Text

Part 3 of 3 - Annual Radioactive Effluent Release Report - References, Appendix a, Dose Conversion Factors
	ML021280013
Person / Time
Site:	Seabrook
Issue date:	04/30/2002
From:	; North Atlantic Energy Service Corp
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML021280013 (141)
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REFERENCES A.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", U.S.

Nuclear Regulatory Commission, Revision 1, October 1977.

B.

Hamawi, J. N., "AEOLUS A Computer Code for the Determination of Continuous and Intermittent-Release Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents in Open-Terrain Sites, Coastal Sites, and Deep-River Valleys for Assessment of Ensuing Doses and Finite-Cloud Gamma Radiation Exposures," Entech Engineering, Inc., March 1988.

C.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water Cooled Reactors", U.S. Nuclear Regulatory Commission, March 1976.

D.

National Bureau of Standards, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure", Handbook 69, June 5, 1959.

E.

Slade, D. H., "Meteorology and Atomic Energy - 1968", USAEC, July 1968.

F.

Seabrook Station Technical Specifications.

ODCM Rev. 21 R.-1

APPENDIX A DOSE CONVERSION FACTORS ODCM Rev. 21 A-1

APPENDIX A METHOD I DOSE CONVERSION FACTORS I.

LIQUID PATHWAYS - SEABROOK SITE SPECIFIC DCF'S The models used to assess doses resulting from effluents into liquids is derived from Appendix A of Reg. Guide 1.109. Since Seabrook is a salt water site, the assumed pathways of exposure taken from Reg Guide 1.109 are Aquatic foods - fish; Aquatic foods -invertebrates; and dose from shoreline deposits (direct dose). No drinking water or irrigation pathways exist because of the salt water environment. In addition, exposures resulting from boating and swimming activities have been included for key radionuclides even though Reg. Guide 1.109 identifies these pathways as not contributing any significant contribution to the total dose, and therefore does not provide dose equations for them. For completeness, the swimming and boating pathways have been included using the dose models from the HERMES code (HEDL-TME-71-168, Dec. 1971) section G, Water Immersion.

The Method I dose conversion factors are derived by calculating the dose impact to individuals via the site specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by radionuclide are calculated for each of the 7 organs (including whole body) for each of the four age groups (adult, teen, child, and infant). The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all the exposure pathways combined.

The list of dose factors in the ODCM then represents a combination of different limiting organs and age groups which, when used to calculate a dose impact from a mix of radionuclides released in liquid effluents, gives a conservative dose since it combines the exposure to different organs and age groups as if there was a single critical organ-age group.

As an example of how the liquid dose conversion factors are developed, the following calculation for Co-60 is shown. The critical organ/age group is selected based on the full assessment of all organs and age groups.

Factor for fish Ingestion:

The general equation for ingestion doses in RG 1.109 is eq. A-3.

1119.7* Uap*Mp Ri* Dap

e-At F

The full assessment for the ODCM dose factors indicated that for i = Co-60, the maximum dose (mremn/yr) is to the GI-LLI of an adult as the target organ and age group, therefore:

Uap 21 kg/yr adult usage factor for fish ODCM Rev. 21 A-2

Mp 0.1 mixing ratio for near field dilution provided by submerged multiport diffuser.

F 918 cu. ft./sec effluent flow rate for circulating water system Qi 1.0 curies/year released of Co-60 assumed Bip 100 equilibrium bioaccumulation factor for Co-60 in salt water fish, in liters/kg Daipj 4.02

10" mrem/pCi. adult GI-LLI ingestion dose factor from RG-1.109, table E-11.

1.501

l0e decay constant for Co-60 in l/hrs.

tP 24 time between release and ingestion, in hrs.

1119.7 is the factor to convert from Ci/yr per ft3/sec to pCilliter. Note that RG 1.109 uses 1100 as a rounded approximation.

Therefore the dose from fish to adult GI-LLI is (mrem/yr):

1119.7

U,0* Mp *Q B

D.*

e"O*tP = 0.0103 F

Factor for invertebrate ingestion:

Next, the dose from invertebrates to the adult GI-LLI is given by the same general equation but with the following variables changed:

Uap 5

kg/yr usage factor Bp:

1000 1/kg bioaccumulation factor all other variables the same as above therefore the dose from invertebrates is (mrem/yr):

1119.7

Uap

Mp

Q

R.

Daipj

e,-'tP = 0.0245 F

Factor for shoreline direct dose:

The general equation for direct dose from shoreline deposits is taken from equation A-7 in RG-I.109 as (mrem/yr):

ODCM Rev. 21 A-3

111970* U2p

MP* W QiQ*

T* Daipi *.6,,.[1 e*l.e..,b]

Fi It is assumed that all internal organ doses also receive exposure from direct external sources, therefore each organ dose due to ingestion must have an external component added. For the above equation, the site specific variables for an adult exposure to a 1 curie per year release of Co-60 are:

Uap

=

334 hrs/year usage factor used for assumed shoreline activities at Seabrook.

Mp 0.1 mixing ratio for near field dilution provided by the submerged multiport diffuser and assume to be extended to the beach continuously.

W 0.5 shorewidth factor for ocean sites, dimensionless

=

1.923*103 1.70*10-8 0.0

=

131400

=

1.0 radioactive half life in days for Co-60 dose factor for Co-60 due to deposits in sediments, units of (mrem/hr)/(pCi/m2) transit time to point of exposure, hrs period that sediment is assumed to be exposed to water contamination for long term buildup, set at 15 years for Method I DCF's curies per year, Co-60 assumed conversion factor to convert (Ci/yr)/(ft3/sec) to pCi/liter and account for the proportionality constant used in sediment model Therefore the dose to the whole body and each organ due to direct exposure to the shoreline (mrem/yr) is:

111 9 70* U.* MpW

Qi

T* Daipj

e"'*

[1 - e'A*']= 0.0573 F

ODCM Rev. 21 T

tp tb Qi 111970 A-4 I

Direct dose due to Swimming:

The dose due to immersion in water (swimming) is taken from the HERMES computer code.

The original ODCM calculation was based on some preliminary dilution assumptions which gave a near field prompt dilution factor for the multiport diffuser of 8. For single unit operation with both service water and circulating water flow (412,000 gpm), a value of 10 is more realistic. This surface area of the plume is restricted to a small area over the diffuser and does not touch the shoreline approx. 1 mile away. Since the over all impact from swimming is small when compared to the other exposure pathways, the original conservatism on dilution are kept here.

The dose from swimming is given by the following equation:

1.0 1012 UP, Qi*DR.

(mrem/yr)

F.

Where:

up 45 hrs/yr, usage factor for swimming for maximum age group (teen) from HERMES.

Fa 6.56* 1011 liters/yr, estimated annual dilution effluent flow in multiport diffuser Qi 1.0 Curies/yr, assumed release rate of nuclide i.

DFim

=

4.6* 10 mtrem-liters per hrs-pCi, dose factor for Co-60 for water immersion taken from HERMES.

1.0* 1012 constant for pCi/Ci Therefore the swimming dose for a 1 curie release of Co-60 is (mrem/yr):

1.0*1012*U *Mp* Qj*DFR, =3.155*10-5 Fa As can be seen, the contribution of the swimming dose is only about one 30000ths of the total of the RG 1.109 pathways, and can be ignored in the case of Co-60. Similarly, the boating dose as given in HERMES is taken as half of the swimming dose, (and corrected for change in usage assumptions). The resulting dose is found to be less than the swimming dose and can also therefore be discounted in this case.

ODCM Rev. 21 A-5

Total liquid Pathway dose:

The sum of the above liquid pathway doses can now be added to give the total maximum

-T individual dose to the critical organ (adult-GI-LLI) for Co-60. This gives:

0.0103 + 0.0245 + 0.0573 = 0.0921 mrem/yr Since the internal doses given by the RG-1.109 methods actually are 50 yr dose commitments resulting from one year exposure to the quantity of activity assumed to be released into the water, and the direct dose represents the dose received for the period assumed to be exposed to the pathway, and the activity release was taken as a unit quantity (i.e. Q = 1 Ci), the above total liquid pathway dose can be stated as site specific committed dose factor in mrem/Ci released.

For Method I in the ODCM, the critical organ dose factor is seen to be 0.0921 mrem/Ci, as shown above. The value reported on Table B.I-l1 (9.22 E-08 mrem/[LCi) was generated by a computational routine which gives rise to the round-off difference between it and the above example. The whole body site specific dose factor for the ODCM was calculated in the same way treating the whole body as a separate organ.

ODCM Rev. 21 A-6

II.

GASEOUS PATHWAYS - SEABROOK SITE SPECIFIC DCF'S The models used to assess doses resulting from gaseous effluents in the form of iodines, tritium, and particulates are derived from Appendix C of Reg. Guide 1.109. For Seabrook, it is assumed that at the off site location which exhibits minimum atmospheric dilution for plant releases the following exposure pathways exist: inhalation, ground plane, ingestion of goats milk, meat, stored vegetables, and leafy vegetables.

The Method I dose and dose rate factors are derived by calculating the dose impact to all age group individuals via the site specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by nuclide are calculated for each of 7 organs (including the whole body) for each of the 4 age groups. The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all exposure pathways combined. The list of dose factors in the ODCM then represents a combination of different limiting organs and age groups which, when used to calculate the dose impact from a mix of radionuclides released into the atmosphere, gives a conservative dose since it combines the exposure to different organs and age groups as if they were for all the same critical organ-age group.

As an example of how the gaseous particulate dose factors are developed, the following calculation for Mn-54 is shown. The critical organ/age group for Mn-54 was selected based on a full assessment of all organ and age group combinations. For elevated releases from the plant vent stack to the maximum site boundary (max. dose point due to meteorology), the critical organ and age group for Mn-54 was determined to be the GI-LLI for the adult.

PART A:

INHALATION DOSE CONTRIBUTION The general equations for inhalation doses in RG 1.109 are eq. C-3, and C-4 which together give:

3.17*104 *Ra*[

Q

iQi*DFAija = Dja Where for the case of Mn-54 releases, the variables above are defined as:

3.17* 104 is the number of pCi/Ci divided by the number of second per year Ra2 8000 the breathing rate for age group a (adults) in m3 /yr.

X-7.5

10-7 the long term average depleted atmospheric dispersion factor, in sec/m3, at the maximum exposure point off site (S.B.)

Qi 1

the release rate of nuclide i to the atmosphere in Ci/yr ODCM Rev. 21 A-7

DFAija := 9.67*10.6 the inhalation dose factor for nuclide i (Mn-54), organ j (GI-LLI),

and age group a (adult) taken from RG 1.109, table E-7, in mrem/pCi inhaled.

Therefore, the inhalation dose to the maximum potential off site individual is given as:

3.17*104 *Ra

Q]

DFAij, = 0.00184 mrem/yr per Ci PART B:

GROUND PLANE DIRECT DOSE CONTRIBUTION The general equations for ground plane external direct dose in RG 1.109 are equations C-1 and C-2 which together give the dose DG as:

8760e *.0*1-12 *SF

[ e *vZ es

DFGo i

Where for the case of Mln-54 releases, the variables in the above equation are defined as:

1.0*1012 is the number of pCi per Ci SF 0.7 D

1.5*10-8 the shielding factor provided by residential structures (dimensionless) for use in calculation accumulated doses over time. Note that for determination of dose rate factors (i.e.

instantaneous dose rates) the shielding factor is set equal to 1.0, or in effect no credit for dose reduction is taken for determination of dose rates at points in time.

the long term average relative deposition factor at the maximum site boundary location, in 1/m2 i -

0.8105 is the radiological decay constant for Mn-54 (nucide i in this case) in 1/yr.

tb 15 DFGij:=

5.80*10-Qi

=

1.0 is the time in years over which accumulation is evaluated (approx.

midpoint of plant operating life) external dose factor to the whole body, or any internal organ j, for standing on contaminated ground from Mn-54 (RG 1.109 Table E-6) in mrem/hr per pCi/m2 is the unit release quantity assumed for each nuclide i, in Ci/yr.

ODCM Rev. 21

)

7' A-8

is the number of hours in a year Therefore, the contribution to the total dose made by exposure to the ground plane at the maximum off site exposure location for Mn-54 is given as:

8760*1.0*1012"*SF*D*Qi* 1*-i

DFGi = 0.658

[Q-i*DG 0

5 mrem per yr per Ci ODCM Rev. 21 8760 A-9

PART C:

INGESTION DOSE CONTRIBUTION:

As an initial step to determining the dose contribution from ingestion of milk, meat, stored vegetables, and leafy vegetables, we must first calculate the radionuclide concentration in forage, produce, and leafy vegetables resulting from atmospheric tranfers of the activity to the surface of the vegetation and onto the soil for root uptake. For all radioiodines and particulate nuclides (except tritium and C-14), the concentration of nuclide i in and on the vegetation at a point of interest can be calculated using R.G.

1.109 equations C-5 and C-6, which combined gives:

Di*Ql* *l'e'

+Bi*

l-e'

e"*

t b

1.14*108* [

]*Q*[r*

+Biv*

ei*th Yv*A2E P*'J, PART C. 1: Concentration in Produce (stored vegetables)

For the case of Mn-54 released in air emissions to the maximum site boundary, the concentration of Mn in produce grown in the hypothetical garden at that location can be calculated from the above equation where the variables are defined as:

1.14*10"

-D -=1.5*10"8 Q

Qi

=

r 0.2

%Ei 0.00219 tb 131400 Yv 2.0 2.9*10-2 is the number of pCi per Ci divided by the number of hours in a year (8760).

is the relative deposition factor, in 1/m2, at the maximum exposure point off site (S. B.)

the release rate of nuclide i to the atmosphere in Ci/yr fraction of deposited activity retained on crops, leafy vegetables, or pasture grass (1.0 for iodines) effective removal rate constant for Mn-54 from crops due to decay and weathering, in hr-1 soil exposure time to deposition, in (equal to 15 yrs, or mid plant life) agricultural productivity (yield) for produce, in kg/m-2 concentration factor for uptake of Mn-54 from soil by edible parts of crops in pCi/kg (wet weight) per pCi/kg dry soil ODCM Rev. 21

.9 A-10

Xi 9.252*10-5 radioactive decay constant for Mn-54, in hrs-I P

240 effective surface density of soil, in kg/m2 th 1440 crop holdup time after harvest and before ingestion, in hrs te 1440 crop exposure time to plume, in his Therefore, the concentration of Mn-54 in stored vegetables produced at the location of maximum deposition for a unit activity release is given as:

1-14"10*

D

Qi*

r*

+IBi*

e"ith = 67.379 pCi/kg Yv *2,Ej P*A i.

PART C.2: Leafy Vegetable Concentration For leafy vegetables, the above equation is repeated with the value for th, crop holdup time after harvest is changed from 1440 hrs to 24 hrs, i.e.:

th 24 crop holdup time after harvest, in hrs.

Therefore the concentration of Mn-54 in leafy vegetables at the maximum deposition point due to a unit activity release is given as:

1.14 "10'*

Q ]*Qi*[

1 - '

3t l e'*t'ttb

r VvQ+b

]v *.e-&,*th=76.811 pCi/kg YQ

E Ai; J~/

PART C.3.a: Animal Feed concentration (pasture): Cp Next, we can repeat the above calculation to determine the concentration of Mn-54 in pasture grass used as animal feed. This will allow for the determination of dose contribution from milk and meat.

For pasture grass, all the above variables remain the same except for:

Y, 0.70 for agricultural productivity of pasture grasses, kg/m 2 te 720 for grass exposure time to plume, hrs th 0.0 for holdup time after harvest ODCM Rev. 21 A-11

Using these variables in the above equation gives the concentration in pasture grass as:

ll DI~sF~

[1 "er* t 1 -e*,'I q

1.14"B10*

D Qi* r

-Bi,**

=179.227 LQ Yv* 2E P *Ai J pCi/kg PART C.3.b: Animal Feed Concentration (stored feed): C, For stored feed that would be given to goats, or meat animals, the average concentration would be calculated by changing the following variables in the above calculation to:

Y, 2.0 U

1440 t

=

2160 agricultural productivity for stored feed feed crop exposure time to plume in hrs feed crop holdup time after harvest, hrs Putting these values back into the above equation gives the concentration in stored animal feed (goat and meat animal) of Mn-54 for a unit activity release to the maximum exposure point.

[]D

[1-e"st' 1 -e 1't,

Q.*14*

+10

e *Ith=63.037 1Q Yv* Am P*Ai pCi/kg PART C.3.c.: Concentration in Goat's Milk: Cm The Mn-54 concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated from RG 1.109 general equation C-10 as:

Fm

Cv

QF

e-A'*tr = conc. in milk, pCi/liter where the variables are defined as:

Fm 2.5*10-4 QF 6.0 tf

=

2.0 average fraction of animal's daily intake of Mn-54 which appears in each liter of milk, in days/liter amount of feed consumed by a goat per day, in kg/day (50 kg/d for meat) average transport time of activity from feed into milk and to receptor, in days.

ODCM Rev. 21 A-12

Xi 2.22* 10-3 decay constant of Mn-54, in days-1 In addition, the C, term for the concentration of a nuclide in the animal's feed is given from RG 1.109 general equation C-11 as:

C =fp*

Cf + [I -fP]

C, + fP * [1-fJ]* C, where the following equals:

fP 0.5 fraction of the year that animals graze on pasture f,

1.0 fraction of daily feed that is pasture grass when the animal grazes on pasture CP 179.227 concentration of Mn-54 in pasture grass as calculated from above, pCi/kg Cs 63.037 concentration of Mn-54 in stored feed as calculated from above, in pCi/kg Therefore, the concentration in the total animal's feed is estimated to be:

fp* f.* Cp + [1I-f P* C. + fP* [1-fj]* C, = 121.132 pCi/kg When this value of 121.132 is put back into the above general equation for nuclide concentration in milk, we get:

[C, 121.132 pCi/kg ]

and Fm*Cv* QC

e'i

= 0.181 pCi/liter of Mn-54 in goats milk PART C.3.d.: Concentration in Meat: Cf Similar to milk, the concentration of the nuclide in animal meat is calculated. RG 1.109 general equation C-12 is given as:

Cf = Ff

CV

QF

e-Al'ts Here the variables are set as:

Ff 8.0*10-4 QF 50.0 fraction of animals daily intake of Mn-54 which appears in each kg of flesh, in days/kg animal's daily feed intake, in kg/day A-13 ODCM Rev. 21

20.0 average time from slaughter to consumption, in days C

121.132 concentration on Mn-54 in animal's feed, same as calculated above for goat, in pCi/kg Therefore, the concentration of Mn-54 in animal meat is calculated to be:

Ff

Cv

QF

e-'*t' = 4.635 pCi/kg in meat for Mn-54 PART D:

DOSE FROM INGESTION OF FOODS PRODUCED AT MAXIMUM LOCATION Now that we have calculated the concentration of Mn-54 in milk, meat, leafy vegetables, and stored vegetables produced at a location of maximum air deposition, the resulting dose to any organ j and age group a can be calculated from the following general equation C-13 taken from RG 1.109:

XDFIija * [UV. *fg *Cv +Uma *aCm + UFa

Cf + ULa *fl *CL]

For Mn-54 set equal to i, we find that from the evaluation of all organs for all age groups for combination of all exposure pathways, the adults GI-LLI is the critical age group/organ. Therefore, the variables in the above dose equation can be defined as:

DFIija

=

1.40* 10-5 ingestion dose factor for adults/GI-LLI for Mn-54, in mrem/pCi ingested (RG 1.109, Table E-11)

Uva

=

520.0 vegetable ingestion rates for adults, kg/yr f9 0.76 fraction of stored vegetables grown in the garden f,

1.0 of leafy vegetables grown in the garden U.a 310.0 milk ingestion rate for adults, liter/yr UFa

=

110.0 meat ingestion rate for adults, kg/yr Um 64.0 leafy vegetable ingestion rate for adults, kg/yr C

67.379 concentration of Mn-54 in stored vegetables, in pCi/kg (from above)

Cm

=

0.181 concentration of Mn-54 in milk, in pCi/liter (from above)

Cf

=

4.635 concentration of Mn-54 in meat, in pCi/kg (from above)

ODCM Rev. 21 A-14

76.811 concentration of Mn-54 in leafy vegetables, in pCi/kg (from above)

The dose from the combination of ingestion pathways for this example is calculated by substituting the above listed variables back into the ingestion dose equation:

DFIija * [U,.

f9

CV + Uma

Cm + UFa

Cf + UL.

f,

CL]-- 0.4495 mrem-/yr per Ci By breaking the above dose equation down into the different pathways which combine to give the total ingestion dose, we can see the individual dose contribution made by each exposure pathway.

Therefore, we have:

Dose for ingestion of stored vegetables Dose for ingestion of goat's milk Dose for ingestion of meat Dose for ingestion of leafy vegetables DFIija *Uva *fg *Cv = 0.373 DFIija *Uma *Cm = 7.855* 10-4 DFIija *UFa *Cf= 0.00714 DFIija *ULa *fl *CL = 0.0688 PART E:

TOTAL DOSE FROM ALL EXPOSURE PATHWAYS The total dose from all exposure pathways assumed to be present at the maximum receptor location can be found by simply adding the individual pathway doses calculated above. Since all the calculations above assumed a unit activity release from the plant vent stack, the combined dose can be stated as dose factor per unit activity released. This then demonstrates the development of the Seabrook ODCM Method I dose factors for gaseous release of particulates from the vent stack.

