ML19296A826

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Radiological Assessment of Individual Dose Resulting from Routine Operation-Demonstration of Compliance w/40CFR190
ML19296A826
Person / Time
Site: 07001201
Issue date: 01/28/1980
From:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML19296A825 List:
References
NUDOCS 8002190093
Download: ML19296A826 (28)
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Text

DOCKET NO.-

70-1201 LICENSEE:

Babcock & Wilcox Company (B&W)

FACILITY:

Commercial Nuclear Fuel Plant (CNFP)

SUBJECT:

RADIOLCGICAL ASSESSMENT OF INDIVIDUAL DOSE RESULTING FROM ROUTINE OPERATION-DEMONSTRATION OF COMPLIANCE WITH 40 CFR 190 I.

Background

The EPA uranium fuel cycle standards, specified in 40 CFR 190 limits the total dose to an individual in the general public from radioactivity (radon and its daughters excepted) associated with routine operation of the nucleac fuel cycle facilities to 25 nrem per year to the total bod'/,

75 mrem /yr to the thyroid, and 25 mrem /yr to any other organ.

The standard became effective on December 1,1979, for all uranium fuel fabrication plants used for the production of LWR fuel.

The Babccck & Wilcox Company's plant (the licensee) is an urarium oxide fuel facility subject to the EPA standara.

Using current plant operation, emission and monitoring data, the NRC staff has carried out a radiological assessment to determine if the licensee is meeting the EPA standard for fuel cycle f acilities.

As a part of this assessment, an action level on the rate of effluent releases from routine operation of the facility is established to provide assurance that the licensee will comply with the standard during future plant operation.

6q&uW@B

2 II. Discussion A.

Descriatien of be Facility 1.

General Descriotion of Plant The C;iFP is located on a 525 acre irregularly shaped parcel of land about 4 to 5 miles east of Lynchburg, Virginia and is bcunded on three sides by the James River and on the fourth side by Virginia State Route 726.

Two other Babcock & Wilcox facilities, the Naval Nuclear Fuel Division (NNFD) and the Lynchburg Research Center (LRC), also occupy the site.

The CNFP occupies about 25 acres of the 525 acre site.

The manufacturing operations are conducted mainly in a windowless metal paneled structure 600 feet long by 60 feet wide with an average roof height of 24 feet.

2.

Cuerations The CNFP is presently licensed to possess and use up to 20,000 kg 23~5 of U as oxide in powder or pellet form with a maximum 4.05 percent 35U enrichment.

Uranium dioxide powder, recei/ed 1

as the input feed material, is pelletired, loaded into zircalloy cladding material and fabricated into fuel assemblies for use in cocaercial power reactors.

At the present time there is no chemica! processing.

The principal steps in the manufacturing process are the following:

3 (a) Po.vder Eiendina.

Uranium dioxide powder is processed in a blender to insure homogeneity of the basic plant feed material.

Any additives that are required are included in the mixing operation.

(b) Powder 51uccino and Granulatina.

The olended powder is slug pressed (slugging) and then granulated to produce a free flowing powder having the appropriate particle size distribution.

(c) Pellet Pressina.

The granulated powder is pressed to the desired " green" density ard geometric snape.

(d) Pellet Sinterinc.

The " green" pressed ;ellets are placed in trays in preparation f ar sintering to final density.

Pellets are sintered in an electric furnace in a pure hydrogen or 75 percent H and 25 percent N atmosphere at 2

2 approximately 1,700 C.

Lubricant additives are deccaposed during the crocess and are released as 0, H O and H '

2 2

2 (e) Pellet Grin.cina.

Following sintering, pellets undergo centeriess gricding to final dimensions.

(f) Rod Loadina.

Fuel rods are fabricated by inserting a measured column of pellets into the clad material along with other rod com;cnents.

One end csa is already in

i 4

f place.

The second cap is positioned and welded immediately after rod loading.

(f) Fuel Rod Processina.

The fuel rods are cycled through a number of production and quality control steos, including drying, ultrasonic testing, pressurization with helium, t

cleaning, radiometric evaluation, and finally helium leak

^

testing.

