Text

Rev 11 to Draft Odcm
	ML20203K323
Person / Time
Site:	Point Beach
Issue date:	12/02/1997
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
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ML20203K296	List: ML20203K298; ML20203K308; ML20203K312; ML20203K320; ML20203K323; NPL-97-0804, Forwards Response to Request for Addl Info Re TS Change Requests for Radiation Monitoring Sys,Radiological Effluent Tech Specs,Health Physics Manager Qualification & Radiation Protection Program;
References
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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997-

= OFFSITE DOSE CALCULATION MANUAL TABLE 3.7 2 LIQUID PATHWAY MONITOR '

CALCULATED DEFAULT SET POINTS MONITOR ELOWRATE (com) SET POINT (uCi/ce) 1 (2) RE-229 6@3700' 2.78E 05 1 (2) RE-219 & 200 3.09E 3 1 (2) RE-222 RE-230 1670 3.70E-04 RE 220 700 8.83E-04 RE 218 & 100 6.1SE-03 RE 223 1 (2) RE-216 4000 1.55E-04

' sis service water pumps at normal cooldown flow rates t

?h P

h ji Page 15 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION M \NUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 3.8 Determination of EMEC for Atmospheric Releases The maximum concentration of the mixture of radionuclides that is tilowable at the site boundary is called the effective maximum effluent concentration (EMEC). The EMEC for an effluent mixture is defined by the equation EMEC =

ICi / I(C i/ MEC)i where Ci = concentration of radionuclide "i" MEC = maximum effluent concentration for radionuclide i from 10 CFR 20, Appendix B, Table 2 I(C /i MEC) = isununation of fractions (SOF), as discussed in Section 3.6, applied to atmospheric releases The EMEC is calculated from the reference radionuclide mixture. This mixture is obtained from the 1985 1991 average annual atmospheric releases and the corresponding concentrations determined from the highest c.nnual average x/Q. (Details of the EMEC calculation are found in Appendix B.)

The calculated EMEC, corrected for H-3, of 1.92E-08 Ci/cc was obtained to be used in the set point calculations.

Page 16 of 120 i

. NUCLEAR POWER BUSINESS UNIT- 'ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997

- OFFSITE DOSE CALCULATION MANUAL 3.9 Determination of Gaseous Effluent Monitor Alarm Set noints

-The ahtrm set point for each monitor is based upon maintaining the concentration of the reference radionuclide mixture at or below the EMEC. The set point is calculated using the formula

=

SP 2.12E+03

EMEC /(x/Q

FR) where SP = set point in pCi/cc 3 3 2.12E + 03 = conversion factor for ft / min to m /sec EMEC = 1.92E-08 pCi/cc 3

x/Q = highest site boundary annual average 1.5E-06 sec/m 3

FR = the flow rate in ft / min of the efiluent pathway being monitored.

Combining the above numerical values yields SP(pCi/cc) = 2.71E + 01/ FR Gaseous effluent pathway discharge flown i s and monitors associated with each pathway are summarized in Table 3.9-1.

TABLE 3,9-1 SUMM ARY OF G ASEOUS EFFLUENT PATIIWAY DISCII ARGE FLOW RATES DISCllARGE FLOW RATE MONITOR (S) g3SEOUS EFFLUENT PATHWAY CFAI IN EFFLUENT PATHWAY

a. Auxiliary Building Vent 66,400 RE-214 & SPING 23

b. Combined AirEjector 20 RE-225

- c. Unit Air Ejector 10 1 (2) RE-215

d. Containment Purge Vent

1) I fan operating 12,500 1 (2) RE-212 &

2) 2 fans operating 25,000 . SPINGS 21 & 22 i

e. ' Gas Stripper Building 13,000 RE-224 -

f. Drumming Area Vent 43,100 RE-221 & SPING 24 Page 17 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSiTE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Alarm set points are to be normally established based upon maximum waste discharge flow rates and the highest annual average yfQ value at the site boundary. The alarm nt points may be adjusted for release periods if actual flow rates are reduced to less than maximum values or actual yfQ values are calculated.

Alarm set point adjustments to higher values are to be made in accordance with the provisions and methodologies of this section and require MSS approval. Default set point values obtained using the flow rates in Table 3.91 are presented in Table 3.9-2. An additional reduction factor of 1/4 has been applied to the four release point monitors so that the maximum allowable site boundary concentrations will not be exceeded in the event simultaneous releases from these points occur. Lower set point values may be used for any of the monitors without MSS approval if the default value is outside the upper range of the monitor or if compliance with applicable release limits will not be compromised, The set point values for the SPINGs will be the same as the corresponding release point monitor; RE 214 (SPING 23),1(2)RE 212 (SPINGS 21 and 22) or RE 221 (SPING 24).

TABLE 3.9-2 ATMOSPHERIC PATIlWAY MONITOR DFFAULT RMS SET POINTS MONITOR FLOW RATE SET POINT U// min) (uCi/cc)

RE-214 66,400 1.02E-04 RE-225 20 1.36E+00 1RE-215 10 2.71E+00 2RE-215 10 2.71 E+00 1RE-212 25,000' 2.73E-04 2

2RE-212 38,000 1.78E-04 RE-224 13,000 2.09E-03 RE-221 43,000 1.5SE-04

' 2 fans (with I fan the flow rate is 12,500 cubic fect' minute)

2 fans + 13,000 cfm from the gas stripper building Page 18 of 120

NUCLEAR POWER BUSINESS UNIT- ODCM' ,

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 -

OFFSITE DOSE CALCULATION MANUAL 3.10 Determination of Maximum Release Rates ,

Technical specifications restrict the rate of release (Ci/sec) of radionuclides to the atmosphere to that value, which if continued for one year, would result in the following annual dose rates at or beyona the site boimdary: 500 mrem /yr to the whole body and 3000 mremlyr from noble gases; and,1500 mrem /yr to any organ frcm 1 131,1 133, H 3, !

and particulates with a half life >8 days.

3.10.1 Noble gas release rate The release rate for noble gases are calculated using the Reg. Guide 1.109 dose factors and the annual average isotopic noble gas release for the years 1985 - 1991 as shown in Table B-1. The calculated annual skin dose from the average 1985 - 1991 isotopic mixture with a total of 4.51E+01 curies is 4.12E-03 mrem. Therefore the maximum release rate is calculated from the formula Ci/sec = total Ci

dose limit / (see/>r

dose from total Ci).

Based on skin dose, the release rate formula Ci/sec = 4.51E+01 Ci

3000 mrem /yr/(4.12 03 mrem

3.15E+07 sec/yr) yields a release rate of 1.04E+00 Ci/sec.

Using the same total curies with the same isotopic mixture but with the whole body dose of 8,21E 03 mrem /yr and the whole body dose limit of 500 mrem /yr, the release rate becomes 8.72E-02 Ci/sec.

Therefore the whole body dose rate is limiting and the maximum allowable PBNP noble ges release rate is 8.72E-02 Ci/sec. This rate is at higher than any PBNP noble gas release rate from 1985 - 1991 based on the highest reported hourly average release rates of approximately 4.3E-02 Ci/sec.

),

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. NUCLEAR POWER BUSINESS UNIT' ODCM

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL l 3.10.2 Release rate for 1-131,1 133. H 3, and particulates released to the atmosphere -

with half lives >8 days During the time period of 1985 '- 1991, PBNP released an annual average of 116.30457 Ci to the atmosphere consisting ofI-131,1 133, H 3, and -

particulates whole half-life >8 days. Of this quantity,116.30 was H 3 and 4.57E-03 was 1-131, I-133, and particulates whose half-life was >8 days. The doses from this mixture, calculated using ODCM methodology are shown in .

Table 3.10.1.

l Table 3.10-1 MREM from all radionuclides (1985 - 1991 average)

MREM from all radionnelides (1985 - 1991 average)

Bone Liver T. Body Thyroid Kidney . Lungs GI-LLI Skin ADULT 1.66E-02 3.68E 02 5.74 E-02 5.44E-02 2.01E 02 1.42E-02 1.23E 02 3.27E-02 TEEN. 2.69E 02 5.25E 02 5.57E-02 4.64E-02 2.56E-02 1.72E-02 1.29E-02 3.27E-02 CIIILD 6.31E-02 8.30E-02 5.48E 02 7.70E 02 3.73E 02 2.31E-02 1.60E-02 3.27E-02 INFANT . 5.04E-02 6.77E 02 3.58E-02 1.04E-01 2.00E 02 9.39E-03 2.59E 03 3.27E 02 s If the 1985 - 1991 average isotopic effluent mixture released to the atmosphere contributions is broken down into the following grouping: H-3,1 131 and 1-133, and the remaining radionuclides, the groups contribution to the various organ doses are revealed (Tables 3.10 3.10-4).

, Table 3.10-2 MREM from I-131 and 1 133 (2.42E-03 Ci)

MREM from I-131 AND I-133 Hone Liver T. Body Thyroid - Kidney Lungs GI-LLI Skin ADULT 9.26E 05 1.32E 04 1.10E 04 4.31E 02 2.29E-04 0.00E+00 3.66E-05 4.20E 05 TEEN 8.52E-05 1.20E 04 9.82E 05 3.44E 02 2.06E-04 0.00E+00 2.50E-05 4.20E 05 CillLD 1.86E-04 1.88 E-04 1.41E 04 6.17E 02 3.09E-04 0.00E+00 1.79E-05 4.20E 05 INFANT 2.63 E-04 3.10E-04 1.71 E-04 1.01E 01 3.62E-04 0.00E+00 1.17E-05 4.20E 05 l Table 3.10-3 MREM from H-3 (116.3 Ci)

MREM from II-3 Bone Liver T. Body Thyroid Kidney . Lungs GI-LLI Skin ADULT - 0.00E+00 1.13E 02 1.13E 02 1.13E 02 1.13E-02 1.13E-02 1.13E 02 0.00E+00

. TEEN- 0.00E&00 1.19E 02 ' l.19E-02 1.19E-02 1.19E-02 l.19E-02 1.19E-02 0.00E+00 CillLD 0.00E+00 1.53E-02 1.53E-02 1.53E-02 1.53 E-02 1.53E-02 1.533 62 0.00E+00 INFANT 0.00E+00 L 2.35E-03 2.35E 03 2.35E-03 2.35E 2.35E-03 2.35E 03 0.00E+00 Page 20 of 120

NUCLEAR POWER 3USINESS UNIT ODCM

- OFFSITE DOSE CALCULATION. MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL

] Table 3.10-4 MREM from alliadionuclioes except H 3 and radiciodines (2.15E-03 Ci) f i

MREM from all radionuclides except II 3 and radiolodines j Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ,

ADULT 165E 02 2.53E-02 4.59E 02 2.08E-09 8.49E-03 2.84E-03 9.41E-04 3.27E-02 i TEEN 2.68E 02 4.04E 02 4.37E 02 2.64 E-09 1.35E-02 5.2SE-03 9.76E-04 3.27E-02 ;

ClllLD - 6.29E-02 6.75E-02 3.94E 02 4.94E-09 2.16E-02 7.81E-03 6.72E-04 3.27E 02 !

INFANT 5.0l E.02 6.51E 02' 3.32E 02 1.88E-09 1.73E 02 7.04E-03 2.27E-04 3.27E 02 As evHent from Tables 3.10-1 through 3.10-4, H 3 contributes a significant portion of the thyroid do age groups for the 1985 - 1991 mixture of radionuclides released to the atmosphere. Comparison of 3.10-5 ar'd 3.10-6 to Table 3.10-4 reveals that the major portion of the organ doses from radionuclide than H-3 and racioiodines results from cobalt and cesium. Cs-134 and Cs-137 are the major dose co to 'the bone, liver, skin and kidneys whereas cobalt is the major contributor to the GI LLI dose. There dose results obtained from the 1985 - 1991 radionuclide mixture is consistent with the dose results fr ,

effluents.

Table 3.10 5 MREM from Cs-134 and Cs 137 (1.84E 03 Ci)

. MREM from Cs-134 and Cs-137 Ilone - Liver T.Ilody Thyroid Kidney Lungs GI-LLI Skin ADULT 1.62E-02 2.53E 02 4.21E 02 0.00E+00 8.48E-03 2.82E-03 4.76E-04 2.84E-02 TEEN 2.64E 02 4.04 E-02 3.98E-02 0.00E+00 1.35E 02 5.22E-03 5.52E-04 2.84E-02 CIIILD 6.22E-02 6.74E 02 3.54E 02 0.00E+00 2.16E-02 7.78E-03 4.05E-04 2.84E-02 INFAST 5.01 E-02 6.50E-02 2.95E 02 0.00E+00 1.73E 02 7.02E-03 1.96E-04 2.84E 02 I

Table 3. 6 MREM from Co-57, Co-58, and Co 60 (1.93E-04 Ci)

MREM from cobalts Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ADULT 0.00E+00 2.24E 05 3.72E-03 0.00E+00 0,00E+00 2.32E 05 4.26E-04 4.32E 03 TEEN 0.00E+00 2.97E-05 3.73E 03 0.00E+00 0.00E+00 3.40E-05 3.88E-04 4.32E-03 CIIILD 0.00E+00 4.35E 05 3.80E-03 0.00E+00 0.00E+00 2.76E-05 2.43E-04 4.32E-03 INFANT 0.00E+00 7.75 E-06 3.69E 03 0.00E+00 0.00E+00 1.78E-05 1.86E-05 4.32E-03 Page 21 of 120

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NUCLEAR POWER BUSINESS UNIT - ODCM.

Revision 11 DRAFT j 1OFFSITE DOSE CALCULATION MANUALL December 2,1997- ,

LOFFCITE DOSE CALCUL^ TION MANUAL' 3

-i 2 Based on these results, the release ratea for various radionuclide mixture can be determined using.

Tthe methodology in Section 3.10.1. :

For the total radionuclide' mixture, the maximum release rate is i Ci/sec =1.16E+02 Ci fl500 mrem /yr/ (1.04 01 mrem

3.15E+07 sec/yr) or 5.33E-02 Ci/sec, 3

For radiciodines (I 131 and 1 133), the maximum release rate is

. Ci/sec =4.42E-03 Ci *1500 mrem /yr/ (1.0101 mrem

3.15E+07 sec/yr) -

or 1.14E 05 Ci/sec, For113, the maximum release rate is 1 .

. Ci/sec =1.16E+02 Ci

1500 mrem /yr/ (1.53E-02 mrem ' 3.15E+07 sec/yr) e .or 3.62E 01 Ci/sec, . ,

For all radionuclides (other than 11-3 and radiciodines) with a half-life > 8 days, the maximum l release rate is

i 4

' Ci/sec =2.15E 03 Ci

1500 mremlyr/ (6.75-02 mrem

3.15E+07 sec/yr) 1 or 1.52E-06 Ci/sec,

- For cesium, the maximum release rate is Ci/sec =1.84E 03 Ci *1500 mremlyr/ (6.74 02 mrem

3.15E+07 sec/yr) or 1.30E 06 Ci/sec, _

For cobalts, the maximum release rate is-Ci/sec =1.93E 04 Ci *1500 mrem /yr/ (4.26-02 mrem

3.15E+07 sec/yr) .

4 or 2.16E-05 Ci/sec, Page 22 of 120 t .; x. . ;.. , ,_;..-.._

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 0FFSITE DOSE CALCULATION MANUAL -

Finally, for the total of all radionuclides in the mixture except H 3, the maximum release rate is Ci/sec =4.57E-03 Ci

1500 mrem /yr/ (1.01E 01 mrem

3.15E+07 sec/yr) or 2.15E-06 Ci/sec.

Because the limiting n lease rate is that of the radioiodines, a mixture of radionuclides whose half-lives is 28 days should be restricted to 1.14E 06 Ci/sec. However, if there is no 1-131 and 1 133, the cesium doses become limiting and the release rate limit may be raised to 1.52E-06 Ci/sec.

Page 23 of120 t

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 43 DEMONSTRATING COMPLIANCE WITH 10 CFR 50. APPENDIX i 4.1 Introductinn Maintaining effluents within the dose objectives of Appendix 1 is demonstrated at PBNP by periodic calculations. Compliance with Appendix ! limit.;is demonstrated by periodically calculating doses to the maximum exposed individual using the methodology set forth in Regulatory Guide 1.109, Rev.1, October 1977 and in other recognized sources such as ICRP publicat i ons.

In order to aid in the dose calculations, the formulae in Reg Guide 1.109 were rearranged to calculate the dose per curie released (mrem /Ci) to the environment. For each pathway given in Reg Guide 1.109, a radionuclide's mrem /Ci values for the whole body and the organs were calculated for each of the two release modes, liquid and atmospheric. All of the pathway doses for a radionuclide yia the release mode under consideration were summed to obtain the radionuclide's total mrem /Ci released. These values, called total dose factors (TDFs), are listed in Tables 5.1.1 and 5.1.2. The application of TDFs are given in Section 5; the calculations used to obtain them, in Appendix C.