Inhalation dose (Part A)

Ground plane dose (Part B)

Ingestion dose total (Part D)

Total dose all pathways (critical organ is GI-LLI of an adult for Mn-54) 0.00184 mrem/yr per Ci 0.658 mrem/yr per Ci 0.449 mrem/yr per Ci 1.11 mrem/yr per Ci ODCM Rev. 21 CL A-15

APPENDIX B CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND TAKEN FROM 10 CFR 20.1-20.602, APPENDIX B ODCM Rev. 16 B-1

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C4 001)

C40q N

4 CL E

cr z

W 0 co (r

W z

cr K rm Cl) "p.

z 08 1,- Z Z

W 00 7'

m 8

cg,Y, CO cq 0

ci cv Un X

a z

W a.

(L E

E E

E

.2

-2 C:

E 10

cri 000

000 000 9007000000000 0

1 NN6166-666666666000 xxxxx X~x x XXXXXXxxxxxXXXXX)>

M N 00 V 0 N

%0 WO x

x xWW Q

x PS tO (5 o o cc;F 6

6 6

ýo o

o 6

6 6

c----

-~ll l"

-n -49

-444099

-9944

-ww F

F4t 4

4 49 4

-2

.rrx xx 0~~~

~ ~

9

~cc 11 K.xxxxxxxxxxxxxxxXxxxxXXxXXXXxXXX)<

.',xxxxxxxxxXXXXXXXXXX x

x4 XXXXXXXXXXXXXXX-mr CL C

Z C

' 'D m

.0 in cc0

'm W) mEU in 1/

U)

V)f~f (nU

)

OU-i

)

U) co co liZE W 0 V

a)1 11 00 0

o l co I

N ii 0

4 03 I

o 4'4 zI I

Pf. 20 [§§ 20.1-20.602], App. B 10 CFR Ch. 1 (1-1-93 Edition)

APPENDIX B TO §§ 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued (See footnotes at end of Appendix B]

Isotope' Table I I

Element (atomic number)

CO 1

011Air I 001.2 Iui/d Water

_________________j

~~_J(pCi/mi)

Molybdenuim (42).............................. IMo 9...............

Neodymium (60)................................

INd144A..............

Nd 147............

S SI SI Nd 149......

IS Neptunium (93)

INp 237.............. IS Np 239...........I Nicktel (28)......

.).....................

INi 59...............

Ni 63...............

Ni 65........

Niobium (Columbium) (41)................INb 93m............

NbS.

Nb 97.......

Osmium

~.

]Os18 Phosphons(15P Os 19im....

Os 191......

Os 193 Pt 193m-.-.........

Pu 239..----.-.------..-

Pu 240...........

Pu 241...............

Pu 242..............

Pu 243..............

Pu 244...............

S S

I S

S S

S Polonium (84)..................................... IPo 210...............

S 7x10-7 2 x10-1 SX10-1 Ux10-1 4x10-7 2x10-7 2x10't IX 10-'

4 XIO12 I X10- '

8X 10 7x10-1 SX10-7 8X10'7 6x10-2 3x io-,

9X 10' Sx 10-'

1 X10-2 2X10-7 SX 10-2 lX 10'7 6x10'4 SX 10'4 Sx 10-7 5 x10-8 2x10-6 9xIO-4 IX 10'6 4x 10-"

4x10-7 3x10-"

1X10-4 7xl10' 6x10-7 4x10-7 7x 10 SX10-4 ex io 6xl10'J 7X10-16 SXw16 1X10'4 3X O10 6x10-6 5x10-6 SX1 OX 10-7 2x10-1 3X10-tI 2x10-12 4x10-1 2x10-3 4x10-1 9X10'11 4x 106 2X10-1 4x10-"

2x 10-'

2x10',

2xIO1'1 3X io-1, 5x10-"

2XIO1' 5X10-'

1 X 10 2x10-3 2XIO-3 2x 10-3 2xIO0' 8X 10-3 8X 1o-'

9X10-$

4X10-1 4x 101 6x10-1 6x10-'

Sx1 2x10-3 4xi10' 3xj0'3 1 X10-2 1X 10-2 3xI10' 3 XI1-3 3x 10-2 Ux10-2 2xj0'3 2x10-3 7x10-2 7x¶0-2 SXlO-3 SX 10-'

2x10-3 2x 10 1X 10-2 8x 10'3 U10O-3 2xi10' 5X 10..'

7x 10-4 4x 10'3 3x10-2 3x10' Ux10-2 3X10-2 5X10- 2 Ux10-2 3x102 4x10-3 3x10-3 1 X1O-4 ax10o-'

1 X10-4 8X10'1 1 X 10-4 8X 10-4 7x10-3 4x 10-2 I X 10-4 9x10-4 1 X 10-2 1 X10-2 I X10-4 3x10-'

2X10-'

8X 1-4 B-6 Table 11 S1-Air Col. 2 3x10-'

2x 10 7x10'9 4 x 10"I 3x10-11 7X 10 IX10O1 6X10" 8x10-9 6xi10' 6Xt0-1 3x10-'

SX10-1 3x10-1 IXlO"1 3x 10-1 4x10"'

3X10-1 3x10-1 I X 10'1 2x10-1 2x 10-'

3x10-1 2x 10-1 2x10-9 3x 10-1 1 X10-1 7x 10-1 3X10-1 1X 10-'

2x10-8 I X10-4 4X10'9 4x10-'

5x10'9 4x10-1 2XIO-9 I X10-1 3xl10' 1 X10'1 2x10-7 9x10'1 WWI0 9xIO0' 2x10-4 7x10-3 2x10-*

7x10-'

6x10-,

3x10-1 3x10-,

2x10-3 4x10-6 2x10'4 IX10-4 2x10'1 9x10'9 5x10-5 5x10-*

3x10-1 3X10-6 3x 10-4 2x10-1 9XJ-3 ixi0-4 7x10-5 2x10-9 2X10-5 3x10-"

2x10-5 3x10-1 1X10',

2x1O-1 1X10'4 2x10-1 1X1O 2x107 I X 10-'

4x10-4 9X10-4 1X10'6 2x10-1 2x10-7 IX10-10 2x10-7 9XIO-4 3x10O' I x10-'

2xl10$

1 X10-1 7x 10-1 5x10-6 I6X10-52 x10'5 6XIO-14 5x 10-'

1 X10- 12 x1O-$

6x 10-1 5X10-1 1 X10-1 3X10's 3X10-1 2

1x0 6x10-"

5x10'6 SX10-a2 3IxO-1 2x10-: I 7x10-1 7x1Q Q' 3XIO-1 ODCH{

Rev. 16 QC I

Pall.aditim (46)

Pd Pd Pia*vxn (78)

Pt Monk=

Pu I

Nuclear Regulatory Commission Pt. 20 [§§ 20.1-20.602], App. B APPENDIX B TO §§ 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued

[See footnotes at end of Appendix B]

Isotope Table I Table II Element (atomic number)

C l. I 1 Col 2-Co. 1-Air Col. 2 Waler Water

(*C/mI)

(ICI/mI)

(goCI/ml)

(/CL/ml)

Potassium (19)...................

1I<42...............

Praseodymium (59).....................................

I Pr 142....................

Pr 143....................

Prom ethium (61)..........................................

I Pm 147..................

Pm 149..................

Protoactinium (91).......................................

Pa 230...................

Pa 231....................

Pa 233....................

Radium (88)................................................

I Ra 223..................

Radon (75)........

Rheniumn (75)...........................................

Ra 224...................

Ra 226...................

Ra 228.............

Rn 220..................

Rn 2221...........

Re 183..................

Re186................. IS Re 187...................

Re 188..................

Rhodium (45)........................

Rh 103m................

Rh 105...........

Rubidium (37)............

Rb6.....................

Rb 87....................

Ru 103...............

Ru 105...............

Ru 106..............

Samarium (62)................

.............. Sim 147........

Sm 151..................

Sm 153..................

Scandium (21)..............................................

Sc 46.....................

Sc 47.....................

Sc 48.......................

Selenium 34)................................................

Se 75......................

2x 10-'

2x10-1 2x10"'

3x10-'

2x10" 6X10"'

1 X10"1 3x10"1 2x10" 2x1O't 8X 10-1 1X 10"-1 1 X10"10 6X10"7 2xlI0' 2x10'9 2x10"1 2X10-'

7X10'1 7x10-'1 4x10" 3xlO-'J 3x10-'

3x10"4 2X10-1 6x10-7 3X10"'

2X10-'

6X10-'

42x10-'

2x10"'

8X10-6 4X 10"7 2X10-5 5X10-1 6X10-s 3x10-'*

7x10-6 3X10-7 7X10-6 2x10-6 2x10-'

2X10-1 2X10-9 7x10-7 5X10-7 8X10 6X 10 7x10"1 3x10-10 6x10-4 1X10-1 5x10-1 4X10-?

2x10-'

6x10-7 5x10-1 2x 10-.'

1 x10-7 Ix10-1 1 X10-7 6x 10' 9x10-,

9x 10

1 X10"1 I1X10"1 6xI0-'

6XI0"=

6XI0"1 IX 10",

I X10"'

7x10"'

3xI0-5 8X10

4xl0-'

3x10-1 2xtO" Ix10" 7x10-1 2x10-1 4x10-'

9X10-4 8X10-'

7X10-4 2xI0-2 8X10 3x10-1 1 X10" 3

7x10-2 2X10-'

SX10-'

4x10-1 3xI0-'

3X10

4XI0-3 3x10-$

2x10-'

7 X10

3x10-3 5X10-1 1 X10-2 1 X10-2 2x10-2 2x10-3 3XW0 3X10- 1 4X10-1 3x10-1 2x 10-3 2x10-2 1 x10" 12X10-2 2x10-1 I xl0" 1X10-1 3x10-1 3x10-1 8X10-,

8X10- 1 9X10 3 8xtO-1 7X 10" 4X-10' 7x 10" 5XI0-"

lx10-'

6xI0"9 3X 10

1xI0-9 6x10-'

3xx10 4x10".

4XI0-*"

2xi0-9 A6x10-"

6X 10 2X10-11 4x 10-11.

4x 10-,1 3x 10-t" 2xI0-ne 2xI0-9 1XI0-1,

3 X 10 2x10-0 2x`10 15XI0 3x10-1 2x10 5X10-'

2x10"*

Ix X o-'1 1X10-4 6X10-'

3X10-'

2X10-4 3x10

2XI0"=1 2X10-4 2X10-9 3X 10' 2x10-4 1X10-4 6x10-'

2x10-4 3X10-f 2X10-8 2X10-4 3X10"8 2X10-1o 2xl0-4 2x 10-'

9X10-8=

6X10-,

2X10-8 3x10' 2xl0-*

2x 10-6 6XI0-9 2x10"1 2x10-1 2X10-'

SX10-:

5X10-4 2x 106 ex 10-11 2x Io-'

2xI0-'

6x10-'

SX10-9 Ax 10' 4x10-'

3x10" 2xI0-'

3x10-5 3xi0-1 5x t0 5x10-1 2x10' 2x10'1 4X 10 4X 10" 2x10" 2x10""

9x10-'

2x10 lX O10 1 X10-4 7xI0-7 4 X 10-4 WX0-4 3X10-1 3x10 3xI0-9 3x10-s 6x10-1 3X10-'

9X10- 1 5x10-*

3x10"'

2x10"=

6x10-1 3x10-*

1X10"2 I XIO-1 1 X10-4 7x10-5 2x10-6 2x10' 3x10-4 exl0-$

8X10-$

1 X10-4 1 X10-4 1X10-s 1X10-5 6x 10-'

7x10-1 4x10-4 8X10-1 8X10-1 4x10-1 4x10-5 3X10-'

3x10-s 3X10-'

3x10-'

ODCM Rev. 16 Ruthenium (4)..

Ru 97..................

B-7

Pt.-20 [§§ 20.1-20.602], App. B 10 CFR Ch. 1 (1-1-93 Edition)

APPENDIX B TO §§ 20.1--20.602---CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued (See footnotes at end of Appendix B]

Isotope Table I Table II Element (atomic number)

Col. 1-Air C.

2-Col. 1-A.r Col 2 (1+/-Coml)

WIt

(-iCi/ml W

r water.

1(IL ml]

(u1 ;/mI)

S S

S Silicon (14)...........................

31...........

Silver (47).............

Ag 105....................

Ag 110m................

Ag 111..................

6x10-4 1X10-4 6X10-'

8X10-8 2x10"1 1X 10-1 3x10"'

2x10"7 2X10" 9X10-*

1X10-6 1X1O-'

4X10-S 3X10"'

3x10"1 2x10'1 1X10-7 3x10-6 4XI0-1 1X10"9 5X10-9 4x10"7 3X10-7 3x10-'

3X 10°*

3x10-'

4XI0""

2x10-6 8X10"S 3X10-5 6X10"7 2x10-7 2x10-1 2x10"T 1XlO-1 3X10-,

4x10"s lX10-2 2X 10"'

6X10-$

4x10"7 1X10-7 1X10"7 4x10"1 2x10-6 9X10-7 8X10-6 3X10-8 5X10-9 4x10-4 4X10-7 2X10-,

2X10-7 1X10-1 1 xl0-'

3X10-7 3x10'6 3X 10-6 1X10-4 2x10-,

9X10-1 8X10" 1

2x10-7 6X10-1 6 x 10 Sodium (11)...................

.... INa 22....................

Na 24.......

Strontium (38)........................................

Sr 85m...................

Sr 85.......................

Sr 89.....................

sr90.........

Sr 91......................

Tantalum (73)

Ta 182.......

Terbium (65)...........

I Thallium (81)........................

I 1

T1 Tc96...............

S Tc 97m..............

S rc97...................

'S rc99m...........

S I

rTC99................ S I

Te 125m........... S Te 127m........... S Tb 127..0.........

.. S I

Te12 2..........

S Te 129...........

S TeI13...............

S Te 132...............

S I

Te 160....................

S Tb 1600.....................

S I

TI 201.....................

S I

TI1 202.....................

S T1 204..................... ISI

!I 3x10"2 6XI0"=

3x10-"1 3x10"3 9X10-,

9X10"4 1 X 10"1 IX 10-3 9X10-,

6x 10-3 8X10-1 2x10-1 2x10-1 3x10-3 5X10-3 SX10-1 1X O10" Ix10"'

2X10-'

1 X10-3 2x10-3 2x10-3 2x10-3 8X10"=

1X10-3 1X10"3 4x10-1 3x10-1 3x10-2 1 xlO lx10-2 5X10-3 SX10-2 2X10"2 2x 10 8X10-2 1X10-2 5X10-2 5X10-3 3X10-3 2x10-2 2x10-3 8X10-3 5X10-1 1X10-3 6X10-1 2X10-:

2x10-3 2x10-2 1X10-3 9X10"4 6x10-4 IX10-3 lx10-2 1X10

7 X10-2I 7x10-9X 10-3 5X 1 0-,

4X10-'

2X10-,

3x10-1 2x10-'

1 1

ODCH Rev. 16 2X10":

3x10"1 2x10" 3X10"1 "1

x10 3X10-'

exi10 3x10-1 3x10°1 4x10-'

5X10" 1X 10"4 1XI0-,

8X10-'

4X10-'

3x10-,o 1X10-1 3X10"1 2X 10" 10 2x10-4 9X10"9 2X10-,

1X 10"1 9X 10"9 9X10'9 1 X 10"1 7x10"1 3x10'4 1 X 10-4 2x10"l 8x10"1 8X10"1 5X10"1 4x10"1 1X10",

I X 10-4 5X 10"1 7x10-1 2x10-'

1X10"1 4X10 1*

5XI)"s 1XI0)"

6X10-'

3X 10 3x10-1 1 X10"9 2x 10" 1 X10"1 1 xl0" I6x10" 6X10-2 4x10-9 3X10-'

Ix 10-1 7 xl 0" 3X10-1 4X10-1 7X10-'

3x10"1 3x10-1 8X10"'

2X10-'

9X10--1 9X10-,

2x10" I X10-'

3x10-1 3 Xl' 0-3 4x10-1 3x10-'

2x10" 3x10"'

7x10-1 7 X10-1 2X10-'

3x10"6 3x10-'

3x10"1 4X10-1 7x10-1 5X10-$

7x10-1 6x10-3 6x10-3 3x 10-4 4X10 4X10" 1X10-t IX10" 1X10-,

5X10-1 4X10-4 2X 10" 2x10-3 8X1O-4 6X1O-'

3x10-2 3x 10-4 2x10- 4 2X10"1 1 X10-1 6x10-1 5X10-3 3X10-,

2X10-5 3X10-s 8X10-4 8X10"4 6X10-3 4x10-2X10-'

2X10-1 4X10-'

4x10-1 4x 10-'

2x 10""

2x10"1 2X10" 3x10-1 2x10 I X10-1 1X10-5 6X 10-4 ax X t-C Sulfur (16)...

.. S3S.........

Technetium ( )..

Tc 96m................

Tellurium (2 B-8

'-4 0) aa------------------------------------'ý ------ -----

a.

xxUx vx -

x-xxxxxxx x

x xxx x*xxx xxxx xxxX X,XXX XXX xxxXXX XXX )x)

V Il toC'NW'

'-.nN

(..

0r.VN9 CO')N0I V qaCO ca 0L Ca4 0:

co 0

E 0

4 z

z wi 0

m cr w

z z :

z C I-z C;

0 co 0

z CL I~~

E-a N E E

E' ca ca N

N N'

Nn

0)

D n

v 0

0C.

0)-

a a

a I I

I a

I

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a S

a

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.1C" I

0 liii

> I C

C

.0 w I.-

0 E-----------------------------------------------

2 x : 2 r

V.

s.

=1 I Iaf a

V.

~

n 0

0

~

V O

I 66666'ýD66 ýD6666bbb fE

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at

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I

Pt. 20 (§§ 20.1-20.602], App. B 10 CFR Ch. I (1-1-93 Edition)

APPENDIX B TO §§ 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued

[See footnotes at end of Appendix B8 Isotope' Table I Table I1 Element (atomic number)

Col. l Air Col, 2-Col. 1 -Air Col. 2 Water Water

_____m_)

(JCi/ml)

(GI CJml)

(+/-Ci/rml)

Zinc (30)......................................................

Zn65

......... S 1x10-7 3x10-4x10"1 1x10" I

6x10-6 5X10-1 2x10"9 2x 101 Zn69m...................

S 4X10-7 2x10"1 1X10-4 7X10" I

3X10-1 2X10"1 1x10"1 6x10" Zn 69..................... S 7x10-6 5x10-C 2x10"7 2x10 I

9X10-6 5X10"1 3x10"1 2X10" Zirconium (40).............................................

Zr 93.......................

S 1X10-7 2x10-4x10" 8x 10 I

3x10-7 2x10-1 1x10-6 8x10" Zr95.......................

S 1X10-1 2x10"1 4x10-6x101 I

3x10-6 2x10"1 1x10" 6x10 1 Zr97.......................

S 1X10-7 Sx10"1 4x10"9 2x10 1

9x10"6 5x10""

3x109 2x10 Any single radionuclide not listed above...................

Sub I

X103'1.............

3 xi0-with decay mode c.ther than alpha emission or spontaneous fission and with radioactive half-life less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Arty single radionuclide not listed above.................................

3X10-1 9x10"s 1 X 10- 1i 3x10" with decay mode other than alpha emission or spontaneous fission and with radioactive half-rde greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Any single radionuclide not listed 6X10"13 4x10"1 2x10"14 3x10 above, which decays by alpha emis sion or spontaneous fission.

'Soluble (S) Insoluble (I).

2"Sub" means that values given are for submersion in a semispherical infinite cloud of airbome material.

3 mese radon concentrations are appropriate for protection from radon-222 combined with its short-lived daughters.

Alternatively, the value in Table I may be replaced by one-third (%s) wcdting leveL" (A "working lever' is defined as any combination of short-lived radon-222 daughters, poloniunm-218, lead-214, bismuth-214 and polonium-214. in one liter of air.

without regard to the degree of equilibrium, that will result in the ultimate emission of 1.3x103 MeV of alpha particle energy.)

The Table II value may be replaced by one-thirtieth (1/2o) of a "wodring.leveL" The limit on radon-222 concentrations in restricted areas may be based on an annual average.

