.6R

.3R

.3R FitsPetrick 1

BWR 821 5

800 70 1000 20

's 0 2.7

.4 1.7 4.8 C

San Onofra 2. 3 03/21/73 2

FWR 201140 11 3000 145 26 2000 50 SM 12.57 2.67 27 8.55 1.6R

1. R

.6R

TABLE S-1 (Continued)

SIDMART OF TRANSPORTATION DATA POR NUCLRAR POWER RZACTOR SITR$

Ratinated Accumulated RadiationDoege Data from Unirradiated Puel Irradiated Puel Packaged Weste man-rom / year Combined General Public Transport Workare

<1 Draft Net Environmental Number of Power Number of Shipping Number of Number of Shipping

• =6er of Shipping Along

& General Public, Statement teactore Type of Rating, Truck Distance.

Truck Rail Distance.

rock

Distance, Transport the man-ren/ year g

Site Dated At Site Reactor paie Shireente Milea Shigeente Shipments M116e shipments Miles Workere Onlookers Route Per reactor Q

Calvert Cliffe 01/20/72 2

PWR 20 910 12 144 4(Berge) 550 12 600 9.47 2.6T

2. 2' 7.1

.3 Barge

.2 Barge.25arge 1, 2 o,

J~

Butchison Isla'nd 09/13/72 1

PWR 850 5

1400 36 500 15-20 800 1.2

.4

.6

2. 7 3

4 Peach Botton 2,3 10/06/72 2

BWR 201065 12 460 200 (16) 650 164 600 11 1 4.4T 3.2T 9.3 5.1R 2.2R 2R Sales 1,2 10/31/72 2

PWR 201090 11 250 130-150 775 40 530 4.2 2.4 2.5 4.55 Shearon Barris 1-4 11/22/72 4

PWR 40 900 18 31 300 180 400 5.2 2.7 1.5 2.35 Limerick 1, 2 1

/72 2

BWR 201055 12 500 200 (16) 775 70 500 5T 3.1T 3.1T

5. 6 1.1R

.73

.2R North Anna 1-4 12/11/72 4

PWR 40 900 18 300

.c00 (20) 500 200

-%0 ST 5.2T 3.6T 4.2 4.1R 2.9R 2R S

Crystal River 3 09/11/72 1

PWR 830 5

10 350 18 853

.6

.3

.4 1.3 Daablo Canyon 1,2 12/12/72 2

PWR 201150 10-14 3000 10-18 3000 9

1003 1.4

.8

.7 1.45 g

Newbold 1,2

~12/20/72 2

BWR 291088 6

92 (16) 900 400 3.4 1.4 1.6 3.2 Cook 1,2 11/09/72 2

PWR 201100 10 64 (21) 900 36 503 3

1.4 1.3 2.85 Millstone 12/30/72 2

SWR /PWR 650/830 4/5 70/72 (6/8) 1000 80 803 6.7T 2.8T 4T 6.75 2.5R 1.2R 1.73 Trojaa 01/05/73 1

PWR 1130 5

3100 7

3100 9

253

.3

.2

.2 0.7 Mine Mile Point 01/17/73 1

BWR 1120 6

800 76 (6) 1000 42 1003 3.6T 5.2 1.3R

.7R

.9R Susquehana 1,2 01/19/73 2

BWR 201100 13 21 600 52 400 1.1 of

.6 1.25 Prairie Island 1.2 01/22/73 2

Pvt 20 540 80 1000 16 1000 6.9 1.2 1.2 4.65 N Seaver valley 03/ /73 1

PWR 852 5

53 (6) 520 22 750 1.7 1

.8 3.5 Raddam Neck 03/26/73 1

PWR 600 4

50 (7) 950 4

500 1.6

.7 1.

3.3 PES's for SURRY 1 and SURRY 2 were tasued separately, but both PES's treated both unite.

@1 A11 reactors listed except Port St. Vrain are light-water-cooled power reactors fueled with pelletised 1-41 enriched UO2 i' II'#*ll I **d**

2 la most cases, shipment is either by truck or by rail. Where truck and rail are optional, rail is shown in parenthesis Q3 la most cases. two values are give; the dose identified with a T is for truck only and an R is for rail onlyg if neither T nor R, the transport to by truck only. For averaging, the higher values were used.

N

TABLE S-2 ESTIMATED RADIATION DOSES TO TRANSPORT WORKERS AND THE GENERAL PUBLIC

^

FROM TRANSPORTATION OF FUEL AND WASTE FOR A NUCLEAR POWER REACTOR

.1 cc Range of Values, Standard 90 Percent le man-rem / year Average Doses, Deviation, Value,3_

1-Min Max man-rem / year man-rem / year man-rem / year Transport Workere1/

0.24 6.4 2.04 1.48 4

General Public !

0.24 3.8 1.45 0.92 3

1!

0.48 9.3 3.50 2.26 7

Comoined:

Tre.nsport Workers and General Public

-1/ Based on data for 83 reactors, t

-2/ Based on data for 84 reactors.

