ML19207B465

Draft Offsite Dose Calculation Manual

ML19207B465
Person / Time
Site:	Crystal River
Issue date:	04/19/1979
From:	FLORIDA POWER CORP.
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ML19207B461	List: ML19207B460 ML19207B465
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NUDOCS 7908290506
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DRAFT OF CRYSTAL RIVER - UtilT 3 0FFSITE DOSE CALCULATI0t1 fMfiUAL APRIL 19, 1979 (for use with Draft of Crystal River - Unit 3 Technical Specifications, April 19,1979, Based on NUREG-0472, Revision 2, February 1978) e 853 221 7908290506 ,

TABLE OF CONTENTS 1.0 Introduction 2.0 Radioactive Liquid Effluent Instrumtr.t ? tion Setpoints (Speci fication 3.3.3.8) 3.0 Radioactive Gaseous Process and Effluent Instrumentation Setpoints (Specification 3.3.3.9) 4.0 Radioactive Liquid Effluent Releases and Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) 4.2 Radioactive Liquid Effluent Projected Dose (Specification 4.11.1.3) 5.0 Radioactive Gaseous Effluent Dose Caiculations 5.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) 5.2 Radioactive Gaseous Effluent Other Than Noble Gas Dose Rate (Speci fIcation 4.11.2.1.4) 5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Speci fication 4.11.2.2) 5.4 Radioactive Gaseous Effluent Other Than Noble Gas Cumulative Dose (Specification 4.11.2.3) 5.5 Radioactive Gaseous Effluent Projected Dose (Speci fica tion 4.11.2.4.1) 6.0 Radiological Environnental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports (Specification 6.9.1.9) 8.0 Revisions to the ODCM (Specification 6.14.2) 853 222

1.0 Introduction This Offsite Dose Calculation Manual (0DCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable Limiting Conditions for Operation (LCOs) contained in the Appendix A Technical Specifications for Crystal River Unit 3, 853 223

2.0 Radficactive_ Liqui.d Ef fluent Instrumentation Setpoint Specification 3.3.3.G 3.0 Radoiactive Gaseous Process and Effluent Instrumentation Setpoints Specification 3.3.3.9)

The radiological effluent Technical Specifications require alann/ trip setpoints fer radiation monitors and flow measurement devices for each

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effinc ut line. Mpoint values are to be calculated to assure that alani and trip actions occur prior to exceeding the limits of 10 CFR 20 a? the release point to the unrestricted area. The calculated alann and trip action setpoints to be specified in the ODCM for each radioactive liquid effluent line monitor and flow measurement device must satisfy the following equation:

cf Rf $ C where:

C= the cffluent concentration limit (Specification 3.11.1) implementing 10 CFR 20 for the site, in uCi/ml c= The setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentracion in the effluent line prior tc dilution and subsequent reiease; the setpoint, which is propo.-tional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effTuent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area f= the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below F= the dilution water flow setpoint as measured prior to the release point, in volume.per unit time.

(Note that if no dilution is pruided, c 1 C. Also, note that when (F) is large compared to (f), then F+f 2 F.)

The equation is satisfied when the following alarm / trip setpoints are provided for each effluent line in the ODCM:

f 1[F_ (in ml/sec; for example),

c F1 (in ml/sec; for example).

cf (in uCi/ml; for example).

Scme plants may be operated using a fixea value for or re of these three variables, c, f or F.

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853 224

Eg mple 1 By using a constant capacity radwaste system discharge pump (on the undiluted stream) the value of (f) is fixed; therefore, the setpoints to be given are:

f= ml/sec (fixed)

F> ml/sec = cf/C c= xF uCi/ml I CF/f If c = 3x10-8 pCi/ml, f = 4000 ml/sec and F > 4x106 ml/sec, the radiation monitor setpoint is calculated as follows:

c 1 CF/f

,(3x10-81F = 7.5x10-12F pCi/ml.