"For soluble mixtures of U-238. U-234 and U-235 in air chemical toxicity may be the limiting factor. If the percent by weight-enrckhment) of U-235 is less than 5. the concentration value for a 40-ho workweek. Table I. is 0.2 milligrams uranium per cubic meter of air average. For any endchm the product of the average concentration and time of exposure dunrin a 40-hour workweek shall not exceed 8x 10- SA jCi-hr/ml, where SA is the specific activity of the uranium inhaled. Te concentration value for Table i1 is 0.007 milligrams uranium per cubic meter of air. The specific activity for natural uranium is 6.77x10- curies per gram U. The specific activity for other mixtures of U-238. U-235 and U-234. if not known, shall be:

SA=3.6x10-1curles/gram U U-depleted SA=(0.4+0.38 E-+0.0034 E j 10-'

E->0.72 where E is the percentage by weight' of U-235. expressed as percent_

NoTE: In any case where there is a mixture in air or water of more than one radionuclide. the limiting values for purposes of this Appendix should be determined as follows

1. If the identity and concentration of each radionuc*de in the mixture are known, the limiting values should be derived as follows Determine, for each radionuclide in the mixture. the ratio between the quantity present in the mixture and the limit otherwise established in Appendix 8 for the specific radionuclide when not in a mixture. The sum of such ratios for all the radlonuclides in the mixture may not exceed '1" (Le.. "unity" EXAmPlE: If radionuclides A, B. and C are present in concentrations CA, C&, and Cc. and if the applicable MPC's. are MPC.,

and MPC., and MPCc respectively, then the concentrations shall be limited so that the following relationship exists:

(CA/MPCAJ+(C&/MPC2)+(CC/MPCc)

-<1

2. If either the identity or the concentration of any radionuclide in the mixture is not known, the limiting values for purposes of Appendix B shall be:

a. For purposes of Table I. Col. 1-6 x 10

b. For purposes of Table I. Col. 2-4x 10"

c. For purposes of Table II, Col. 1-2x 10"'

d. For purposes of Table H. Col. 2-3x 10

3. If any of the conditions specified below are met, the corresponding values specified below may be used in lieu of those specified in paragraph 2 above.

a. If the identity of each radionuclide in 'the mixture is known but the concentration of one or more of the radionuclides in the mixture is not known the concentration limit for the mixture isithe limit specified in Appendix "B" for the radionuclide in the mixture having the lowest concentration limit: or

b. If the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides specified in Appendix "B" are not present in the mixture, the concentration limit for the mixture is the lowest concentration limit specified in Appendix "B" for any radionuclide which is not known to be absent from the mixture; or B-10 ODCM Rev. 16

Nuclear Regulatory Commission Pt. 20 [§§ 20.1-20.6021, App. C Table I Table II Col.

Cot. 2--

Col. 1 -

Col. 2 c, Element (atomic number) and isotope Ai Water Air (l+/-Ci/

Water r,AtrljC/l (p.CO/Ml)

M l)

{tJ.A /m l)

If it is known that Sr 90. I 125. I 126, 1 129. 1 131 (I 133, Table 11 only), Pb m

210. Po 210. At 211. Ra 223. Ra 224. Ra 226. Ac 227. Ra 228. Th 230. Pa 231, Th 232. Th-nat, Cm 248. Cf 254. and Fm 256 are not presen L 9Xx1" 3x 10" If it is known that Sr 90. 1 125. 1 126. 1 129 (1 131. 1 133. Table II only). Pb 210. Po 210. Ra 223, Ra 226. Ra 228. Pa 231. Th-nat. Cm 248, Cf 254.

and Fm 266 are not present.......................

6x1 2x10' If it is known that Sr 90. 1 129 (1 125. I 126, I 131, Table It only). Pb 210. Ra 226, Ra 228. Cm 248, and Cf 254 are not present..

200-1....................

6xl1" If it is known that (I 129. Table I only). Ra 226. and Ra 228 are not present...........

3X10 1x10 7

If it is known that alpha-emitters and Sr 90. 1 129. Pb 210. Ac 227. Ra 228.

Pa 230. Pu 241. and Bk 249 are not present...................

3x1O' I x 1o "I...................

If it is known that alpha-emitters and Pb 210, Ac 227, Ra 228, and Pu 241 are not present................................................................................

3x 10"1 1 x10- 1...................

If it is known,.t alpha-emitters and Ac 227 are not present.....

3x1O ".....................

Ix10- =...................

if its known that Ac 227. Th 230. Pa 231. Pu 238. Pu 239. Pu 240. Pu 242.

Pu 244. Cm 248. Ct 249 and Cf 251 are notpresent..........

3x10-IX!0 -

4. If a mixture of radionuclides consists 01 urainium and its daughters in ore dust prior to chemical separation of the uranium from the ore, the values specrfied below may be used for uranium and its daughters through radium-226. instead of those from paragraphs 1. 2. or 3 above.

a. For purposes of Table I. Col. 1-1x10"L° ICi/ml gross alpha activity. or 5x10"" jCI/ml natural uranium or 75 micrograms per cubic meter of air natural uranium.

b. For purposes of Table II. Col. 1-3x10-* -ICi/ml gross alpha activty. 2x10" = CLi/ml natural uranium: or 3 micrograms per cubic meter of air natural uranium.

5. For purposes of this note, a radionuclide may be considered as 'not present in a mixture if (a) the ratio of the concentration of that radionuclide in the mixture (CA) to the concenlaltioil limit for that radionuclide specified in Table 11 of Appendix "B" (UPCA) does not exceed Vzo. (i.e. CA/MPCLS1_/10) and (b1) the sum of such ratios for all the radionuclides considered as not present in the mixture does not exceed V4 Le.

(CA/MPC,.+C/MPCS..... + 9/4).

ODCM Rev. 16 B-1I

APPENDIX C EMS SOFTWARE DOCUMENTATION ODCM Rev. 22 C-1

APPENDIX C EMS SOFTWARE DOCUMENTATION TABLE OF CONTENTS CONTENTS Effluent Management System Software Test Report for Seabrook Station, May 1994 Resolutions of EMS Software Test Report Discrepancies Software Requirements Specification for North Atlantic Energy Service Corporation, Seabrook Station, Effluent Management Systems, Revision 04, FP 75486 Technical Reference Manual, Effluent Management System NAESCO Seabrook Station, July 1994, FP 75486 C"

ODCM Rev. 22 r00 PAGES C-3 Cover ii 1-11 C-4 1-2 C-5 1-35 C-6 36-93 C-2

EMS SOFTWARE DOCUMENTATION ATTACHMENT 1:

EFFLUENT MANAGEMENT SYSTEM SOFTWARE TEST REPORT FOR SEABROOK STATION, MAY 1994 ODCM Rev. 16 APPENDIX C :

c-3

EFFLUENT MANAGEMENT SYSTEM:

SOFTWARE TEST REPORT FOR SEABROOK STATION MAY 1994 Prepared by Reviewed by Approved by

taeeY

'Elate bate Dat Date r(A:)

Yankee Atomic Electric Company Nuclear Services Division 580 Main Street Bolton, Massachusetts 01740

Table of Conte'nts

1.0 INTRODUCTION

I

1.1 Background

1 1.2 Acceptance Criteria.............

1 2.0

SUMMARY

OF FINDINGS.........

2 2.1 EMS Dose and Dose Rate Conversion Factors.......

2 2.2 Liquid Release Testing..................

4 2.3 Gaseous Release Testing.................

4 3.0 TEST CONCLUSIONS............

7 4.0

SUMMARY

OF DISCREPANCIES....................

9 References......................

.11 ii (7,

1.0 INTRODUCTION

Software testing as described in Reference [1] has been conducted for the Seabrook Station version of the Canberra Effluent Management System (EMS).

The results and conclusions are presented in this report.

1.1 Background

Canberra Industries Inc. developed the EMS software to assist nuclear power plant personnel track effluent emissions and perform associated dose calculations.

North Atlantic Energy Service Corporation purchased a Seabrook specific version the Canberra EMS software which must meet specific requirements and incorporate site-specific information provided in the Offsite Dose Calculation Manual (ODCM)

[2].

Software testing was conducted to provide assurances that the Seabrook EMS program produces results which are consistent with current ODCK assumptions and methods.

All executions of the EMS program were performed at Seabrook Station on the target software.

All executions of ODCM Method II were conducted at Yankee Atomic Electric Company in

Bolton, Massachusetts.

1.2 Acceptance Criteria The operability of the EMS software will be accepted if (i) information contained in the EMS data files is consistent with the ODCH, (ii) test results from the EMS program are consistent with results from ODCM methods, (iii)

Technical Specifications requirements are met by the EMS software, and (iv) the EMS software meets design specifications.

Final user (Seabrook) acceptance is contingent on Seabrook approval of verification testing results and criteria established by user needs.

2.0

SUMMARY

OF OBSERVATIONS The EMS software testing included (i) identifying appropriate meteorological set up data, (ii) review of dose and dose rate conversion factor development, (iii) assessments for liquid releases, and (iv) assessments for gaseous releases.

ODCM Method I was used initially to confirm dose results from the EMS program.

However, the simplified nature of ODCM Method I made it difficult to change the values of various parameters or obtain meaningful comparisons (other than "bottom line" comparisons).

The more adaptable ODCK method, Method II, was then used to confirm EMS doses.

Observations made during the software testing are summarized below.

2.1 EMS Dose and Dose Rate Conversion Factors The EMS software uses precalculated conversion factors which are contained in a data file. The dose conversion factors for both liquid and gaseous effluent releases were developed for four age groups (adult, teen, child and infant), and for specific organs (bone, livertotal body, kidney, lung, GI tract and skin).

The liquid release dose conversion factors in the EMS program are the summation of the components for water recreation and ingestion of aquatic foods.

The gaseous release dose conversion factors are exposure pathway-specific (e.g.,

inhalation, ground plane, milk ingestion, etc.).

Dose conversion factors are provided in the EMS program for all exposure pathways addressed in the ODCM.

The development of all dose conversion factors in the EMS program followed the pathway-specific equations in the Effluent Management System Technical Reference Manual [3].

The EMS conversion factors for several radionuclides were examined to determined that the development process was consistent to the Technical Reference Manual and the ODCM.

2

2.1.1 Liquid Release Dose Conversion Factors" Although the individual components for the ingestion of aquatic foods were found to be consistent with the ODCM, a discrepancy was discovered in the water recreation component.

The mixing ratio for shoreline activity used in the development of the EMS dose factors is equal to 0.025.

While this value is inconsistent with ODCM Method I (which employs a mixing ratio of 0.1),

it is consistent with ODCM Method II.

It is identified as a discrepancy because it is unclear which set of ODCM assumptions (those for Method I or those for Method II) the EMS program is expected to adopt.

2.1.2 Gaseous Release Dose Conversion Factors The EMS program uses dose conversion factors from Regulatory Guide 1.109 for assessment of noble gas releases.

The dose factors in the EMS program were verified against and found to be consistent with Table B-I of Regulatory Guide 1.109 [4].

The development methods for the other gaseous dose factors (i.e., for inhalation, ground plane, milk ingestion, meat ingestion, and ingestion of vegetables) were reviewed against applicable equations in the Technical Reference Manual and information in the ODCM.

It is noted that the dose factors for ingestion of milk and meat are based on the fraction of year that animals are allowed to graze on pasture land (Fp) equal to 1.0.

This is not consistent with the ODCM which calls for the use of an Fp value equal to 0.5.

The dose conversion factors in the EMS program for gaseous releases incorporate a shielding factor (SF) equal to 1.0.

The EMS program is designed with a way of changing the value of SF (via use of the Options Table), but the factor is applied uniformly to both doses and dose rates.

In contrast, the ODCM calls for the use of different values for SF in the calculations for doses and 3

dose rates.

2.2 Liquid Release Testing Dose estimates from the EMS program for hypothetical liquid effluent discharges (containing single nuclide and radionuclide mixtures) are nearly identical to results from ODCM Method II when input data are based on the same mixing ratio value, indicating that the calculation method used in the EMS program is consistent with the ODCM.

Additionally, the EMS routine(s) responsible for liquid effluent concentrations comparisons to MPC values and monitor set point determinations was observed to be operating properly.

2.3 Gaseous Release Testing The agreement between estimates for total body dose rates, skin dose rates, and air (gamma and beta) doses due to emission of noble gases from the ODCM methods and the EMS program is excellent, indicating that the EMS calculation method is consistent with the ODCM.

There is also excellent agreement between inhalation doses from the EMS program and ODCH Method II indicating that, for the inhalation pathway, the calculational method and assumptions in the EMS program are consistent with those in the ODCM.

The evaluation of the dose estimates via inhalation pathway included both long and short release durations for an elevated (mixed mode) and a ground level release point.

The excellent agreement between the EMS and ODCM Method II also confirms that the release duration adjustment term, t-a, is applied properly in the EMS program.

However, an incorrect receptor location was reported on the EMS printout in the tests (D-2c and D-2d) in which the Plant Vent was changed to be recognized as a ground level release point.

Also noted during testing was that the EMS routine(s) responsible for calculating effluent concentration-to-MPC ratios and radionuclide release rates 4

appears to be operating properly for gaseous-releases.

The EMS program incorporates the assumption that the fraction of elemental iodine is equal to 1.0 (consistent with NUREG-0133 [5]).

In contrast, the fraction of elemental iodine is assumed equal to 0.5 in the ODCM methods (consistent with Regulatory Guide 1.109).

Consequently, the EMS program produces dose estimates due to radioiodine that are at least a factor of two greater than doses from the ODCM methods.

This difference increases to about a factor of 4 when the current values for Fp and SF assumed in the EMS program and ODCM methods are used in the dose calculations.

The different assumptions for elemental iodine fractions should.not present a problem because each program is based on NRC guidance: the EMS is based on NUREG-0133, the ODCM methods are based on Regulatory Guide 1.109.

The EMS program takes the more conservative approach for determining doses from radioiodine.

Making appropriate adjustments for Pp, SF, and the fraction of elemental iodine (when radioiodine input was used) and comparing results for organ doses due to 1131, H3, Co60 and Cs137 revealed that the calculational methods used in the EMS program are consistent with the ODCM for all exposure pathways (i.e.,

ground plane, inhalation, milk ingestion, meat ingestion, and vegetables ingestion).

Technical Specification 3.11.2.1 and the ODCM require the calculation of organ dose rates due to effluent discharges of 1131, 1133, H3 and particulates with a half-life greater than 8 days.

However, in all test cases involving these types of nuclides, organ dose rate information did not appear on Page 4 of the EMS printout.

Instead, the message "No calculations performed - check Sample &

Receptors" appeared.

The EMS set up data and input were reviewed with no apparent error identified. Since the test cases included Cs137, Co60, 1131, and 5

H3, the missing dose rate information was uxiexpected.

It is noted that organ dose rate information was provided on Page 4 of the EMS printout during a demonstration of the EMS program prior to testing.

6

3.0 TEST CONCLUSIONS Although the dose conversion factors are based on information which is not completely consistent with the assumptions in the ODCM, the calculational methods used to determine doses from liquid and gaseous effluent discharges are consistent with the ODCM methods.

Other conclusions are:

1. As stated in Section 2.1.1, the development of the EMS liquid effluent dose factors is consistent with ODCM Method II, but not with Method I due to the mixing ratio value.

If the EMS program is intended to be a hybrid method, the dose factors are consistent with the ODCM and are acceptable.

On the other hand, if the EMS program is intended to provide automated ODCM Method I calculations, then the dose factor should be recalculated using a mixing ratio for shoreline activity equal to 0.1.

2.

Since the EMS program is not designed to support the use of two shielding factors* (one for dose rates and one for doses),

use of a shielding factor equal to 1.0 is acceptable with the understanding that, although the dose rates produced by the EMS program will be consistent with the ODCM, the doses from the EMS program will be based on a more conservative assumption than doses from the ODCM methods.

3. Under the normal ODCM assumption for elemental iodine, the results from the EMS program will be at least a factor of two greater than results from the ODCM methods.

The different assumptions regarding the elemental iodine fraction do not present a problem because each program is based on NRC guidance: the EMS program is based on NUREG-0133, and the ODCM is based on Regulatory Guide 1.109.

Of the two methods, the EMS program takes the more conservative approach toward estimating doses from 7

radioiodine in gaseous effluent.

4.

The radiation monitor set point determination method for liquid releases produces a set point value that is consistent the ODCH set point method.

5.

The EMS routine that is responsible for comparison of liquid effluent concentrations and HPC values is operating properly.

6.

The release duration adjustment term, t-1, is used consistently to the ODCM.

8

4.0 SUEKHARY OF DISCREPANCIES Discrepancy Area of Impact Potential Solution(s)

Mixing ratio for Doses associated with Clarify whether the EMS shoreline activity liquid effluent program is expected to used in EMS discharges.

follow ODCM assumptions program.

for Method I or Method II.

If determined to follow Method I, recalculate dose factors for liquid releases.

EMS dose factors Doses due to ingestion of Recalculate EMS dose based on Fp value milk and meat.

factors for milk and meat which is not ingestion pathways to consistent with incorporate Fp value ODCM.

consistent with the ODCM.

Accept added conservatism in EMS in calculations of doses via milk and meat ingestion pathways.

Shielding factor Doses associated with Accept use of SF -

1.0 and (SF) applied gaseous effluent the added conservatism for uniformly to dose discharges.

doses.

rates and doses in EMS program.

Modify EMS software to accommodate use of two values for SF (one for dose rates and one for doses).

Incorrect receptor Potential assignment of Discuss with Canberra.

location doses to the wrong identified on EMS receptor.

printout for ground level release point.

Assumed fraction Dose estimates due to Accept added conservatism of elemental iodine in gaseous in doses due to iodine.

iodine used in EMS effluents.

program differs Modify EMS software to use from ODCM methods.

fraction for elemental iodine that is consistent with ODCM.

9

(N)

C 10 Discrepancy Area of Impact Potential Solution(s)

Missing organ dose Technical Specification Discuss with Canberra.

rate information required dose rate not on EMS printout calculated.

for effluent discharges containing 1131, 1133, H3, and particulates.

References.

1.

Yankee Atomic Electric Company, Effluent Monitoring System Software Test Plan for Seabrook Station, May, 1994.

2.

NAESC, Station Offsite Dose Calculation Manual, Rev 13, 9/24/93.

3.

Southern Nuclear Operating Company Effluent Management System Technical Reference Manual (07-0545), January 1993.

4.

NRC Regulatoiy Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision I, October 1977.

5.

NRC NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978.

11

EMS SOFTWARE DOCUMENTATION ATTACHMENT 2:

RESOLUTIONS OF EMS SOFTWARE TEST REPORT DISCREPANCIES ODCM Rev. 16 APPENDIX C:

C-4

2.

Resolution of EMS Software Test Report Discrepancies The following discrepancy resolutions apply to the findings contained in the "Effluent Management System Test Report for Seabrook Station, May 1994" as noted on pages 9 and 10 (see Attachment #1 of Appendix C of the ODCM).

With the positive resolution of the discrepancies identified in the EMS dose code, use of EMS as a computerized alternative approach (designated as Method IA in the ODCM) to determine compliance with the radioactive effluent dose and dose rate limits is acceptable since the results are comparable with the currently approved dose methods.

Discrepancy:

Mixing ratio for shoreline activity used in EMS Program not equal to the value used in the ODCM Method I (Mp

- 1.0).

I Resolution:

The mixing ratio for the shoreline activity pathway in the EMS is consistent with the ODCM Method II approved value of 0.025, and therefore does provide for a calculated dose that is within the parameters already approved in the ODCM.

The use of the EMS code (ODCM Method IA) for calculating liquid doses is acceptable for determining compliance with the dose limits of the Technical Specifications without the need to modify the assumption used for the shoreline mixing ratio.

I Discrepancy:

EMS dose factors based on Fp (fraction of year animals are on pasture) value which is not consistent with ODCM.

I Resolution:

ODCM Method I assumes that the pasture season in the North East is 6 months long each year (Fp + 0.5).

Method II allows for the pasture fraction to be set equal to 0.0 for the first and fourth quarters which equates the non-growing period of the year.

The second and third quarters correspond to the growing season where the pasture fraction is assumed to be 1.0.

The EMS software assumes an Fp value of 1.0 for animal grazing (meat and milk pathways) for all conditions.

This is a moderately conservative approach compared to Method I and the off grazing season conditions modeled in Method II.

It is equal to the grazing season assumptions of Method II as applied in the second and third quarters.

As a result, the added conservatism in the EMS calculations for doses via milk and meat pathways are within acceptable margins and guidance provided in NRC NUREG-0133 for demonstrating compliance with Technical Specification dose limits.

No changes to the EMS software are necessary.

I Discrepanc :

I Shielding factors (SF) applied uniformly to dose rates and doses in the EMS program.

1

2.

Resolution of EMS Software Test Report Discrepancies (Continued) r Resolution:

The EMS program for gaseous releases incorporates a shielding factor (SF) equal to 1.0 for both dose rate and total dose determinations.

In contrast, both Method I and II use a SF value of 1.0 instantaneous dose rate calculations, but a value of 0.7 for integrated doses based on assumptions in NRC Reg. Guide 1.109.

The use of a SF equal to 1.0 for the external ground plane exposure pathway for both dose rate and total dose is a moderately conservative assumption that is within the bounds already assumed in the ODCM dose modeling.

As a result, no modification to the EMS code as an acceptable approach (Method IA) for demonstrating compliance with Technical Specification dose/dose rate limits is required for SF.

I Discrepancy:

Incorrect receptor location identified on EMS printout for ground level release point.

I Resolution:

Incorrect name is identified on report with no impact on dose or dose rate calculations which were verified to be correct.