4.2 Dose Limits To define the limits and coriditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environment, to ensure that these releases are as low as is reasonably achievable in conformance with 10 CFR Parts 50.34a and 50.36a, to ensure that these releases result in concentrations of radioactive materials in liquid and gaseous effluents released to unrestricted areas that are within the limits specified in 10 CFR 20, and to ensure that the releases of radioactive material above background to unrestricted areas are as low as is reasonably achievable, the following design release limits as defined in Appendix ! to 10 CFR 50 apply:

l A. The calculated annual total quantity of all radioactive material above background that may be released from each light-water-cooled nuclear power reactor to unrestricted areas should not result in an annual dose or dose commitment from liquid effluents for any individual in an unrestricted a ea from all pathways of exposure in excess of 3 millirems tc the total body or 10 millirems to any organ.

l B. The calculated annual total quantity of all radioactive material above background that may be released from each light-water-cooled nuclear power reactor to the atmosphere should not result in an annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas in excess of 10 millirads for gamma radiation or 20 millirads for beta radiation, or tha: this quantity should not result in an annual extemal dose from gaseous effluents to any individual in unrestricted areas in excess of 5 millirems to the total body or 15 millirems to the skin.

Page 24 of 120

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NUCLEAR POWER BUSINESS UNIT' ODCM

? OFFSITE DOSE CALCULATIONM' ANUAL- ' Revision 11 DRAFT December 2,' 1997

-OFFSITE DOSE CALCULATION MANUAL _

C.1 - The calculated annual total quantity of all radioactive iodine and radioactive lI material in particulate form above background ?het may be released from each light water cooled nuclear power reactor in effluents to'the atmosphere should not result in an annual dose or dose commitment from such radioactive iodine

. and radioactive ms;erial in paniculate form for any individt.al in an unrestricted area from all pathways of exposure in excess of15 millirems to any organ.

=D. : Pursuant to NRC. interpretation as statea m PBNP TS 15.7.8, the dose guideline of Section 4.2.C, above, applies only to 1-131,1-133, H 3, and all particulate material released to the atmosphere which has a half-life >8 days.

Particulates with shorter half lives are not considered because of their :

negligible dose contribution.

4.3 - R

_ elease Limits Based on the Appendix I dose limits, Point Beach, being a tvo (2) unit nuclear plant, may-release into the environment the quantities of radionuclides at ave background that fulfill the criteria listed below.

A,. Pursuant to Section 4.2.A, the doses from radionuclides in the unrestricted area in liquids shall not exceed ,

1. Six (6) millirem to the whole body, or

2. Twenty (20) millirem to any cun.

B, Pursuant to Section 4.2.B, the doses from gaseous radionuclides in the unrestricted area shall not exceed- ,

1. Twenty (20) millirads to the air from gamma radiation,

2. Forty (40) millirads to the air from beta radiation,

3. Ten (10) millirem to the whole body, or

4. Thirty (30) millirem to the skin.

C. Pursuant to Section 4.2.C, the dose from radiciodine and radioactive material in particulate form released to the atmosphere in the unrestricted area shall not exceed thiny (30) millirem to any organ.

<lj D. Quarterly release limits are defined as H the annual limits.

Page 25 of 120

7 NUCLEAR POWER BUSINESS UNIT ODCM

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULAflON MANUAL 4.4 EPA Reculations Compliance with the provisions of Appendix 1 to 10 CFR 50 is adequate demonstr : tion of conformance to the standards set forth in 40 CFR 190 regarding the dose commitment to individuals from the uranium fuel cycle. For 40 CFR 190 compliance, quanerly dose

- calculations shall include exposures frem effluent pathways and direct radiation

- contributions from the reactor units and from any outside storage tanks.

The above calculations do not include contributions from the Kewaunee Nuclear Power -

Plant (KNPP) which is some four miles north of PBNP. Under normal operations using the PBNP annual average x/Q and assumirg that the KNPP source term is ideatical to either PBNP unit, the greatest KNPP dose contribution occurs at the north sector PBNP boundary However, the total KNPP-PBNP dose at that point is Icss than the dose in the highest sector (south bourdary) from PBNP alone. The KNPP contribu: ion in this sector adds only 1 percent to 8 percent to the total dose depending upon the release mode. Even in the highly unlikely event that PBNP and KNPP operated for an entire year at twice the Appendix I levels, the small percentage contribution from KNPP .vould be insufficient to yicid doses exceeding 40 CFR 190 limits.

'5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS Technical Specification 15.7.8.3 requires that an effluent release sununary and dose calculations i

be perfonned periodically. This section describes the methodology for the calculation of doses for comparison to the corresponding dose limits. For Appendix I compliance, the organ and whole body doses shall be calculated for the maximumly exposed individual in each age group using the appropriate total dose factors in mrem /Ci released which were obtained using Regulatory Guide 1.1n9 and other documented methodologies.

5.1 Annendix I Dose Calculations 5.1.1 Liquid Release Mode The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix ! dose limits will be accomplished by the Radiological Engineering Group of RE. These calculations will be done monthly, within fifteen (15) days of receipt of the final effluent curie values from the PBNP Chemistry Section. The doses from each radionuclide will be calculated for each age group and for each organ, including the whole body, and sunmied over all the identified radionuclides released. The total dose is compared to the corresponding liquid release mode Appendix I dose limit for the organ in-

question.' Noble gases released in liquids are added to the atmospherically released noble gases for Appendix I dose compliance calculaticns.

Page 26 of 120

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9 iNUCLEAR POWER BUSINESS UNIT ODCM h OFFSITE DOSE CALCULATION MANUALn Revision 11 DRAFT - j

- December 2; 1997 !

!OFFSITE DOSE CALCUL^ TION MANOAL :

i

._The~ doses are calculated using the following formula: .;

s 1 API' =

_ I Doseaomi = I(TDFaomi X. Ci ) s; K om mrem

=j

.where . 1 API - = the Appendix I dose for compliance evaluation in mrem:

a Dosenom!

= the dose to the specific age group- (a) and organ (o) via ,

release mode (m) from radionuclide (i) ;

TDF aomi -

= total dose factor for the specific age group (a) and organ (o) ,

via release mode (m) from radionuclide (i) from Table 5.1 1 in mrem /Ci Ci curies ofradionuclide (i) released Kom

= the Appendix ! dose limit for organ (o) and release mode (m) for which the calculation is being made.

The methodology and the values used to obtain the TDFaomi values are given in Appendix C.

.It'is recognized that some of the release quantities may not be available at the end of the month because the samples from these release paths are sent to a vendor for analysis. Usually, the only radionuclides affected by these delays >

- are St 89 and St-90 Because the quantities of these two radionuclides are but a small fraction of the total release, the absence of their dose contributions

{ from the initial monthly dose calculation will not significantly affect the total dose obtained from the remaining radionuclides. The dose for the month will be updated upon the receipt of the vendor isotopic results and upon the receipt -

of any corrections to previous release quantities.

. ; instead of using the precalculated total dose factors, the Appendix ! dose

. Lealculation may be modified to reflect the actual liquid discharge volume

during the release period using the methodology in Appendix C..

c ..._

~ '

Page 27 of 120

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NUCLEAR POWER BUSINESS UNITE ODCM: ,

OFFSITE DOSE CALCULATION MANUALL - Revision 11 DRAFT

- December 2,1997.

, _ ?FFSITE DOSE CALCULATION MANUAL LTABLE 5.1-1 LIQUID EFFLUENT DOSE FACTOR Summation of dose per curie released factor calculations over the pathways: potable water, aquatic food, y shoreline deposit, irrigated fobds (milk), and irrigated foods (meat).

Dose factor - Iquid release pathway (rnrem/Ci released)

H3-nr s . Bone -Liver- T. Body. > Thyroid = Kidney. : Lungs _ - GI LLI - ,

Adult < 0.00E+00 4.57E-06 4.57E 06 4.57E 06 4.57E-06 4.57E-06 4.57E-06

. Teen

0.00E+00 = 4.11E 06 4.11E 06 4.IIE 06 4.11E 06 4.IIE-06 4.11E 06 Child . 0.00 E+00 6.76E 06 6.76E-06 6.76E-06 6.76E-06 6.76E-06 6.76E 06 i

Infant - 0.00E+00 7.80E 06 7.80E-06 7.80E406 7.80E 06 7.80E-06 7.80E-06

=

Dose factor - liquid release pathway (mrenvCi released) -

F 18 '

Bone, Liver: : T Body -. : Thyroid

, Kidney. ; Lungs n . -;GI LLI:

Adult 1.15E 07 9.12E 89 - 1.28E 08 0.00E+00 5.14E 89 0.00E+00 3.40E-09 Teen 1.21E 07 7.59E 89 1.35 E-08 0.00E+00 4.35E 89 0.00E+00 1.09E-08 Child 1.51E-07 1.08E 88 1.50E 08 0.00E+00 5.74E-89 0.00E+00 108E-08 infant l 2.0$E 12 0.00E+00 1.75E 13 0.00E+00 0.00E+00 0.00E+00 4.83 E-13 -

Dose factor liq 2d release pathway (mrem /Ci released)

Na-22

Bone < Liver- cT, Body; , 3 Thyroid v _4KidneyJ ; L5gs . GI LLi--

- Adult - 4.71E 03 4.7IE 03 4.82E-03 4.7IE 03 4.7 ! E-03 4.71E-03 4.7IE 03

~

, Teen 5.48E 03 5.48E 03 6.07E 03 5.48 E-03 5.48E-03 5.48E 03 5.48E 03 4 --

Child - 8.32E 03 - 8.32E 03 8.45 E-03 8.32 E-03 8.32E-03 8.32E-03 8.32E 03 Infant > 7.2 tE 03 7.21E 03 7.21E 03 7.21 E-03 7.21E-03 7.21E-03 7.21E 03 Dose factor - liquid release pa'hway (mrem /Ci released)

Na-24 .

Bone- Liver, gT Body- Thyroid -- : Kidney -Lungs, GI .LLi '-

Adult c > l.85E 04 1.85E 04 1.85E 04 1.85 E-04 1.85E-04 1.85E-04 1.85E-04 Teen' - 1.98E 04 1.98E 04 1.98 E-04 1.98 E-04 1.98 E-04 1.98E-04 1.98 E-04 Child c 2.40E n4 2.40E 04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 ~ 40E 04

+

infant > 8.06E 05 8.06E 05 8.06E-05 8.06E-05 8.06E-05 ! 4.06E-05 8.06E 05 w-

" w

. Dose factor - liquid release pathway (mrem /Ci released) _

Sc , p cBone: Liver ~ <T. Body Thyroid - Kidney - Lungs- GI-LLI 0.00E+00 3.09E-07 0.00E+00 1.61 E-03

~

-Adult 1.70E 07 3.3 t E-01 8.92E-06 zTecnr - 1.52E 2.97E 07 - 4.94E 0.00E+00 - 2.84E 07 0.00E+00 1.0lE-03 Child a 3.54E 4.85E-07 1.05E 0.00E+00 4.29E-07 0.00E+00 7.09E-04

-Infant - 3.42E 4.94 E-07 1.54E 07 0.00E+00 3.25E 07 - 0.00E+00 3.22E-04

- Page 28 of 120

_ . .. a . .

i NUCLEAR POWER llUSINESS UNIT ODCM :

I OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997

- OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 i

Dose fattor . hquid release pathw my (mrem /Ci released)

Mn-54 Hone Liver T. Dody Thyroid Kidney Lungs GILLI !

T Adult 000E+00 3.28E 03 6.34L 04 0.00E400 9.75E 04 0.00 E+00 1.00E-02 Teen 000E+00 3 22E 03 6.86E 04 0.00E+00 9.59E 04 0.00E+00 6.60E 03 r Child < 0.00E+00 2.60E 03 7.041! 04 0.00 E+ 00 'l.30E 04 0.00E + 00 2.19E 03 Infant 0.00E+00 1.92E 04 4.34E 05 0.00L+00 4.25 E-05 0.00E+00 7.04E-05 r

Dose f actor hquid release pathway (mrem'Ci releasedI l Cr 51 Hone Liver T. DoJy Thyroid.. Kidney- Lungs GI LL' Adult - 0.00 E+ 00 ON E+00 1.01 E 06 - 5.84E 07 2.15E 07 1.30E 06 2.46E 04

' Teen 0 00lH00 0$,d+00 1.I7E 06 $.60E 07 2.21E 07 1.44E 06 1.70E 04 +

" Child 0.00E+00 0.00E4 00 1.10E 06 6.44E 07 1.76E 07 1.18E 06 6.15E 05

/

Infant- 0.00E+00 0.00E+ 00 1.72 L-07 1.12E 07 2.45E 08 2.18E 07 5.01E 06 f

s ibst factor . liquid telease pathway (mrent'Cl released)

Mn56 llone Liver T. Body Thyroid Kidney _ . Lungs GILLI

}Adult 0.00E4 00 3.18E 06 5.65E 07 0.00E+00 4.04E 06 0.00E+ 00 1.02E 04 Teen-. ~ 0.00E+00 3.3iE-06 5.94E 07 0.00F +00 4.22E 06 0.00E4 00 2.19E 04

, Ch' 0.00E+00 3.04E 06 6.86E 07 0.00E400 3.67E-06 0.00E+00 4.40E 04 Info 'J.00E+00 1.9?E Il 3.39E 12 l0.00E+00 1.69E Il 0.00E+00 1.79E 09 7-4 Dose factor . I qad release pathw ay (mrent'Ci released)

Ye.55 lione Liver T. Dody Thyroid Kidney - _ '. Lungs . GI LLI Adult 5.98E 04 4.13E 04 9.63E 05 0.00 E+ 00 0.00E+00 2.3 l E 04 2.37E 04 Tc7n 6.llE 04 4.33E 04 1.01E 04 0.00E+ 00 0.00E+00 2.75E 04 1.88E 04 >

Child 9.35 E-04 ' 4.96E 04 . l .!4 E-04 0.0011&00 0.00E+00 2.80E 04 ' 9.19E-05 Infant - 1 1.55E 04 1.00E 04 2.68E-05 0.00E+00 0.00E+00 4.91E 05 1.2SE 05 t

Dose factor . liquid relea:e pathway (mrent'Ci relciued) l Fe 59 Honc l'iver T,Dody. Thyroid : Kidne, Lungs GlLLt

, Adult = 9.12 E-04 2.14E 03 8.23E 04 0.00E+00 0.00E+00 5.99E 04 7.14E 03 Tecn; 9.22E 04 2.15E.03 8.40E 04 0.00E+00 0.00E+00 6.79E 04 5 09E 03 >

Eild e 1.29E 03 2.09E 03 1.04 E-03 0.00E+ 00 0.00E+00 6.07E 04 2.18E-03 ,

infant 3.34 E-04 5.84E-04 230E-04 0.00E+00 0.00E+00 1.73E 04 2.79E 04 Page 29 of 120

NUCLEAR POWER BUSINESS UNIT ODCM [

OFFSITE DOSE CALCULATION MANUAL Revis10n 11 DRAFT ;

December 2,199T ;

OFFSITE DOSE CALCULATION MANUAL - f Table 5.1 1 l

Dose iactor

liquid release pathu ay (mrerCCI released) 130nc Liver T.13ody Thyroid Kidney Lungs GI LLI Adult 000E+00 2.02E 05 3.57E 05 0.00d +00 0.00E+00 0.00E+00 5.13E 04 i Teen 0.00E400 2.06E 0$ 4.62E 05 0.00E+00 0.00E+00 0.00E+00 3.83E 04 l f

Child 0.00E+00 2.3lE 05 4.93E 05 0.00E+00 0.00E+ 00 0.00E400 1.89E 04 In!' ant 000E+00 1.24E 05 2.02E 05 0.0( E+00 03E+00 0.00E+00 4.24F 05 Dese f actor

hquid release pathw ay (mrem /Ci released)

Co.58 lione -Liver T. Ilody : 1hyroid Kidney . Lungs .GI LLI i L

8.49E 05 1.93E 04 0.00E+00 0.00E+0d 0.00E+00 1.72E 03 Adult 0.00E+00 '

Teen 0.00E+00 8.30E 05 2.04E 04 0 00E+00 E 0E+00 0.00E+00 1.14E 03 Child

0.00E+00 8.32E 05 2.57E 04 0.00E+00 0.00E +00 0.00E400 4.85E 04 Irfant 0.00E+00 3.84E 05 9.58E 05 0.00E400 0.00E+00 0.00E+00 9.57E 05 o

IDose factor liquid release pathway (mrem'Ci released) i Co-60 Ilone Liver T. Ilody 1hyroid . Kidney Lungs ' GILLI Adult 0.00 E+00 2.48E 04 6.82E-04 0.00E+00 0.00E400 0.00E+00 4 66E 03 Teen 0.00E+00 2.44E 04 1.30E 03 0.00E+00 0.00E+00 0.00E+00 3.17E 03

Child - 0.00E+00 2.49E 04 8.92E 04 0.00E400 0.00E

00 0.00E+00 1.38E-03 0.00E400 0.00E+00 0.00E+00 0.00E+00 2.79E 04 Infant 1.17E 04 2.77E 0 _

Dose tactor . liquid release pathway (mrem /Ci released)

Ni 63 13one Liver . T. Jody Thyroid - Kidney , (Lungs; ..Gi LLI Adult t 3.03E 02 2.10E 03 1.02 E-03 0.00E+00 0.00E+00 0.00E+00 4.38 E-04 Teen: 3.13E-02 2.21E 03 1.06 E-03 0.00E+ 00 0.00E+00 0.00E+00 3.52E 04 Child - 5.00E 02 2.67E 03 1.70E 03 0.00E+00 0,00E+00 1 ~5.+00 1.80E 04 Infant - 1.27E-02 7.85E 04 4.41 E-04 0.00E+00 0.00E+00 030E+00 3.91 E-05 Dose factor liquid release pathway (mrem /Cl released)

Ni 65

-Ilone-

- Liver ' ' T. Ilody , 'I hyroid - . Kidney - Lungs- e GI LLI '

Adult . 3.39E-06 4.40E 07 2.01E-07 0.00E+00 0.00E+00 0.00E+00 1.12 E-05 [

Teen 3.66E 06 4 68E-07 2.13E 07 0.00E+00 0.00E+00 0.00E+00 2.54 E-05 4.68E 06 2.57E-07 0.00E+ 00 0.00E+00 0.00E+00 5.40E 05 i Child - 4.41 E-07 infant 1.74E 10 - 1.971711 8.95E 12 0.00E+00 0.00E+00 0.00E+00 1.50E 09 Page 30 of 120

. _ . - - - a . - , -- - . _ - - . . - = . , . - . - - - - ,

NUCLEAR POWER BUSINESS UNIT ODCM !

0FFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 l OFFSITE DOSE CALCULATION MANUAL !

Table 5.1 1 !

Dose factor liquid release pathway (mrem'Ci released) j Cuh4 ~

~

Donc Lher T. Body Thyroid Kidney Lungs GILLI Adult 0.00 E+ 00 4.02E 06 1.89E 06 0.00E+00 - 1.0lE 05 0.00E+ 00 3.43E 04 i Teen 000E+00 4.31E 06 2.04E 06 0.00E+ 00 1.09E 05 0.00 E+ 00 3.340 ')4 l Child 0.00E+00 430E 06 2.60E 06 0.00E+00 1.04E 05 0.00E+00 2.02 E-04 }

Infant 0.00E+00 1.41 E-06 6.52E 07 0.00E+00 2.38E n6 0.00E* 00 2.89E-05 ;

i Dose factor . liquid release pathway (mrem'Ci released)

Zn 6%

Bone .. Liver T.llody Thyroid Kidney Lungs GILLI 5 50E 02 2.49E 02 0.00E+00 3.68E.02 0.00E+ 0r, 3.46E 02 l Adult - 1.73E 02 Teen 1.58E-02 5.50E 02 2.57E 02 0.00E+ 00 3.52E 02 0.00E+00 2.33E 02 ,

Child 1.68E-02 4.47E 02 2.78E 02 0.00E+00 2.82E 02 0.00E+00 7.85E 03 ;

' infant. 132E 03 4.51E 03 2.08E 03 0.00E+00 2.19E 03 0.00E+ 00 3.81 E-03 s

Dose Iactor liquid release pathway (mrem /Ci released)

Zn 69 lione. Liver T. Body D yroid Kidney Lungs. GlLLI Adult - 1.97E 05 3.76E-05 2.62E 00 0.00E+00 2.44E 05 0 00E+00 5.65E 06 Teen- 2.14 L-05 4.08E 05 2.86E-06 0 00E+00 2.67E 05 0.00E+ 00 7.52E 05 Child 2.77E 05 4.00E 05 3.70E-06 0.00E+03 2.43E 05 0.00E+00 2.52b 03 Infant 5.98E 07 1.08E-06 8.0lE 08 0.00E+ 00 4.47E-07 0.00E+00 8.78E 05 Dose factor liquid release pathw ay (mrem /Ci released)

Zn 69m Bone Liver T.Dody Tinyroid Kidney Lungs- - GI LLI Adult - 3.25E 04 7.79E 04 7.12E-05 0.00E+ 00 4.72E 04 0.00E+00 4.76E 02 Teen' 3.50E-04 8.25E 04 7.57E 65 0.00E+00 5.01E 04 0.00E+00 4.53E 02 Child - 4.49E 04 7.65E 04 9.04E 05 0.00E+00 4.44 E-04 0.00 E+00 2.49E 02 l Infant - 9.61 E-06 1.96E 05 1.79E-06 0.00E+00 7.94E 06 0.002+00 2.72E-04 Dose factor . liquid release pathway (mrem'C6 released) 1 Br 82 lione- Liver T. Body -. Thyroid Kidney- . Lungs ,

GILLl-Adult e 0.00E+00 0.00E+00 1.39E-03 0.00E+00 0.00E+00 0.00E+00 1.59E 03 Teen 0.00E+00 0.00E+00 1.47E-03 0.J0E+00 0.00E+ 00 0.00E+ 00 0.00E+ 00 Child - 0.00E+00 0.00E400 1.71E 03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Infant - 0.00E400 0.00E+00 4.43 E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 31 of 120

NUCLEAR POWER llUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose f actor . hquid release pathw ay (mrem /Cs released) lir 83 lione Liver T. llody Thytold Kidney I.ungs = Ol LLI Adult 0.00E+00 0.00E+00 9.06E 07 0.00E+00 0.00E+00 0.00E+00 130E 06 Teen 000E+00 0.00E +00 9.85E 07 0.00E+00 0.00E+00 0.00L+ 00 0.00E+00 Child 0.00E+00 0.00E+00 1.27E 06 0.00E+00 0.00E+00 0.00E +00 0.00E+00 Infant- 0.00E +00 0.00E+00 2.93E Il 0.00E+00 0.00E+ 00 0.00E+00 0.00E+ 00 Dose factor liquid release pathway (mrem /Cl released) lit 84 flone Liver T. Ilody - Th>Toid k. " Lungs- - Ol LLI Adult - 0.00E+00 0.00E+00 3.12E-05 0.00E+00 0.00Es 0 00E+00 2.44E.10 Teen- 0.00E+00 0.00E+ 00 3.43E 05 0.00E+00 0.00 E *. 0.00E+00 0.00E+00 Child 0.00E+00 0.00E+00 4.33E 05 0.00E+00 0.00E+00 0.00 E+00 0.00E+00 Infant 0.00E+00 0.00E+00 1.20E 05 , 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose factor liquid release pathway (mrem /Cl released) lir-S$

lione Liver T. Ilody Thyroid Kidney Lungs Gl.LLI Adult 0.00E+00 0.00E + 00 4.24E 82 0.00E+00 0.00 E+00 0.00E+00 0.00E+00 Teen 0.00E+00 0 00E+00 4.60E 82 0.00E+ 00 0.00 E+ 00 0.00E+00 0.00E+00 Child 0.00E+00 0.00E+00 5.94E 82 0.00E+00 0.00E+ 00 0.00E+ 00 0.00 E+ 00 Infant - 0.00E+00 0.00E+00 9.35E 309 0.00 E+00 0.00E +00 0.00E+00 0.00E+00 Dose factor liquid release pathway (mrem /Ci released)

Rb 36 Done Liver - T. Ilody e lhyroid . . Kidney . -Lungs GI LLI Adult - 0.00E+00 7.36E 02 3.43E 02 0.00E400 0.00 E +00 0.00E+ 00 1.45E 02 Teen - 0.00E+00 7.98E 02 3.75 E-02 0.00E+00 0.00E+00 0.00E+00 1.18E 02 Child 0.00E+ 00 7.93E 02 4.88E 02 0.00E+00 0.00E+00 0.00E +00 5.10E 03 Infant - 0.00E+00 9.07E 03 4.48E 03 0.00E+00 0.00E+00 0.00E+00 2.32E 04 Dose iactor liquid release pathway (mrem /Ci released)

Rb88

^

< 11one - Liver - .T.Ikdy- Thyroid Kidney Lungs GILLI Adult - 0.00E+00 1.41 E.16 7.46E 17 0.00E+00 0.00E+ 00 0.00 E+00 1.94E 27 Teen- 0.00E+00 - 1.51E 16 8.04E 17 0.00E+00 0.00E+00 0.00E +00 1.29E 23 Child 0.00E+00 1.45E 16 1.0lE.16 0.00E+00 0.00E+00 0,00E+00 7.12E 18 infant , 0.00E+00 5 68E 54 3.12E 54 0.00E+00 0.00E+00 0.00E+00 5.54 EA4 Page 32 of 120

NUCLEAR POWER BUSINESS UNIT ODCM 0FFSITE DOSE CALCULAT!ON MANUAL Revision 11 DRAFT ;

December 2,1997 0FFSITE DOSE CALCULATION MANUAL Table 5.1 1 i

Dose iactor - liquid release pathw ay (mrem /Ci released)

Rb 89

' lione Liver T.11ody 1hyroid Kidney Lungs GlLLI Adult 0.00E + 00 1.28E 18 8.99E 19 ~.00E+00 0 0.00E+00 0.00E+00 7.42E 32 Teen 0.00F +00 1.34 E.18 9.45E.19 0.00E+00 0.00E+ 00 0.00E+00 2.0$E 27 Child - 0.00E +00 1.23 E.18 1.09E.18 0.00E + 00 0 00E+00 0.00E+00 1.07E 20 :

infant 0.00E+00 1.15E 61 7.93E 62 0.00E+ 00 0.00E+00 0.00E+00 3.92E 6. ,

i Dose iactor . liquid release pathway (mrem /Ci released)

St89 lione : ther T. llody Thyroid . Kidney Lungs GI,LLl

' Adult 2.26E 02 0.00E+00 6.48 E-04 0,00E + 00 0 00E+00 - 0.00E+ 00 3.62E 03 Te'en 2.43E 02 0.00E+00 6.95E 04 0.00E+ 00 0.00 E+00 0.00li+ 00 2.89E 03 Child s 4.27E 02 0.00E + 00 1.22E 03 0.00E +00 0.00E+ 00 0.00E+00 1.65E 03 Infant . 2.$8E 02 0.00E+ 00 7.40E 04 0.00E+00 l 0.00E+00 0.00E+00 5.30E 04 r

Dose f actor . liquid release pathway (mrem /Ci rcleased)

Sr 90 S

lione- 4.<er T. !!ody thyroid Kidney- Lungs GILLI Adult 5 63E 01 0.00E+ 00 1.38E 01 0.00E+ 00 0.00E+00 0.00E+00 1.63E 02 Teen 4.64 E-01 0 00E+00 1.15E-01 0.00E+ 00 0.00E+00 0.00E+00 1.30E 02 g Child 5,59E Ol 0.00E+00 1.42E 0I 0.00E+00 0.00E+00 0.00 E+ 00 7.53E 03 1.95 E-01 0 00E+00 4.97E 02 0.00E+00 0.00E+ 00 0.00E+00 2.44E 03 l Infant

~

E Dose f actor hquid releat.c pathway (mrem'Ci released)

St 91 flone Lher T.Dody 1hyroid - Kidney Lungs ' GILLI Adult 1.27E .04 0.00E+00 5.14E 06 0.00E+00 0.00E+00 0.00E+00 6.0$E 04 Teen. 1.38E 04 0.00E+00 5.5 l E 06 0.00E+00 0.00E+00 0.00E+00 6.24E 04 Child 1.830 04 0.00E+00 6 9lE 06 0.00E+00 0.00E+00 0.00E+00 4.04E 04 Infant 1.59E 05 0 00E+00 5.76E-07 0.00E+00 0.00 E+00 0.00E+00 1.88E 05 Dose factor - liquid release pathway (mrem /Ci released)

Sr 92

..Done1 Liver: T.Dody Thyroid Kidney -Lungs GILLI ,

Adult t 5.21 E-06 0.00E+00 2.26E-07 0.00E+ 00 OM E+00 0.00E+ 00 1.03 E-04 l Teen - 5.64 E 0.00E+00 2.42E 07 0.00E+00 0.00E+00 0.00E+00 1.44 E-04 2.89E 07 0.00E+ 00 0.00E+00 0.00E+00 1.36E 04 I Child 7.20E 06 0.00E+00

Infant . 9.41E 10 0.00E+00 3.50E Il 0.00E+00 0.00E+00 0.00E+00 101 E-08 Page 33 of 120 j w_ ,~ . - ..- - :. - -. -- - - - - - -. . --. . , - - . .

NUCLEAR POWER DUSINESS UNIT ODCM:

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose factor liquid release pathway (mrern/Ci released)

Y 90 Bone Liver T. Body 1hyroid Kidney Lungs GILLI Adult 4.85E 07 0.00 E+ 00 1.30E 08 0.00E+ 00 0.00E+00 0.00E+00 5.15E 03 Teen 5.16EdI O.00E+00 1.40E 08 0.00E +00 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E+ 00 0.00E400 4.26E;0{I 2 disd Child 8.67E 07 0.00E+ 00 2.32E 08 Infant 130E 07 0.00E+00 1.29E 08 0.00E+00 0.00E+00 0.00E+00 6.63 E-04 a

Dose factor liquid release pathway (mrerrCl released)

Y 91

.Done Liver T. Body Thyroid Kidney Lungs, - Gl.LLI .

Adult 9.20E 06 0.00 E+00 2.53E 07 0.00E+ 00 0.00E+ 00 0.00E+00 5.06E 03 Teen 9 68E 06 0.00E400 2.97E 07 0.00E+ 00 0.00E+00 0.00E+00 3.97E 03 Child - 1.74 E-05 0.00E+ 00 4.74E 07 0.00E+00 0.00E + 00 0.00E+ 00 2.32E 03 Infant , 1.03E 05 0.00E + 00 .; i 0.00E+00 0.00E+00 0.00E+ 00 7.35E 04 3 ++ .v m- 7 Dose factor liquid telease pathway (mrem /Cl released)

'i 9im Bone Liver T. Ilody. Thyroid Kidney - Lungs - 01.LLI Adult - 1.7 t E 13 0.00E+00 5.10E 14 0.00E+00 0.00E+00 0.00E+00 5.02E 13 Teen' l.85E 13 0.00E400 2.55E 13 0.00E+00 0.00E400 0.00E+ 00 8.72E 12 Child 2.36E 13 0.00E+00 6 04E !4 0.00E+ 00 0.00 E+00 0.00E400 4.62E 10 Infant ; 2.62E 26 0.00E+00 8.92E 28 0.00E+00 0.00E+00 0.00E+00 8.72E 23 Dose factor liquid release pathway (mrem /Ci released)

Y-92 Bone Liver T. liody Thyroid Kidney Lungs Ol LLI Adult 3.51E 09 0.00E+00 2.88E 10 0.00E+00 0.00E+00 0.00E+00 6.15E 05 Teen 3.83E 09 0 00E+00 1.15E 09 0.00E+00 0.00E +00 0.00E+00 1.05E 04 Child 4.92E 09 0 00E+00 3.57E 10 0.00E+v0 0.00E+00 0.00E+00 1,42E 04 Infant 5.88E 12 0.00 E+00 1.65E 13 0.00E+00 0.00 E+00 0.00E+00 1.12E 07 Dose factor liquid release pathway (mrenVCi released)

Y 93 Bone- - Liver T. Ilody - T.hyroid ; Kidney:- = Lungs - Ol LLI Adult 5.32E 08 0.00E+00 - 2.33E 09 0.00E+00 0.00E+00 0.00E+00 1.69E 03 Teen S.77E 08 0.00E+00 6.38 E-09 0.00E+00 0.00E+ 00 0.00E+00 1.76E 03 Caild ' 7.75E 08 0.00E+00 3.13 E-09 0.00E400 - 0.00E400 0.00E+ 00 1.16E 03 Infant ' 8.33 E-09 0.00E+00 2.27E 10 0 00E+00 0.00E+00 0.00E+06 6.58E 05 t

Page 34 of 120

..- _ _ . _ _.. ___ _ __ .. a

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT Decernber 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose iactor . liquid release pathway (rnrem/Ciieleased)

Zr 95 lione Liver T. llody Thyroid- Kidney Lungs Oi LLI Adult - 1.23E 06 3.94E 07 1.79E 06 0.00E+00 6.19E 07 0.00L+ 00 1.25E 03 Teen 1 llE 06 3.52E-07 8.74 E-06 0.00 E+ 00 5.17E 07 0.00E+ 00 8.11E 04 Child - 2.480 06 5.45E 07 2.26E 06 0.00 E+00 7.80E 07 0.00E400 5.69E 04 Infant. 1.87E-06 4.56E-07 3.23E 07 0.00E+00 4.91E 07 0.00E+00 2.27E 04 Dose f actor + liquid release pathway (mrem /Cl released)