-3/ The cumulative doses calculated for 90% of the 83 or 84 reactors are lower than these values.

N C.71 CD

8-1 I

I I

i 19 18 1.0- 1.4 g

0.5-0.9 1r 10 FIGURE 1 14 1.5-1.9 13 a

12 e

"i r

11 2

5 U

E a:

10 g

g r

2.0-2.4 8

3.0-3.4 2.5-2.9 7

6 5

0-0.4 4

3.53.9 6.46.4 3

4.5-4.9 5.5-5.9 2

S.0-5.4 1

4.0-4.4 g

g g

1 2

3 4

5 6

7 Estimated Accumu:ated Radiation Doses-Transport Workers (man-rem / year per reactor).

G 2185 011 D{

l 0.5-0.9 24 22 d

20 FIGURE 2 18 1.0-1.4 16 2.0-2,.4 m

3<>

N 14 a

E cc z

U o

5 5 12 8

z 10 1.5-1.5 0-0.4 8

3.0-3.4 6

4 3.5-3.9 2.5-2.9 I

0 1

2 3

4 5

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

a-

- 10 28!5 2185 012 1.0-1.9 l

l l

l l

I 18 2.0-2.9 16 Ea 14 FIGURE 3 s

F b

er 12 g

3.0-3. 9 c

3 4.0-4.9 E

g 10 5

5z 8

6.04.9 6

0-0.9 5.0-5.9 8.0-8.9 4

7.0-7.9 9.0-9.9 2

~

O-1 2

3 4

5 6

7 8

9 10 11 12 Estimated Accumulated Radiation Dose Combined Transpurt Workers and General Public (man <em/ year per reactor).

'0 dBiS 2185 013 a

TABLE S-3 ESTIMATED RADIATION DOSES TO INDIVIDUALS

, };

FROM SHIPMENTS OF FUEL AND WASTE FOR A NUCLEAR POWER REACTOR V'

Range in Numbers of Range in Individual Overall Average Persons Exposed Doses, millirem / year Individual Doses, millirem / year, 1!

Transport Workers 20 to 200 5 to 500 10 General Public On] r-oke 10 to 1100 1.3 1.3 !

Al-

'te route 36,000 to O to 0.06 0.002_/

U 2

1,200,000 1!

For 83 reactora 2_/

Tor 84 reactors N

LTI C"3

SUMMARY

T/.BLE S-4 ENVIRONMENTAL IMPACT OF TRANSPORTATION OF FUEL AND WASTEg TO AND FROM ONE LIGHT-WATER-COOLED NUCLEAR POWER REACTOR Normal Conditions af Transport Environmental Impact Heat (per irradiated fuel cask in transit) 250,000 Btu /hr Weight (governed by federal or state restrictions) 73,000 lbs. per truck; 100 tons per cask per rail car Traffic density Truck less than 1 per day Rail less than 3 per month Estimated Range of Doses Number of to Exposed Cu_alative Dose to 2

Exposed Persons Individuals Exposed Population Population Exposed (per reactor year)

(per reactor year)3 Transportation workers 200 0.0 to 300 millirem 4 man-rem General public Onlookers 1,100 0.003 to 1.3 millirem )

• • "~'**

Along Route 600,000 0.0001 to 0.06 millirem)

Accidents in Transport s

Environmental Risk Radiological effects Small Common (nonradiological) causes 1 fatal injury in 100 reactor years; 1 non-fatal injury in 10 reactor years; $475 property damage per reacter year.

1 Data supporting this table,re given in the Commission's " Environmental Survey of Transportation of Radioactive Materials To and From Nuclear Power Plants," WASH-1238, Decembec 1972.

2 The Federal Radiation Council has recommended that the radiation doses from all mources of radiation other than natural background and medical exposures should be limited to 5,000 millirem per year for individrals 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.

3 Man-rem is an expression for the summation of whole bocy 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-reu 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.

[ (c! [,'U b h a

E! ! [l fi () 1 [3

TABLE S-5 NUMBER OF SHIPMENTS AND SHIPPING DISTANCES FOR FUEL AND WASTE FOR NUCLEAR POWER REACTORS Number of Shipments

" Typical" Number Shipp'ng Dittance,

'*rypical" Distance Method of Per Year Per Reactor of Shipments miles in WASH-1238, Shipment Min Max Average in WASH-1238 Min Max Average miles 1!

Unirradiated Fuel Truck 3

7 4.9 6*

10 3000 922 1000 Irradiated Fuel Truck -

10 100 48.8 60*

150 2000 739 1000 l!

U Rail 4

13 8.35 10*

300 3100 1102 1000 Packaged Waste Truch!

1 250 34.6 46 10 1000 510 500 1_/

For 82 reactors

• plus an equal ntater of shipments for return of empty packagings.

2_/

For 53 reactors 3_/

For 31 reactors N

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