I Discrepancy:

Assumed fraction of elemental iodine used in EMS program differs from ODCM Methods I and II.

I Resolution:

For ODCM Methods I and II, the fraction of elemental iodine assumed for gaseous releases in 0.5 based on the guidance in NRC Reg. Guide 1.109.

The EMS code assumes an elemental iodine fraction of 1.0 based on the guidance in NUREG-0133.

Consequently, the EMS program (Method IA) will produce a moderately conservative estimate of dose impact (factor of 2) for iodine radionuclides if present in the release estimations when compared to existing approved methods.

As a result, no modification to the EMS code is necessary for use in the ODCM for determining compliance with Technical Specification dose limits.

I Discrepancy:

I Missing organ dose rate information on EMS printout for effluent discharges containing 1-131, 1-133, H-3, and particulates.

I Resolution:

This required information is easily obtainable from the permit closure process with flashing indication if any dose or dose rate limits are exceeded.

2

EMS SOFTWARE DOCUMENTATION ATTACHMENT 3:

SOFTWARE REQUIREMENTS SPECIFICATION FOR NORTH ATLANTIC ENERGY SERVICE CORPORATION, SEABROOK STATION, EFFLUENT MANAGEMENT SYSTEMS, REVISION 04, FP 75486 ODCM Rev. 16 APPENDIX C:

C-5

Software Requirements Specification for North Atlantic Energy Services Corporation Seabrook Station Effluent Management Systems 48-8448 Revision 04 Nuclear Data Systems Division Software Product Originator:

Approved:

Engineering (Cl/NDS)

Pr&o8j anager (teabrook Station)

Date:___

Date:

//-X Date:

Date:

0/________

Software Requirements Specification Revision History Date 2/26/93 3/22/93 4/30/93 8/3/93 9/14/93 Revision 00 01 02 03 04 r

r initials DJH DJH DJH DJH DJH Description Initial version Updated incorrect dose equation Updated to include all dose and dose rate equations Updated based on modifications to software and customer's requested modification to the use of the default nuclide for gaseous permit processing.

Updated based on customer's request to remove modification to the default nuclide for gaseous permit processing.

RS-8448-04 7are--, cvý

Software Requirements Specification

1.

Scope 1

2.

Applicable Documents 1

3.

Interfaces 1

3.1 Hardware 1

3.2 Software 1

3.3 Human 2

3.4 Packaging 2

4.

Definitions 2

5.

Principal Changes from Existing Packages 2

6.

EMS Functionality 4

- 6.1 Database Maintenance Transactions 4

6.2 Editing Values through INGRES QBF 7

6.3 Liquid Pre-Release Processing 8

6.3.1 User Interface and Functionality 8

6.3.2 Associated Reports 9

6.3.3 Underlying Calculations 10 6.4 Liquid Post-Release Processing 11 6.4.1 User Interface and Functionality 11 6.4.2 Associated Reports 12 6.4.3 Underlying Calculations 12 6.5 Liquid Permit Editing 13 6.5.1 User Interface and Functionality 13 6.5.2 Associated Reports 13 6.5.3 Underlying Calculations 13 6.6 Liquid Permit Deletion 13 6.7 Gaseous Pre-Release Processing 14 6.7.1 User Interface and Functionality 14 6.7.2 Associated Reports 15 6.7.3 Underlying Calculations 15 6.8 Gaseous Post-Release Processing 21 6.8.1 User Interface and Functionality 21 6.8.2 Associated Reports 21 6.8.3 Underlying Calculations "22 6.9 Gaseous Permit Editing 27 6.9.1 User Interface and Functionality 27 6.9.2 Associated Reports 27 6.9.3 Underlying Calculations 27 6.10 Gaseous Permit Deletion 27 6.11 Semi-Annual Reporting 28 6.11.1 User Interface and Functionality 28 6.11.2 EMS Trend Plots 30 6.12 End-of-the-Year Data Archiving 30 6.12.1 User Interface and Functionality 30 RS-8448-04

Software Requirements Specification

1.

Scope This document establishes the software requirements for the Effluent Management System (EMS) software to be installed at North Atlantic Energy Services Corporation's Seabrook Station.

2.

Applicable Documents 2.1 The following two documents are included as part of this SRS, and this SRS refers to specific sections of them:

2.1.1 "Southern Nuclear Operating Company Effluent Management System Operator's Manual" (07-0544), Version 1, January 1993.

2.1.2 "Southern Nuclear Operating Company Effluent Management System Technical Reference Manual" (07-0545), Version 2, January 1993.

Note:

The above documents contain material (including screens and report formats) imported from final manuals for other EMS packages. Utility and plant names shown on screens and reports in these manuals are not significant, since they are determined by database data that will be customized to fit the Seabrook Station's usage.

2.2 The following document is a reference source for calculation methods of the EMS software. This SRS may refer to specific sections.

(

2.2.1 "Seabrook Station Offslte Dose Calculation Manual," Revision 12, January 1993.

3.

Interfaces 3.1 Hardware The EMS software shall run on the following CPU model: DEC Microvax 3100, Model 80.

3.2 Software The software shall be written under VMS version 5.4-2 or later, using INGRES version 6.4 or later. It shall be written in VAX/FORTRAN or VAX-DCL. Utility programs provided by INGRES that are installed on the hardware configuration may be used if applicable.

RS-8448-04

Software Requirements Specification 3.3 Human The user may be expected to have received operator training from the system manager, CanberralNDS, or the plant training department prior to using any part of the EMS software. Knowledge of INGRES or VMS shall not be assumed. The menus of operations are intended to be self-explanatory, but an Operator's Manual shall be developed.

The user may be expected to have enough knowledge of USNRC-regulated nuclear power plant effluent management to provide accurate and appropriate inputs, and to determine the validity of the software's results.

3.4 Packaging A distribution kit will be produced for the customer. Any removable medium supported by the operating hardware delivered to the Seabrook Station Is an acceptable distribution medium.

4.

Definitions EMS - Effluent Management System. Software for determining effluent monitor setpoints, tracking activity releases and dose impacts of individual releases, and generating semi annual release reports.

SRS - Software Requirements Specification.

SNC - Southern Nuclear Operating Company

5.

Principal Changes from Existing Package The following paragraphs summarize the principal changes to the existing software that are required for the Seabrook Station system, and are intended only as introductory material.

Specifics of the required Seabrook Station EMS functionality are presented in the following sections.

5.1 The EMS software will be developed by customizing the generic EMS package.

In general, the most important changes from previous versions are as follows:

5.1.1 Modification to Gaseous Permit Processing to allow scaling of nuclides for Plant Vent Spike release point.

5.1.2 Modification of noble gas dose rate and dose calculation methods to use a third set of X/Q values. RS-4K48-04

Software Requirements Specification 5.1.3 5.1.4 5.1.5 5.1.6 5.1.7 5.1.8 5.1.9 (7 C

Modification of noble gas dose rate and dose calculation methods to multiply X/Q and D/Q values by a factor depending on the release duration.

Modification to setpoint calculations to calculate setpoints for low gamma concentration releases.

Modification of Permit Processing to automatically correct the expected waste flow if it is greater than the calculated maximum waste flow.

Modification of Liquid Permit Processing to determine dilution flow rate based on the number of pumps operating.

Modification of the permit reports to include Month-to-Date Cumulative Doses and Alert Setpoints.

Modification of Post-Release Permit Processing to update the monitor response.

Addition of data to database to support and control the above operations.

RS-8448-04

Software Requirements Specification

6.

EMS Functionality 6.1 Database Maintenance Transactions The functionality of the EMS Database Maintenance transactions shall be described in section 2 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.1.1 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

" SCALNUC: For a gaseous release, a flag to denote that this release point will have nuclide concentrations scaled so that the total concentration matches a value entered by the user.

6.1.2 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)] and the Discharge Point Setpolnt transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

"DILOOKUP: For a liquid release, a flag to denote that permits for this release point will have a selection screen appear for the user to select the proper dilution flow for the release based on the number of pumps operating.

6.1.3 On the Release Point Setpolnt transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

"* DEFNUC: For a liquid or gaseous release, this parameter will contain the default nuclide that will be used in setpoint calculations for low gamma concentration releases. This parameter is used in conjunction with the DEFCONC parameter.

6.1.4 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

" DEFCONC: For a liquid or gaseous release, this parameter will contain the default concentration that will be used in setpoint calculations for low gamma concentration releases. This parameter is used in conjunction with the DEFNUC parameter.

RS-8448-04

Software Requirements Specification 6.1.5 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

DEF_TYPE: For a liquid or gaseous release, this parameter will contain the default nuclide type that will be used in setpoint calculations for low gamma concentration releases. This parameter is used In conjunction with the DEF__NUC and DEFCONC parameters. (Note: For a gaseous release, the default nuclide type shall determine which monitor setpoint should use the default nuclide and concentration.)

6.1.6 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

ALRTSET: For a liquid or gaseous release, this parameter will contain the multiplier to be used in the calculation of Alert Alarm Setpoints for permit reports.

6.1.7 On the Release Point transaction [EM-DM-RP (Form 1)], the meaning of the Response Option will change. When set to '";, this option will denote the display of a Monitor Response window during the Post-Release Permit Processing, rather than during the Pre-Release Permit Processing. The Response Option parameter, itself, will remain unchanged for this transaction, but the response entered should include the monitor background values.

6.1.8 On the Dilution Streams transaction [EM-DM-DS], the following parameters will be removed: the number of extra dilution flow rates and the four dilution flow rates.

These parameters will be replaced with two column fields. One column will contain the dilution flow rate, while another will contain the pump configuration description (such as "Jockey Pump" or "5"). In this transaction, the dilution flow rate for particular pump configuration can be added.

6.1.9 On the Meteorological Data transaction [EM-DM-ME (Form 1)], several menu options will added to the list of MET DATA TABLES. These additional menu items are as follows:

X/Q - Noble Gases (Gamma)

"a" Factor - D/Q-Part/iodines "ae Factor - Noble Gases "a" Factor - X/Q-Partfiodines "a" Factor - Gamma Noble Gases RS-4A48-04

Software Requirements Specification 6.1.10 On the Meteorological Data transaction [EM-DM-ME (Form 1)], the following menu items will be used to store short-term (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) D/Q and XJQ values.

D/Q - Partics/Radiolodines X/Q0- Partics/Radioiodines X/Q - Decayed Noble Gases X/Q - Noble Gases (Gamma)

Note:

This specification item only denotes a change in the meaning for the values on this transaction and requires no further changes to the software.

On the Meteorological Data transaction [EM-DM-ME (Form 1)], the X/Q, D/Q, and maw Factor values are defined for various elevations, distances, and directions from the plant vent or stack. This combination with the "mode of release" parameter on the Release Point transaction [EM-DM RP (Form 1)], and the receptor definition on the Gas Receptors transaction [EM-DM-GR], allow the X/Q, D/0, and "a" factors to be different for each receptor and/or release point.

Note:

This specification item is only for clarification and no additional code changes need to be made to this transaction.

Jay, 6.1.11 RS-8448-04

Software Requirements Specification 6.2 Editing Values through INGRES QBF In addition to the interactive forms-based EMS Database Maintenance transactions, certain flags and values must be edited through INGRES QBF on the database tables which contain data not accessible through the forms-based transactions.

6.2.1 Some columns of the Quarterly Dilution Volume table (QDVOL), which has no other use in the Seabrook Station version of EMS, will be used for recording monthly dilution volume for use in semi-annual reports. Once per month, an authorized user will use QBF to append a record to the QDVOL table as follows:

sampleid (sample ID) dvdate (dilution volume date)

(total volume)

(average flowrate) 0 [not used]

The first day of the month to which the volume applies (time not required).

Dilution volume for the month, in user units.

0 [not used] C )

tvol aflow RS-4M48-0.4

Software Requirements Specification 6.3 Liquid Pre-Release Processing 6.3.1 User Interface and Functionality Uquid Pre-Release Processing functionality for the EMS software shall be as described In section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.3.1.1 On the Uquid Permit Definition Screen (Screen 3.04):

Upon entering the permit definition screen, If the DILOOKUP parameter is set to "YV for the release point associated with the current permit being processed, the Dilution Flow Rate parameter will default to zero.

If a user uses the "Tab" or wReturn" key to exit the Dilution Flow Rate parameter on the Permit Definition Screen and the Dilution Flow Rate parameter has a value of zero, a selection screen with two columns of data will appear. One column will contain the pump configuration description, while the other will contain the dilution flow rate for each associated pump configuration.

Upon selection of the Dilution Flow Rate, the selection screen will disappear and the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. The cursor will then automatically advance to the Dilution Volume Parameter.

6.3.1.2 On the Uquid Permit Definition Screen (Screen 3.04):

When a "Fill* (F1 4) or a "Save" (F1 0) without a "Fill" is executed, if the DILOOKUP parameter is set to "Yu for the release point associated with the current permit being processed and the Dilution Flow Rate parameter is set to zero, a selection screen, as described above will appear.

Once a selection of the Dilution Flow Rate Is complete, the selection screen will disappear and the "Fill" operation will continue. Upon completion, the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen.

If the Dilution Flow Rate parameter on the Permit Definition Screen is not set to zero and the DILOOKUP parameter is set to "Y", the fill will proceed as normal without the dilution flow rate selection screen appearing. RS-8448-04

Software Requirements Specification 6.3.1.3 Prior to entering the Liquid Permit Approval Screen (Screen 3.09):

If It is determined that the computed maximum waste flow is less than the anticipated waste flow, the anticipated waste flow will be changed to have the value of the computed maximum waste flow. If the anticipated waste flow is modified, setpoint, dose, and dose rate values will be recalculated based on the new value.

6.3.1.4 For releases with low or zero gamma emitter concentrations that result in a pre-diluted MPC ratio less than 10%, a default concentration will be used for setpoint calculations. This default concentration will not be used for updating curie, dose rates, or dose totals.

The default nuclide will be attained from the DEFNUC parameter. The default concentration for this nuclide will be attained from the DEF_CONC parameter. The default type for this nuclide should be attained from the DEFTYPE parameter.

6.3.1.5 The Monitor Response Screens for Release Points and Discharge Points (Screen 3.08) will no longer appear while processing a Pre-Release Permit when the Response Option Is set to *Y" on the Release Point transaction [EM-DM-RP (Form 1)].

6.3.2 Associated Reports Liquid Pre-Release Permit Reports shall be as described in section 3 (pages 3-53 through 3-58) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.3.2.1 On the Pre-Release Permit Report (3.01), the Cumulative Month-to-Date Doses will appear on the page with the report category of Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all 'Open" and "Closedo permits Including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.

6.3.2.2 On the Pre-Release Permit Report (3.01), an Alert Alarm Setpoint will appear below the Max Monitor Setpoint Value. The Alert Alarm Setpoint will be calculated by using the multiplying the release point setpoint value by a multiplier specified with the ALRT_SET parameter mentioned above.

6.3.2.3 On the Liquid Special Report (3.02), an Alert Alarm Setpoint will appear below the Release Point and Discharge Point Setpoint values in the Radiation Monitor(s) portion of the report.

RS-4M48-04

Software Requirements Specification 6.3.2.4 RS-8448-04 On the Pre-Release Permit Report (3.01), the calculation of setpoint data for additional dilution flow rates (under Pre-Release Calculations) will use dilution flow rate values from the Dilution Streams transaction [EM-DM DS] for a specific dilution stream. Up to four dilution flow rates which are lamer than the dilution flow rate parameter entered on the Uquid Permit Definition Screen (3.06) will be used.

6.3.3 Underlying Calculations The calculations performed by the EMS software for Uquid Pre-Release Permits shall produce the same results as those described In Chapter 2 (sections 2.1-2.6) of the EMS Technical Reference Manual (Reference 2.1.2), with no revisions.

Software Requirements Specification 6.4 Liquid Post-Release Processing (r')

6.4.1 User Interface and Functionality Uquid Post-Release Processing functionality for the EMS software shall be as described in section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.4.1.1 On the Liquid Permit Definition Screen (Screen 3.13):

If the DILOOKUP parameter is set to "Y" for the release point and a user uses the "Tab" or "Return" key to exit the Dilution Flow Rate parameter on the Permit Definition Screen and the Dilution Flow Rate parameter has a value of zero, a selection screen with two columns of data will appear.

One column will contain the pump configuration description, while the other will contain the dilution flow rate for each associated pump configuration.

Upon selection of the Dilution Flow Rate, the selection screen will disappear and the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. The cursor will then automatically advance to the Dilution Volume Parameter.

6.4.1.2 On the Liquid Permit Definition Screen (Screen 3.13):

When a Fill" (F1 4) or a "Save" (F1 0) without a "Fill" is executed, if the DILOOKUP parameter is set to "Y" for the release point associated with the current permit being processed and the Dilution Flow Rate parameter is set to zero, a selection screen, as described above will appear.

Once a selection of the Dilution Flow Rate is complete, the selection screen will disappear and the "Fill" operation will continue. Upon completion, the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen.

If the Dilution Flow Rate parameter on the Permit Definition Screen is not set to zero and the DILOOKUP parameter is set to "Y", the fill will proceed as normal without the dilution flow rate selection screen appearing.

6.4.1.3 (Item removed since actual waste flow is known at time of post release processing.)

RS-4W48-04

Software Requirements Specification 6.4.1.4 The Monitor Response Screens for Release Points and Discharge Points (Screen 3.08) will appear while processing a Post-Release Permit when the Response Option is set to "Y" on the Release Point transaction [EM DM-RP (Form 1)]. These screens will appear following the Nuclide Concentration Screen (Screen 3.15). The monitor response values entered should include the monitor background values.

6.4.2 Associated Reports Liquid Post-Release Permit Report shall be as described in section 3 (pages 3-59 through 3-62 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.4.2.1 On the Post-Release Permit Report (3.03), the Cumulative Month-to-Date Doses will appear on the page with the report category of Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all "Open" and "Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.

6.4.3 Underlying Calculations The calculations performed by the EMS software for Liquid Post-Release Permits shall produce the same results as those described in Chapter 2 (section 2.7) of the EMS Technical Reference Manual (Reference 2.1.2), with no revisions. RS-8448-04

Software Requirements Specification 6.5 Liquid Permit Editing 6.5.1 User Interface and Functionality Functionality for editing liquid permits through the EMS software shall be as described In section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

The appearance and functionality of the liquid permit definition screen and the monitor response screen shall be modified as described for the Pre-Release stage in sections 6.3.1 and 6.4.1 above.

6.5.2 Associated Reports The permit report format and contents for edited open and closed liquid permits shall be as specified above for original permit reports, in sections 6.3.2 and 6.4.2, respectively.

6.5.3 Underlying Calculations The calculation methods for editing open and closed liquid permits shall be as specified above for original calculations, in sections 6.3.3 and 6.4.3, respectively.

6.6 Liquid Permit Deletion Functionality for deleting liquid permits through the EMS software shall be described section 3 or the EMS operator's Manual (Reference 2.1.1). C0 RS-448-04

Software Requirements Specification 6.7 Gaseous Pre-Release Processing 6.7.1 User Interface and Functionality Gaseous Pre-Release Processing functionality for the EMS software shall be as described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.7.1.1 On the Gaseous Permit Definition Screen (Screen 4.05):

The Initial Pressure and Final Pressure parameters shall be deleted.

6.7.1.2 On the Gaseous Nuclide Concentration Screen (Screen 4.06):

If the SCALNUC parameter is set to "Y", when exiting the Concentration Screen by hitting "Process* (Do), the user will be prompted for the total nuclide concentration of permit. The concentrations are then "scaled" and then stored internally. As a result, the concentrations displayed on the screen will remain unchanged. (See the Underlying Calculations section for Pre-Release Permit Processing for an explanation of the "scaling" of concentrations.)

NOTE: -This method requires the VAXGSP (F12) file transfer has occurred bringing the representative nuclide concentration values to the screen prior to "Save" of data.

6.7.1.3 For releases with low or zero gamma emitter concentrations that result in a pre-diluted MPC ratio less than 10%, a default concentration will be used for setpoint calculations. This default concentration will not be used for updating curie, dose rates, or dose totals.

The default nuclide will be attained from the DEFNUC parameter. The default concentration for this nuclide will be attained from the DEFCONC parameter.-The default type for the default nuclide should be attained from the DEFTYPE pýarameter.

6.7.1.4 The Monitor Response Screens for Release Points and Discharge Points (Screen 4.08) will no longer appear while processing a Pre-Release Permit when the Response Option is set to "Yo on the Release Point transaction [EM-DM-RP (Form 1)].

6.7.1.5 Prior to entering the Gaseous Permit Approval Screen (Screen 4.09):

If it is determined that the computed maximum waste flow is less than the anticipated waste flow, the anticipated waste flow will be changed to have the value of the computed maximum waste flow. If the anticipated waste flow is modified, setpoint, dose, and dose rate values will be recalculated based on the new value.

.14 RS-8448-04

Software Requirements Specification 6.7.2 Associated Reports (I

Gaseous Pre-Release Permit Reports shall be as described in section 4 (pages 4 49 through 4-58) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.7.2.1 On the Pre-Release Permit Report (4.01), the Cumulative Month-to-Date Doses will appear on the pages with the report category of Cumulative Dose at Site Boundary and Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all "Open" and "Closed" permits including the permit for which the report is being generated. These dose values will appear Immediately below the "This Release" row of doses.