(h) Fuel Sundle Assembly.

Comaleted fuel rods are inserted into the rod holding cage and the end fitting is attached to the end of the fuel bundle assembly. The completed fuel buncle assembly is cleaned, inspected, packaged inta an approved shipping container and shipped to the utility's reactor site.

B.

Waste Confinement and Effluent Controls 1.

Gaseous Effluents Air streams which could be contaminated with radioactive materials are prefiltered, then pass through wo stages of HEPA filters with a maximum collection efficiency of 99.95 percent for 0.3 micron particles.

Figure i summarizes the air effluent handling system of the plant.

5 l

EFFLUENT A SAMPLE POINT (s8000 CFM)

OUAL FILTRATION HEPA y-------

l PRE. FILTER PRE. FILTER l3,g g,

.g I CONTROL INTERLCCKS l TO ASSIST IN BALANCING FURNACES ROOM AIR A!R FLOWS A.'40 TO lCONSERVINGWARM SAMPLE POIN7 PICKUP PROVICE METHOD FOR l

RECI8CULATINS SYSTEM AIR l

RCOM AIR OUAL R E TU R r; I dEP4 s15,000 CFM

[

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A PIE-F:LTER PRE. FILTER PRE. FILTER A

A A

PROCESS PROCESS HCCOS ROOM AIR GLOVESCIES PICKUP AND EQUIPMENT 3ABCOCK & WILCOX COMMERCIAL NUCLEAR FUEL PLANT Flow Diagram of Air Handling System LYNCH 8URG VIRGINIA ENVIRONMENTAL REPORT Figure i

6 2.

Licuid Efflueny All controlled arec liquid wastes containing radioactive material are discharged to one of two 1000 gallon liquid waste retention tanks (shown schematically in Figure 2).

Each tank has a high level alarm whicn sounds when the tank is nearly full. When the alarm sounds, the flow is manually switched to the second tank while the full tank is air agitated, sampled, and analyzed for gross alpha count and for pH.

If necessary, the pH is adjusted to the range of 6.5 to 8.0 by the addition 3

of soda ash to the tank prior to discharge to the James Rive.

If the uranium content were to exceed limits stated in 10 CFR 70, the contents would be diluted prior to disposal.

3.

Solid Wastes Salid waste materials and artitles contaminated with uranium are collected in suitable receptacles according to combustible-noncombustible categories.

Scrap uranium :naterials are not considered as wastes; they are recycled directly to the manufacturing process or are recovered.

Contaminated noncom-bustible waste inc'udes pumos, motors, valves, filters from air effluent control systems, filter or centrifuge sludges, etc.

Contaminated ccmcustible wastes incluce such items as paper, cloth, and plastics.

Contaminated solid wastes are disposed of by a licensed contractor.

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C.

Semi-Annual Effluents Emission Data Section 40.65 of 10 CFR Part 40 requires that the licensee submit effluent acnitoring reports on a semi-annual basis after January 1, 1976.

Tacles 1 and 2 stmmari::e the results of the radioactivity measurements for airborne and liquid effluents during the past few years (1975-1979).

4 0.

Descriotion of the Site Environment Related to the Radioloaical Assessment at the Maximum Nearest Resident The fo' lowing description of the site environment provides informaticn specific to the evaluation of radiological impact on an individual at the nearest residence frcm radiolcgical effluents released frcm the plant's normal operation.

Other general infor-mation concerning the site environ: rent can be referred to in The Envircnmental Report (ER)I submitted by the licensee in December, 1974 i, car.nection with their license renewal action at that time.

1.

S4te location and Tocoarachy T1e Ccomercial Nuclear Fuel Plant (CNFP) is located on a 525 acre site in Campbell County near Lynchburg, Virginia.

This 525 acre site also.contains the Naval Nuclear Fuel Division (NNFD) facility and tne Lynchburg Research Center (LRC) cwned and operated by Sabcock & Wilcox under authority of separate NRC licenses.

(See Figure 3).