Zr97

" llone: Liver T. llody Thyroid - Kidney Lungs GlLLI Adult . 1.07E 08 2.16E 09 1.23E 08 0.00E+ 00 3.27E 09 0.00E+00 6.70E 04 Teen 1.llE 08 2.19E 09 6.42E 08 0.00E+00 3.33 E-09 0.00E+00 5.94E 04 Child 2.2 t E 08 3.19E 09 1.5 l E 08 0.00E +00 4.58E 09 0.00E+00 4.83E 04 Infant 1.92E 08 3.29E 09 1.50E 09 0.00E+ 00 3.32E 09 0.00E+00 2.10E 04 Dose factor liquid telease pathway (mrrm/Ci teleased)

Nb-95 lione Liver T. lkdy lhyroid Kidney Lungs GlLLI Adult 3.23E 04 1.79E 04 9.73 E-05 0.00E+00 1.77 E-04 0.00E+00 1.09E+00

. Teen 3.25 E-04 1.80E-04 1.04 E-04 0.00E+00 1.75E 04 0.00E400 7.70E 01 Child 3.84 E-04 1.49E 04 1.08E-04 0.00E+ 00 1.40E 04 0.00E+00 2.76E-01 Infant 5.36E 07 2.21E 07 1.28 E-07 0.00E400 1.58E 07 0.00E+00 1.86E 04 Dose factor liquid release pathway (mrem!Ci released)

Nb 97 lione - Liver T. flody. Thyroid - Kidney Lungs . Gl LLI Adult- 2.69E 09 6.81E 10 2.51E 10 0.00E+00 7.95E 10 0.00E+00 2.51E 06

-Teen > 230E-09 7.20E 10 2.73E 10 0.00E+ 00 8.41E 10 0 00E400 'l.72E 05 Child 3.68E 09 6.65E 10 3.12E 10 0.00E+00 7.38E 10 0.00E+00 2.05E 04 Infant- 5.81E 21 1.24E 10 4.47E 22 0.00E+00 9.68E 22 0.00E+00 3.91E 16 Dose factor - liquid release pathway (mrern/Ci released)

Mo-99

^

^ tione Liver T, llody -Thyroid; Kidney Lungs . GI LLI Adult c 0.00E+00 1.49E 04 2.84 E-05 0.00E+00 3.18E 04 0.00E+00 3.46 E-04 Teen 0.00E+00 1.76 E-04 3.36E 05 0,00E+00 4.03E 04 0.00E+00 3.15E 04 Child - 0.00E+00 2.79E-04 6.9 t E-05 0.00E+00 5.96E 04 0.00E+00 2.31E 04 Infant < 0.00 E+00 4.35E 04 8.54E 05 0.00E+00 6.54E 04 0.00E +00 1.44E 04 Page 35 of 120

NUCLEAR POWER IAUSINESS UNIT ODCM OFFSITE DOSE CALCU' ATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOS.E CAI C'*!.. . ION MANUAL -

Table 5.1 1 Dose lactor hquid release pathw ay (mrem'Ci released)

Tc 99m Done Liver T. Body Thyroid Kidney Lungs GILLI Adult 1.68E 09 4.7 tE 09 6.07E 08 0.00E+00 7.20E 08 2.32E 09 2.81E 06 Teen 1.74E 09 4 86E 09 6.46E-08 0.00E+00 7.24E 08 2.70E-09 3.19E 06 Child 2.19E 09 4.29E 09 7.15E 08 0.00E +00 6 24E 08 2.18E 09 2.44 E-06 Infant 3.78E 10 7.79E 10 1.00E 08 0.00E+00 8.38E 09 4.07E 10 2.26E 07 Dose factor hquid release pathway (mrem /Cl released) 1c 101

- tione . Liver T. Ilody Thyroid - Kidney -Lung: GILLI Adult I.60E24 5.19E 24 5.10E 23 0.00 E+00 9.34E 23 2.65E 24 1.56E 35 Teen 3.89E 24 5.53E 24 5.49E 23 0.00E+00 1.00E 22 3.37E 24 9.45E 31 Child 4.98E 24 5.22E 24 6.63E 23 0.00E+00 8.90!! 23 2.76E 24 1.66E 23 Infant 9.73 E-69 1.23E 68 1.21E 67 0.00E+00 1.46E.67 6.69E 69 2.08 E. 66 ~

Dose factor liquid release pathway (mrem Ci released)

Ru 103 Bone Liver -T. Body 1hyroid Kidney Lungs GI-LLI Adult 3.47E 05 0.00E+00 1.56E 05 0.00E+00 1.32 E-04 0.00E+00 4.0$E 03

-Teen 2.96E 05 0.00 E+ 00 1.64E 05 0.00E+00 1.04 E-04 0.00E+00 2.47 E-03 Child 5.53E 05 0.00E+00 2.20E-05 0.00 E+00 1.39E 04 0.00E+00 1.43 E-03 Infant 1.33E 05 0.00E+ 00 4.43E 06 0.00E+00 2.76E-05 0.00E+ 00 1.61E 04 Dose f actor - liquid release pathway (mrem /Cl released)

Ka 105 Bone Liver T. Body. Thyroid Kidney . Lungs GlLLI Adult 4.13 E-08 0.00E+00 1.75E 08 0.00E+00 5.34E 07 0.00E+00 2.53 E-05 Tecn- 4.45E 08 0.0dE+00 0.00E+00 5.62E 07 0.00E+00 3.59E-05

~2.42 E-08 Child 5.71E 08 0.00E+00 2.22E 08 0.00E+00 5.02E 07 0.00E+00 3.73 E-05 Infant ' 6.98E 10 0.00E+00 2.35E 10 0.00E+00 5.13E 09 0.00E+00 2.78 E-07 Dose factor . liquid release pathw ay (mrem /Ci released)

Ru 106 Bone -- Liver . T. Body - Thyroid .. Kidney. . Lungs GILLI Adult . 6.71E 04 0.00E+00 8.76E-05 0.00E+00 1.30E-03 0.00E+00 4.34 E-02 Teen 5.86E 04 0.00E+00 8 85E-05 0.00E+00 1.13E 03 0.00E+00 2.81E 02 Child - I.13 E-03 0.00E + 00 1.44 E-04 0.00E+00 1.53 E-03 0.00E+00 1.76E-02 Infant t 2.23 E-04 0.00E+00 2.78E-05 0.00E +00 2.63E 04 0.00E+00 1.69E 03 Page 36 of 120

_-. _ _ _ _ ~ . _ _ _ _ _ - . . . _ _ . _ - . - _ _ _ _ _ _ . _ . _ . _ - -.

NUCLEAR POWER BUSINESS UNIT ODCM ;

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 ;

Dose f actor . hquid release pathway (mremb released)

Rh 105 I Ilone Liver T.13ody Th>Toid - Kidney Lungs GI LLI ;

Adult 3.35E 06 2.45E 06 1.62E 06 0.00E+00 1.04E-05 0.00E+00 3.90E-04 Teen 4.10E 06 2.96F 06 1.97E 06 0.00E400 1.26E-05 0.00E+00 3.77 E-04 0.00E+00 2.80E 04 i Child 8.43E 06 4.52E 06 3.88 E-06 0.00E+00 1.80E 05 Infant 1.08E-05 7.0$E 06 4.74E 06 0.00E+00 1.96E-05 0.00E+00 1.75E-04 Dose lactor liquid release pathway (mrem /Ci released)

Ag 110m

Done Liver T. Body Thyroid: Kidney Lungs GI LLI >

Adult 3.06E-05 2.83E 05 3.83E 05 0.00 E+00 5.56E 05 0.00E+00 1.15E-02

~

Teen. 3.74E 05 3.54E 05 1.41 E-04 0.00E+00 6.75E 05 0.00E+00 9.94E 03 Child 6.78E 05 4.58E 05 6.17E 05 0.00E+00 8.53E 05 0.00E+00 5.45E 03 Infant 8.87E 05 6.47E 05 4.28L-05 0.00E400 9.26E 05 0.00E+00 3.36E 03 l Sn 113 liquid release pathuay(mrem /Cl released)

Bone Li/cr W.!!ody 1hyroid Kidney . Lungs GlLLI l

Adult 6.40E 03 2.17E-04 6.78E 04 1.26E 04 0.00E+00 0.00E+00 1.32 E-01 Teen 6.96E 03 2,33 E-04 7.33E 04 1.28E 04 0.00E+00 0.00E+00 1.08 E-01 Child - 9.03E 03 2.28E 04 9.44E 04 1.66E 04 0.00E + 00 0.00E+00 4.61E 02 Infant 1.42E 04 4.43E 06 1.47E 05 3.07E 06 0.00E+00 0.00E+00 3.50E 04 Dose factor liquid release pathway (mrem /Ci released) -

Sb 124 Ilone Liver T. Ilody . Thyroid -Kidney Lungs -- G1LLI Adult 5.42E 04 1.02E 05 2.2 i E-04 1.32E 06 0.00E+ 00 4.22E 04 1.54E 02 Teen 5.66E 04 1.04 E-05 2.5.' E-04 1.28E 06 0.00E+00 4.94 E-04 1.14E 02 Child 7.89E-04 1.02E 05 - 2.83E 04 1.74 E-06 0.00E+00 4.38E-04 4.94E-03 Infant 1.95 E-04 2,86E-06 6.03E 05 5.17E 07 0.00E+00 1.22E 04 - l 6.00E 04 Dose factor liquid release pathway (mrerWCi released)

Sb 125 Bone Liver T. Body Thyroid . Kidney. Lungs GILLI Adult : 3.49E-04 3.90E 06 1.07E 04 3.55E-07 0.00E+00 2.69E 04 3.85E 03 d' Teen 3.65 E 3.99E-06 2.19E 04 3.49E-07 0.00E+00 3.21 E-04 2.84E 03 Child ' 5.14E 04 3.96E 06 1.35E 04 4.76E-07 0.00E+00 2.86E-04 1.23 E-03 Infant 1.14E 04 1.l l E 06 2.35E 05 1.43 E-07 0.00 E+ 00 7.17E-05 1.52 E-04 Page 37 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 i OFFSITE DOSE CALCULATION MANUAL POINT BEACil NUCLEAR PLANT UNITS 1 AND 2 OFFSITE DOSE CALCULATION MANUAL WISCONSIN ELECTRIC POWER COMPANY December 2,1997 Revision 11

- NUCLEAR POWER BUSINESS UNIT- ODCM '

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 51 1 Dose factor liquid release pathway (mrem'Ci released) ,

Te 125m ,

Bone Liver T. Body Thyroid Kidney Lungs - GI-LLI Adult 3.30E-04 1.20E-04 4.43E 05 9.93E 05 1.34E 03 0.00E+00 1.32E-03 Teen 3.36E-04 1.21E 04 4.53E-05 9.39E-05 0.00E +00 0.00E+00 9.92E-04 Child 5.74 E-04 1.56E 04 - 7.67E 05 1.61E 04 0.00E+00 0.00E+00 5.54 E-04 Infant 2.47E 04 8.27E 05 3.35E 05 8.33E 05 0.00E+00 0.00E+00 1.18E 04 F

Dose factor liquid release pathway (mrem /Cl released)

Te l.??

Bone Liver T. Body D yroid. Kidney

Lungs GILLI Adult - 3.15E 05 1.13E 05 6.83 E-06 2.34E 05 1.28E 04 0.00E+00 2.49E 03 Teen- 3.45E 05 1.22 E-05 7.43E 06 2.38E 05 1.40E 04 0.00E+00 2.67E 03 Child 4.45 E-05 1.20E 05 9.54E 06 3,08E 05 1.27E 04 0.00E+00 1.74E 03 Infant - 3.10E-07 1.04 E-07 6.67E 08 2.52E 07 7.56E 07 0.00E+00 6.5]E 06 Dose iactor liquid release pathway (mrem /Ci released)

Tc.127m Done- Liver T. Body. Thyroid Kidney . Lungs - Gl LLI Adult 8.63 E-04 3.08E 04 1.05E 04 2.21E 04 3.51E 03 0.00E+00 2.89E 03 Teen 8.74E 04 3.10E-04 1.04 E-04 2.08E-04 3.54E 03 0.00E+00 2.18E 03

~ Child 1.50E 03 4.05E-04 1.79E-04 3.60E-04 4.29E 03 0.00E+00 1.22E 03 Infant 6.28 E-04 2.08 E-04 7.61E 05 1.82E 04 1.55E 03 0.00E+00 2.54E 04 I Dose factor liquid release pathway (mrem /Ci relca.ed)

Te 129 Bone Liver T. Body Thyroid -- Kidney : Lungs GI-[ Li l

Adult 1.68E 08 6.32E 09 4.10E-09 1.29E-08 7.07E 08 0.00E+00 1.27E 03 Teen 1.83E 08 6.82E-09 4.45E 09 1.31 E-05 7.68E 08 0.00E+00 1.00E-07 Child ' 2.36E 08 6.58 E-09 5.60E 09 1.68E-08 6.90E 08 0.00E+00 1.47E 06 Infant :-- 1.08E 18 3.73E 19 2.53E 19 9.07E 19 2.69E 18 0.00 E+00 8.65E 17 Dose factor liquid release pathway (mrem /Ci released)

Te 129m

<' Bone Liver T. Body- Thyroid Kidney : Lungs - ; GI-LLI.

Adult -- 1.35E-03 5.04 E-04 2.14E-04 4.64 E-04 5.63 E-03 0.00E+00 6.80E-03 Teen v 1.37E-03 5.10E-04 2.18E-04 4.43 E-04 5.75 E-03 0.00E+00 5.16E 03 Child : 2 34E-03 6.54 E-04 3.64 E-04 7.55E-04 6.88E-03 0.00E+00 2.86E-03 Infant - 1.04 E-03 3.58E 04 1.61E 04 4.01 E-04 2.61E 0.00E+00 6.23E-04 Page 3S of 120

, . .. - . .. - _. -- -- ~. . _ . - - ~

NUCLEAR POWER BUSINESS UNIT ODCM I Revision 11 DRAFT I OFFSITE DOSE CALCULATION MANUAL December 2,1997 OFFSITE DOSE CALCULATION MANUAL I

Table 5.1 1 ,

Dose factor liquid release pathway (mrem:Cl released) ,

' le7131m r lione Liver T. Body 1hyroid Kidney Lungs . GI LLI Adult - 1.04 E-04 5.08 E-05 4.24E 05 8.0$E-05 5.15E 04 0.00E+00 5.05E 03

. Teen 1.llE-04 5.34 E-05 4.49E 05 8.03 E-05 5.56E 04 0.00E400 4.28E 03 Child . l .63 E-04 5.63E 05 6.00E-05 1.16E-04 5.45 E-04 0.00E+00 2.28E-03 Infant 5.46E 05 2.20E 05 4.45E-05 1.51 E-04 0.00E+06 3.70E 04 l 1.81E-05 4

Dose factor liquid release pathway (mrerWCi released) f Te 131 Bone Liver T. Body 1hyroid Kidney Lungs GI LLI Adult 2.97E 15 1.24E 15 9.40E 16 2.44E 15 1.30E 14 0.00E+00 4.21E 16 ;

Teen- 3.21 E 15 R.32E 15 1.0lE 15 2.47E 15 1.40E 14 0.00E+ 00 2.63E 16 Child 4.12E 15 1.2SE 15 1.23E 15 3.15E 15 1.24E 14 000E+00 2.16E 14 infant 4.22E-41 1.56E 41 1.18E 41 3.77E 41 1.08E 40 0.00E+00 1.71E 39 Dose factor liquid release pathway (mrem { released)

Te132 Bone Liver T. Body Thyroid Kidney 1.ungs GI LLI Adult 1.96E 04 1.26E 04 1.19E 04 1.40E-04 1.22E 03 0.00E+00 5.98E 03 Teen 2.05 E-04 1.30E-04 1.22E74 1.37E 04 1.24 E-03 0.00E+00 4.llE 03 I Child 3.15 E-04 1.39E 04 1.69E-04 2.03 E-04 1.29E 03 0.00E+00 1.40E-03 Infant 1.48 E-04 7.32E-05 l 6.83E-05 1.08 E-04 4.58E 04 0.00E+00 2.71E 04 1

Dose factor liquid release pathway (mrentCi released) 1 131 Bone -Liver T. Ilody 8 Thyroid Kidney : Lungs GI LLI Adult 2.09E 04 2.99E 04 1.71 E-04 9.78E T 5.12E-04 0.00E+00 7.88E-05 Teen' 2.41 E-04 3.37 E-04 1.81 E-04 9.83E Of 5.80E 04 0.00E+00 6.66E 05 Child 4.90E-04 4.93 E-04 2,80E 04 d.63E 01 8.09 E-04 0.00E+00 4.39E 05 ,