6.7.2.2 On the Pre-Release Permit Report (4.01), the "scaled" noble gas concentrations shall appear on the Isotopic Identification page of the report if the SCALNUC parameter is set to "Y" for the release point where the release is being made.

6.7.2.3 On the Pre-Release Permit Report (4.01), the Noble Gas Alert Alarm Setpoint will appear below the Max Monitor Setpoint values. The Alert Alarm Setpoint will be calculated by multiplying the noble gas monitor setpoint value by a multiplier specified with the ALRT.SET parameter mentioned above.

6.7.2.4 On the Gaseous Special Report (4.02), the Noble Gas Alert Alarm Setpoint will appear below the Release Point and Discharge Point Setpoint values in the Radiation Monitor(s) portion of the report. It will be calculated as mentioned above.

6.7.2.5 On the Pre-Release Permit Report (4.01), the Initial and Final Pressure parameters will be removed from the Pre-Release Data section of page one of the report.

6.7.3 Underlying Calculations The calculations performed by the EMS software for Gaseous Pre-Release Permits shall produce the same results as those described in Chapter 3 (section 3.1-3.6) of the EMS Technical Reference Manual (Reference 2.1.2), with the following revisions and clarifications:

RS-8448-04

Software Requirements Specification 1 Dose Calculations will appear in the site specific technical reference manual as follows:

For Noble Gas Total Body Dose Rate (for vents or stacks < 80 meters):

Dt

=

shf - X/Qg

8 76 0-a

Fo ° z (Ki - QRiv) where Dt

= the total body dose rate due to gamma emissions by noble gas releases from ventv (mremnyr) shf

= shielding factor (dimensionless)

QRjv

= release rate of noble gas radionuclides, i, in gaseous effluents from vent or stack v ( pCi/sec).

Fo

= occupancy factor defined for the receptor at the given location (dimensionless)

Ki

=

total body dose factor due to gamma emissions for noble gas radionuclide I (mrem/yr per pCi/m3 )

X/Qg =

highest value of the noble gas 1-hour X/Q for gamma radiation for vent or stack v at the site boundary, (sec/m3 )

8 76 0 -a= adjustment factor used to convert the 1-hour X/Q value to an average 1 year X/Q value (dimensionless) where 8760 =

number of hours in a year

.-a

=

a" factor for gamma noble gas X/Q For Noble Gas Total Body Dose (for vents or stacks < 80 meters):

shf-Fo0 Z (Ki* QRiv) - X/Qg-t~a Db =

(5.256 - 105 / dur) where Dtb

=

total body dose from gaseous effluents (mrem) 5.256 ° 105 = number of minutes in a year dur

= duration of the release (minutes) 6.7.3.

RS-8448-04 I !I

Software Requirements Specification t-a

=

adjustment factor to convert the 1-hour X/Q value to the short term X/Q value for the release (dimensionless) where t

=

duration of release (hours) a

=

"a" factor for gamma noble gas X/Q For Noble Gas Skin Dose Rate (for vents or stacks < 80 meters):

Ds =

shf - Fo 0 1 QRiv [(Li - X/Q - 8760-b) + (1.11Mi - X/Qg. 8 7 6 0 -a)]

where Ds X10 1.11 b

=

skin dose rate from gaseous effluents (mremnyr)

=

highest value of the noble gas 1-hour X/Q for vent or stack v at the site boundary (sec/m3 )

=

air dose factor due to gamma emissions for noble gas radionuclide I (mrad/yr per pCV/m3 )

=

conversion factor from mrad to mrem

=

skin dose factor due to beta emissions for noble gas radionuclide I (mrem/yr per iCi/m3 )

= "a" factor for noble gas X/Q For Noble Gas Skin Dose (for vents or stacks < 80 meters):

shfs Fo" Z QRiv [(

XQ t-b) + (1.11 M,. X/Qg t'a)]

(5.256 105 / dur) where Dsk

= total skin dose from gaseous effluents (mrem)

ý A

RS-8448-04

' Software Requirements Specification

For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80 meters):

Dy

=

(3.17 - 10"8) - X/Qg. t-a - F0 xh Mi!

Qiv where SD

=

total gamma air dose from gaseous effluents (mrad) 3.17

10-8 = inverse of number of seconds in a year Qiv

=

release of noble gas radionuclides, i, in gaseous effluents from vent or stack v (/Ci)

Qiv

=

QRiv

dur - 60 where 60 = number of seconds in a minute For Noble Gas Air Dose due to beta radiation (for vents or stacks <

80 meters):

Dp

=

(3.17 -10

~X/Q.fbF 0

t

~

e

ii D.

= (3.7

108)

/ *tb - Fo

X: Ni - Qiv where Dp

= total beta air dose from gaseous effluents (mrad)

Ni

= air dose factor due to beta emissions for noble gas radionuclide i (mrad/yr per pCVm3 )

For Critical Organ Dose Rate-inhalation Pathway and all Pathways for H-3, C-1 4 (for vents or stacks < 80 meters):

DR ra =

WaQr 8760"c ° I Pipa - QRiv where DR.a =

dose rate for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem/yr)

Pipra = dose factor for each radionuclide i, pathway p, organ T, and age group a (mrem/yr per pCi/mr) RS-8448-04

Software Requirements Specification War

=

highest value of the radioiodine/particulate 1-hour X/Q for vent or stack v at the site boundary (sec/m3 )

o

=

Wa factor for Radioiodine/Particulate X/Q Note:

It is assumed Pip*a will not contain long term X/Q or D/Q values.

For Critical Organ Dose Rate--Ground and Food Pathways (for vents or stacks < 80 meters):

DRTa =

D/Q

8760-d

RipTa aQRiv where D/Q

=

highest value of the 1-hour deposition factor at the distance of the site boundary (1/m2 )

d

= "a factor for D/Q RipTa = dose factor for each radionuclide i, pathway p, organ T, and age group a (m2

mremrn/yr per pCi/sec)

Note:

It is assumed RipTa will not contain long term X/Q or D/Q values.

For Critical Organ Dose-Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 meters):

DTa

=

(3.17-10-8 ) X/Qr'tc-Fo0 ZPipTa °Qiv where Dra Note:

It is assumed PipTa will not contain long term X/Q or D/Q values.

= dose for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem) r\\

N C

C RS-848-04

Software Requirements Specification For Critical Organ Dose-Ground and Food Pathways (for vents or stacks < 80 meters):

D~a

=

(3.17,10-8),D/Q~t-d*Fo-ZRipra*Qiv Note:

It is assumed Rip~a will not contain long term X/Q or D/Q values.

6.7.3.2 On the Nuclide Concentration Screen (Screen 4.06), nuclide concentrations will be "scaled* If the SCALNUC parameter is set property for a Release Point. This "scaling" is described as follows:

Cinew = (t I

s) Ci where

'Cinew

= concentration (after "scaling") of nuclide, s

= sum of all nuclide concentrations on the Nuclide Concentration Screen.

t

= total nuclide concentration entered by the user Co

= concentration (before "scaling") of nuclidel fcv RS-4W48-04

Software Requirements Specification 6.8 Gaseous Post-Release Processing C>

6.8.1 User Interface and Functionality Gaseous Post-Release Processing functionality for the EMS software shall be as described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.8.1.1 On the Gaseous Permit Definition Screen (Screen 4.14):

The Initial Pressure and Final Pressure parameters shall be deleted.

6.8.1.2 On the Gaseous Nuclide Concentration Screen (Screen 4.15):

If the SCALNUC parameter is set to "Y", when exiting the Concentration Screen by hitting "Process" (Do), the user will be prompted for the total nuclide concentration of permit. The value entered for the total nuclide concentration while opening the permit shall be displayed as a default value which can be modified. Once the value is entered/accepted the concentrations are then "scaled" and then stored internally. As a result, the concentrations displayed on the screen will remain unchanged. (See the Underlying Calculations section for Post Release Permit Processing for an explanation of the "scaling" of concentrations.)

NOTE: 'This method requires the VAXGSP (F12) file transfer has C

occurred bringing the representative nuclide concentration values to the screen prior to "Save" of data.

6.8.1.3 The Monitor Response Screens for Release Points and Discharge Points (Screen 4.08) will appear while processing a Post-Release Permit when the Response Option is set to "Y" on the Release Point transaction [EM DM-RP (Form 1)]. These screens will appear following the Nuclide Concentration Screen (Screen 4.15). The monitor response values should include the monitor background values.

6.8.1.4 (item removed. since actual waste flow is known at time of post release processing.)

6.8.2 Associated Reports Gaseous Post-Release Permit Reports shall be as described in section 4 (pages 4-58 through 4-63) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: C, RS-8448-04

Software Requirements Specification 6.8.2.1 On the Post-Release Permit Report (4.03), the Cumulative Month-to-Date Doses will appear on the pages with the report category of Cumulative Dose at Site Boundary and Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all "Open" and "Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.

6.8.2.2 On the Post-Release Permit Report (4.03), the "scaled" noble gas concentrations shall appear on the Isotopic Identification page of the report if the SCALNUC parameter is set to "Y" for the release point where the release Is being made.

6.8.2.3 On the Post-Release Permit Report (4.03), the Initial and Final Pressure parameters will be removed from the Pre-Release Data section of page one of the report.

6.8.3 Underlying Calculations The calculations performed by the EMS software for Gaseous Post-Release Permits shall produce the same results as those described in Chapter 3 (section 3.7) of the EMS Technical Reference Manual (Reference 2.1.2), with the following revisions and clarifications:

6.8.3.1 Dose Calculations will appear in the site specific technical reference manual as follows:

For Noble Gas Total Body Dose Rate (for vents or stacks < 80 meters):

Dt

= shf X/Qg. 8760"a - Fo.

z(Ki. QRiv) where Dt

= the total body dose rate due to gamma emissions by noble gas releases from vent v (mrem/yr) shf

= shielding factor (dimensionless)

QRiv

= release rate of noble gas radionuclides, i, in gaseous effluents from vent or stack v ( pCi/sec).

F0

= occupancy factor defined for the receptor at the given location (dimensionless)

K.i

= total body dose factor due to gamma emissions for noble gas radionuclide I (mrem/yr per yCi/m 3 ) S RS-8448-04

Software Requirements Specification X1Qg

=

highest value of the noble gas 1-hour X/Q for gamma radiation for vent or stack v at the site boundary, (sec/m3 )

8 76 0 "a= adjustment factor used to convert the 1-hour X/Q value to an average 1 year X1Q value (dimensionless) where 8760 = number of hours in a year a

=

wa" factor for gamma noble gas X/.

For Noble Gas Total Body Dose (for vents or stacks < 80 meters):

shf* Fo0 Z (Kij QRiv) - X/Qg-t-a Db =

(5.256

105 / dur) where Dtb

= total body dose from gaseous effluents (mrem) 5.256* 105 = number of minutes in a year dur

= duration of the release (minutes)

(.)

t-a

= adjustment factor to convert the 1 -hour X/Q value to the short term X/Q value for the release (dimensionless) where t

=

duration of release (hours) a

=

a" factor for gamma noble gas X/Q For Noble Gas Skin Dose Rate (for vents or stacks < 80 meters):

Ds =

shf Fo ° z QRiv * [(L1_ X/Q - 8760-b) + (1.11Mi

. X/Qg

8760"a)]

where Ds

=

skin dose rate from gaseous effluents (mrem/yr)

X/O

=

highest value of the noble gas 1-hour X/O for vent or stack v at the site boundary (sec/m3 ) 1C,-

RS-8448-04

Software Requirements Specification Mi

= air dose factor due to gamma emissions for noble gas radionuclide I (mrad/yr per pCVm 3 )

1.11

=

conversion factor from mrad to mrem

= skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per yiCVm 3 )

b

=

"a" factor for noble gas X/Q For Noble Gas Skin Dose (for vents or stacks < 80 meters):

Dsk

= -shf

Fo* 0X QRiv - [(Lj X/O - t-b) + (1.11 Mi

X(Og. t'a)]

(5.2565 105 / dur) where Dsk

=

total skin dose from gaseous effluents (mrem)

For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80 meters):

-Dy

=

(3.17 10"8 )*XQgt-a4°Fol*ZMiQiv where Dy Y

=

total gamma air dose from gaseous effluents (mrad) 3.17

10-8 = inverse of number of seconds in a year Qv ff= release of noble gas radionuclides, i, in gaseous effluents from vent or stack v (pCi)

Qiv

=

QRiv - dur ° 60 where 60 = number of seconds in a minute RS-8448-04

SSoftware Requirements Specification For Noble Gas Air Dose due to beta radiation (for vents or stacks <

80 meters):

Dp

= (3.17*10"8).X/Q.tb*Fo0 zN1 *Qiv where Dp

= total beta air dose from gaseous effluents (mrad)

N1

= air dose factor due to beta emissions for noble gas radionuclide i (mrad/yr per pCVm 3)

For Critical Organ Dose Rate-Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 meters):

DRTa =

Qr 87600" ° PipTa "QRiv where DRTa = dose rate for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrermfyr)

PipTa =

ndose factor for each radionuclide,i pathway p, organ T, IPa=and age group a (mrem/yr per IzClm 3)

X/Or

= highest value of the radioiodine/particulate 1-hour X/Q for vent or stack v at the site boundary (sec/m3 )

c

= "a" factor for Radioiodine/Particulate X/Q Note:

It is assumed PipTa will not contain long term X/Q or D/Q values.

For Critical Organ Dose Rate-Ground and Food Pathways (for vents or stacks < 80 meters):

DRTa =

D/Q - 8760"d

Z Ripra ° QRiv where D/Q

= highest value of the 1-hour deyosition factor at the distance of the site boundary (1/me) d

=

Ma" factor for D/Q C RS-8448-04

Software Requirements Specification RipTa = dose factor for each radionuclide i, pathway p, organ r, and age group a (m2. mrem/yr per MCVsec)

Note:

It is assumed Rip~a will not contain long ternr X/Q or D/Q values.

For Critical Organ Dose-Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 meters):

DTa

=

(3.17

10"8)

X/Qr

t' a Fo

Z PipTa"* Qiv where DTa

=

dose for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem)

Note:

It is assumed Pip*a will not contain long term X/Q or D/Q values.

For Critical Organ Dose-Ground and Food Pathways (for vents or stacks < 80 meters):

DTa

=

(3.17.10"8).D/Qft4-Fo. ZRipTa. Qiv Note:

It is assumed RIPza will not contain long term X/Q or D/Q values.

6.8.3.2 On the Nuclide Concentration Screen (Screen 4.15), nuclide concentrations will be 'scaled" if the SCALNUC parameter is set properly for a Release Point This "scaling" is described as follows:

Cinew = (t I s)- Ci where Cinew = concentration (after "scaling") of nuclide, s

= sum of all nuclide concentrations on the Nuclide Concentration Screen.

t

= total nuclide concentration entered by the user Ci

= concentration (before "scaling*) of nuclidei RS-8448-04

Software Requirements Specification 6.9 Gaseous Permit Editing (N*

6.9.1 User Interface and Functionality Functionality for editing gaseous permits through the EMS software shall be described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

The appearance and functionality of the gaseous permit definition screen, the monitor response screen, and nuclide concentration shall be modified as described for the Pre-and Post-Release stages in sections 6.7.1 and 6.8.1 above.

6.9.2 Associated Reports The permit report format and contents for edited open and closed gaseous permits shall be as specified above for original permit reports, in sections 6.7.2 and 6.8.2, respectively.

6.9.3 Underlying Calculations The calculation methods for editing open and closed gaseous permits shall be specified for original calculations, in sections 6.7.3 and 6.8.3, respectively.

6.10 Gaseous Permit Deletion Functionality for deleting gaseous permits through the EMS software shall be described section 4 or the EMS operator's Manual (Reference 2.1.1). RS-8448-04

Software Requirements Specification 6.11 Semi-Annual Reporting 6.11.1 User Interface and Functionality Semi-Annual Reporting functionality for the EMS software shall be as described in section 5 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.11.1.1 On Report 5.01 (Gaseous Summation of All Releases):

a Compute each value on line A.3 of the report by taking the greater of I where 100 Dag / QLag 100 : Dab / QL-a Dag = the gamma air dose in the applicable quarter at the site boundary receptor due to noble gas emissions (mrem)

Dab = the beta air dose in the applicable quarter at the site boundary due to noble gas emissions (mrem)

QLag = the quarterly limit on Dag (mrem) [usually 5]

QLab = the quarterly limit on Dab (mrem) [usually 10]

A note will be made at the bottom of the report stating whether the beta air dose and its associated limit or gamma air dose and its associated limit were used for the Percent of Applicable Limit of Fission and Activation Products..

The values on lines B.3, C.3, and D.3 will be the equivalent. They will be calculated as follows:

the greatest (over ") of 1 100l(Z Di,T)/Q L RS-8448-04

Software Requirements Specification where Di,T = the dose to organ T of the controlling receptor, in the applicable quarter, due to gaseous emissions of radionuclide i (mrem)

The summation is over all non-noble gas radionuclides with half-lives greater than 8 days, including radioiodines, particulates, and trtium.

QLrp = the quarterly limit on the controlling receptor organ dose due to gaseous effluents (mrem) [usually 7.5]

6.11.1.2 On Report 5.02 (Liquid Summation of All Releases):

"For each quarter q in the report, calculate the reportable dilution volume (DVrq, in liters) for the portion of the quarter that is within the report dates. It is the sum of the reportable monthly dilution volumes (DVrm) in user units for all the months in the quarter that are within the report dates:

DVrq = 28.31685 - sdlvolf

X DVrm The values DVrm are from the column tvol of the QDVOL table. The value DVrq Is included in the report on line F, and Is used in the calculations below. "sd Ivolr should be the user unit conversion factor to convert from user units to ft3. 28.31685 is a unit conversion factor fromC ft3 to liters.

"For each space on a line titled "AVERAGE DILUTED CONCENTRATION DURING PERIOD-, the average concentration (Cq, in pCI/ml) for the respective quarter is computed as follows (where I ranges over only the nuclides in the category):

.Cq = Z Ciq = Z [Actiq / (1000 - DVrq)]

where Actiq

= total activity of nuclide i released during the portion of the quarter q that is within the period (p Ci)

DVrq

= reportable dilution flow for the portion of quarter q that is within the report period (liters), as calculated above.

Compute each value on line A.3 and B.3 of the report by taking the greater of J 100

DIt / QLft 100

Dio I OLIo RS-8448-04

Software Requirements Specification where Dft

= the liquid total body dose in the applicable quarter at the site boundary receptor (mrem)

Dio

= the liquid maximum organ dose in the applicable quarter at the site boundary (mrem)

QLft =

the quarterly limit on Dit (mrem) [usually 1.5]

QL10 = the quarterly limit on Dio (mrem) [usually 5]

A note will be made at the bottom of the report stating whether the liquid total body dose and its associated limit or maximum organ dose and its associated limit were used for the Percent of Applicable Umit.

Compute each value on line C.3 of the report as follows:

Pq = 100 I

Cq / Ldg where Cq

=

sum of noble gas concentrations Pq

=

Percentage applicable to a given quarter for dissolved and entrained gases Ldg

=

Uquid dissolved gas limit (pCVml) [usually 2.OE-04]

6.11.2 EMS Trend Plots Trend Plotting functionality for the EMS software shall be described in section 5 of the EMS Operator's Manual (Reference 2.1.1) with no revisions.

6.12 End-of-the-Year Data Archiving 6.12.1 User Interface and Functionality End-of-the-Year Data Archiving functionality for the EMS software shall be described in section 6 of the EMS Operator's Manual (Reference 2.1.1) with no revisions. RS-8448-04

Documentation Review Report Document Reviewed Does the document meet the requirementss or No Is the document approved?* or No if not please state the exceptions:

C Signature:

Date:

'/

00-5792

(

A0,0

'17,OAJ E)PS Rj-V4'99-044 1?S f

W-r-M A f..'& 4W.

Document Reviewed Documentation Review Report Does the document meet the requiremenits? or No Is the document approved?(ýi or No It not please state the exceptions:

Signature:

C-.

Date:

I/,?11 7.

00-6792

'4ýA,6c-

APPENDIX C: EMS SOFTWARE DOCUMENTATION ATTACHEMENT 4: TECHNICAL REFERENCE MANUAL, EFFLUENT MANAGEMENT SYSTEM NAESCO SEABROOK STATION, JULY 1994, FP 75486 ODCM Rev. 22 C-6

Canberra Industries, Inc.

Printed in U.S.A.

OXX Ruzz Jj@';

.1

This manual contains proprietary information; no part of it may be reproduced or used in any form or by any means - graphic, electronic, or mechanical, including photocopying, recording, or information storage and retrieval systems - without the written permission of Canberra Industries.

The information in this manual describes the product as accurately as possible, but is subject to change without notice.

Printed in the United States of America.

fn37 A0

TABLE OF CONTENTS Page CHAPTER 1 INTRODUCTION..........................................................................................