9 Table 1 Gasecus Effluent Release Data Babcock & Wilccx (CNFP)

Period Isotope (microcuries) 234 235 236 238 g

g g

U Total

  • 7/1/75-12/31/75 3.68

.150

.0100

.570 4.51 1/1/76-6/30/76 8.17

.329

.0132 1.72 10.23 7/31/76-12/31/76 5.47

.250

.0400 1.71 7.47 I

1/1/77-6/30/77 1.44

.0660

.0110

.449 1.97 7/1/77-12/31/77 1.82

.0831

.0138

.566 2.48 1/1/78-6/30/78 2.82 ~

.130 0120

.650 3.61 l

7/1/78-12/31/78 2.02

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.0088

.462 2.58 1/1/79-6/30/79 2.83

.126

.0128

.663 3.63 "The total micrecaries are measured values; L9e release for each isotope is calcu?ated based on 4% uranic.m enrichment.

i i

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10 i

Table 2 i

Liquid Effluent Release Data i

Sabcock ?. !lilccx (C"FP) t Period Iso;cpe (microcuries) 236 238 234U 2359 U

U Total 7/1/75-12/31/75 146.

5.84

.360 26.

179 1/1/76-6/30/76 420.

16.9

.680 39 526 7/1/76-12/31/76 162.

7.36 1.22 50.

221 1/1/77-6/30/77 712.

32.5 5.37 222.

972 7/1/77-12/31/77 1490 66.7 7.31 342.

1906 1/1/78-6/30/78 884.

39.4 3.88 202.

1129 7/1/78-12/31/79 796.

35.5 3.50 183.

1018 1/1/79-6/30/79 673.

30.0 3.03 157.

863

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12 The site can be reached frcm Highways 460 or 609 to State Route 726.

The site is serviced by a spur of the Chesapeake and Ohio Railroad which runs through the Babcock & Wilcox property.

The site is also conveniently located for truck and automobile access.

About two miles from the plant, State Route 726 connects with U.S. Highway 460, which is a major iink between Roanoke and Richmond.

The plant site is located on a river bend and generally exhibits a rolling surface of gentle slopes.

The dominant topographic feature of the site is a hill located approximately at the center of the property, the crest of which rises to 693 feet above mean sea level :MSL).

The ground is inclined toward the river from the hilltop to the river bank, which 's at approximately 470 feet MSL.

The highest point in the sicinity of the site is the top of Mt. Athos, where the elevation is 890 feet MSL.

Figure 3 also shows the surrounding topography of the site.

2.

Land and Water Use

, Land use in the general area is ccminated by farming and forestry.

Amherst and Campbell Counties are relatively important agricultural areas.

However, because of the unfavorable terrain, the five-mile study area surrounding the site contributes relatively little to total production.

Field surveys showed mainly small acreage plots uNer cultivation within the fi /e-mile stucy area.

13 The CNFP, the NNFD, are the LRC use botn James River water and groundaater.

The river water is withdrawn at a rate of about 190 gpm.

The discharge rate of this withdrawal water corre-sponcs to 0.01 percent of the annual average river discnarge rate of 3300 cfs.

The City of Lyncnburg's water supply comes frca the Pedlar River,which is substantially upstream from the James River.

Average usage for Lynchburg is about 16 million gallons per day.

3.

Diffusion Climatolocy 01 site meteorological data have been collected at the Lynchburg Research Center since Marcn 1964.

One year of this data, January 1965 to December 1965, has ceen reduced from strip charts.

Tables 3-6 provide joint wind direction-speed-stability frequency data at the Lynchburg Research Center that can be appliea to the CNF?.

lie annual morning mixing heigtt of the area is about 450 meters and an annual afternoon mixing 2

height is about 1550 meters.

Calculations by Holzworth show that a metecrological potential for air pollution woula exis;

a. the site on an average of 5 days per year.

Meteorological discersicn facters, annual average x/0. are estimated c3ing the Caussian piume nedel and diffusica coefficients for Pasquill type turbulence.

(A computer code generated from Reg. Guide 1.111 ).