Infant 5.71E 04 6.73E 04 2.96E 04 2.2 i E-01 7.86E 04 c.00E+00 2.40 E-05 Dose factor liquid release pathway (mrem /Cireleased) 1 132 Bone- Liver T, llody Thyroid . Kidney. . Lungs O! LLI Adult 1.43 E-07 3.81E-07 1.34 E-07 1.33 E-05 6.07E-07 0.00E+00 7.16E-08 Teen : 1.49E-07 3.90E-07 1.41 E-07 1.32E 6.15 E-07 0.00E+00 1.70E-07 Child c 1.85E 07 3.39E 07 1.56E 07 1.57E-05 5.19E 07 0.00E+00 3.99 E-07 Infant- 1.64 E I l 3.32E Il 1.18E Il 1.56E-09 3.7 t E Il 0.00E+00 2.69E 11 Page 39 of 120

NUCLEAR POWER DUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 ;

- OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose factor liquid release pathway (mrern/Ci teleasedl ~

l 133 Bone Liver T. Body '1hyroid - Kidnr., Lungs GILLI Adult 3.33E 05 5.80E-05 1.77E 05 8.52E 03 1.01 E-04 0.00E+00 5.21 E-05 Teen > 3.74E 05 6.34E 05 1.94F 05 8.85E-03 1.1 lE 04 0.00E+ 00 4.800 05 ;

Chi!d 6.27E 05 7.75 E-05 2.94E-05 1.44E 02 1.29E 04 0.00E40 3.13E 05 Infant - 4.77E 05 6 95E 05 2.04E 0,5 1.26E 02 8.17E 05 0.00E+00 1.18E 05 Dose factor liquid release pathway (mrerwCi released) -

1 134 9

13one - Liver T. Body Thyroid Kidney Lungs GILLI i Adult 2.09E 10 5.69E 10 2.04E 10 9.85 E-09 9.04 E- 10 0.00E+00 4.96E 13 Teen- 2.20E 10 5.82E 10 2.10E 10 9.70E-09 9.18E 10 0.00E+00 7.67E 12 Child 2.72E 10 5.05E 10 2.33E 10 1.16E 08 7.72F 10 0.00E+00 3.35E 10 ;

Infant 5.37E 22 1.10E 21 3.91E 22 2.56E 20 1.23L 21 0.00E+00 1.14E 21 Dose factor liquid release pathway (mrem /Cl releascd) 1135 Bone Liver T. Body Thyroid - Kidney Lungs GILLI Adult 3.37E 06 8 F 3 E-Ob 3.26E-06 5.82E 04 1.41 E-05 0.00E+00 9.97E-06 Teen 3.55E 06 9.14E 06 3.4 t E 06 5.88 E-04 1.14 E-05 0.00E+ 00 1.0lE-05 Child 4.54E 06 8.17E 06 3.87E-06 7.24 E-04 1.25E 05 0.00E+00 6.23 E-06 Infant 4.48E 07 8.92E 07 3.25E-07 7.99E-05 0.00E+00 3.23E 07 9.93-07 Dose fabtor liquid release pathway (mrern Ci released)

. Cs 134 Bone- Liver T. Body . Thyroid . Kidney Lungs GI LLI -

Adult - 2.19E 01 5.21 E-01 4.26E-01 0.00 E+00 1.69E-01 5.60E 02 9.12 E-03 Teen 2.25 E-01 5.30E 01 2.46E-01 0.00E+00 1.68E-01 6.43 E-02 6.59E-03 Child - < 2.76E-01 4.52 E-01 9.55E 02 0.00E+00 1.40E-01 5.03E 02 2.44E 03 Infant 1.07E 02 2.00E-02 2.02E 03 0.00E+00 5.16E 03 2.llE-03 5.44E 05

}

Dose factor liquTa'r7153e pathw ay (mrem'Ci released)

Cs 134m zBone. Liver T. Body. : Thyroid Kidney -Lungs- GILLI Adult 4.21E 06 8.85E-06 4.52E 06 0.00E+00 4.80E 06 7.56E-07 3.12E-06 ,

Teen 4.42 E-06 9.16E-06 4.71 E-06 0.00E+00 5.10E 06 8.95 E-07 6.0E-06 Child 5.48 E-06 8. l l E-06 5.29E-06 0.00E+00 4.28E-06 7.07 E-07 1.03 E-05

. Infant - 5.19E Il 8.64 E-I l 4.37E Il 0.00E+00 3.33E il 7.57E 12 6.84E Il Page 40 of 120

- NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose f actor liquid release pathway (mrem /Ci released)

Cs136 Bone Liver T. Body 1h) Told Kidney Lungs GILLI AOlt 2.23 E-02 8.815 02 634E 02 0.00E+00 4.90E 02 6.72E-03 1.00E 02 Teen 2.25E 02 8.85 E-02 5.95E 02 0.00E+00 4.82E 02 7.59 E-03 7.12E 03 Child - 2.69E 02 7.40 E-02 4.79E-02 0.00 E+00 3.94E 02 5.87E 03 2.60E 03 InfiEt EiBE 03 3.47E 03 1.29E 03 0.00E+00 1.38E 03 2.83E 04 5.27E 05 Dose factor liquid release pathway (mrem /Ci released)

Cs 137 Bone. Liver T. Body Th>Toid - Kidney Lungs GI LLI Adult 2.81E-01 3.84E 01 2.52E 01 0.00E+00 1.30E-01 4.33E 02 7.43E 03 Teen 3.02E 01 4.0lE-01 1.40E-01 0.00E+00 1.36E 01 5.30E 02 5.71E 03 Child 3.85E 01 3.69E 01 5.45E 02 0.00E+ 00 1.20E 01 4.33E 02 2.31 E-03 Infant - 1.49E 02 1.74E 01 1.24E-03 0.00E+00 4.68E 03 1.89E 03 5A$E 05 Dose factor - liquid release pathw ay (mrem!Ci released)

Cs 138 Bone Liver T. Body Th)Toid Kidney . Lungs GILLI Adult 3.57E .l l 7.04E Il 3.49E Il 0.00E+00 5.18E Il 5 llE 12 3.00E 16 Teen 3.82E Il 7.34E il 3.67E Il 0.00E+00 5.42E Il 6.30E 12 333E14 Child 4.84E Il 6.73E Il 4.27E Il 0.00E+00 4.73 E-I l 5.10E 12 3.10E Il Infant 1.63E 32 2.65E 32 1.28E 32 0.00E+00 1.32E E 2.06E 33 4.23E 32 Dose factor hquid release pathway (mrem /Ci released)

Bel 39 Bone Liver T. Body - Th>Toid Kidney Lungs GILLI Adult 1.67E-09 1.19E 12 4.93E Il 0.00E+00 1.12E 12 6.77E-13 2.77E-09 Teen 1.83 E-09 1.29E 12 5.50E Il 0.00E+00 1.21E 12 8.87E 13 1.63E 08 Child - 2.35E-09 1.25E 12 6 84E 11 0.00E+00 1.09E 12 7.37E 13 1.36E 07 Infant = 3.30E 16 2.19E 19 9.55E-18 0.00E+00 1.31E 19 1.33E 19 2.09E 14 Dose factor liquid relea'e pathway (mrem /Ci released)

Ba 140 y <

.-Bone Liver T. Body. Th>Toid - Kidney Lungs GI-LLI Adult- - 5.34 E-04 6.71 E-07 3.51E-05 0.00 E+00 2.28 E-07 3.84 E-07 1.10E-03

-Teen- 5.41 E-04 6.63E 07 3.56E-05 0.00E+00 2.25E 07 4.46E-07 8.35E 04 Child " 1.32 E-03 1.16E-06 7.72 E-05 0.00E+00 3.76E-07 6.89 E-07 6 69E-04 Infant 1.52E-03 1.52 E-06 7.84E-05 0.00E+00 3.61E-07 9.34E 07 3.74 E-04 Page 41 of 120

NUCLEAR POWER BUSINESS UNIT -ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose factor hquid release pathway (mrem /Ci released)

~

lla-141 Bone Liver T. Body Th)Toid Kidney -Lungs- GILLI Adult ' 4.57E 19 3.45E 22 163E 20 0.00E+00 3.21E 22 1.96E 22 2.15E 28 Teen 4.96E 19 3.70E 22 2.14E 20 0.00E400 3.44E 22 2.53E 22 1.06E 24 Child 6.37E 19 3.57E 22 2.18E 20 0.00E+00 3.09E 22 2.10E-21 3.63E 19 Infant 1.58E 53 1.08E 56 4.99E 5$ 0.00E+00 6.52E 57 6.60E 57 1.93E 52 Dose factor liquid release pathway (mrenvCi released)

La 140 Bone i Liver T. Body Thyroid - Kidney - Lungs GILLI Adult 3.66E 08 1.84E 08 1.03E 07 0.00E+ 00 0.00E+00 0.00E400 1.35E-03 Teen 3.68E 08 1.81 E-08 5.5 l E 07 0.00E+00 0.00E400 0.00E+00 1.04E 03 Child 8.2 i E-08 2.87E 08 1.24E 07 0.00E+00 0 00E+00 0.00 E+00 8.00E 04 Infant 8.$6E 08 3.38 E-08 8.69E 09 0.00E+00 0.00E+00 0.00E+00 3.97E 04 Dose factor liquid release pathu ay (mrenvCi released)

La 142 Bone Liver T.13ody - Thyroid Kidney. Lungs GILLI Adult 2.92 E-l 1 1.33 E. I 1 4 94E-l1 0.00E+00 0.00E+00 0.00E+ 00 9.7IE 08 Tee 3.12 E-I l 1.38 E-I l 2.6lE 10 0.00E+00 0.00E+00 0.00E+00 4.2 t E 07 Child - 3.93E Il 1.25E Il 5.77E Il 0.00E+00 0.00E+00 0.00E +00 2.48E 06 Infant 7.74E 18 2.84E 18 6.8 t E 19 0.00E+00 - 0.00E+00 0.00E+00 4.83E 13 4

Dose factor - liquid release pathway (mrenvCi released)

Cc 141 1- Bone. . Liver 1. Body . Thyroid . Kidney Lungs - GI LLI Adult - 2.05E 07 1.39E-07 2.42 E-07 0.00E+00 6.45 E-08 0.00E+00 5.31E 04 Teen 2.06E-07 1.37E 07 4.88E 07 0.00E+00 6.47E 08 0.00E +00 3.93E-04 Child 5.80E 07 2.89E-07 1.42E-07 0.00E+00 1.27E 07 0.00E+00 3.61E 04 Infant < 7.llE-07 4.34E 07 5.llE 08 0.00E+00 1.34E 07 0.00E+00 2.24 E-04 Dose factor liquid release pathway (mrem /Ci released)

Cc 143 Bone', Liver- T. Body . Thyroid Kidney Lungs . .GI LLI Adult - 1.47E-08 1.09E-05 1.78E 08 0.00E+00 4.78 E-09 0.00 E+00 4.06E 04 Teen 1.49E-08 1.08 E-05 9.40 E-08 0.00E400 4.86E-09 0.00E+00 3.26 E-04 Child 4.01 E-08 2. I A5 2.25E 08 0.00E+00 9.12E-09 0.00E+00 3.18E-04 Infant - 5.10E-08 'J 3.38E 05 3.85E-09 0.00E+00 9.85 E-09 0.00E+00 1.97 E-04 Page 42 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision !I DRAFT December 2,1997 4

0FFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose la; tor liquid telease pathw ay (mrem /Ci released)

. Cc.144 Ilone Liver T. llody lhytold Kidney Lungs GlLLI Adult 1.12E-05 4.67E 06 1.04 E 0 ' O.00E+00 2.77E 06 0 00E+00 3.78E 03 leen 1.12E 05 4 65E 06 3.03E 06 0.00E + 00 2.78E 06 0.000+00 2 82E 03 Child 3.17E 05 9.92E 06 2.20E 06 0.00E+00 5.50E 06 0.00E+00 2.59E-03 Infant 2 80E 05 1.15E 05 1.57E-06 0.00E+00 4.63E 06 0.00E+00 1.610. 03 Dost, factor liquid release pathwdy imrem/Ci released)

Pr 143 Bone Liver T. Dody 1hyroid - Kidney Lung: GI LLI Adult 5.69E 07 2.280 07 2.82E 08 0.00E400 1.32E 07 0.00E +00 2.49E 03 Teen e wb07 2.40E 07 2.99 E-08 0.00E+00 1.39E 07 0.00E+ 00 1.97E 03 Child 1.07E 06 3.21E 07 5.3]E-OS 0.00E400 1.74E 07 0.00600 1.15E 03 Infant 6.81 E 'J7 2.55E 07 3.38E 0X 0.00E+00 9.47E OH 0.00E+00 3.60E 04

, Dose factor liquid release pathway (mrem /Ci released)

Pr144 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 3.76E 22 1.56E 22 2.24E 23 0.00E+ 00 8.80E 23 0.00E+00 5.4lE 29 Teen 4.09E 22 1.67E 22 3.91E 23 0.00 E+ 00 9.61E 23 0.00E+00 4.5lE 25 Child 5.29E 22 1.64E 22 3.05E 23 0.00E+00 8.66E 23 0.00E+00 3.52E 19 infant- 1.72E 59 6.66E 60 8.67E 61 0.00E+00 2.41 E-60 0.00E+00 3.10E 55 i

Dose factor liquid release pathway (mrem /Ci rei< sed)

Nd 147 ~

Bone Liver T. Body 1hyroid Kidney . Lungs GI LLi Adult - 3.82E 07 4.42 E-07 1.130 07 0.00E+00 2.58E 07 0.00E+ 00 2.12E-03 Teen 4.23h 07 4.60E 07 5.09E 07 0.00E+00 2.70E 0* 0.00E+00 1.66E 03 Child - 7.45E 07 6.03 E-07 1.47E 07 0.00E+00 3.31 E-07 0.00E+00 9.55E 04 Infant 4.53E 07 4.65 E-07 2.85E 08 0.00E+00 1.79E-07 0.00E+00 2 95E-04 Dose factor liquid release pathway (mrem /C released)

Eu 152

Bone-- Liver IT. Body - 4 Th> Told - Kidney Lungs- GlLLI 7 Adult 1.31 E-05 2.99E-04 1.63 E-04 0.00E+f 9 1.85 E-05 0.00 E+00 1.72E 03 Teen, 1.21 E-05 2.92E 06 9.00E 04 0.00E+00 1.35E 05 0.00E+00 1.07E-01 Child L 1.84 E-05 3.34 E-06 1.91E 04 0 00E+00~ 1.4 t E-05 0.00E+00 5.49E 04 Infant 6.27E-06 1.67E-06 1.40E-06 0.00E+00 4.67E-06 0.00 E+00 1.48 E-04 Page 43 of 120_

I NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT Decemtwr 2,1997 0FFSITE DOSE CALCULATION MANUAL Table 5.1 1 Dose factor liquid release pathuay (mrerwCi released)

W 187 Hone Liver T. Body lhyroid Kidney Lungs- GILLI Adult 1.52E 04 1.27E 04 4.45E 05 0.00E+ 00 0.00E+00 0.00E+00 4.17E 02 Teen 1.65E 04 1.34 E-04 4.71E 05 0.00E + 00 0.00E+00 0.00E + 00 3.63E 02 l Child 2.09E 04 1.24E 04 5.57E-05 0.00E400 0.00E+00 0.00E+00 1.74E 02 ?

~

1nfant 2.25E 06 1.57E 06 5.41 E-07 0.00E+00 0.00 E+00 0.00 E+ 00 9.2]E 05 Dose factor

liquid release pathway (mrerWCl released)

Np239 Hone Liver T.Hody- Thyroid Kidney - Lungs- GILLI _

Adult 3.15E 08 3.09E 09 2.30E Of 0.00E+00 9.65E 09 0.00E400 6.34E 04

. Teen , 3.42E 08 3.22E 09 1.2 i E 0'l 0.00E+00 1.01E 08 0.00E+00 5.19E 04

Child 6.77E 08 4.86E 09 2.83E 08 0.00 E+ 00 1.41E 08 0.00E+ 00 3.60E 04 infant 5.720 08 5.12E 09 2.39E 09 0.00E+ 00 1.02E-08 0.00E + 00 1.48E 04 Dose factor liquid release pathway (mrem /Ci released)

U 235 Done Liver T. Body 1hyroid Kidney - : Lungs - GI LLI -

Adult 3.05E 02 0 00E+00 1.89E 03 E06E+00 7.13E 03 0.00E+00 2.98E 03 Teen 3.17E 02 0.00E +00 2.13E 03 0.00E+00 7.43 E-03 0.00E+00 2.30E 03 Child 6.92E-02 0.00E+ 00 4.23E 03 0.00 E+00 1.14E 02 0.00E+00 1.63E 03 Infant 4.42E 02 0.00E+00 3.37E 03 0.00E+00 9.40E 03 0.00E+00 7.67E 04 Dose factor . liquid release pathway (mrem /Ci released) ;

U 238 Done Liver T. Body - 1hyroid . Kidney . 1 Lungs GILLI Adult 2.92E 02 0.00 E +00 1.73 E-03 0.00E+ 00 6.67E 03 0.00E+00 2.10E 03 Teen 3.03E 02 0 00E+00 1.81E 03 0.00E+00 6.96E 03 0,00E+00 1.62E-03 .