4000-If F is measured at some value in excess of the limiting value (the 6

limiting value is 4x10 ml/sec in this exgmple), then c may be established proportionately. If F = 8x10 ml/sec, the alarm setpoint is:

c = 7.5x10-12F (uCi/ml per ml/sec)(ml/sec)

= 7.5x10-12.(8x106) = 6x10-5 pCi/ml.

In this case, the alarm setpoint for the radioactive liquid effluent line nomitor can be established at 6x10-5 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:

c/F < 7x5x10-12 pCi/ml per ml/sec.

Example 2 By using a constant capacity dilution pump (on the dilution stream prior to a mixing box), the value of (F) is fixed; therefore, the setpoints to be given are:

1. < ml/sec = CF/c F= ml/sec (fixed) c= x (1/f)uCi/ml I CF/f If C = 3x10-8 uCi/ml, F = 4x106 ml/sec and f < 4000 ml/sec, the radiation monitor setpoint is calculated as follows:

c I CF/f

= (3x10-8 x 4x106 1 = 0.12(1/f) uCi/ml.

f 853 225

If f is measured at some value less than the limiting value (the limiting salue is 4000 ml/sec in this example), then c may be establisned proportionately. If f = 1000 ml/sec, the alarm setpoint is:

c = 0.12(1/f)(uCi/sec)(sec/ml)

= 0.12 = 1.2x10-4 uCi/ml.

1000 In this case, the alarm setpont for the radioactive liquid effluent line monitor can be established at 1.2x10-4 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:

cf > 0.12 pCi/sec.

Value of c A detailed description of the ethod to be used to obtain the value of (c) should be provided. Since (c) is dependent on the radionuclide distribution, yields, calibration and the monitor's parameters, each of these sariable: should be considered and the fixed or adjustable setpoint method o# determination described for each effuent monitor.

This may be accomplished by tabulation.

853 226

4.0 Radioactive Liquid Effluent Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) m The dose contributions for the total time period I att shall be t=1 determined by calculation at least once per 31 days and a cumulative sumation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:

m Dt =I[Ait I att Ci g Fr]

i t=1 where:

Dt = the cumulative dose or dose commitment to the total body or an organ t fran the liquid effluents for the total time period m

I atg in mrem t=1 at g= the length of the gth time period over which Cjg and Fg are averaged for all liquid releases, in hours.

Ci g= the average concentration of radionuclide i in undiluted liquid effluent during the time period att from any liquid release, in pCi/ml.

Ait= the site related ingestion dose or dose cannitment factor to the total body or any organ t for each identified principal gamma and betta emitter listed in Table 4.1-1, in mrem-ml per hr-uCi .

Fr= the near field average dilution factor for Cig during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the produce of the average flow from the site discharge structure to unrestricted receiving water times 1.0.

For radionuclides not detennined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly canposite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual canposite analyses.

The dose factor Ait for each nuclide, i, embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin.

The adult total body dose factor and the maximum adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose factor is written:

Ait = ko(Uw/Dw + UfBFi + UjBIj)DFj 853 M

where:

Ait = composite dose parameter for the total body or critical organ of an adult for nuclide, i, for all appropriate pathways, mrem /hr per pCi/ml.

ko= units conversion factor,1.14x105 = 106 pCi/uCi x 10 3ml/kg +

8750 hr/yr.

Uw = 730 kg/hr, adult water consumption (fresh water cite only).

Vf = 21 kg/hr, adult fish consumption (all sites).

Uj = 5 kg/yr, adult invertebrate consumption (salt water site only).

BFj = Bioaccumulation factor for nuclide, i, in fish (fresh or salt water site, as applicable), pCi/kg per Ci/1, from Table A-1 of Regulatory Guide 1.109 (Rev.1,10/77).

BIj = Bioaccumulation factor for nuclide, i, in invertebrates (salt water only), pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109 (Rev. 1, 10/77).

DFj = Dose conversion factor for nuclide, i, for adults in pre-selected organ, t, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109 (Rev. 1, 10/77).

Dw = Dilution factor from the near field area within one-quarter mile of the release point (s) to the potable water intake for the adult water consumption (fresh water site only).