Since most of the plant stack heights are less than two and one-half times the building m

l '.

- m i. :.

im Frequercy of Occurrerne /O, Wind Direction vs. Sceed From 1/55 : 12/55 a: Ea:cccx & Wilccx L.C Speed Class (mph) Stabili:y = Stable Calm 1-3 A7 3-12 13-13

'i-C A 2 5 :.':

Unkncwn Total lite

.00

.32

.08

.02

.C0

.00

.03

.02

.36

.!E

.00

.;9

.11

.03

.00

.C0

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.00 1.02.

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.00

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.00

.00

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.00 43

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.00

.00

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.00

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.00

.00

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.00

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.C5

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.C0

.C0

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.00

.13

.02

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.00

.00

.00

.20 S

.00

.25

.C0

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.00

.C0

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.00

.32

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.C0

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.02

.00

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.C0 1.13

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.00 1.31

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.97

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.C0

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.C0

.C0 3.90 UtiK iC

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.03

.00

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.00

.00

.55

.65 TOTAL 3.90 10.96 1.25

.15

.03

.00

.03

.62 16.94

15 TA3LE Frequency of C::urrence (';), Wind Direction vs. S;:eed Feca 1/55 :0 12/55 a: 5abc:ck i Wilcax LRC Sceed Class (:;:5) Sta:ili:y = Slign:ly Stable Calm 1-3 2-7 5_-12 13-13 19-21 25-03 Unknown Total N.'lE

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.54

.73

.29

.11

.03

.00

.02 2.71

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.53

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.00 19

.23

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.00 1.11

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.C0

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.00 1.40 1.02

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.02

.C0

.C0

.00 2.55 NNW

.00 1.11

.59

.21

,C6

.00

.00

.00 1.98 N

.C0 44

.12

.C3

.02

.C0

.00

.05

.65 VAR

.00 -

.15

.00

.C0

.C0

.00

.00

.05

.23 CAL:t 2.29

.C0

.00

.00

.00

.00

.00

.00 3.29 UNK:;0

.00

.73 15

.C0

.00

.00

.00 45 2.37 TOTAL 3.29 1 3.91 5.62 1.37 41

.05

.00 1.61 26.75

.s 16 l

TABLE 3

~

Frequency of Cccurrence (,), Wind Direction vs. Sceed Frca 1/55 to 12/55 a: Saccock & Wilcox LRC Speed Class (mph) Stacility = Neutral Stable Calm 1-3 2-7 3-12

!3-13 19-2 25-3c Unknown Total NUE

.00

.75 45

.11

.08

.C2

.00

.00 1.40 NE

.C0

.25

.11

.09

.02

.00

.00

.00 47 ENE

.00

.25

.15

.03

.06

.00

.00

.00

.50 E

.00

.11

.05

.02

.03

.00

.00

.00

.20 ESE

.00

.33

.06

.C8

.02

.00

.00

.00

.49 SE

.00

.30

.17

.08

.02

.00

.00

.02

.58 SSE

.00

.06

.33

.00

.00

.00

.00

.00

.09 5

.00

.02

.C0

.00

.00

.00

.00

.00

.02 SSW

.00

.04

.03

.02

.00

.00

.00

.00

.12 SW

.00

.14

.02

.02

.00

.00

.C0

.00

.17 WSW

.00

.1E

.06

.02

.CO

.00

.00

.00

.26 W

.00

.22

.14

.05

.00

.00

.00

.00 43 WNW

.C0

.52

.35

.18

.00

.00

.00

.00 1.16 NW

.00

.38

.30

.17

.02

.00

.00

.02

.88 NNW

.00

.37

.15

.09

. 09

.02

.C0

.02

.73 3

.00

.09

.C9

.05

.02

.03

.00

.00

.27

'/AR

.00

.C5

.00

.00

.00

.00

.00

.00

.05 CAUt

.54

.00

.00

.00

.C0

.C0

.00

.00

.84 UNKNO

.C0

.25

.08

.00

.00

.00

.00

.37

.70 TOTAL

.84 4.49 2.24

.97

.33

.06

.00

.41 9.35

17 I

8 TABLE 6 Frecuency of 2:urrence ["), '.lind Dir20 tion vs. Spec.d Frca 1/65 :: 12/55 3-5accock i Wilc0x L3.0 Speed Class (-.:h) Sta:flity = Unstacle Cala 1-3 2-7 3-12 13-13 19 ~ -