1.1 SETPOINT CALCULATIONS.....................................................................................

1.2 RELEASE PROCESSING..........................................................................................

1.3 COMPOSITE NUCLIDES.......... !.........................................................................

CHAPTER 2 LIQUID RELEASE CALCULATIONS...........................................................

2.1 LIQUID PRE-RELEASE PERMIT.............................................

2.2 1 0CFR20 COMPLIANCE......................................................

Dissolved and Entrained Gases........................

2.3 MAXIMUM W ASTE FLOW..........................................................................................

2.4 MINIMUM DILUTION FLOW RATE.....................................................................

2.5 SETPOINTINS Recommended Setpoil t

Setpoiflt in pCi/mI...............................

Recommended Setpoint in User Units (e.g. cpm)..............................

Setpoint for Discharge Point........................................................................

Setpoints in pCi/sec...........................................................................................

2.6 DOSE CALCULATIONS FOR LIQUID RELEASES..................................

2.7 31 DAY PROJECTED DOSE CALCULATIONS..................................

2.8 POST-RELEASE PROCESSING..............................................................................

CHAPTER 3 GASEOUS RELEASE CALCULATIONS........................................

3-1 3.1 GAS PRE-RELEASE PERMIT.............................................................................

3.2 RADIONUCLIDE ACTIVITIES AND COMPOSITE VALUES......................

.3 Activ.ty Relea.sed............................................................................................

3.3 10CFR20 COMPLIANCE...................................................

3.4 SETPOINT DETERMINATION...........................................................................

Noble Gases.......... !............................................

Naooblne G ases Particulate.......................................................

Radioiodinles arid Particulates..........

3. 4a SETPO INTS..............................................................................................................

3.4b REPORTED SETPOINTS................................................

Setpolnts in pCi/se o...........................................................................................

3.5 MAXIMUM WASTE FLOW....................................................................................

3.6 DOSE RATE AND CUMULATIVE DOSE CALCULATIONS......................................

Noble Gas Dose and Dose Rate Calculations..................................................

Pi C>IxJD t

rb-V 2.2-(oir A-.

i -li C(.i 0.

1-1 1-2 1-3 1-3 2-1 2-1 2-1 2-4 2-4 2-5 2-5 2-8 2-8 2-10 2-11 2-13 2-13 2-17 2-18 3-1 3-1 3-2 3-2 3-5 3-5 3-6 3"-6 3-10 3-11 3-12 3-12 3-12

Organ Dose Calculations...........................................................

............. 3-15 3.7 RESOLVING DOUBLE-COUNTING OF DOSE AND ACTIVITY............................

3-16 3.8 31 DAY PROJECTED DOSE CALCULATIONS........................................................

3-17

3.9 GAS POST-RELEASE PROCESSING.......................................................................

3-18 CHAPTER 4 LIQUID DOSE FACTOR EQUATIONS........................................................

4-1 4.1 POTABLE WATER....................................................

4-2 4.2 AQUATIC FOODS PATHWAYS................................................................................

4-2 4.3 SHORELINE RECREATION PATHWAY....................................................................

4-3 4.4 IRRIGATED VEGETABLE PATHWAY.......................................................................

4-4 4.5 REDUCTION TO NUREG-0133 EQUATIONS...........................................................

4-5 CHAPTER 5 GAS DOSE FACTOR CALCULATIONS.....................................................

5-1 5.1 INHALATION PATHWAY............................................................................................

5-1 5.2 GROUND PLANE PATHWAY..... *.........

5-2 5.3 MILK PATHWAY............................ a..........................................................................

5-2 Carbon-14 in Milk........................................................................................

5-4 Tritium in Milk....................................................................................................

5-4 5.4 MEAT PATHWAY......................................................................................................

5-5 Carbon-14 in Meat..................................

5-5 Tritium in Meat...................................................................................................

5-6 5.5 VEGETABLE PATHWAY...........................................................................................

5-6 Carbon-14 in Vegetables...............................................

5-7 Tritium in Vegetables.....

5-7 5.6 REDUCTION TO NUREG-0133 EQUATIONS..........................................................

5-7 APPENDIX A REFERENCES...........................................................................................

A-1

ii f53

CHAPTER 1 INTRODUCTION The Effluent Management System (EMS)

Software implements the requirements for determining limits and doses for the routine liquid and gaseous releases from nuclear power plants.

The calculations and methodology are based on those described in U.

S.

Nuclear Regulatory Commission Regulatory Guide 1.109 and references described therein.

These equations reduce to those described in NUREG-013 3 by proper selection of parameters.

This manual describes the calculations used in the LRW/GRW program for handling liquid and gaseous releases and preparing the semi annual report, and the equations used in the DFP option for calculating the relevant dose factors.

This manual describes the new 10CFR20 (1992) as well as old 10CFR2Q requirements.

For a nuclear power plant, the Off-Site Dose Calculation Manual (ODCM) describes the methods used at that plant for complying with the effluent release portions of the technical specifications and the requirements of 10CFR20 and Appendix I of 10CFR50.

The concentration and dose limits that are required to be met are:

o For radioactive liquid effluents, the concentrations released to areas beyond the site boundary are limited to:

MPC values given in old 10CFR20, Appendix B, Table I1.

OR ECL values given in new 10CFR20, Appendix B, Table 2.

where ECL values are effluent concentration limit values.

"o For radioactive liquid effluents, the maximum dose to any member of the public will be less than the limits given in 10CFR50, Appendix I.

"o For gaseous effluents, the old 10CFR20 requires that the dose rate at any location beyond the site boundary will be limited to the annual dose limits given in the Technical Specifications and corresponding to the concentrations in Appendix B of the old 10CFR20.

The old 10CFR20 approach for gaseous effluents has been accepted by the NRC for use under the new 10CFR20.

1-1 Q}GM r'z

r.

C.

"O For gaseous effluents, the maximum dose to any member of the public will be less than the limits given in

10CFR50, Appendix I.

"o The maximum dose to any member of the public will not exceed the limits given in 40CFR190.

The equations employed for calculating the dose and dose factors are taken from NUREG-0133 1 and Regulatory Guide 1.109.2 For a particular nuclear plant,. the ODCM describes the physical configuration of release sources and release points for routine and non-routine liquid and gaseous effluents, the monitor setpoint calculations, dose, and dose rate calculations.

.1.1 SETPOINT CALCULATIONS Calculations are made for the radiation monitors to determine the alarm/trip setpoint so that IOCFR20 compliance is met.

For the old IOCFR20 compliance, liquid calculations use the maximum permissible concentrations from 10CFR20 App.

B, Table 2, column 2, and the more conservative value (smaller) of the soluble and insoluble values while gas calculations use dose rate equations and limits from NUREG-0133.

To comply with the new 10CFR20 requirements, the effluent concentration limits are used for liquid setpoint calculations.

For gaseous setpoint calculations under the new 10CFR20, the NRC is still allowing the use of dose rate equations and limits from NUREG-0133..

In the terminology of EMS, individual sources of radiation, such as storage tanks, the-containment building, etc.,

are defined as "release points." Several release points may lead to the same "discharge point."

Setpoint calculations produce monitor limiting values in activity units (pCi/ml or PCi/cc).

These are then converted to user units, e.g. counts per minute (cpm).

For gaseous releases, setpoint can be reported as release rates (pCi/sec):.

The reporting units for each monitor can be defined separately.

EMS allows setpoints to be set for both the release points and the discharge points.

In the case that the release point and the discharge point are the same, or use the same physical monitor, the same discharge setpoint value is reported for both.

This use of the same discharge setpoint value can be disabled.

1"2

~L4j

For continuous releases, many installations prefer not, to generate an actual pre-release permit, but for the sake of analogous operation, pre-release calculations must still be made in EMS.

After review, the post-release calculations are made to update the database.

EMS does not allow more that one open release at a time for a single release point.

However, multiple releases may be open for one discharge point.

Also, for discharge points, the setpoint is calculated by summing over all open releases for the time period involved. An alternative approach if a new permit must be opened before the actual information for the previous permit are available is to go ahead and close the release using the pre-release values and then edit this closed release later when the actual information becomes available.

1.3 COMPOSITE NUCLIDES The standard radionuclide analysis, with high-resolution germanium detectors, quantifies the gamma-emitting radionuclides.

Pure beta emitters, nuclides that decay by Ik-capture, and alpha emitters are handled with other detection mechanisms.

These are usually not tracked individually by sample, but as a composite of many samples over a month or quarter period.

The concentrations of the composite nuclides are combined with the concentrations of the individual nuclides determined from gamma analysis for each sample.

1-3 C.

C '.

o xw. Ce.vZZ_

EMS has a "nuclide specific" option.

In this option only the nuclides listed in the monitor slope table are used in the setpoint calculations.

1.2 RELEASE PROCESSING For batch releases, the processing of releases consists of sampling the tank or volume of air, analyzing the radionuclide content, then using the radionuclide concentrations and -estimated release flows, volumes, etc. and calculating the doses and setpoints, comparing to the IOCFR20 limits, and comparing to the 10CFR50 limits.

If the limits are not exceeded, the pre-release permit is signed off and the release can occur.

After the release, post-release processing performs the same calculations (except the setpoints are not needed) and the database is updated with the actual. values for the release.

For liquid releases, the composite nuclides are generally H-3, Fe-55, Sr-8 9, Sr-90, and gross alpha.

For gaseous releases, Fe-55 is generally not included.

In EMS, these are contained in an editable file designated by the composite ID number.

Each release point definition specifies which composite ID is used with the release point.

These can be the composite nuclides, or any other nuclides desired.

Composite samples produced by taking portions of the samples from individual releases are analyzed after the releases are over.

Since these generally do not vary much from one period to the next, it is common to use the most recent values.

However, EMS provides the option of updating the composite values for the proper time period and recalculating the activity and dose. values in the database.

The EMS composite update process processes only those nuclides listed in the Composite ID for-the release point. For each nuclide, the curies and doses based on the previous value are subtracted from the cumulative totals and the curies and doses based on the correct value are added into the cumulative totals.

For the setting of flags to control options in the EMS code, see the NAESCO Seabrook Station EMS Operator's Manual 07-0589.

1-4 Aa~~e.Z 4

C

CHAPTER 2 LIQUID RELEASE CALCULATIONS 2.1 LIQUID pRE-RELEASE PERMIT A liquid pre-release permit is generated with a program that uses the nucli'de activities to determine the radiation monitor setpoint (for 1oCFR20 compliance) and the potential doses for 10CFR50 compliance.

Continuous releases are treated similarly.

2.2 10CFR20 COMPLIANCE 10CFR20 compliance calculations are broken down into two paths.

The first path calculates compliance with the old 10CFR20. in which the calculations are based on Maximum Permissible Concentrations.

The second path complies with the new 10CFR20 and is Effluent Concentration Limits based.

10CFR20 requires that the sum of concentrations divided by MPC (old 10CFR20) or ECL (new 10CFR20) values must not exceed unity for MPCs or I0 for ECLs:

OLD 10CFR20 S

= Z. C /MPC.

5 1 ii 3

OR 1 NEW 10CFR20 S = ZI C /ECL.

< 10 I

for concentrations Ci released from the site.

MPCi is the maximum permissible concentration from the old loCFR20, Appendix B, Table II, Column 2, for nuclide i and ECLi is the effluent concentration limit from the new 10CFR20, Appendix B, Table 2, Column 2, for nuclide i.

2-1 C.

If the summation is greater than the limit, then dilution is required.

The required dilution factor is:

If the 10CFR20 option is OLD:

C.

req f

R max where Dreq = Total required dilution factor Ci

=

Concentration of nuclide.i in pCi/mL MPCi = Maximum permissible concentration of nuclide i in Pci/mL f

=Release point setpoint safety factor (usually equal to.

0.5) from the release point definition.

Rmax The maximum MPC ratio from the release point setpoint definition.

If the 10CFR20 option is NEW:

C.

1 ECL.

D

-i=g 1

"reqrg f

0 R max C.

1 ECL.

D i=ng L

req, ng f

0 R max D

=

D req req,.g

+

Dreq,ng where D

Required dilution factor for ganma-emitters Dreq, g Dreqng=

Required dilution factor for non-galmma-emitters ECLi Effluent concentration limit of nuclide i in 2-2 Ctcp/%Lk (ci/Za?_

and the sums extend over gamma-emitters (g) and non-gamna-emitters (ng),

respectively Any nuclides with MPCi 5 0 are excluded from thesum.

Any nuclides with ECLi 5 0 are excluded from the sum.

The available dilution flow is the minimum dilution stream flow that can be ensured for the period of the release, corrected for other releases in process and any.activity in the dilution stream, and reduced by a safety factor.

F avail = ant (f f/100) (1 - Z C./XXX.)

where Ci

= Concentration (Pci/mIl) for nuclide i for the dilution stream sample XXXj

=

mpci or ECLi ff

= Flow safety factor, in percent Fant = Anticipated dilution flow rate for the release.

The anticipated dilution factor is then Dat = ( Fwaste+ f alloc F avail )/F waste where Fwaste waste flow anticipated for this release F a l= available dilution flow fraction of availabli dilution stream flow allocated to alloc this release 2-3 P5 4 L9 O.DUV%- Rc'v 7--Zý

Dissolved and Entrained Gases To implement 10CFR20, it is also required that the total concentration of dissolved and entrained gases in liquid effluents be less than a specified value (normally, 2 E-04 pCi/mL under OLD.

10CFR20, or 1 E-04 pCi/mL under NEW 10CFR20).

EMS stores this limit in the Activity Limits transaction, checks this limit for each liquid permit, and indicates on the permit approval screen whether or not it is exceeded.

To include dissolved noble gases in the Dreg calculation, the database must also contain the same limiting value, as the liquid MPC or ECL for each noble gas nuclide.

2.3 MAXIMUM WASTE FLOW The maximum waste flow calculation is based on the setting of the SETOPT option in the WFLOWM class of options in the Release Point Setpoint definition.

This option can take on four values:

NONE, NWAS (no waste),

CALC or DOSE.

For liquid releases, NONE,

NWAS, and CALC are allowed.

For liquid releases, Wmax = the minimum of Rwmax and Rcwmay where Wma=x = Maximum permissible waste flow rate for this release Rwmax

= Release point maximum waste flow rate, as set in the release point definition If the SETOPT option-NONE:

Rcwax-= waste flow rate for the sample, Fwaste If the required dilution factor, Dreq (section 2.2) for the sample is greater than 1, Rcwmx becomes:

Favail fallbc R

R'wniax Dreq 1.0 If the SETOPT option = CALC Favail

falloc + Fwaste Rcwmax*

Dreq 2-4 L-

if the SET-OPT option = NWAS Favail

falloc

-cwrDax =

Dreq 2.4 MINIMUM DILUTION FLOW RATE If Dreq > 1, the minimum dilution flow rate is determined as follows:

If the SETOPT option is NWAS:

Fwaste Dreq C.

min_df low =C alloc" 0(ff

/ 100)

[

I-

]

3.xxx.

where XXXi is MPCi under OLD 10CFR20, and is ECLi under NEW 10CFR2o.

If the SETOPT option is other than NWAS:

Fwaste 0 (Dreq -

1.0) mindflow C.

f~aioc * (ff / 100)

[ i-

i.

x

]

Otherwise:

min dflow = 0.0 2.5 SETPOINT CALCULATIONS Setpoints are calculated for individual release points, and for the discharge point that may combine several release points.

A setpoint adjustment.factor, Sadj is determined from the value of Dreq-C.

2-5 P35Lb eA2-2.

If Dreq > 1 or the dilution factor option is N,

and the setpoint equation is set to STD:

Sadj = Dant / Dreq If the dilution factor option is Y, and 0 < Dreq < 1.0 or if the dilution factor option is Y, and the setpoint equation is set to NO DIL, then no credit is taken for dilution, and the setpoint adjustment factor is:

Sadj = I/Dreq If neither of these conditions is true, Sadj =0.

After the above tests, further tests are made based on the setting of the setpoint equation option, SETPEQN.

These ma change Sadj as follows:

If the SETP-EQN is set to DILUT, and Fwaste > 0, then:

Fant + Fwaste 5adj Ewaste If the SETPEQN is set to STD, and the SETOPT option is set to

NWAS, and Fwaste > 0, then:

falloc 0 Favail Sadj =

Fwaste

Dreq Otherwise, if the SETPEQN option is set to STD, and the SETOPT option is set to other than NWAS, and Fwaste > 0, then:

(falloc 0 Favail) + Fwaste Sadj=

Fwaste

Dreq Otherwise, if the SETPEQN option is set to LOWACT, and the SETOPT option is set to NWAS, and Fwaste > 0, then:

(falloc 0 Favail)

Dreg, ng Fwaste Sadj Dreq, g

,2-6 f

2

Otherwise, if the SETPEQN option is set to LOWACT, and the SETOPT option is set to other than NWAS, and Fwaste > Q, then:

(falloc 0 Favail) + Fwaste Dreqfng Fwaste Sadj =

Dreq, g Otherwise, Sadj is unchanged.

The setpoint adjustment factor is further tested against a limiting value (Sadjflim which is set using the.Release Point transaction in Database Maintenance)

If Sadj > Sadj,lim then Sadj Sadjlim All of this leads to the maximum setpoint value, Smax, based on the gamma-emitting radionuclide mix:

Smx (pci/mi) = Sadj Z C.

where the sum extends over all gamma-emitting nuclides (nudlides of type other than 0) in which their concentrations are.greater than 0.

in user units (cpm or other as set in the Flow Monitor* Parameters transaction in Database Maintenance),

the maximum setpoint is:

Smax (cpm) = Sadj (Rmon B)

+

B where B

= monitor background (cpm)

Rmon

= monitor response (cpm)

= offset + slope 9 Z CI + quad * (Z Ci) 2

+ B where offset, slope, and quad are the coefficients in a quadratic fit to the monitor response to nuclide activity.

(0 2-7 DCA& M4,wf L2

EMS provides an option to calc~ulate nuclide specific responses so that Rmon is the sum of responses for each nuclide, rather than the sum of the nuclide concentrations, as shown above.

In the nuclide specific case, 2

R Z Eoffset.+ slope.* C.

+ quad. 0 (Ci) ] + B mon 1

1 1

where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest.

Recommended Set-oint The setpoint recommended for actual use is based on a comparison of the maximum setpoint calculated as above, to setpoints based on expected response time a tolerance factor (to allow for variations in monitor response during release) and to default values determined by the user.

The user can restrict which setpoint 'value is usually reported by what values are used when setting these tolerance factors and default setpoint values.

The default setpoint in user units (e.g. cpm). can be defined with or without background included.

If the cunitnopt parameter (defined in the release point and discharge point tables) equals 0, the-default value does not include background; and the current background is added to the default value to get the reported-default setpoint.

Otherwise, the current background is not added to the default value.

Setpoint in UCi/ml Note:

In this version of the software, the reported setpoint is the user units setpoint. The setpoint calculations using the original concentrations (pCi/ml) is still being done by the software and stored in the sampledata table. To get reported setpoints in pCi/ml, the monitor slope should be set to 1.0 in the Release Point transaction of Database Maintenance and the UNITS parameter for the monitor should be set to pCi/ml in the Activity Monitors transaction.

If the Isotopic specific response option is turned on for the release point,.then this individual nuclide slopes in the Monitor Slopes can be used to map the response from the nuclide to that of a monitor calibration source (e.g.

Cs137 equivalent response) 2 -'SP-5

C.

A candidate setpoint is calculated based on the expected response:

S e,= f I C exp tol C.

where f t=

setpoint tolerance factor (can be set for the fto= release point using QBF)

= 2 if not specified by the user Now compare the Sexp value to the default table value Sdef:

If Sexp < Smax and if Sexp< S def d Sdef S m then use Sdef Case 1 Otherwise use Sexp.

Case 2,5 If Sexp 2_ Smax use Smax.

Case 3 If Smax = 0, use Sdef Case 4 Case 4 occurs if no activity is detectable in the-sample (Sadi = 0).

C.

2-9 PD c S2

Case 1 Case 2 Case 3 Case 4 Case 5 Sexp ----

Sdef ---

Smax Smax Smax Smax Sexp Sexp Sde f -...

Sde f...

Sdef.....

Sde f -.

0 0 0

0 ---

Use Sdef Use Sexp Use Smax Use Sdef Use Sexp Schematic of Liquid Setpoint Cases Recommended Setpoint in User Units (e.g. cpm)

The candidate setpoint based on expected monitor response is calculated as follows:

S (cpm) fto (R

- ~B)

+ f tleB Sexp(Cm

=tol (mon-

)+fBtol where fBtol = background tolerance factor (set using QBF on the releasept table) if. the default setpoint value includes background:

2-1*0 SfY$M

- ~42.2.

r.

if the default setpoint value does not include background:

Brp=B where B is the monitor background count rate and Brp is used below.

If Sexp (cpm)

< Smax (cpm) and if Sexp (cpm) < Sdef (cpm) + B3p and Sdef (cpm).+ Brp Smax (cpm) then use Sdef (cpm) + Brp Otherwise, use Sex (cpm)

If Sexp (cpm) > Smax (cpm) use Smax (cpm)

If Sma-x (cpm) = 0, use Sdef

+ Brp 1OTE:

Smax is due to concentration only (i.e.,

excludes background) for Case 4 Setpoint for Discharqe Point For the discharge point, the total MPC/ECL fraction is:

Tc.MPC.)o

" F

+ ( ZC /lPC.) - F F

+F OR

(

C /ECL.)