Child 6 62E 02 0.00E+00 3.93E 03 0.00E+00 1.06E-02 0.00E400 1.15E 03 Infant = 4.23 E-02 0.00E+00 3.15E 03 0.00 E+00 .78E 03 0.00E+00 5.41E 04 Dose factor liquid release pathway (mrem'C teleased)

Am 241 U . Bone Liver T. Body Thyroid Kidney _ Lungs GILLI Adult - 5.25E 02 = 1.85E 02 3.47E-03 0.00E + 00 2.6 t E-02 0.00E+00 4.75E-03 Teenx 4.10E 02 1.5bE-02 2.77E 03 0,00E+00 2.0$ E-02 0.00E+00 3.74E-03 Child - 4.10E-02 1.83 E-02 2.93E 03 0.00 E+00 1.79E 02 0.00E+00 2.19E 03 infant 1.42E 02 6.68E-03 1.01 E-03 0.00E+00 6.10E 03 0.00E+00 7.17E 04 Page 44 of 120

, - _ _. _. _ . _ . _ . ~ . _ . . _ . . . . _ . _ - . _ _ _ _ _ _ _ _ _

t NUCLEAR POWER DUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRArf December 2,1997 :

OFFSITE DOSE CALCULATION MANUAL Atmospheric Release Mode: Radiciodine, Tritium, and Paniculates I 5.1.2 t

The dose calculations for demonstration of compliance with the 10 CFR 50, j

- Appendix I dose limits for radiciodines, tritium, and particulate radionuclides released to the atmosphere will be done in the manner similar to the liquid ;

release dose calculations described in Section 5.1.1. The total dos: is compared to the corresponding atmospheric release mode Appendix ! dose limit for the organ in question.

i i

The doses are calculated using the following formula:

API = I Dosenomi =

I (TDFaomi x C) 4 s K om mrem j Where ,

API = the Appendix ! dose for compliance evaluations in mrem .

Dosesomi

= the dose to the specific age group (a) and organ (o) via release mode (m) from radionuclide (i) i TDFoomi = total dose factor for the specific age group (a) and organ (o)

via release mode (m) from radionuclide (i) from Table 5.12 in mrem /Ci C=i curies of radionuclide (i) released Kom = the Appendix 1 dose limit for organ (o) and release mode (m) for which the calculation is being made.

The methodology and the values used to obtain the TDFaomi values are given in Appendix C.

t e

i Page 45 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 0FFSITE DOSE CALCULATION MANUAL lt is recognized that some of the release quantities may not be available at the end of the month be ause the samples from these release paths are sent to a vendor for analysis. Usually, the only radionuclides affected by these delays are St 89 and St 90. Because the quantities of these two radionuclides are but a small fraction of the total release, the absence of their dose contributions from the initial monthly dose calculation will not significantly affect the total dose obtained from the emaining radionuclides. The dose for the month will be updated upon the receipt of the veridor isotopic results and upon the receipt of any corrections to previous release quantities.

Instead of using the precalculated total dose factors, the Appendix ! dose calculation may be modified to reflect the a:tual y/Q during the release period using the methodology of Appendix Page 46 of 120

NUCLEAR POWER BUSINESS UNIT ODCM i 0FFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT i December 2,1997 i OFFSITE DOSE CALCULATION MANUAL !

TABLE 5.12 AIRBORNE EFFLUENT DOSE FACTOR Summations of dose per curie released were made for calculations over the pathways: ingestion of produce, leafy vegetables, milk, rneat; inhalation of airborne radionuclides, and direct exposure to deposited radioactivity.

Dose factor airborne telease pathway (mrentCircleased) -

113 lione Liver T. Body Thyroid Kidney Lungs GI-LLI Skin i Adult 0.00E+00 9.78E 05 9.78E 05 9.78E 05 9.78 E-05 9.78E 05 3.78E-05 0.00E+00 0.00E+00 e Teen 0.00E+ 00 1.03E 04 1.03E 04 1.03E 04 1.03E 04 1.03E 04 1.03 E-04 Child 0.00E+00 1.32E 04 1.32E 04 1.32 E-04 1.32E 04 1.32E 04 1.32E 04 0.00E+ 00 ,

Infant 0.00E+00 2.03E 05 2.03E 05 2.03E 05 2.03 E-05 2.03E 05 2.03E 05 0.00E+00 ,

1 Dose factor airborne release pathway (mtcuvCl released) ,

F.18 Bone - Liver T. Body Thyroid Kidney- Lungs GILLI Skin Adult 1.12E 04 0.00E + 00 9.61E 04 0.00 E+00 0.00E+00 0.00 E+ 00 2.19E 06 2.23 E-03 Teen 1.55E 04 0.00E +00 9 65E 04 0.00 E+00 0.00E +00 0 00E+00 9.230 06 2.23 E-03 Child 2.06E 04 0.00E+ 00 9.69E 04 0.00E+00 0.00E+00 0.00E+00 3.70E 05 2.23E 03 '

Infant 1.63 E-04 0.00E +00 9.62E 04 0.00E+ 00 0,00 E+00 0.00E+00 2.53E 05 l 2.23 E-03 4

Dose factor airborne release pathway (mrenVCi rekosed)

Na 22 Bone Liver T. Body . Thyroid Kidney -- Lungs - GI-LLI Skin Adult 4.83 E+00 4.83 E+00 2.89E+01 4.83 E+00 4.83 E +00 4.83 E+00 4.83EeJO 3.79E+01 Teen 7.41 E+00 7.41 E+00 3.15 E+01 7.41 E+00 7.4 l E+00 7.41 E+ 00 7.41 E+00 3.79E+01 Child 1.50E+0! 1.50E+01 3.90E+0i 1.50E+01 1.50E+01 1.50E+0 ! l.50E+0i 3.79E+01 Infant 1.81E+0i 1.81E+01 4.21 E+0 i 1.81E+01 1.8lE+0i 1.81 E+01 1.8tE+01 3.79E+01 Dose tactor airborne release pathway (mrenrCi released)

Na-24 Bone Liver T Body . Thyroid Kidney. Lungs GILLI Skin Adult 9.48 E-04 9.48E 04 1.77E 02 9.48E 04 9.48 E-04 9.48E 04 9.48E-04 7.64E 02 Teen 1.36E 03 1.36E-03 1.8 tE 02 1.36 E-03 1.36E 03 1.36E-03 1.36E 03 7.64E-02 Child 2.37E 03 2.37E 03 1.91 E-02 2.37E 03 2.37E-03 2.37E-03 2.37E 03 7.64E 02 Infant 3.14 E-03 3.14E 01 1.99E 02 3.14E-03 3.14E 03 3.14E 03 3.14E 03 7.64E-02 page 47 of 120

i NUCLEAR POWER BUSINESS UNIT ODChi I OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT l December 2,1997 I l

OFFSITE DOSE CALCULATION h!ANUAL Table 5.12 !

l i

Dose f actor airbome release pathway (mrem /Cl released) ,

Sc 46 Done Liver T. Body lhyroid Kidney Lungs GILLI Skin f

Adult 1.33E 02 2 $^* 02 2.00E+00 0 00E+00 2.42E 02 0.00E+00 2.40E+00 2.69E + 00 r Icen 1.75E 02 3.4 12 2.00E+00 0.00E+00 3.26E 02 0.00E+00 2.09E+00 2.69E+ 00 l Child 2.23E 02 3.0$L ,2 2 00L+00 0.00E+00 2.70E 02 0 00E+00 1.32E+00 2.69E+00 ~

Infant 1.56E-02 2.25E 02 2.00E+00 0.00 L+ 00 1.48E 02 0.00E+00 1.35E 03 2.69E+ 00 ,

l 1 I Dme factor airborne release pathway (mrem'Cl released) +

Mn 54 Done Liver T. Dody Thyroid 4 Kidney Lungs. GI LLI Skin l

Adult 0.00E+00 2.32E 01 1.99E+00 0.00E+00 6.89E 02 4.15E 02 7.08E 01 2.28E+00 Teen 0.00E + 00 3.34E 01 2.0 l E+ 00 0.00E+00 9.95E 02 5.89E 02 6.83E 01 2.28 E+ 00 Child 0.00E+ 00 4.86E 01 2.07E+00 0.00E+00 1.36E 01 4,68E 02 4.08E 01 2.28E+00 Infant 0.00E400 2.03E 02 1.95E+00 0.00E700 4.47 E-03 2.97E-02 7.38E-03 2.28E+00 Dose Iactor . airborne release pathway (mrem /Ci released)

Cr Si Bone Liver T. Body Thyroid Kidney Lungs GlLLI Skin Adult 0.00L+00 0.00E+ 00 6 59E 03 2.68E 05 9.86E 06 4.83E 04 1.07E 02 7.73E 03 Teen- 0.00E+00 0.00E+00 6.60E 03 3.39E 05 1.34E 05 7.03E 04 9.66E-03 7.73 E-03 I

Child - 0.00E+00 0.00E+ 00 6.66E-03 6.30E-05 1.72E 05 6.14 E-04 5.81E 03 7.73E 03 ,

infant 0 00E+00 0.00 E+00 6.58E 03 2.42E 05 5.31E 06 4.25 E-04 1.02E 03 7.73E 03 4

Dose factor airborne release pathway (mrem.'Ci released) >

Mn 56 Done Liver T. Body. Thyroid Kidney Lungs- GI LLI : Skin Adult 0.00E+00 4.81 E.08 1.27E 03 0.00E +00 5.31E 08 2.80E 04 6.0lE 04 1.50E 03 Teca- 0.00E+ 00 6.0$E 08 1.27E 03 0.00E+00 6.61E 08 4.51 E-04 1.70E 03 1.50E 03 Child - 0.00E+00 6.26E 08 1.27E 03 0.00E+00 6.58E 08 3.90E 04 3.66E-03 1.50E 03 Infant 0.003+ 00 4.57E 08 1.27E 03 0.00E+ 00 3.27E 08 3.72E-04 2.13 E-03 1.50E 03 t

Dose tactor a cirborne release pathway (mrem /C6 released)

Fe 55 Bone- Liver T. Body - Thyroid e Kidney Lungs- i GI-LLI Skin Adult - 3.20E 01 2.2tE-01 5.15E-02 0.00E+00 0.00 E +00 1.25 E-01 1.27E 01 0.00F+00 Teen 3.80E-01 2.70E 01 6.29E 02 0.00E+00 0.00E+ 00 1.74E 01 1.17E 01 0.00E +00 Child . 8.65 E-01 4.59E 01 1.42 E-01 0.00 E+00 0.00E+00 2.62 E-01 8.49E-02 0.00E+00 infant 7.36E 02 4.'15E 02 1.27E-02 0.00F+ W 0.00E+00 2.56E 02 6.02E-03 0.00E+00 Page 48'of 120 [

=_- .. - . . . - _ . , - . . . - - . . - - . - . . - . . . . _ . , .. - . . - -. .-

NUCLEAR POWER DUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.12 Dose factor . airbome release pathw ay (mtem/Ci released)~

le 59 Bone Liver T. Body 1h>Toid Kidney Lungs GILLI Skin Adult 2.01E 01 4.73E 01 5.65E 01 0.00E+ 00 0.00E +00 1.62E 01 1.58E+00 4.50E 01 Teen 2.25E 01 $.24E 01 5 86E 01 0.00E+00 0.00E+00 2.10E 01 1.24 E+00 4.50E 01 Child 4.62 E.01 7.480 01 7.56E 01 0.00E+00 0.00E+00 2.54E 01 7.80E-01 4.50E 01 Infant 6.14E 02 1.07E 01 4.26E-01 0.00E + 00 0.00E+00 6.16E 02 5.16E-02 4.50E-01 Dose fac tor . airborne release pathw ay (mrem /Ci released)

Co57 Bone Liver T. Body Thyrold Kidney Lungs GILLI Skin Adult 0.00E+00 1.17E 02 4.93E Ol 0.00E+00 0.00E400 1.10E 02 2.97E-01 6.13E 01 Teen 0 00li+00 1.59E 02 5 00E 01 0.00E+00 0.00E+00 1.74E 02 2.97 E-01 6.13E 01 Child 0.00E+00 2.57E 02 5.26E-01 0.00E +00 0.00E+00 1.50E 02 2. l l E 01 6.13 E-01 Infant 000E+00 4.38E 03 4.81 E-01 0.00E +00 0.00E+ 00 1.13E 02 1.50E 02 6.13E 01 Dose factor airborne release pathway (mrem /Ci released)

Co 58 lione Liver T. Body Thyroid Kidney Lungs GI LLI Skin Adult 0.000.+ 00 3.14E 02 6.02E 01 0.00E +00 0.00E+00 2.75E 02 6.38 E-01 6.23E 01 Teen 0.00E + 00 4.00E 02 6.24 E-01 0.00E+00 0,00E+00 3.99E L' 5.53E 01 6.23E 01 Child - 0 00E+00 5,73 E-02 7.07E 01 0 00E+00 0.00E+ 00 3.28 r. -02 3.35E On 6.23E 01 Infant 0.00E+00 9.90E-03 5.57E 01 0.00E+ 00 0.00E+00 2.31E 02 2.49F 02 6.23E 01 4

Dose f actor . airborne release pathway (mrem /Ci released)

Co 60 _

Done Liver T.Dody - Thyroid Kidney - Lungs ' GI LLI Skin Adult 0.00E+00 1.68E 01 3.06E+01 0.00E+00 0.00E+00 1.77E 01 3.16E+00 3.56E+01 Teen 0.00E+00 2.23E 01 3.07 E+0 i 0.00E+00 0.00E+00 2.59E 01 2.90E+00 3.56E+0i Child 0.00 E + 00 3.28E 01 3.12 E+01 0.00E+00 0.00E+00 2.10E 01 1.82E+00 3.56E+ 01 Infant 0.00E+00 5.86E 02 3 04E+01 0.00E+00 0.00E+00 l 1.34E 01 1.40E 01 3.56E+01 Dose factor

airbome release pathway (mrem /Ci released)

Ni 63

- Done - Liver T.Dody. Dyroid . Kidney Lungs ' Gl.1 LI hi Adult 2.39E+0 i 1.6)E+00 8.00E 01 0.00E+00 0.00E +00 5.29E 03 3.45 % 01 k$ "

Teen 2.93 E+0 i 2.07 E+00 9.92 E-01 0.00E+00 0.00E+00 9.llE 03 3.29E-01 0.00E+00 Child 6.73 E+01 3.60E+00 2.29E+00 0.00E+00 0.00E+00 8.16E-03 2.43E 01 0.00E+00 Infant 2.l lE+0 i 1.30E+00 7.32E 01 0.00E+00 0.00E+00 6.19E 03 6.49E 02 0.00 E+00 Page 49 of 120

NUCLEAR POWER BUSINESS UNIT ODCM i 0FFSITE DOSE CALCULATION MANUAL Revision 11 DRAIT !

December 2,1997 1 0FFSITE DOSE CALCULATION MANUAL Table 5.1-2 !

Dose factor airborne release pathway (mrem /Ci released)

Ni 65 lione Liver T. Body- Thyroid 4 Kidney Lungs GILLI Skin Adult 8.95 E-08 1.19E 08 4.17E 04 0.00E+ 00 0.00E400 1.66E 04 3.66E 04 4.85E 04 ;

leen 106E-07 1.39E-08 4.17E 04 0.00E+00 0.00E+00 2.78E 04 1.09E-03 l 85E 04 Child 1.64E-07 1.58E 08 4.17E-04 0.00E+00 0 00E+00 2.43E 04 2.49E 03 4.85E 04 Infant 7.17E 08 8.5lE 09 4.17E-04 0.00E+00 0.00E+ 00 2.41 E-04 1.49E 03 4.85 E-04 ,

J 9

Dose factor airborne release pathway (mrem /Ci released)

Cu 64 Bone' Liver T. Body Thyroid Kidney Lungs - GI LLI Skin ,

Adult 0.00E+00 1.12E 05 8.57E 04 0.00E+00 2.82E 05 2.01E 04 2.40E 03 9.65E 04 Teen 000E+00 1.40E 05 8.58E 04 0.00E+00 3.54 E-05 3 30E n4 2.90E 03 9.65E 04 !