25-U3 Unknown T:tal N:E

.C0 2.18 1.34

.55

.11

.02

.00

.03 4.22

?;E

.00 1.a5

.51

.29

.17

.03

.02

.02 2.62 E!!E

.00 1.25

.93

.32

.06

.02

.02

.09 2.68 E

.00

.37

.50

.09

.02

.00

.00

.02 1.49 ESE

.00 1.48

.56

.03

.C0

.00

.00

.00 2.12 SE

.00

.38

.a3

.09

.00

.00

.00

.00 1.40 SSE

.00

.70

.17

.03

.02

.00

.00

.00

.91 5

.00

.13

.02

.05

.C0

.C0

.00

.00

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.00 1.02

.C8

.05

.00

.00

.00

.00

.14 SW

.~ 00 40

.15

.01

.02

.00

.00

.00

.59 WSW

.00

.57

.14

.05

.C0

.C0

.02

.00

.35 W

.00

.72

.53

.20

.00

.00

.00

.03 '

1.52 W::W

.00 2.37 2.07

.59

.15

.00

.00

.00 5.19 NW

.00 1.53 1.28 29

.C8

.00

.00

.00 3.67

?!NW

.00 1.30 1.11 47

.CS

.05

.00

.06 3.53 N

.00

.52 44

.23

.05

.00

.00

.00 1.23

'/12

.00

.25

.00

.00

.00

.00

.00

.00

.25 CAL:t 2.3a

.C0

.00

.C0

.00

.00

.00

.00 2.34 U?.GC

.00

.55

.30

.05

.C0

.00

.00

.57 2.48 TOTAL 2.34 18.95 10.30 3.54

.73

.12

.05

.81 38.54 i

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19 heights and due to the topography of the site, ground level release with the ef fect of building wake are assumed.5 Table 7 summari:es tne annual average x/Q values in 16 sectors up to a distance of 50 mile radius frca the site.

4.

The Nearest Resident The nearest resident is lucated at about 0.5 mile ENE of the i

site.

The annual average x/Q values shown in Table 7 indicate that at a given distance from the plant, the individual (if there is any) located at E, ESE, SE, SSE, SSW, WSW and WNW nay have higher impact (based on higher x/Q values) than at the ENE direction.

However, after evaluating the x/Q values at "arious oirections and the locations of the other existing residents which are furtner away from the plant, the staff concluded that et the present time the nearest resicent will encounter the maximum

pact fecm the CNFP operation.

E.

Environmental Imoact from Routine Plant Oceration 1.

Methodclocy for Radiolocical Assessment The general approach for the demonstration of compliance with the dose linits of the standard is as follows:

(i) Effluent releases frce the plant will be monitored to determine the quantitites of radionuclides discharged into the environment.

1 l

20 i

(ii) Envircnmental dose models developed by NRC are used to estimate dose commitmsnt rates from all significant pathways.

1 It is only when there is a potential for noncompliance that a catailed environmental monitoring program will be required to i

supplement such effluent monitoring.

The above approaches to cemonstrate compliance are in conformit) with the recommendations of the EPA as specified in their Final Environmental Statement (FES) for Environmental Radiati an Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle.6 i

The source terms (radioactivity release rates) from CNFP operations are actual measured /alues.

The atmospheric dispersion model is based on F.cg. Guide 1.111.4 Other environmental pathways and models are based on Reg.

7 Guide 1.109 with the exception that for inhalation the dose conversion factors for various organs are generated using the ICRP Task Group Lung Model." 11 The dose contersion factors 0-from the Task Group Lung Model depend on particle size and solubility of the released radioactive ccapounds released.