Inserting the usage factors of Regulatory Guide 1.109 (Rev.1,10/77) as appropriate into the equation gives the following expression:

Ait = 1.14x10 5(21BFj + 5BI j)DFj 853 228

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Table 4.1-1 LIQUID EFFLUENT INGESTION DOSE FACTORS Ait Dose or Dose Conmitnent Factors BF BI Critical DF (mrem-ml per br-pCi)

Radionuclide (t/kg) (t/kg) Orga n (mrem /pCi) Total Body Critical Or9ans H-3 9.0E-01 9.3E-01 All 1.05E-07 2.80E-01 2.80E-01 Na-24 6.7E-02 1.9E-01 All 1.70E-06 4.60E-01 4.60E-01 P-32 2.9E+04 3.0E+04 Bone 1.93E-04 6.45E+05 1.67E+07 C r-51 4.0E+02 2.0e+03 GI-LLI 6.69E-07 5.58E+00 1.40E+03 Mn-54 5.5E+02 4.0E+02 GI-LLI 1.40E-05 1.35E+03 2.16E+04 Fe-55 3.0E+03 2.0E+04 Bone 2.75E-06 8.23E+03 5.llE+04 Fe-59 3.0E+0i 2.0E+04 GI-LLI 3.40E-05 7.27E404 6.32E+05 Co-58 1.0E+02 1.0E+03 GI-LLI 1.51E-05 1.35E+03 1.22E+04 Co-60 1.0E+02 1.0E+03 GI-LLI 4.02E-05 3.82E+05 3.25E+04 Zn-65 2.0E+03 5.0E+04 Liver 1.54E-05 2.32E+05 5.13E+05 Sr-89 2.0E+00 2.0E+01 Bone 3.08E-04 1.43E+02 4.99E+03 S r-90 2.0E+00 2.0E+01 Bone 7.58E-03 3.01E+04 1.23E+05 Zr-95 2.0E+02 8.0E+01 GI-LLI 3.09E-05 3.50E+00 1.62E+04 Nb-95 3.0E+04 1.0Et02 GI-LLI 2.10E-05 1.34E+02 1.51E+06 f50-99 1.0E+01 1.0E+01 GI-LLI 9.99E-06 2.43E+01 2.96E+02 Tc-99M 1.0E+01 5.0E+01 GI-LLI 4.13E-07 5.00E-01 2.17E401 Ag-llOn GI-LLI 6.04E-05 2.55E-01 1.75E+02 I-131 1.0E+01 5.0E+01 Thyroid 1.95E-03 1.79E+02 1.02E+05 I-132 1.0E+01 5.0E+01 Thyroid 1.90E-05 1.00E+01 9.96E+02 1-133 1.0E+01 5.0E+01 Thyroid 3.63E-04 3.95E+01 1.90E+04 I-135 1.0E+01 5.0E+01 Thyroid 7.65E-05 2.24E+01 4.01E+03 Cs-134 4.0E+01 2.5E+01 Liver 1.48E-04 1.33E+04 1.63E+04 Cs-137 4.0E+01 2.5E+01 Liver 1.09E-04 7.85E+03 1.20E+04 Ba-140 1.0E+01 1.0E402 GI-LLI 4.18E-05 1.08E+02 3.38E+03 cy3 La-140 2.5E+01 1.0E+03 GI-LLI 9.25E-05 2.00E-01 5.83E+04 t;, Ce-141 1.0E+01 6.0E+02 GI-LLI 2.42E-05 3.00E-01 8.86E+03 tsa Ce-144 1.0E+01 6.0E+02 GI-LLI 1.65E-04 9.60E+00 6.04E+04 Np-239 1.0E+01 1.0E+01 GI-LLI 2.40E-05 1.91E-03 7.llE+02 N

N 4

4.2 Radioactive Liquid Effluent Projected Dose (Soecification 4.11.1.3) 853 230

5.0 Radioactive Gaseous Effluent Dose Calculations 6.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1)

a. Release rate limit for noble gases:

E [Kj (x/Q) Qj] < 500 mrem /yr, and i .