F

+ (

C./ECL.)

F F

+ F 0

2-11 Case 1 Case 2, 5

Case 3 Case 4.

Th@'

P5 6LI Dm v r

where (7' Ci/MPCi o= total MPC fraction for existing concurrent releases for this discharge point excluding this additional release.

Z Ci/1PCi =

total MPC fraction for the new release (Z Ci/ECLi )o=total ECL fraction for existing concurrent releases for this discharge point, excluding this additional release.

z Ci/ECLi =

total ECL fraction for the new release F

=

discharge point waste flow excluding new the release point waste flow to be added.

F =

projected waste flow for the new release point to be added The radiation monitor for the discharge point has setpoint equations identical to those presented above for the release points with the following exceptions:

1.

The LOW ACT setpoint equation option is not. supported.

2.

For the nuclide-specific response, the concentrations are modified as in:

dP = C

[F/(F + F )J R' =

X (offset.+ slopei. Cdp + quad (cap mon2 dpmon

3.

+ quad.

0 C~)

where C#p

= the discharge point isotope concentration from this release point Rdpmon = the discharge monitor response in user units Rdpmono= the discharge monitor response before the current release is added including the background 2-12 9

ONCYV\\ Y-GV 2 C.

where:

The sum extends over all time periods.

DiTr = the cumulative dose or dose commitment to the total body or an organ T by nuclide i for receptor r from the liquid effluents for the total time period of the release, in mrem.

AiTr = site-related ingestion dose or dose commitment factor for receptor r to the total body or organ T for radionuclide i, in mrem/hr per pCi/ml.

AiTr is available as an editable

table, but can be recalculated with different parameters and pathways with the Dose Factor Processing (DFP) option.

The 2-13 obcw_ Ie Z-?

For non-isotope specific response:

Rdpmono=l[ offset + slope 9 CdP + quad * (CdP) 2

] + Rdpmono where CdP =

X Z Ci] [F/(F+FO)]

Setpoints in UCi/sec Setpoints in units of pCi/sec can be obtained by setting the UNITS parameter for the monitor to "pCi/s"t or "pCi/sec" (Case sensitive.

Ist 5 characters must match) in the Activity Monitors transaction and setting the monitor slope to 1.0 as in the pCi/ml setpoint calculation. The user units setpoint, as calculated above for the setpoint in pCi/ml units, will be multiplied by the corresponding effluent flow rate (release point or discharge point) for the monitor to get a reported setpoint in pCi/sec.

2.6 DOSE CALCULATIONS FOR LIQUID RELEASES The EMS software calculates and stores the dose for each receptor, for-each nuclide, and for each organ.

The dose is the total over all pathways which apply to that receptor.

A receptor is defined by receptor ID, age group (infant, child, teen, or adult),

sector, and distance from the plant.

The equation used in the liquid permit processing to calculate the dose received by receptor r from a released nuclide i is:

D A

2 At S Ci F Dirt n.ATr ts is sr C,.0 C.

equations used are presented in Chapter 4 of this manual.

Ats =

length of time period s, over which the concentration and F value are averaged, for all liquid releases, in hours.

the average concentration of radionuclide i

in undiluted liquid effluent during time period Ats from any liquid release, in pCi/ml.

Fsr = the near field average dilution factor for receptor r during any liquid effluent release.

F w F

sr Denom The value of Denom depends upon several variables and nested if statements. The derivation of the Denom value is shown in the logic and equations shown below.

2-14 c~b w,.-

ksJ Z-Z

C.

Denom = 1000.

end of if denom is too large end of if denom is greater than 0.0 Denom = Denom / (Uf/60) 2-15 P3,56.

If the STREAMFLO option in the OPTIONS Table is set to Y, then Denom

=

Fstrm *

(Uf /60)

(Rmix) else (river stream flow is not used)

If the denomtyp option from the options Table is 1, (dose from a dilution stream) then Denom=

(Uf/60)

(1/Rmix)

Else if denomtyp is 2,

(dilution flow i ncludes waste flow) then Denom

= Fdil 0 (UTf/60)

(I/Rmnj) else (denom typ is not 1 or 2) if the QVOPT option in the OPTIONS table is set to ON, (dilution flow is from the QDVOL table) then Denom = (tw + Fqvol)

(Uf/60)

(1/Rrni-)

else (the normal standard calculation)

Denom = (Fw + Fdil)

(Uf/60)

(I/Rmi.)

end of if on QVOPT option end of if on denom typ option end of if on stream flo option If Denom is greater than 0.0 then If Denom > 1000. and option to limit the denominator is Y,

then

Where:

FstRm=

River stream flow past the site in user liquid flow rate units.

The value used during permit processing is the value obtained from the STATIONDATA table.

The..value is entered into the STATIONDATA table using the QBF.utility.

If the value is to be changed

often, it would be possible to write a command procedure which get the value from the user and write it into the table.

Fw flow rate of undiluted waste effluent in user liquid flow rate units.

Uf/60 = Flow rate units conversion factor for liquid releases/60. Uf converts from user units to CFM so this-factor converts to CFS.

Fdil =flow rate of the dilution flow in user liquid flow rate units.

- U=,

=

mixing ratio

= fraction of the release that reaches the receptor.

Separate mixing ratios are stored for each pathway for each receptor.

A mixing ratio of zero for a pathway receptor indicates that the pathway is not present for the receptor.

The first non-zero value is used in the dose calculation.

The different mixing ratios for the pathways are incorporated into the composite Ai factors calculated by the dose factor processing (DFP) progralm.

FqvoI= Flow rate from user entered quarterly dilution flow rate. These values are from the AFLOW column of the QDVOL table for the release..

If stream flow option is being used and the average river stream flow is known at the time the liquid release is processed, then the command procedure which runs the liquid permit processing could be modified to ask for the stream flow value and put it into the stationdata table before the permit is processed. If the average river stream flow is not known at the time the liquid release is processed, then some other provision must be made for correcting the cumulative dose totals in the CUMDOSE table so that it is based on the correct stream flow value.

if the average stream flow for 2-16

C.

the month is used, then each liquid release point entry in the CUMDOSE table for the month could be multiplied by the ratio of the actual stream flow for the month divided by the default value contained in the STATIONDATA table.

Caution: Since there is no record stored in the database of what stream flow value was used to calculate the dose values, the user must verify that no correction is applied more than once to each dose value.

2.7 31 DAY PROJECTED DOSE CALCULATIONS The 31 Day Projected Dose values appear on the Standard and Special Permit Reports.

The Projected Dose values are calculated as f ollows:

DpT = (Dr T @P) + D aT where:

DpT =the 31 Day-Projected Dose by organ T, by reactor unit DT =the total dose in mrem by organ T, by reactor unit for the quarter containing the release start date from all closed and open releases when an answer of "Y" is specified for the "Update Totals" field on the release point definition screen.,

p

=the Projection Factor which is the result of 31 divided by the number of days from start of the quarter containing the release start date to the end of the release.

The quarterly and annual projection values on the standard pre-release report use a projection factor with 92 days or 365 days instead of 31 days in the numerator and do not include the additional anticipated dose term.

DaT =Additional Anticipated Dose for liquid releases by organ T and quarter of release by reactor unit.

NOTE:

The 31 day dose projections on the Approval/Results screen is the site total for all units.

2.8 POST-RELEASE PROCESSING After the release is made, actual concentrations are used to check 1oCFR20 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

2-17 P5 AI

("V r.-. 0

For batch releases, the duration is determined from the start and end dates and times, and is used with the volume input to calculate the release rate.

Dose calculations are the same as for the pre-release, but with actual release flow rates and release duration.

Setpoint calculations are not performed at the post-release stage.

P3 5:

2-18

CEIAPTER 3 GASEOUS RELEASE CALCULATIONS The "annual average X/Q"' method is used, in which fixed X/Q and D/Q values are used for each receptor for all dose calculations, regardless of actual wind direction and speed prevailing during a given release.

Doses are calculated for each receptor location and age group specified in the Gas Rec.eptors transaction.

The controlling individual is the age group and location which receives the maximum organ dose.

3.1 GAS PRE-RELEASE PERMIT The pre-release permit is produced by a program that uses user entered estimates of flow rates and release times to calculate doses and activities.

The dose rate from the potential release is added to the maximum dose rate occurring for all other releases during the duration of this release for 10CER20 compliance.

The noble gas or air doses and the organ doses are checked against the corresponding limits for 10CFR50 corpliance.

3.2 RADIONUCLIDE ACTIVITIES AND COMPOSITE VALUES The radionuclide results are read from one set of composite activity database records, and from three spectrum analysis result files, and saved in an activity array; If a nuclide appears in more than one spectrum, only the last value read for that nuclide is used.

In case of duplication, the one not desired should be edited out of the nuclide list.

The saxrples are read in the following order:

3-1 C.

esbcIv-R.-V -z-z

I. Composite Records

2. Particulate File

3. Radioiodine File

4. Noble Gas File The activity (Qi) and the activity release rate Q

are calculated for each nuclide i.

Activity Released For the plant stack and turbine building vent:

Qi = C1 e V.

28316.85

UF 0 le-6 (pCi) =(pCi/ml)(cubic feet) (ml/cubic feet) where:

Vv = vent release volume in user units (usually FT3 )

Cr = concentration in pCi/ml.

UF = the flow-rate units conversion factor which converts from user units to CFM Note:

The Ci value also includes the scaled noble gas nuclides for a release (if any exists).

The activity release rate in pCi/sec is

= Ci

Vf 9 28316.85

UF/60 For containment purge:

i=

Ci pump release rate (CFM)

- 28316..85 UTF/60 Q duration of release (min)"-

60 3.3 10CFR20 COMPLIANCE The maximum dose rate during the release is determined by summing together the dose rates for this release, with all concurrent releases'in the database for the time of the release.

3-2

r.

Z shf I.

[ V.

Qi. ] <

500 mrem/yr

falloc*fs Elevated Stack z: 80m Z. shf (L.

+ 1.lMi) 1 M (X/Q)

Qiv]

< 3000 msem/yr f

Sv r iv OR Z shf X.M(.

WO/)

+ 1.13

.I<00 Bmy v

1 [.

r ir iv

<.3000 mRem/yr

falloc s

Elevated Stack t 80m where the terms are defined below.

(b)

Release rate limit for all radionuclides and radioactive materials in particulate form, with half lives greater than 8 days:

i I E [f P.

W Qi ] < 1500 niRem/yr

falloc fs rp v

p p

my where :

The database contains all releases for which both pre-and post release reports have been made (the post-release program enters the data into the cumulative totals).

Pre-releases that have not been completed, and which occur during the release under consideration, are also added into the maximum dose rate to account for releases not yet added to the cumulative totals.

The three dose rates (whole body, skin, organ) are compared to the old 10CFR20 limits (old and new 10CFR20 are described below) as defined in the Dose Limits transaction in Database Maintenance.

The dose rate at or beyond the site boundary due to gaseous effluents from the site is limited to:

(a)

Release rate limit for noble gases:

X.K. shf Z [ (X--)

Qi

< 500 mRem/yr f

f 1 vyr iv alloc s OR C-.

3:-3 PD 6Lf

i =

index over all radionuclides v =

index over all vents or stacks for the unit p =

index over all pathways r =

index for receptor locations Ki =

the total body dose factor due to gamma emissions for noble gas radionuclide i, in mrem/yr per pCi/m3.

Li =

the skin dose factor due to beta emissions for noble gas radionuclide i, in mrem/yr per pCi/m3*

Vir = the elevated plume gamma total body dose factor for nuclide i at receptor location r, in mrem/yr per pCi/sec.

Mi=

the air dose factor due to gamma emissions for noble gas radionuclide i, in mrad/yr per pCi/m:3.

Bir = the elevated plume gamma skin dose factor for nuclide i at receptor location r, in mrad/yr per pCi/sec.

1.1 =

mrad to mrem conversion factor in mrem/mrad pip = the dose factor for the critical organ for nuclides other than noble gases for the inhalation pathway (in units of mrem/yr per pCi/m3 ) and for ground plane and food pathways (in units of m2 (mrem/yr per pCi/sec)).

The most restrictive age group is used.

f

=

factor to select which pathways are included in the calculation.

Factor = 1 to include a pathway, 0 to exclude.

Wmv=

(X/Q) mv for tritium and the inhalation pathway and =

(D/Q) v for other nuclides and pathways.

(X/Q-)vr = the highest value of the annual average atmospheric dispersion factor at the site boundary, for all sectors, in sec/m 3.

(4Qmy = the highest value of the annual average atmospheric dispersion factor at the distance of the site boundary, for all sectors, in sec/m3.

3-;-4 N

C),bcvv--- Q4 2--c-

500 =

3000 =

site dose rate limit for whole body in mrem/year.

site dose rate limit for.skin in mrem/year 1500 = site dose rate limit for any organ in mrem/year shf noble gas dose shielding factor falloc= fraction of the dose limit allocated to this release point fs =

safety factor for the release point 3.4 SETPOINT DETERMINATION Setpoints are determined from Dose Rate Limits set forth in the Technical Specifications and stored in the Dose Limits Table.

The ratio of dose rate limit to dose rate for a single release point is given below for these three cases:

Noble Gases nratio = rg lesser of the ratios (total body dose rate limit/tlotal body dose rate) and (skin dose rate limit/skin dose rate)

= for a vent release, lesser of 500 mrem/yr shf X.K (X/Q) iv my 3-5

td ci.

K-i.

(D/Q)mv = the highest value of the annual average deposition factor at the distance of the site boundary, for all sectors, in m 2 Qiv =

the average release rate o.f nuclide i in gaseous effluent from release point v, in pCi/sec.

Noble gases may be 'averaged over a period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and any other nuclides may be averaged over a period of 1 week.

and 3000 mrem/yr shf Z (L

+ 1.1M.

Q*

(X/Q) 1 1

iv my

= for an Elevated Stack 2 80m, lesser of 500 mrem/yr shf Z V. i Q

i r i

and 3000 mrem/yr shf X [ L.

(X/Q)

+ l'iB.i]

Qi Radioiodines and Particulates In these cases, the ratio is obtained by summing over the appropriate nuclide indices:

1500 mrem/yr rpratio =

maximum organ dose rate IPi " Qiv 0 Wmv When the sum is over nuclides and the inhalation, ground plane and cow's milk pathways are all turned on.

3.4a SETPOINTS Setpoints are determined for radiation monitors on individual release points, and also for radiation monitors at the discharge points that may combine the effluent from several release points.

Calculations for the monitor response are made for noble gases, radioiodines, and particulates.

For a release point, the expected monitor response to a given nuclide concentration is:

Rmon = monitor response (cpm).+ B

= offset + (slope

Z Ci] + [quad

(

Ci) 2 ] + B 3-6 p

I rev Z' -z_

C.

where offset, slope, and quad are the coefficients in a quadratic fit to the monitor response to nuclide activity, and B is the monitor background.

EMS provides an option to calculate nuclide specific responses so that Pmon is determined from the response for each nuclide, rather than the sum of the nuclide concentrations, as shown above.

In that

case, P-mon

. 2

( offseti + [slopei a Ci] + [quadi -

( Ci) 2])

+ B

The expected response for discharge points is based on the sum of the expected response for releases already in progr~ess plus the expected response due to release point being considered.

R R

+ X [offset.+ slope.

Cp

+ quad.

0 (C p) 2 dpmon=

dpmono i

3.

where Cp

=

C.. (F

/F dp i

rp d

CA

= concentration for the release point m@

3S-7 ObC~nA Cc-'J Z, 0@

Frp flow rate for the release point Fdp flow rate for the discharge point Rdpmon = discharge point monitor response for the release in progress Rdpmono= the discharge monitor response before the current release is added including the background and offseti, slopei and quadi are the quadratic response coefficients of the discharge point monitor.

Non-isotope specific response:

RZn = offset + slope (Z C#)

+ quad' (aC~

p) 2 +Rdpmon 0

All other equations are the same as for the individual release

point, but use the discharge point monitor response and the discharge point allocation factor and.safety factors.

EMS allows for setpoint calculations based on the standard or response method.

Thus, each release point will have associated with it, a

setpoint equation: STD or RESP.

This can be set in the Release Point (Setpoint) transaction of Database Maintenance.

If the release point setpoint equation = STD The limiting setpoint for the monitor (in pCi/ml) is given by:

Max s

alloc "ratio

SUM The limiting setpoint for the monitor (in user units, e.g.,

cpm) is given by:

SUmax =fs falloc

ratio

(Rmon -B)

+ B 3-.8

offset = I.

2.

3.

slope

1.

2.

3.

quad

- 1.

2.

3.

noble gas offset factor radioiodine offset factor particulate offset factor noble gas slope factor radioiodine slope factor particulate slope factor noble gas quadratic factor radioiodine quadratic factor particulate quadratic factor fs safety factor for the release point falloc = dose rate allocation factor for the release point ratio

1. nratio for noble gases

2. rpratio for radioiodines

3. rpratio for particulates SUM

=

2.

3.

Rmon =

2.

3.

Z noble gas concentrations, for noble gases I radioiodine concentrations, for radioiodines I particulate concentrations, for particulates noble gas monitor response radioiodine monitor response particulate monitor response B

=i. observed background response for the noble gas monitor

2. observed background response for the radioiodine monitor

3. observed background response for the particulate monitor NOTE :Separate calculations are made for noble gases, radi6iodine, and particulates The limiting setpoint for gaseous releases is determined separately for noble gases, radioiodines, and particulates for each release point and discharge point.

)

3-9 4

where I C)

if the release point setpoint equation-= RESP :

The reported setpoint for the monitor (in pCi/ml) now becomes:

Smax=mrtol (SUM - B)] + (mrtolb e B)

The limiting setpoint for the monitor (in user units, e.g.,

cpm) now becomes:

SUmax = [mrtol * (Rmon

-B)]

+ (mrtolb

B) where mrtol

=

1.

monitor response tolerance factor (noble gas)

2.

monit-or response tolerance factor (radioiodine)

3.

monitor response tolerance factor (particulate)

SUM

=

as defined above B

=

as defined above

.mrtolb

= I.

monitor tolerance background factor (noble gas)

2.

monitor tolerance background factor (radioiodine)

3.

monitor tolerance background factor (particulate)

Rmon

= as defined above 3.4b REPORTED SETPOINTS The setpoint reported on the pre-release reports are in user defined units. If the release point setpoint equation is

STD, then the maximum setpoint is compared with the response and default setpoints.

NOTE :The response setpoint as defined in this section is not necessarily the same as the maximum setpoint based on the RESP setpoint equation, as defined in the previous section.

Sresponse is defined below.

3-10 P_

-VCe 2 The reported setpoint is as follows:

1. Reported = Sresponse.

if Sresponse < Sma-% < Sdefault OR if Sdefault < Sresponse < Smax

2. Reported =Smax if Sresponse > Smax

3. Reported = Sdefault if Sresponse < Sdefault < Smax where

=

as defined in the previous section Sresponse =

r mrtol

SUM L [rrtol * (Rmon-B)I + (mrtolb

B)

[PCi/mlj

[User Units]

(N)

Sdefault

=

normal setpoint defined for the release point in units of [pCi/ml] and (User Units].

NOTE v Separate checks are made for each setpoint in (pCi/ml] and.

[User Units) for the noble gas, radioiodine, and particulate monitors.

Setpoints in iCi/sec Setpoints in units of pCi/sec can be obtained by setting the UNITS.

parameter for the monitor to "pCi/s" or "pCi/sec" (Case sensitive.

Ist 5 characters must match) in the Activity Monitors transaction and setting the monitor slope to 1.0 as in the pCi/m! setpoint calculation. The user units setpoint, as calculated above for the setpoint in PCi/ml units, will be multiplied by the corresponding effluent flow rate (release point or discharge point) for the monitor to get a reported setpoint in pCi/sec.

3-11 f572L r

4V

3.5 MAXIMUM WASTE FLOW The maximum waste flow calculation is based on what the WFLOW_M option (release point setpoint calculation option) is set to.

This option can take on one of three values: NONE,

DOSE, and CALC.

Gaseous release point setpoint WFLOWM can be set to either NONE or DOSE.