If this informatica is not available from the licensee, a reasonable, and scmetimes :anservative approach will be applied for the radiological impact assessment.

For example, the particle size is assumed to have an average diamter (AMAD) of 0.3 um for effluents passing through HEPA filters and 1.0 um AMAD for

l 21 i

perticles not passing through HEPA filters; the particles released are conservatively assumed to be 100% insoluble which will provide a maximum lung dose for the inhalation calculation and then tne released particles are conservatively assumed to be 100% soluble to provida a maximum bone dose for the ingestion calculation.

It is only when such conservative assumptions a.*e critical to the standards (i.e.

near or exceeds 25 mrem /yr)

I i

t that the licensee will be required to conduct studies to obtain j

l more accurate information for a more realistic assessment.

2.

Maximum Individual Dose l

The radiological imcacts are assessed by calculating the max' mum individual dose to the closest resident, who is living at about 0.5 mile east-northeast (ENE) of the CNFP.

Except where specified, tre term " dose" as referred to in this assessment is actually a 50 year dose commitment, that is, the total dose to the reference organ that will accrue curing the remaining lifetime (50 years) of the individual from 1 years intake of radionuclides.

Table 1 summarizes the semi-annt.al release rate of radiological airborne effluents which can be used as source terms for the radiolcgical assessment.

Ine release rates in total micro-curies were, measured values and the isotopic ccmposition of uranium was calculated based on 4% enriched uranium.

For the

i I

22 i

convenience of calculation, the totai radioactivity was assumed to be frcm U-234, the most restrictive nuclei.

From Table 1, the staff used the most current release rate, i.e., from 7/1/78 to 6/30/79 as a source term.

The annual release rate of uranium compounds was 6.21 microcuries.

It was also conserva-tively assumed that the releassd uranium compounds are all in insoluble form for inhalation calculations and are all in a soluble form for ingestion calculations.

From Table 2, the total annual release rate for liquid l

effluents was 1881 microcuries all of which is assumed to be U-234.

The uranium comocunds are conservatively assumed to be a soluble form and eventually released into the James River.

i Far airbcrne effluents released into the environment, the t

pathways considered in the inoividual cose estimate include (a) direct irradiation, (b) direct inhalation, (c) inhalation from resuspension and (d) ingestion pathways (vegetation, meat, milk) due to deposition.

For released liquid effluents, the pathways include (a) aquatic fcod (fish), and (b) shoreline deposition. According to the licensee, the nearest resident does not use the James River for potable water or for irriga-tion.

Therefore these two patt. ways, at the nearest resident, were eliminated in the calculation.

The models and various assumptions involved in the above environmental pathways can be

' referred to in great detail in Regulatory Guide 1.1097

23 Tar;1e a summarizes the results of the calculations of estimated maximum dose to the nearest resident from airborne and liquid effluents.

As shown in Table 8, the critical pathway, resulting in a maximum dose to the lung of 0.0053 arem/yr is due to inhala-tion.

The above calculation assumes a normal adult; the staff also considered a critical individual at the nearest resident.

The critical individual in the inhalation pathway is an infant (0-1 years of age).

The lung dose to the infant will be.

l' increased by a factor of about 3, i.e., 0.011 mrem /yr ' which represents only 0.044% of the environmental standard.

There-fore, the staff concludes that the maximum annual lung dose is well below tne 25 mrem annual limit as specified on 40 CFR Part 190 and that there is no adverse effect due to the release o' effluents f rom the CNFP normal operation of the CNFP.

The staff also considered the cumulative impact of activities at the B&W site.

There are two other B&W facilities, the Naval Ncclear Fuel Division (NNFO) and the Lynchburg Research Centee (LRC).

The NNFD fabricates and asseccles unirradiated highly enriched uranium elements into complete nuclear reactor cores or replacement fuel modules far the United States Navy nuclear propulsion program.

The Lynchburg Research Center is a research laboratory. Both of these facilities are not used commercially for the production of electricity and are not

24 f

TABLE 3 MAX ~MU DOSE FRCM AIREORNE AND L!CUID EF:LUENTS TO THE NEAREST RE5ICENT Pathways Orcan Oose (millirens)

Total-Body Lung Bone A.