I [(Lj + 1.1 Mj)(x/Q) Qj)] < 3000 mrem /yr i mrem /yr where:

Kj = The total body dose factor due to gamma emissions for eqch identified noble gas radionuclide, in mrem /yr per uCi/mo.

Lj = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, iij = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 (unit conversion constant of 1.1 mrem / mrad converts air dose to skin dose).

Qi = The release rate of radionuclides, i, add in gaseous effluent from ail release points at the site in pCi/sec.

(x/Q) = sec/m3 The highest calculated annual average relative concentration for any area at or bayond the exclusion area bounda ry.

5.2 Gaseous Effluents Other than Noble Gas Dose Rate (Specification 4.11.2.1.4)

Release rate limit for all radionuclides and radioactive materials in particulate fonn and radionuclides other than noble gases:

I Pj [W Qj] < 1500 mrem /yr i

where:

Pj = The dose factor for radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases for the inhalation pathway, in mrem /yr oer aCi the food and ground plane pathways in /yr) m2 (mrem per /m3 and fo pCi/sec from Tchle 4.11-4. The dose factors are based on the critical individual organ and most restrictive age group (i nfa nt) .

W= The high calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:

W= sec/m3, for the inhalation pathway. The location is the exclusion area boundary in the sector.

853 231

W= meter-2, for th- food and ground plant pathways.

The location is the exclusion area boundary in the sector.

Qj = The release rate of radionuclides, i, add in gaseous effluent from all release points at the site in uCi/sec. 853 232

SPECIAL NOTES: (1) In all cases, the tritium relgases use the first W parameter, based on relative concentration (sec/m ). (2) All radio-iodines are assumed to be released in elemental form. If analysis includes the capability of detemining elemental and nonelemental foms in all releases, the food pathway rarameter may be adjusted accordi ngly.

The dose rate from the ith radionuclide (except tritium) is:

Pj(inhalation)(x/Q) Q + [Pj(food) + Pj(ground plant)] (F/iJ) Q (mrem /yr) and for tritium, is:

Pj (inhalation)(x/Q) Q + P j(food)(x/Q) Q = 3.0 x 10 (x/Q) 3 Q (mrem /yr)

Calculation of P4 (Inhalation)

Pj = K'(BR) DFAj (mrem /yr per pCi/m3) where:

K' = a constant of unit conversion,106 pCi/pCi.

BR = the breathing rate of the infant age group, in m /yr.3 DFAj = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFA j.

is the infant group. The infant's breathing The age group considereg/yr rate is taken as 1400 m from Table E-5 of Regulatory Guide 1.109 (Rev. 1, 10/77). The inhalation dose factors for the infant, DFAj are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem /pC1.

Resolution of the units yields:

Pj (inhalation) = 1.4 x 109 DFAj Calculation of Pi (Ground Plane)

Pj = K'K"DFGj (1-e-Ai t)Aj (m2 . mrem /yr per pCi/sec) where:

K' = a constant of unit conversion,106 pCi/pCi.

K" = a constant of unit conversion, 8760 hr/ year.

Aj = the decay constant for the ith radionculide, sec -1 t = the exposure period, 3.15 x 10 sec7 (1 year).

DFGj = the ground plane dose conversica factor for the ith radionculide (mrem /hr per pCi/m').

853 233

The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for the ith radionuclide, DFG-are presented in Table E-6 of Regulatory Guide 1.109 (Rev.1,10/7f),,

in units of mrem /hr per pCi/m2 ).

Resolution of the units yields:

Pj (Ground) = 8.76 x 199 DFGj (1-e-Ai t)f39, Calculation of P4 (Food)

Q P j = K ' r _F(Vap) F 0Fl i [e-A tif

] y2. mrem /yr per uCi/sec)

Yp TAj+Aw ) m where:

K' = a constant of unit conversion 106 pCi/uCi.

QF = the cow's consumption rate, in kg/ day (wet weight).

Uap = The infant's milk consumption rate, in liters /yr.

Yp = the agricultural productivity by unit ared, in kg/m2 ,

Fm = the stable element transfer coefficients, in days / liter, r = fraction of deposited activity retained on cow's feed grass.