Child . 0.00E + 00 2.19E 05 8.65E 04 0.00E+00 5.28E 05 2.84E 04 2.llE 03 9.65 E-04 Infant 0.00 E+ 00 3.42E 05 8.68E 04 0.00E+00 5.79E 05 2.76E 04 1.15E 03 9.65E 04 Dose f actor airborne release pathway (mrenVCl released) 4 Zn 65 Bone Liver T. Body Thyroid Kidney Lungs GlLLI Skin ,

Adult - 1.2iE+00 3.85 E+00 2.79E+00 0.00E+00 2.57E+ 00 2.56E 02 2.42E+00 1.21E+00 Teen II63E+00 5.67E+00 3.69 E+ 00 0.00E+00 3.63 E +00 3,68E 02 2.40E+00 1.2iE+00 Child = 3.12E+00 8.31 E+00 6.22 E+ 00 0.00E+00 5.24E+00 2.95E 02 1.46E+00 1.2iE+00 Infant 2.95 E+ 00 1.O l L 201 5.7tE+00 0.00E+00 4.91 E+00 1.92E 02 8.54 E+00 1.2tE+00 i

Dose factor attborne release pathway (mrem /Ci released)

Zn-69

- Bors Liver T. Body , Thyroid I Kidney _ Lungs GILLI Skin Adult 3.0lE 06 5.76E 06 4.0lE 07 0.00E+00 3.74E 06 2.73E 05 1.35 E-06 0.00E+00 Teen 4.64E 06 8.83 E-06 6.18E 07 0.00E+00 5.77 E-06 4.70E 05 2.47 E-05 0.00E+00 Child 1.08E 05 1.56E-05 1.45 E 06 0.00E+00 9.49E 06 4.22E 05 1.29E-03 0.00E+00 ,

infant "1.93 E-05 3.48E-05 2.59E 06 0.00E+00 1.45E 05 4.36E 05 3.23E 0? 0.00E+00

' Dose factor airborne release pathway (mrem /Ci released)

Zn 69m Bone Liver T. Body- Thyroid . . Kidney - Lungs - GI LLI Skin Adult 4.99E-05 1.20E-04 3.07E-03 0.00E+00 7.26E 05 5.65E 04 1.13E 02 5.74 E-03 ,

Teen- 7.60E 05 1.79E 04 3.07E-03 0.00E +00 1.09E-04 9.30E 04 1.49E 02 5.74E 03 Child : 1.76E-04 3.00E 04 3.09E-03 0.00E+00 1.74 E-04 8.08E-04 1.27E 02 5.74E 03 Infant 3.llE 04 6.35E 04 3.12E-03 0.00E+00 2.57E-04 7.93 E-04 1.00E 02 5.74E-03 Page 50 of 120 ,

NUCLEAR POWER BUSINESS UNIT .ODCM ,

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT !

December 2,1997 l OFFSITE DOSE CALCULATION MANUAL l Table 5.1 2 l Dose f actor . airborne release pathway (mrem'Ci released) [

lit 82 ~

Bone Liver T. Llody Thyroid Kidney Lungs GI LLl- Skin {

Adult 0.00E+00 0.00E+00 5.44E 02 0.00E+ 00 0.00E400 0.00L+00 8.47E 03 6.41 E-02 Teen 0.00E+00 0.00E+00 5.89E 02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.41E 02 ,

Child - 0.0011+00 0.00E+00 7.04E 02 0.00E + 00 0.00E +00 0.00E +00 0.00E+00 6.41E 02 l

(

Infant 0.00E +00 0.00E+00 8 32E 02 0.00E + 00 0 00E+00 0.00E+00 0.00E+00 6.41 E-02 i

Dose factor airborne release pa hway (mrem /Ci released) lit 83 '

lione Liver T. Body 1hyroid Kidney Lungs GILLI Skin Adult 0.00" + 00 0.00E+00 1.65E 05 0.00E+00 0.00E+00 0.00E+00 6.89E 06 2.84E 03 Teen 0.00E+ 00 0.00E+ 00 1.96E 05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.84 E-03 Child . O %:i+00 OLE +00 2.34E 05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.84E-03 Infant . 0.00E + 00 0.00E+00 2.07E 05 0.00E+00 0 00E+00 0.00E+00 0.00E+00 2.84E 03 ,

l Dose factor . airborne release pathw ay (mrem'Cl released) fir 84 i

lione Liver T. Ilody 1hyroid Kidney Lungs Gl-LLI Skin Adult 0 00E+00 0.00E+ 00 2.59E 02 0.00E+00 0.00E+00 0.00E+ 00 1.11E 09 2.49E 01 -

Te an 0.00E+00 0.00E+00 2.60E 02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.49E 01 Child - 0.00E+ 00 0.00E+00 2.63E 02 0.00E+00 0.00E+00 0.00E+00 0 00E+00 2.49E 01 !

Infant 0 00E+00 0.00E+ 00 2.66E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 2.49E-01 ,

Dose factor airborne release pathway (mrem'Ci released)

Lir 85 Bone ther T. Body - -Thyroid . Kidney Lungs. GILLI Skin :

Adult 0.00E + 00 0.00E+00 4.95E 06 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 2.63 E-04 Teen 0.00E+00 0.00E400 7.06E 06 0.0011+ 00 0.00E+00 0.00E+00 0.00E+00 2.63E 04 Child = 0.00E+00 0.00E+00 2.02E-05 0.00 E +00 0.00E+00 0.00E+00 0.00E+00 2.63 E-04 Infant 0.00E+00 0.00 E +00 4.2iE 05 0.00E+00 0.00E+00 0.00E+00 0.00E +00 2.63 E-04 Dose factor . airborne release pathway (mrem'Ci released)

Rb 86 Bone- Liver T. Body Thyroid Kidney Lungs - GI LLI - Skin -

Adult 0.00E+00 8.21E-01 3.95 E-01 0.00E4 00 0.00E+ 00 0.00E+00 1.61E 01 1.44E 02 Teen 0.00E+00 1.23E+00 5.92E-01 0.00E+00 0.00E+00 0.00E+00 1.82E-01 1.44 E-02 Child 0.00E+00 2.18 E+00 1.35E+00 0 00E+00 0.00E+00 0.00E+00 1.40E-01 1.44 E-02 l Infant ' O.00E400 4.17 E +00 2.07 E+00 0.00 E+ 00 0.00E+00 0.00E+00 1.07E 01 1.44 E-02 I

Page 51 of 120 l

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NUCLEAR POWER llUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL

' fable 3.1 2 l

Dose factor . airborne release pathway (mrem /Ci released)

Rb 88 Bone ther T. Body .1hyroid Kidney Lungs GILLI Skin Adult 0.00 E+00 1.15E 05 5.22E 05 0.00E+00 0.00E+ 00 0.00E+ 00 9.92E 17 4.3 f E 05 Teen 0.00E+00 1.62E 05 5.45 E-05 0 00E+00 0.00E+ 00 0.00E+00 8.66E 13 5.31E 05 Child 0.00E+ 00 1.67E 05 5.73E 05 0.00E400 0.00E+00 0.00E+00 5.12E 07 5.31E 05 000E+00 0.00E +00 0.00E+00 1.01E 05 5 31E 05 Infant = 1.65E 05 l $ 50E-05 l 0.00E+00 i

Dose factor airborne release pathway (mrem'Cl released)

Rlw89

-Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult i.00E+ 00 7.60E 06 1.78E 04 0.00E +00 0.00E+00 0.00E+00 2.75E 19 2.07E 04 !

Teen- 0 00E+00 1.04E 05 1.80E 04 0.00E+ 00 0.00E+00 0.00E+00 1.00E 14 2.07E-04 Child - 0.00E+00 1.02E 05 1.81E 04 0.00E+ 00 0.00E+ 00 0.00 E+00 5.61E 08 2.07E 04 Infant - 0.00E + 00 9.51E 06 1.79E-04 0.00E+00 0.00E+ 00 0.00E+00 2.02E 06 2.07E 04 r

Dose f actor . airborne release pathway (mrem /Cl released)

~

St 89 Bone Liver 1. Body 1hyroid Kidney Lungs GILLI Skin ,

Adult 7.63 E + 00 0.00E+00 2.19E 01 0.00E+00 0.00E+ 00 4.15E-02 1.23E+00 3.53 E-05 Teen 1.lhE+01 0.00 E+00 3.34E 01 0.00 E+00 0.00E+00 7.17E-02 1.40E+00 3.53E-05 Child - 2.77E+01 0.00E+00 7.90E 01 0.00E+00 0.00 E+00 6.40E 02 1.08E+00 3.53E 05 Infant 3.66E+00 0.00E+ 00 1.05 E-01 0.00E+00 0.00E+00 6.02E-02 7.69E 02 3.53E 05 Dose factor airborne release pathway (mrent/Ci released)

St90

~

11one . Liver T. Body- 1hyroid Kidney Lungs GILLI Skin Adult 5.10E+02 0.00E+00 1.25E+02 0.00E+00 0.00E+00 2.85 E-01 1.47E+01 0.00E+00 Teen 6.33 E+02 0.00E+00 1.56E+02 0.00E+ 00 0.00E+00 4.89E-01 1.77E*01 0.00E+00 Child - 1.05E+03 0.00E+00 2.65E+02 0.00E+00 0.00E+00 4.38E 01 1.41 E +0 i 0.00E+00 Infant - 7.33 E+01 0.00E+ 00 1.84E+01 0.00E+00 0.00E+00 3.34E 01 9.04 E-01 0.00E+00 i

Dose factor . airborne release pathway (mrent /Ci released)

Sr 91

-Bone- Liver T. Body lhyroid Kidney Lungse GILLI Skin Adult 2.29E-04 .).00E+00 3.03E 03 0.00E+00 0.00E+00 1.08 E-03 6.76E 03 3.53 E-03 Teen 2.20E 04 0.00E+00 3.03E-03 0.00E+00 0.00E+00 1.80E 03 8.68E-03 3.53E 03 Child - 4.09E 04 J 0.00E+00 3.03 E-03 0.00 '+00 0.00E+00 1.58E 03 6.06E 03 3.53 E-03 Infant 5.29E l1.00E+00 3.02E-03 0.00E+00 0.00E+00 1.56E-03 2.24E 03 3.53E 03 Page 52 of 120

)

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITU DOSE CALCULATION MANUAL Revision 11 DRAFT Decembet 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1 2 -

Lose fartor airborne release pathway (mrem Ci released)

St92 Done Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 5.04E 07 0.00E+00 165E 03 0.00E+00 0.00E+ 00 4.891604 1.28E 03 3.15E 03 Teen 5.66E-07 0.00E+00 1.65E 03 0.00E400 0 00E+00 8.14E 04 3.54E 03 3.15E 03 Child 9.08E 07 0.00E +00 1.65E 03 0.00 E+ 00 0.00E + 00 7.12E 04 7.20E-03 3.15E 03 Infant < 3.12 E-07 0.00E+00 1.65 E-03 0.00E+00 0.00E+00 7.06E 04 4.15E 03 3.15 E-03 i

Dose factor airborne release pathw ay (mrem /Ci released)

Y 90 llone Liver T. Body 1hyroid Kidacy Lungs -GI LLI Skin Adult 7.17E-05 0.00E+00 8.23E 06 0.00E+ 00 0.00E+00 5.03E 03 1.19E 01 7.45E 06 Teen 9.77E 05 0.00E+ 00 8.93E 06 0 00E+00 0.00E+00 8.69E 03 9.20E-02 7.45 E-06 Child - 1.39E 04 0 00E+00 1.00E 05 0.00 E+ 00 0.00E+00 7.76E 03 5.63E 02 7.45E 06 Infant 9.77E 05 0.00E+ 00 8.93 E-06 0.00E+00 0.00E+00 7.98E 03 3.26E 03 7.45E 06 Dose factor + airborne release pathway (mrem /Ci released)

Y 91 Done j Lner T,llody n yroid Kidney Lungs GI LLI Skin Adult 1.78 E-02 0.00E+00 1.98E 03 0.00E400 0.00E+ 00 5.06E 02 2.26E400 1.70E 03 Teen 2.55E 02 0.00E +00 2.19E 03 0.00E + 00 0.00E+00 8.71 E-02 2.44E+00 1,70E-03 Child 4.10E 02 0.00E+00 2.60E 0) 0.00 E+00 0.00E+00 7.79E 02 1.86E+00 1.70E 03 Infant 1.75 E-02 0.00E+00 0.00E+00 7.27E 02 3.72E 03 1.70E 03 0.00E+(L97E-03

~

Dose factor airborne release pathway (mrem:Ci released)

Y 9tm Dole Liver T, Body . n yroid Kidney Lungs GI-LLI - Skin Adult - 3.58E 06 0.00E+00 2.31 E-04 0.00E+ 00 0.00E+00 5.70E 05 1.0iE-05 4.33E 04 Teen 6.15 E-06 0.00E+00 2.3 tE 04 0.00 E+00 0.00E+00 9 49E 05 2.91E 04 4.33E 04 Child 1.50E 05 0.00E+ 00 2.31E 04 0.00E+00 0.00E+00 8.34E 05 2.94 E-02 4.33 E-04 Infant - 1.21 E-08 0.00E+00 2.31 E 04 - 0.00E+00 0.00E+00 8.27E 05 6.98E 05 4.33 E-04 Dose factor airborne release pathway (mrem /Ci released)

Y 92 lione- Liver T.13ody Thyroid -l Kidney Lungs GILLI Skm Adult 3.35E-05 0.00E+00 - 4.3SE-04 = 0.00E+00 0.00E+ 00 4.65 E-04 5.83E OL 2.90E 02 Teen 5.80E-05 0.00E+00 4.39E-04 0.00E+00 0.00E+00 7.95E-04 1.58E+00 2.90E-02 Child 1.42 E-04 0.00E+00 4.41 E-04 0.00E+00 0.00E+00 7.09E 04 4.09E+00 2.90E 02 Infant 4.86E-07 0.00E+00 4.37 E-04 0.00E+00 0.00 E+00 7.27 E-04 3.76E-03 2.90E 02 -

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NUCLEAR POWER DUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.12 Dose factor attborne release pathway (mrem /Ci released)

Y 93 Done Liver T Body Thyroid Kidney Lungs- GlLLI Skin Adult 1.08E 04 0.00E400 I43E 04 0.00E+00 0.00E+00 1.44E 03 3.35 E+00 6.58E 02 Teen 1.86E-04 0.00E+ 00 4.45E 04 0.00E+00 0.00E+00 2.47E 03 5.59E+00 %.58E 02 Child 4.53E 04 0.00E+00 4.52E 04 0.00E +00 0.00E+00 2.21E 03 6.69E+00 d.58E 02 Infant- 4.45E 06 0.00E+00 4.40E 04 0.00E+00 0.00E400 2.27E 03 4.95E-03 6.58E 02 Dose factor . airborne release pathw my (mrem /Cl released) lt 45

Bone - Liver T. Body , Thyroid - Kidney ,laigs , GILLI Skin Adult 4.79E 03 1.54 E-03 3.45E 01 0.00E+00 2.42E 03 5.25 E-02 1.64 E+00 3.98E 01 Teen - 6.16E-03 1.941103 3.45E-01 0.00E+ 00 2.ASE 03 7.98 E-02 1.35E+00 3.98E 01 Child 9.47E 03 2.08E 03 3.45E 01 0.00E+00 2.97 E-03 6.62E 02 8.81E 01 3.93E 01 Infant 3.43E 03 8.27E 04 3.44E 01 0.00E+00 9.23E 04 5.19E 02 9.12E 04 3.9 tie Gi ,

Dose factor airborne release pathway (mrent'Ci released)

/.t 97 Bone Liver T. Dody Thyroid Kidney Lungs .GI LLI Skin Adult . 3.12E 06 6.31E 07 4.16E 03 0.00E +00 9.56E-07 2.34 E-03 3.09E 02 4.84E 03 Teen 4.31E 06 8.52 E-07 4.16E 03 0.00E+00 1.29E 06 3.85E C3 3 09E 02 4.84E 03 Child 5.98 E-06 8.66E 07 4.16E 03 0.00E+ 00 1.24E 06 3.36E 03 1.95E 02 4.84E 03 Infant ' 4.45E 06 7.60E 07 4.16E 03 0.00E+00 7.69E-07 3.27E-03 4.16E 03 4.84 E-03 Dose factor . airborne release pathway (mrern/Ci released)

Nb-95 Bone- Liver T, Body. Thyroid Kidney - Lungs- -. Gi LLi- Skin Adult - 1.3?E 03 7.75E 04 1.92E 01 0.00E+00 7.67E-04 1.50E-02 3.30E+00 2.26E 01 Teen 1.39E 03 7.72E 04 1.92E 01 0.00E+00 7,48 E-04 2.23E 02 1.99E+00 2.26E 01 Child -- 2.22E-03 8.65E 04 1.93E 01 0.00E+00 8.13E 04 1.82E 02 1.10E+00 2.26E-01 Infant 6.0SE-04 2.49E 04 1.92E 01 0.00E+00 1.82E 04 1.42E 02 4.99E 02 2.26E 01 Dose factor airborne release pathway (mrem /Cl seleased)

Nb-97 1 Bone- : Liver-. . T. Body . ; Thyroid : : Kidney Lungs- ' GI-LLI -

Skin Adult ~ 2.05E 06 5.17E 07 4.17E 0.00E+00 6.03E 07 7.12E-05 1.91E 03 3.20E 03 Teen 3.50E-06 8.68E 07 4.17E 04 0.00E+00 1.02 E-06 1.17E 04 2.07E-02 3.20E-03 Child - 8.49E-06 1.53 E-06 4.17E 04 0.00E+00 1.70E 06 1.01 E-04 4.73 E-01 3.20E-03 Infant 1.0lE 08 2.16E 09 4.17E 04 0.00E+00 1.69E 09 9.84E 05 7.98 E-04 3.20E-03 Page 54 of 120

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NUCLEAR POWER BUSINESS UNIT ODCM :

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 !