For gaseous releases, Wmax = the minimum of Rwmax and Rcwmax where

= Release point maximum waste flow rate as stored in the release point definition If WFLOW M option = NONE Rem

= waste flow rate for the sample, Vf If WFLOWM option = DOSE fs

nratio

Vf Rcwmax =

Fwsfac where fs

= Safety factor for the release point nratio = nratio as described in section 3.4 Vf

= Waste flow rate for the release (sample)

Fwsfac = Waste flow rate DOSE setpoint safety factor 3.6 DOSE RATE AND CUMULATIVE DOSE CALCULATIONS Noble Gas Dose and Dose -Rate Calculations The dose rate and dose contribution due to noble gases in gaseous effluents are calculated using the following expressions:

3-12 Oqw_ *'*93

For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80 meters):

D

=

(3.17 10-8)

X/Qg

t-a fo 0 2 Mi 0 Qiv For Noble Gas Air Dose due to beta radiation (for vents or stacks < 80 meters):

Dp =

(3.17

10-8)

X/Q

t-b. fo 0

x Ni -

Qiv e Gas Total Body Dose Rate (for vents or stacks < 80 meters):

Dt = shf

X/Qg e 8 7 6 0 -a

fo

Z (Ki a QRiv) e Gas Total Body Dose (for vents or stacks < 80 meters):

shf fo X (Ki

QRiv)

X/Qg

t-a Dtb =

(5.256 e 105 / dur)

Le Gas Skin Dose Rate (for vents or stacks < 80 meters):

Ds

= shf

_f

Z QRiv

" [(Li

X/Q

8 7 6 0 -b) + (1.11mi

" X/Qg 870; 1)]

.e Gas Skin Dose (for vents or stacks < 80 meters):

shf e. +/-o a Z QRv 0 [.(Li. X/Q t-b) + (l.llMi, X/

t-a))

Dsk =

5 (5.256

105 / dur)

D D

=

Dt=

Dt

=

Ds=

DSk Dsk1 total beta air dose from gaseous effluents (mrad) total gamma air dose from gaseous effluents (mrad) the total body dose rate due to gamma emissions by noble gas releases from vent v (mrem/yr) total body dose from gaseous effluents (mzem) skin dose rate from gaseous effluents (mrem/yr) skin dose from gaseous effluents (mrem) conversion factor from mrad to mrem 3-13 For Nobl For Nobl C.

For Nobl For NobJ where C.

P5 f7L4 ODý,ý V:CV z

3.17

10-8 = inverse of number of seconds in a year 5.256 105 = number of minutes in a year 8 7 6 0 -a=

adjustment factor used to convert the 1-hour X/Q value to an average 1 year X/Q value (dimensionless) 8760

= number of hours in a year a

= "all factor for gamma noble gas X/Q b

= "a" factor for noble gas X/Q t -a= adjustment factor to convert the 1-hour X/Q value to the short term X/Q value for the release (dimensionless) t

= duration of release (hours) dur =. duration of the release (minutes) fo

= occupancy factor defined for the receptor at the given location (dimensionless)

Ki = total body dose factor due to gamma emissions for noble gas radionuclide i (mrem/yr per yCi/m3 )

Li = skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per pCi/m3 )"

Mi

= air dose factor due to gamma emissions for noble gas radionuclide i "(mrad/yr per pCi/m3)

Ni =

air dose factor due to beta emissions for noble gas radionuclide i (mrad/yr per pCi/m3 )

3.17

10-8 = inverse of number Of seconds in a year Qiv= release of noble gas radionuclides, i,

in gaseous effluents from vent or stack v (pCi)

QRiv

= release rate of noble gas radionuclides, i,

in gaseous effluents from vent or stack v ( pCi/sec).

shf= shielding factor (dimensionless)

X/Q= highest value of the noble gas 1-hour X/Q for vent or stack v at the site boundary (sec/m )

3-14 P5

£~LYw~ C<W Zý2-

X/Qg

= highest value of the noble gas 1-hour X/Q for gamma radiation for vent or stack v at the site

boundary, (sec/m3 )

Orgran Dose Calculations For Critical Organ Dose Rate--Inhalationi Pathway and all Pathways for H 3, C-14 (for vents or stacks < 80 meters):

DRTa X/Qr

87 6 0-c -w PipTa 0 QRiv For Critical Organ Dose Rate--Ground and Food Pathways (for vents or stacks < 80 meters):

DRTa D/Q a 8 7 6 0 -d 2: RipTa

QRiv For Critical Organ Dose-Inhalation Pathway and all Pathways for H-3, C

14 (for vents or stacks < 80 meters):

DTa =

(3.17 e 10-8)

X/r

t-c fo

Z PipTa

Qiv For Critical Organ Dose-Ground and Food Pathways (for vents or stacks <

80 meters):

Dra=

(3.17

10-8)

.D/Q

t-d. fo & 7 Ripra

Qiv where DRTa

= dose rate for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem/yr)

DTa= dose for age group a and organ r from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem) c

=

"all factor for Radioiodine/Particulate X/Q d

=

"a" factor for D/Q D/Q= highest value of the 1-hour deposition factor at the distance of the site boundary (I/m2)

PipTa = dose factor for each radionuclide if pathway p, organ T, and age group a (mrem/yr per pCi/m3)

Rip~a dose factor for each radionuclide i, pathway p, organ T, and age group a (m2 e mrem/yr per yCi/sec) 3-15 p-7 L

highest value of the radioiodine/particulate 1-hour X/Q for vent or stack v at the site boundary (sec/m3 )

Note:

it is assumed PipTa will not contain long term X/Q or D/Q values.

The maximum exposed individual is determined by the maximum dose received by any organ.

The summation extends over all applicable nuclides and pathways.

3.7 RESOLVING DOUBLE-COUNTING'OF DOSE AND ACTIVITY Gaseous release points fall into three categories for double counting of dose and activity.

One, a release point will not have activity sampled twice.

Two, a release point can have activity that is sampled again downstream and would be double-counted if no corrections were applied.

Three, a release point can have samples containing activity already sampled once upstream which would be double-counted if no corrections were applied.

The last two categories can be called the "CAUSE" release point and the "EFFECT" release point, respectively.

To avoid double-counting dose and-activity, only the "EFFECT" release point will have its activity and concentrations corrected as follows.

Corrected activity is calculated as follows:

Acei Aei -

Aci where.:

Acei =the corrected "EFFECT" release point activity for nuclide i which defaults to zero if its value is less than zero.

Aei

--the initial "EFFECT" release point activity for nuclide i

Aci

-the "CAUSE" release point activity for nuclide i Corrected concentrations are calculated as follows:

Ccei = (Acei / Ve)

35.315 3-16 6Cw

C

where:

Ccei =the corrected "EFFECT"' release point concentrations for nuclide i Ve

=the waste volume for the "EFFECT" release point 35.315 =conversion factor from Ci/ft 3 to pCi/ml (Ci/ft 3 ft 3 /1728 in 3

in 3 /16.387 cm3 )

3.8 31 DAY PROJECTED DOSE CALCULATIONS The 31 Day Projected Dose values appear on the Standard and Special Permit Reports.

The Projected Dose values are calculated as follows:

DpT =(D p) + DaT where:

DpT =the 31 Day Projected Dose.by organ T, by reactor unit WDT

=the total dose in mrem 'by organ T, by reactor unit for the quarter containing -the release start date from all closed and open releases when an answer of "Y" is specified for the "Update Totals" field on the release point definition screen.

p

=the Projection Factor which is the result of 31 divided by the number of days from the start of the quarter to the end of the release.

The quarterly and annual projection values on the standard pre-release report use a projection factor with 92 days or 365 days instead of 31 days in the numerator and do not include the additional anticipated dose term.

DaT =Additional Anticipated Dose for gaseous releases by organ T and quarter of release, by reactor unit.

NOTE:

The 31 day dose projections on the Approval/Results screen is the site total for all units.

3-17 ODC-rev z

3.9 GAS POST-RELEASE PROCESSING After a pre-release permit has been approved, the post-release program is run to:

o Enter actual release start and stop times, flow rates, etc.

o Check IOCFR20 limits o Check IOCFR50 limits o Add the dose and-activity data into the cumulative totals.

Compliance with IOCFR20 limits is checked in the same way as described for the pre-release program.

Dose rates are calculated and compared to IOCFR20 limits.

Monitor setpoints are not calculated at the post release stage.

3-18

.9 CZX2W-(zV2JL

CHAPTER 4 LIQUID DOSE FACTOR EQUATIONS The DFP option is used to calculate the liquid dose factors described previously.

Dose factors are calculated separately for each nuclide, organ, and age group.

The age group, applied to a specific receptor's' dose calculations, is part of the receptor specification.

(

For a particular receptor, the total dose factor (AiTr) is a sum over each pathway p with its specific mixing ratio:

A.

X R

A.

iir mmix, r,p iT r,p

rr BMIX, r where AiTrrp =the dose factor for nuclide i. organ T, receptor age group r, and pathway p Rmixrrp 2= mixing ratio for the pathway RMi.,r = mixing ratio for the receptor, which is the first non-zero value of Pimix,r,p encountered during the calculation The user specifies which pathways are included by setting the mixing ratios for the pathways desired to the correct non-zero value.

If the receptor mixing ratio for a given pathway is zero, that term is not included in the sum.

4-1

The DFP option of EMS uses a more expanded form for liquid dose factors than is given in NUREG-0133.

These equations are taken from R.G.

1.109, and account for nuclide decay as well as-shoreline doses.

If desired, parameters may be selected to reduce the calculations to match NUREG-0133 exactly.

Four different forms of equations are used for the dose factors.

4.1 POTABLE WATER The dose factor for potable water is:

AiT,r,p k o 0 (UrP'/dw)

Ni *.DFiT*r e(-Aitp) where AiT,r,p =dose parameter for organ Ti for the receptor age group r, for nuclide i, due to exposure pathway p, in mrem/hr per pCi/ml kO =

U r~p dw Ni=

DFiTr

-Tr tp =

units conversion factor, = 1.142E5 = iE6(pCi/pCi) 1000 (ml/Kg)/

8760 hr/yr

=

usage factor for pathway p and age group r additional dilution factor for potable water fraction of the radionuclide activity released to the water discharge path that reaches a specific receptor.

ingestion.do-se conversion factor for nuclide i for receptor age group r in organ T, in mrem/pCi (Tables E-7 to E-11 of R.G.

1.109) decay constant for nuclide i average transit time in seconds 4.2 AQUATIC FOODS PATHWAYS The liquid dose factor is Air,r,p =kO Urp BFi,p Ni o DFiT,r.

exp(-Aitp) 4-2

°6

where BF.= bioaccumulation factor for pathway p and nuclide i p

(from Reg.

Guide 1.109, Table A-1).

Other variables are as defined on the previous page.

4.3 SHORELINE RECREATION PATHWAY The pathway-specific dose factors for shoreline deposition are given by:

1

-e b

-A t

A

=k W N Uf e

i sd DFGiT Ai,r,p s

s i

fr,p

A.

where

(

)

WWs shoreline width factor ks conversion factor = ko

kc

mtv/ 3 6 0 0 kc

= water to sediment transfer coefficient in L/kg hr mtv

= Mass density of sediment in kg/m2, 40 kg/m2 3600

= Seconds per hour units conversion factor tb length of time sediment is exposed to contaminated water, 4.716E8 sec tsd transit time to: deposit activity on shoreline DFGiT

=

the dose conversion factor for standing on ground contaminated with nuclide i, in mrem/hr per pCi/m2 4-3

4.4 IRRIGATED VEGETABLE PATHWAY

)

ATrrp= 1.14

10 Uf,r,p iv DFiT,r where:

1.14

105 a units conversion factor CFi

=

the concentration factor for radionuclide i in irrigated vegetables, as applicable to the vicinity of the plant site (pCi/kg) / (pCi/L).

Calculation of the Concentration Factor The calculation of the concentration factor for radionuclide i in irrigated vegetables, CFiv as used in the equation for AiT, is calculated as follows for all radionuclides other than Tritium:

-A t

-b CFiv = Nr M

(1 e

I iv

]

i Y v E i P

For Tritium, the equation is as follows:

CFiv = Ni

M

Lv where M

the additional dilution factor from the near field of the discharge structure to the point of irrigation water usage.

I

=

the average irrigation rate during the growing season (L/m2h)*

r the fraction of irrigation-deposited activity retained on the edible portions of leafy vegetables.

There are separate values available for radioiodines and particulates.

Yv the agricultural productivity of irrigated leafy vegetables (kg/m2).

ObOV\\ i?/ 1

Ofl the fraction of the year that vegetables are irrigated.

Biv =

the crop to soil concentration factor applicable to radionuclide

i. (pci/kg vegetables) / (pCi/kg soil).

P

=

the effective surface density of soil (kg/m2)

Li

=

the decay constant for radionuclide i (h-1 )

kEi =

the effective removal rate for activity.

deposited on crop leaves (h-l), calculated as AEi =i

+ Aw Aw the rate constant for removal of activity from plant leaves by weathering (h-1).

te

=

the period of leafy vegetable exposure during the growing season (h).

tb

=

the period of long-term buildup of activity in soil (h).

th

=

the time between harvest of vegetable and human consumption (h).

LV

=

the water content of leafy vegetable edible parts (L/kg).

4.5 REDUCTION TO NUREG-01 3 3 EQUATIONS NUREG-01 3 3 does not have shoreline deposit equations, which can be eliminated by setting the Water Recreation Mixing Ratio to zero in the Liquid Receptor Transaction definition under EMS.

For the other equations, reduction to NUREG-01 3 3 is obtained by setting :

Ni =1 (this 6an be set in the definition of Fraction of Activity Reaching Receptor in DFP) average transit time tp

=

0 (this can be set in the definition of Dose Calculation Parameters in DFP) 4-ý5 0or)Ycw.

re-V I

CHAPTER 5 GAS DOSE FACTOR CALCULATIONS The DFP option is used to calculate the gas dose factors described previously.

Dose factors are calculated separately for each nuclide, organ, and age group.

The age group, applied to a specific receptor's dose calculations, is part of the receptor specification.

The same gas dose factors are used for both the site boundary dose rate calculations and for the maximum individual controlling location dose calculation.

The dose factor for each particulate or iodine nuclide i (or tritium) is given-below.

It is a function of pathway, organ, and age group.

The pathways considered are:

1. Inhalation

2.

Ground

3.

Milk (Cow or Goat)

4.

Meat

5.

Vegetable 5.1 INHALATION PATHWAY (DFA. (mrem/yr per pCi/m3)

=ia K' (BR)a (DFAiT)a xrmy e

PiTa I(B)a 3Ta K'

=

1E6 pCi/PCi 5-1 c8_

ODCAA-re.,- Z2

(BR)a = breathing rate for age group a, in cubic m/yr (DFAi) a = inhalation dose factor for organ T, for age group a,

for nuclide i, in mrem/pCi 5.2 GROUND PLANE PATHWAY RiTa =

K'K"(SF) DFGiT [(I -

e-Iit)/Ai i

(m2

-mrem/yr per pCi/sec).

where K'

-=

IE6 pCi/FCi K"

=

8760 hr/yr

= decay constant for nuclide i, in sec-I

= exposure time (sec) =4.73E8 (15 years) t DFGiT= ground plane conversion factor for. nuclide i, organ T (The same DFGiT factors apply to all age groups.

The factors labelled total body in the database are applied to all other organs)

SF

= shielding factor 5.3 MILK PATHWAY RiTa = K' (DFLiT) a e-Aitf QF Fmi Uap r rA-w )te) f

(-f e

+

B.

ps Y (Ai+ Aw)

'v P

W (l-A lb) p Ai 5-2 0

6 I

I e

rr(l-e

'we)

(I-e (1-f f

Iv A

(m2 e-iyt pehi

+ B.

(2 mrem/yr per @isc where

\\

t 7d.

(DF K = IE6 pCi/YCi S=

feed consumption rate by the milk animal (cow or goat)

(Kg/day)

Uap age group a milk consumption (cow or goat)

Yp =

agricultural productivity by unit area of pasture feed grass, in Kg/sq. m Y s Kagricultural productivity by unit area of stored feed, in Kg/sq. m F

stable element transfer coefficient for nuclide i, from feed to milk, in days/liter Biv = factor for uptake of radionuclides from soil by crops r

fraction of deposited activity retained on animal feed grass (cow or milk).

Separate values are used for radioiodines than all other particulates.

LiT) a= ingestion dose f actor for organ T, for nuclide i, for receptor in age group a, in mrem/pCi i=

decay constant for nuclide i Aw =

decay constant for removal of activity on leaf and plant surfaces by weathering, in sec-I tf

=

transport time from pisture to cow or goat to milk to receptor, in sec.

th =

transport time from pasture to harvest to cow or goat to milk to receptor, in sec.

te seasonal crop exposure time, in sec.

fp =

fraction of year that animal is on. pasture 5 -3

'7

fs=

fraction of animal feed that is pasture grass while animal is on pasture Carbon-1 4 in Milk

=ia K'"'

F (DFLit)

PC (0.11/0.16) e-itf P'iTa. =Frmi QF Uap FLTa P (m2 -mrem/yr per pCi/sec) where KI"'

=

PC

=

0.11 0.16 IE3 gm/Kg fractional equilibrium ratio fraction of total plant mass that is. natural carbon concentration of natural carbon in the atmosphere (g/m3) and all other parameters as defined above Only QF and Uap depend on cow or goat.

Tritiua in Milk Rita=

K'K"'

Fri Q Uap (DFLiT)a (0.75) (0.5/H) e-Aitf (m2 -mrem/yr per pCi/sec) where S=

0.75 =

0.5 =

IE3 gm/Kg absolute humidity, gm/cubic meter fraction of total feed that is water ratio of specific activity of feed grass water to the atmospheric water and all other parameters as defined above 54 P5 4

Dr~a& FVk, V 2 I I

-Th Only QF and Uap depend on cow or goat.

5.4 MEAT PATHWAY

=i3r

-K' (DFLiT)a e-Aitf QF Ffi Uap r (l-e i

w e}

I -e -

b ff

+ B.

p s

w

-(A.+A )t

-A t 1

t r(

1-e a.w e) 1-e itb

+ (1-f f)eith

+ B.

SYs (Ai+ Aw)

Iv I

where Ffi = stable element transfer coefficient. for nuclide i, from feed to meat, in days/Kg Uap = receptor's me.at consumption (Kg/yr) th =

transport time from crop field to receptor, in sec tf transport time from pasture to receptor, in sec and all other factors are as described for the cow milk pathway Carbon-1 4 in Meat

=iTa

= K'K"' Ffi OF ap (DFLi)

Pc (0.11/0.16) eAitf (m2 -mrem/yr per pCi/sec) where all terms are as defined above.

OI

.rc,j

Tritiumf in Meat T ri t i u m L n M e a (0.7 5 ) (0.5 /H ) e - A it f RiTa = K'K"' Ffi QF Uap (DFLiT)a (m2 -mrem/yr per pCi/sec) where all terms are as defined above.

5.5 VEGETABLE PATHWAY AltL R

K' (DFLiT) uL fLe iL RiTa-a a 2 S(l-(A i +A w)te)

B-A (lt-e-itb)

Y (Ai+ A )"

p A.

+US f

eA it s a

g r(l-e- (lA

+w) e)

B.

(1-e-Aitb)

I v(Ai+

A) p A.1 Ysv i

w (m2 mrem/yr per pCi/sec) where UL =

consumption rate of fresh leafy vegetation for age group a, in Kg/yr us =

consumption rate of stored vegetation for age group a, in Kg/yr fEL =fraction of annual intake of leafy vegetation grown locally fg fraction of annual intake of stored vegetation grown locally 5 --6

tL =

average time between harvest of leafy vegetation and consumption, in sec.

ts=

average time-between harvest of stored vegetation and consumptionr in sec.

tb =

long term sediment exposure time, in sec.

te =

seasonal crop exposure time, in sec.

Yv =

vegetation areal density, in Kg/m 2 Ysv = stored vegetation areal density, in KG/rn2 p =

effective soil surface density Biv soil to vegetation transfer factor for nuclide i All other factors are as defined above.

Carbon-1 4 in Vegetables Rita K'K"'

(UL + US)

(DFLit)a PC (0.11/0.16) e-Aitf (m2-mrem/yr per pCi/sec) where all variables are as defined earlier.

Tritium in Veaetables RiTa = KYK"'

(Ua+

US)

(DFLiT)a". (0.75) (0.5/a) e-Aitf (m2-mrem/yr per *Ci/sec) where all variables* are as defined earlier.

5.6 REDUCTION TO NUREG-01 3 3 EQUATIONS Inhalation and ground plane pathways are the same in R.G.

1.109 and NUREG-013 3.

For the other pathways (milk, meat, and vegetable),

these equations reduce to the NUREG-0133 values by setting:

tbO=

0 5-7 qjr c~cetC z-

te

= 9.999E19 tf

= 0 (in tritium equations only)

There are no C-14 equations in NUREG-0133, which can be obtained by setting Pc = 0.

6 6

5-8 6

APPENDIX A REFERENCES

1.

Boegli, J.S.,

R.R.

Bellamy, W.L.

Britz, and R.L.

Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, "NUREG-01 3 3 "

(October 1978).

2.

Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, U.S.

NRC Regulatory Guide 1.109, Rev.

1 IOctober 1977).

A-1

ML021280013

Contents

Text

1.0 INTRODUCTION

1.1 Background

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.1 Background

SUMMARY

stable element transfer coefficient for nuclide i, from feed to milk, in days/liter Biv = factor for uptake of radionuclides from soil by crops r

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ML021280013

Text

1.0 INTRODUCTION

1.1 Background

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.1 Background

SUMMARY

stable element transfer coefficient for nuclide i, from feed to milk, in days/liter Biv = factor for uptake of radionuclides from soil by crops r

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