DFLj = the maximum organ ingestion dose factor for the ith radionuclide, in mrem /pCi.

Aj = the decay constant for the ith radionuclide, in sec -1 Aw = the dacay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-time),

tf = the transport time from pasture to cow, to milk, to infant, in sec.

A fraction of the airborne deposition is captured by the ground plant vegetation cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering p rocesses.

The values of QF, Va o, and Y are provided in Regulatory Guide 1.109 (Rev.1,10/77), Tables E-3,pE-5, and E-15, as 50 kg/ day, 330 liters / day and 0.7 kg/m2 respectively. The value tf is provided in Regulatory Guide 1.109 (Rev.1,10/77), Table E-15, as 2 days (1.73 x 10 seconds). The fraction, r, has a value of 1.0 for radiciodines and o.2 for particulates, as presented in Regulatory Guide 1.109, (Rev. 1, 10/77), Table E-15.

853 234

Table E-1 of Regulatory Guide 1.109 (Rel,10/77) provides the stable element transfer coefficients, F m, and Table E-14 provides the ingestion dose factors, DFLj , for the infant's organs. The organ with the maximum value of DFLj is to be used.

Resolut. ion of the units yields:

Pj (food) = 2.4 x 10 10 % DFLj[e-A if t ](m . 2mrem /yr per uCi/sec)

A i 'A w f;r all radionuclides, except tritium.

The concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.

Pj = K'K"F 0 Um F apDFLj [0.75(0.5/H)] (mrem /yr per pCi/m3 )

where:

K'" = a constant of unit conversion,103 gm/kg.

H = absolute humidity of the atmosphere, in gm/m3 ,

0.75 = the fraction of total feed that is water.

0.5 = the ration of the specific activity of the feed fass water to the atmospheric water.

From Table E-1 and E-14 of Regulatory Guide 1.lg9 (Rev.1,10/77), the values of Fm and DFLj for tritium are 1.0 x 10- day / liter and 3.08 x 10-7 mrem per pC , respectively. Assuming an average ab. solute humidity of 8 grams / meter {, the resolution of units yields:

Pi (food) = 2.4 x 103 mrem /yr per uCi/m3 for tritium, only.

853 235

5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Specification 4.11.2.2)

The air dose due to noble gases released in gaseous effluents from the site shall be limited during any calendar quarter to the following expressions:

For gamma radiation:

3.17 x 10-8 EMj ((x/Q) Qj + (x/q) gj) 15 mrad, and i

for beta radiation:

3.17 x 10-8 I Nj ((x/Q) Qj + (x/q) gj) i 10 mrad i

where:

3.17 x 10-8 = The inverse of the number of seconds in a year.

M j = The air dose factor due to gamma emissions for eagh identi-fied noble gas radionuclide, in mrad /yr per uCi/m f rom Table 4.11-3.

each identified Nj = The nobleairgas dose factor due in radionuclide, to mrad beta emissions fog from Table

/yr per pCi/m 4.11-3.

x/Q = sec/m3 . The highest calculated annual average relative concentration for any area at or beyond the exclusion area boundary for long term releases (greater than 500 hrs / year).

x/q = sec/m3 . The relative concentration for any area at or beyond the exclusion area boundary for short term releases (equal to or less than 500 hrs /yr).

Qj = The release of noble gas radionuclides, i, in gaseous effluents, for long term releases (greater than 500 hrs /yr),

in pCi. Releases shall be cumulative over the calendar qua rte r.

qj = The release of noble gas radionuclides, i, in gaseous effluents, fer short term releases (equal to or less than 500 hrs /yr), in uCi. Releases shall be cumulative over the calendar quarter.

853 236

5.4 Radioactive Gaseous Effluent Other than Noble Gas Cumulative Dose Specification 4.11.2.3)

The dose to an individual from radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases in gaseous effluents released to unrestricted areas shall be limited during any calendar year to the following expression:

3.17 x 10-8 I Rj (W Qj + w gj ) f 7.5 mrem, and i

where:

3.17 x 10-8 = The inverse of the number of seconds in a year.