Air Effluents

-10 1.

Direct Irradiation 3.6 x 10

-6

-3

-5 2.

Direct Ir.r.alation 3.1 x 10 5.9 x 10 5.0 x 10 3.

Inhalation Due to

-10

-7 Resuapension 2.0 x 10 3.7 x 10 3.2 x 10'9 4.

Ingestion Oue to Airb;rne Deposit

-5

~4 (a) Vegetation

  • 5.5 x 10 8.9 x 10

-6 (b) 6.aat

'2.6 x 10' 4.2 x 10

-6

-5 (c) M;1k 1.1 x 10 1.7 x 10 8.

Liouid Eff12ents

-6

-5 1.

Aquati: Fccd (Fish) 1.2 x 10 1.9 x 10

-19 2.

Shore!ine Deposit 1.1 x 10

-5

-3 Tctal 6.0 x 10 5.9 x 10 9.8 x 10'4

  • Includes non-leafy and leafy vegetable; since site specific information is not available, the staff assumed 76% food product consumed at nearest resident as recommended in Re-y;iatory Guide 1.109
    • Assume ici reside,ce time

i i

25 l

l in:1uded among the nuclear facilities as specified in 40 CFR 190.

i Based on the past monitoring results the NNFO releases about 1020 microcuries of uranium per year and the LRC releases less than 1 microcuries (essentially of plutonium) per year.

The nearest resident is located at about 0.75 miles ENE from both facilities.

Since inhalation 13 the critical pathway, the j

maximum dose to the nearest resident (assumed to be an infant 0-1 years of age) due to the cumulative impact from all three B&W facilities is estimated to be about 0.94 mrem /yr for lung dose which is well below the 25 mrem /yr standard as specified in 40 CFR 190.

F.

Conclusion ana Recommendation The normal operation of the CNFP res.ults in the release of a minut e quantity of radioactivity into the environment.

Based on current operat:en, the annual release of radioactivity includes 6.21 micro -

curies of uranium in airborne effluents and 1881 microcuries of uraniw in surface streams (James Ri"er).

The nearest resident is located at about 0.5 mile ENE of the clant.

The annual lung dose to the critical individual at the neaest residence was calculated using conservative assumctions, to be 0.011 mrem /yr which represents only 0.044*; of the environmental standard as specified in 40 CFR 190.

The staff, therefore, concludes there is no adverse impact from tha release of radioactivity due to the routine operation of the CNFP.

l 26 l

1 The staf' realized that tne nearest resident located at 0.5 mile ENE of the plant does not necessarily represent the point of maximum impact fecm the ChFP operation.

The staff estimated that the maximum trpact in the unrestricted area for ground level release is at the prcperty line adjoining Route 726 about 800 feet E5E of the plant.

This is the prevailing winc direction.

The annual average 3

x/Q at this location is 7.0 x 10-5 3

sec/m.

If a critical indivicual I

(an infant 0-1 years of age) lives at this location in future, the annual lung dose was estimated to be 0.10 mrem /yr based on the existing release rates from the CNFP operation.

The cumulative t

impact frca all of the three B&W facilities would be 4.8 mrem /yr i

which is still belcw the 25 mrem limit.

Tne staff therefore t.oncludes that with the existing operation of the S&W facilities and the boundary location where maximum impact could occur, even a:

the do,e received by a hypothetical critical individual is well I

I below :ne 25 mrem /yr limit.

Since inhalation is the critical pathway for the dose calculation, the staff recommends an action level for the release of uranium it. the I

air effluent to be at 10 uC per quarter and not to exceed 40 uC pr.r year based un the existing plant operation.

This action level will in ure ccepliance with tne standard as specified in 40 CFR 190 for the continued operatica af t."e CNFP facility.

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27 Accordingly, in order to assure compliance with Title 40, Code of Federal Regulations, Part 190 and pursuant to Title 10, Code of Federal Regulations, Parts 40 and 70, Materials License !!o. SNM-ll68 is hereby amended to add the following conditions:

1.