Qj = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate, qj = The release of radiciodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short tenn releases (equal to or less than 500 hrs /yr), in pCi . Releases shall be cumulative aver the calendar quarter or year as appropriate.

W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long tena releases (greater than 500 hrs /yr):

W= x/Q for the inhalation pathway, in sec/m3 f rom Table 4.11-6a.

W= D/Q for the food and ground plane pathways, in meters-2 f rom Table 4.11-6b.

w= The dispersion parameter for estimating the dose to at the controlling location for short term releases less than 500 hrs /yr):

w= x/q for the inhalation pathway, in sec/m3 from Table 4.11-6c.

w= D/q for the food and ground plane pathway, in meters-2 from Table 4.11-6d.

2 Rj = The dose factor for each identified radigriuclide, i, in m mrem /yr per uCi/sec or mrem /yr per pCi/m f rom Table 4/11-7.

The dose factors are based on the most critical individual organ and most restrictive age group from historical dose calculations.

853 237

For the direction sectors with existing pathways within 5 miles from the unit, use the values of Rj for these pathways. If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk Rj assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the Rj for an existing pathway within 5 miles is less than a cow-milk R at 4.5 to 5.0 miles, then use the 3

value of the cow-milk Rj at 4.5 to 5.0 miles. The values used for calculating dose contributions shall be consistent with the results of the land use census performed pursuant to Specification 3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30 days after the completion of each required land use census. The parameters W and w shall correspond to the applicable Rj for the same sector, pathway and location con

500 HR/YR OR > 125 llR/QTR Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-L/ 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.1E-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.1E-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.lE-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.1E-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A U N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NU LJ' N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.lE-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07 u NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.5E-07 1.lE-07 8.8E-08 7.2E-08 N -P-N TABLE 5.1-3 - DISPERSION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR , Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-07 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.lE-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.lE-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.1E-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.lE-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NW N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.1E-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07 [jk NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.5E-07 1.1E-07 8.8E-08 7.2E-08 w N .P. CO 2 TABLE 5.1-4 DISPERSION PARAMETER (x/q) FOR SHORT TERM RELEASES < 500 HR/YR OR < 125 HR/QTR Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 4.0-4.5 4.5-5.0 {3.5-4.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.1E-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-16 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.lE-10 5.lE-10 3.8E-10 ' 0E-10 E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.1E-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNU N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LT. d NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N W TABLE 5.1-5 .' DISPERSION PARAMETER (D/q) FOR S110RT TERM RELEASES < 500 HR/YR OR < 125 ilR/QTR Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.lE-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-10 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.1E-10 5.iE-10 3.8E-10 3.0E-10 E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.lE-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A s.'SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A cy3 NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LJ7 L/4 NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N LD C3 TABLE 5.4-1 - PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES , Inhalation Meat Ground Plane Cow-Milk-Infant Leafy Vegetables Pathway Pathway Pathway Pathway Pathway R- R- R- Rj Radio- (mrem /yr (m2. mrem /yr (m2. mrem /yr (m2. mrem /yr (m2. mrem /yr nucliae per pCi/mh per pCi/sec) per pCi/sec) per pCi/sec) per pCi/sec) LD tr4 N tri 6.0 Radiological Environmental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 4 i s k f l' r . \ i t t s 'T \ s 1  % ' ' e g. J \ r T / s' - s m I k 4, \ t ' , 4 s \ e 4 ~ L . 853 252 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports Specification 6.9.1.91 8.0 Revisions to the ODCM (Specification 6.14.2) Changes to the ODCM shall be made by the following method:

1. Shall be submitted to the Comnission by inclusion in the Monthly Operating Report within 90 days in which the change (s) was made effective and shall contain:

a. sufficiently detailed information to totally support the rationale for the change without berefit of additional or supplemental information. Infonnation submitted should consist of a package of those pages of 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);

b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detenninations; and

c. documentation of the fact that the change has been reviewed by the PRC and approved by the Plant Manager.

2. Shall become effective upon review by the PRC and approval by the Plant Manager.

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