If the radioactivity in plant gaseous effluents exceeds 10 uCi per calendar quarter, the licensee shall, within 30 days, prepare and submit to the Commission a report which identifies the cause for exceeding the limit and the corrective actions to be tak'en by

~

the ifcensee to reduce release rates.I If the parameters important to a dose assessment change, a report shall be submitted within 30 l

't days which describes the changes in parameters and includes an I

1 estimate of the resultant change in dose ccamitment.1 h

2.

In the event that the calculated dose to any member of the public a

in any consecutive 12-mcr.th period is about to exceed the limits p}

specified ia 40 CFR 190.10, the licensee shall take immediate steps ut to reduce emissions so as to comply with 20 CFR 190.10. As provided i

r in 40 CFR 190.11, the licensee may petit, ion the Nuclear Regulatory h

Commission for a variance frcm the requirements of 40 CFR 190.10.

If a petition for a variance is anticipated, the licensee shall submit j

c the request at least 90 days prior to exceeding the limits specified

[

}

in 40 CFR 190.10.

A l The report or petition should be submitted to the Director, Office of Nuclear Material Safety and Safeguards with a copy to the Director of the Regional j

Office cf Ins:ection and Enforceme....

(;

p' '

.I, 1

28 i

I l

Literature References 1.

BAW-1412.

Envirormental Reoort - Babcock & Wilcox Commercial Nuclear Fuel Plant, tyncncurg, Virginia, December 1974 2.

G. C. Holzwteta, " Mixing Heights, Wind 5:eeds, and Potential for Urbar i

Air Polluticn Thrcughout the Contiguous United States," AP-101 Environ-mental Protection Agency, Research Triangle Park, NC, January 1972.

3.

" Meteorology and Atenic Energy," David H. Slade, Editor, USAEC, Division of Technical Information, July 1968, pp.97-104.

i 4.

U.S. Nuclear Regulatory Commission - Reg. Guide 1.111 " Methods for Estimating Ptmosoneric Transoort and Dispersion of Gaseous Effluents in Routine Reltases f rom Light - Water - Coolea Reactors." Office of Stancard Deeelopment, July 1977.

5.

Snyder, W. M., and R. E. Lawson, Jr., " Determination of a Necessary Height for Stack Close to a Building - A Wind Tunnel Study," Atmoscheric Envir. Vol. 10, pp. 633-691.

Pergammen Press, 1976.

6.

40 CFR 190, Environmental Radiation Protacticn Requirements for Normal Operations of Activities in the Uranium fuel Cycle.

Final Environmental Statement, Vol. 1, pp. 143-146.

U5 EPA, November 1976.

7.

U.S. Nuclear Regulatory Ccamission, Re;ualtory Guide 1.lC9.

Calculat'on of Annual Doses to Man Frcm Rcutine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I. March 1976.

8.

Task Group cf CcTaittee 2, ICRP, Task Grouc on Luno Cvnamics for Committee I'. of the ICRP, Health Pnysics, voi. 12,-1966.

9.

Task Grouo of Co?-ittee 2, ICRP. The "ets.bolism of Comoounds of Plutonium a; Ct.,e-Acticides. ICR.s >Lai: cap on

v. Pergammon Press, Oxfora, le7_.

10.

J. R. Houst:n. D. L. Strengh, ar.d E. C. Watson, DACRIN - A Ccmouter Program for ;31cc; sting Orcan Oose f c, Acute or Chrcnic Radienuclides Inhalation, T,.'l 359, 31ttelle Paci f:c teor *.h..est Lsocratcries, Richland, ' Washington,1975.

11.

M. H. Momeni, Y. Yuan and A. J. Zielen, The Uranium Dispersion and Dosimetry (UDAD) Code, NUREG/CR-0553, ANL/ES-72, Version IX, 1979.

12.

NUREG-0172, ?qe-Scecific 1adiation Oose Commitment Factors for a One-Year Chronic Intake, CiWL, Novencer 1977.

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