OFFSITE DOSE CALCULATION MANUAL l Table 5.12 r

Dose factor . airborne release pathw ay (mrem /Ci released) ,

Mo 99 [

-Bone. Liver T. Body 1hyroid Kidney- Lungs GILLI Sxin Adult 0.00E +00 9.10E-03 7.34E 03 0.00E+ 00 2.06E 02 2.71E 03 2.85 E-02 6.50E 0.'

Teen 0.00Et00 1.24E 02 7.97E 03 0.00E+00 2 84E 02 - 4.56E-C3 3.02E 02 6.50E-03 Child 0 00E+00 2.06E 02 1.07E 02 0.00E+00 4.4lE 02 4.02E 03 2.08E 02 6.50E 03 Infant 0.00E H)0 3.82E-02 1.31 E-02 0.00E+00 5.70E 02 4.00E-03 1.40E 02 6.50E 03 ,

L Dose f actor . airborne release pathu ay (mrem /Ci released) ic 99m

[ llone Liver T,11ody Thyroid Kidney Lungs . Gl LLI Skin Adult - 2.92E 09 8.24 E-09 2.59E 04 0.00E+00 1.25E 07 2.27E 05 1.28E 04 2.96E 04 1 Teen 3.11E.09 8,6HE 09 2.59E 04 0.00E+00 1.29E 07 3.42E 05 1.87 E-04 2.96E-04 Child - $.95E 09 1.17E 08 2.59E 04 0.00E+00 1.69E 07 2.82E 05 1.49E-04 2.96E 04 ,

infant 5.14E 09 1.06E 08 2.59E 04 0.00E +00 1.14E 07 2.41 E-0?- 6 33E-05 2.96E 04 i Dose f actor . sirborne release pathway (mrem /Ci rcleased)

Tc lut ilone Liver T.11ody 1hyroid . Kidney Lungs GILLI Skin Adult 1.16E 05 1.67E 05 2.08E 04 0.00E+00 3.0lE 04 2.01E 05 5.06E 17 5.80E 04 Teen- 1.WE-05 2.83 E-05 3.23E 04 0 00E+00 5.12E 04 3.71 E-05 4.87E 12 5.80E 04 Child 4.89 E.05 5.12E 05 6.93 E-04 0.00E+ 00 8.72E 04 4.44E 0I 1.63E 04 5.80E-04 Infant 1.93E 12 2.44E 12 4.44E 05 0.00E+00 2.90E Il I.73 E-05 2.50E 05 5.80E-04 Dose factor airborne release pathway (mrem /Ci released)

Ru-103

-tione Liver T. Body. Thyroid Kidney Lungs GI-LLI Skin Adult 4.360 02 0.00E+00 1.71 E-01 0.00 E+00 1.66E 01 1.50E 02 5.08E+00 1.77E-01 Teen 3.76E 02 0.00 E+00 1.68E 01 0.00E+00 1.33E 01 2.32E 02 3.14 E+00 1.77E 01 Child 7.01E 02 0.00E+00 1.79E 01 0.00E+00 1.77E 01 1.97E-02 1.81E+00 1.77E 01 Infant 6.20E-05 0.00E+00 1.52E 01 ; 100E+00 1.30E 04 1.64E 02 5.05 E-04 1.77EOl]

Dose factor airborne release pathway (mrem /Ci released)

Ru 105

~

. Bone- Liver T. Body Thyroid _ Kidney. Lungs GI LLI - Skin Adult 6.19E 04 0.00E+00 2.07E 03 0.00E+00 7.99E 03 3.25E 04 3.80E-01 1.02E-02 Teen 'I .06E-03 0 00E+00 2.23E 03 0.00E+00 1.34E 02 5.39E-04 8.59E-01 1.02E-02 Child 2.59E 03 0.00E +00 2.76E-03 0 00E+00 2.28E 02 4.72 E-04 1.69E+00 1.02E-02 ,

Infant 3.63E 08 0.00E + 00 1.82E 03 0.00E+00 2.67E-08 4.65E-04 1.44 E-03 1.02 E-02

- Page 55 of 120 -

NUCLEAR POWER '13USINESS UNIT ODCM ,

E OFFSITE DOSE CALCULATION MANUAL-- Revision 11 DRAFT .

December 2,1997 -

l

OFFSITE DOSE CALCULATION MANUAL - t Table 5.12 ;

3 Dose factor airbome release pathway (mrem /Ci released) .

. -Ru 106 ,

< Bone. -Liver. T, Body- - Thyroid Kidney Lungs - - GI-LL1, Skin : ;

l 4 Adult ; 1.65E+00 0.00E+00 8.01E-01 0.00E+00 3.18E+00 2.78E-01 1.06E+02 7.llE 01 .L 0.00E+00 4.77E-01 7.16E+01 7.llE 01 i

. Tecn :E 1.49E+00 0.00E+00 7.81E 01 2.88 E+00 3hild t 9.58E-01 0.00E+00 3.96E+00 4.25E-01 4.55 E+01 7.llE 01 2.93 E+00_ 0.00E+00 ljnfant - 2.67E-03 0.00E+00 5.93E 01 0.00E*00 3.28E-03 3.43E Ol 5.60E-03 7.llE 01 Dose factor airborne release pathway (mrem /Ci re; eased) l Rh 105 l Bone . Liver < T. Body. Thyroid 4 Kidney Lungsr -GI-LL1 Sida l Adult -- 4.8 t E 02 3.52E-02 2.47E-02 0.00E+0C 1.50E 01 5.72E 04 5.61E+00 7,74E 03 l Tecn> 8.33 E-02 6.02E 02 4.10E 02 0.00E+00 2.56E 01 - 9.71 E-04 7.66E+00 7.74E 03 l Child 2.04E 01 1.10ti-01 9.53 E-02 0.00E +00 4.37E-01 8.59E-04 6.80E+00 7.74E 03 l

' infant 7.15E 04 4.68E-04 1.83 E-03 0.00E+00 1.30E 03 8.64E 04 1.22E 02 7.74 E-03 l 4

, Dose factor - nirborne release pathway (mrem /Ci released) l Agil0m Bone Liver.. T, Body Thyroid ; - Kidney : . Lungs GI-LLI Skin Adult 4.10E 02 3.80E-02 4.85 E+00 0.00E+00 7.47E-02 1.37E 01 1.54 E+01 5.63 E+00 Teen- 6.28 E-02 5.94E 02 4.86E+00 0.00E+00 1.13E 01 r2.00E-01 1.66E+01 5.63 E+00 Child : 1.34 E-01 9.04 E-02 4.90E+00 0.00E+00 1.68E-01 1.62 E-01 1.07E+01 5.63E+00 infant ' l.93E 01 1,41E 01 4.92E+00 0.00E+00 2.02E 01 1.09E 01 7.3 t E+00 5.63 E+00 Dose factor - airborne release pathway (mrem /Ci released)

Sb-124

-Bone . Liver - T. Body- Th>Tcid. ; Kidney.; : Lungs; ; .GI-LLI ; Skin Adult 1.44 E-01 2.73 E-03 1.36E+00 3.50E 04 0.00E+00 1.85 E-01 4.09E+00 4.02 E+00 Teent 2.22E 01 - 4.09 E-03 1.39E+00 5.93E 04 0.00E+00 3.07E 01 4.46E+00 4.02E+00 Child. 5.llE-01 6.63E 03 1.48 E+00 1.13E 03 0.00E+00 3.79E-01 3.19E+00 4.02E+00 Infant 6.72E-02 9.90E-04 132E+00 1.78E 04 0.00E+00 1.20E-01 2.06E-01 4.02E+00 Dose factor - airborne sclease pathway (mrem /Ci released)

Sb-125 -

Bone; a Liver :T. Body. . Thyroid: ; Kidney. 1 Lungs LGI-LLI - Skin Adult---- 1.07 E 61 ' l.20E-03 5.38E+00. 1.09E-04 0.00E+00 1.33 E-01 1.17E+00 9.l l E+00 Teen =< l .61 E-01 1.76E-03 5.39E+00 1.54E 04 0.00E+00 2.21 E-01 1.24 E+00 9. l l E+00 Child - 3.69E-O L 2.84E 03 5.43 E+0'., 3.42E 04 0.00E+00 - 2.73 E-01 8.75E-01 9. l l E+00 Infant o 8.33E 02 8.05E 0- 5.37Ed 1.04E 04 0.00E+00 9.99 E-02 1.09E-01 9. l l E+00 Page 56 of 120 w vC,--s aw-r-* - * -m4 w ..,y , . - . __ , , , _ . , _ _ , , _ _ _ _ , , , _ _ _ ,

NUCLEAR POWER BUSINESS UNIT ODCM

'OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 ,

Dose factor - airborne rel:ase pathway (mrerWCi released)

Te 125m Bone . Liver T. Body- Dyroid' _ Kidney. Ltings GI-LLI Skin -

Adult 3.87E 01 1.40E-01 6.67E 02 1.16E-01 1.57E+00 9.30E 03 1.55E+00 3.96E 02 -

' Teen- 5.IIE 01- 1.84 E-01 8.32E-02 1.43 E-01 0.00E400 1.59E 02 1.5 i E+00 3.96E 02 Child 1.17E+00 3.16E-01 1.70E 01 3.27E-01 0.00Ev00 1.42E C2 1.13 E+00 3.96E 02 5.10E-02 2.18E 02 1.72E-02 0.00E+00 1.33 E-02 3.96E 02 Infant - 1.7 t E-02 2.'K 02 Dose factor airborne release pathway (mrem /Ci released)

Te 127 Bone Liver T. Body. D yroid Kidney -Lungs GI-LLI Skin Adult- 4.47 E-06 1.61 E-06 5.15 E-06 3.31 E-06 1.82E 05 1.93 E-04 2.05E 03 4.60E 06 Teen 4.34E 06 1.55 E-06 5.12E-06 3.00E-06 l.76E 05 3.32E-04 2.73E 03 4.60E-06 Child - 8.13 E-06 2.20E 06 5.93 E-06 5.63E 06 2.3 l E 05 2.98E-04 1.98E-03 4.60E 06 Infant 1.25E 06 4.25 E-07 4.45E 06 1.02E-06 3.03E 06 3.07E-04 7.48E 04 4.60E-06 Dose factor airbome release pathway (mrem /Ci released)

Te127m Bone Liver T. Body Thyroid Kidney Lungs / GI-LLI Skin Adult 1.19E+00 4.26E 01 1.54E 01 3.05E 01 4.84 E+00 2.85E-02 4.00E+00 6.16E-02 Teen- IA8E+00 5.26E 01 1.85 E-01 3.52E-01 6.0 l E+00 4.91 E-02 3.70E+00 6.16E-02 Child 3.32E+00 8.94 E-01 4.03E 01 7.94E-01 9.47E+00 4.39E 02 2.69E+00 6.16E 02 Infant 1.96G-01 6.50E-02 3.26E-02 5.66E-02 4.82E-01 3.89E-02 7.96E 02 6.16E-02 l Dose factor airbome release pathway (mrem /Ci released) l Te-129 Bone Liver.- T. Body. Thyroid Kidney Lungs .Gi-LLI - Skin

[

- l Adult - 1.48 E-09 7.10E 10 3.68E 05 1.16E-09 5.56 E-09 5.74 E-05 4.65 E-06 4.36E 05 l Teen - 2. l l E-09 1.00E 09 3.68E-05 1.54 E-09 7.88E 09 9.78E 05 4.79E-05 4.36E-05 l Child 2.90E-09 1.04 E-09 3.68E 05 2.12E-09 7.62E 09 8.71 E-05 7.56E 04 4.36E-04 l Infant 2.34E 09 1.03 E-09 3.68E-05 2.00E-09 5.19E-09 8.89E 05 7.81 E-04 4.36E-05

'bose factor - airbome release pathway (mrem /Ci released)

Te-129m -

Bone- rLiver T. Body Thyroid : - Kidney - -Lungs - GI-LLI . : Skin Adult . 1.39E+00 5.19E 01 2.35 E-01 4.78E-01 5.80E+00 3.44E 02 7.0 l E+00 9.07E-01 Teen 1.94 E+00 7.20E 3.22E-01 6.26E 01 8.12 2+00 5.86E-02 7.30 E+00 9.07E-11 Child ' 4.53 E+00 1.26E+00 7.18E-01 1.46E+00 's.33E+0! 5.23 E-02 5.53 E+00 9.07E-01 Infant - 1.39E-01 4.77E-02 3.66E-02 5.34 E-02 3.48 E-01 4.985-02 8.46E-02 9.07E-01 Page 57 of 120

L NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.12 Dose factor airborne release pathway (mrem /Ci released)

Te 131

-Bone- Liver T. Body Thyroid Kidney Lungs GI-LLI Skit Adult 1.47E-03 6.14 E-04 5.56E. 04 1.21E 03 6.43E-03 4.13E 05 2.09E-04 1.63E-03 Teen 2.52E-03 1.04E 03 8.80E-04 1.94 E-03 1.10E 02 6.93 E-05 2.07E-04 1.63E 03 Child 6.19E 03 1.89 E-03 1.93E 03 4.73 E-03 1.87E 02 6.09E-05 3.25E-02 1.63E 03 Infant ' 5.15E 10 2.44 E-10 9.27E-05 4.69E 10 1.18E-09 6.llE 05 2.44E 04 1.63E-03 1.,

Dose factor airborne release pathway (mrem /Ci released)

Te 13im

= Bone. Liver T. Body Thyroid Kidney : Lungs GI LLI , Skin .

" Adult - 1.30E-01 6.34 E-02 7.45 E-02 1.00E 01 6.43E 01 4.32E-03 6.32 E+00 3.77 E-02 Teen- 2.21 E-01 1.06E-01 1.10E-01 liOE-01 1.llE+00 7.05E-03 8.53 E+00 3.77E-02 Child = 5.38E-01 1.86E 01 2.20E-01 3.83E 01 1.80E+00 6.10E 03 7.56E+00 3.77E 02 Infant . 6.34 E-04 2.56E 04 2.18E-02 5.18E-04 1.76E 03 5.90E-03 7.8IE 03 3.77E-02 Dose factor - airborne release pathway (mrem'Ci released)

Te 132 Hone Liver T. Body Thyroid . Kidney Lungs GI-LLI Skin l Adult : 1.92E-01 1.24 E-01 1.27E 01 1.37E 01 1.20E+00 8.55E 03 5.89E+00 1.32E 02 Teen 3.19E 01 2.02E 01 2.00E 01 2.13 E-01 1.94E+00 1.33E-02 6.42 E+00 1.32 E-02 Child " 7.61 E-01 3.37E-01 4.17E-01 4.91 E-01 3.13E+00 1.12E-02 2.39E+00 1.32E-02 Infant 3.94E-03 1.95E 03 1.17E 02 2.88E-03 1.22E 02 1.0 l E-02 8.50E-03 1.32E-02 Dose factor airborne release pathway (mrem /Ci released) 1 131

' Bone- Liver - T. Body, ; Thyroid : Kidney Lungs-- GI-LLI Skin Adult ' 7.16E-02 1.02 E-01 8.29E-02 3.36E+01 1.76E-01 0.00E+00 2.69E-02 2.93 E-02 Teen 6.57E-02 9.19 E-02 7.35 E-02 2.68E+01 1.58E-01 0.00E+00 1.81 E-02 2.93E-02 Child -- 1.44E 01 1.45E 01 1.07E 01 4.80E+0! 2.38 E-01 0.00E+00 1.29E-02 2.93E-02 Infant. 2.04E O L 2.40E 01 1.30 E-01 7.89E+01 2.80E-01 0.00E+00 8.56E-03 2.93E-02 Dose factor - airborne release pathway (mrem /Ci released) 1 132 Bone- -Liver T. Body _. Thyroid . Kidney Lungs ;GI-LLI Skin Adult 3.44E 05 9.67E-05 1.78E-03 3.40 E-03 1.54 E-04 0.00Et00 1.2 t E-05 2.06E-03 Teen. 4.73 E-05 1.30E 1.80E-03 4.49E-03 2.05E 04 0.00E+00 3.78 E-05 2.06F-03 Child 6.28 E-05 1.21 E-04 1.80E-03 5.74 E-03 1.86E 04 0.00E+00 9.50E-05 2.06E-03 Infant : 5.03 E-05 1.05 E-04 1.79E-03 5.03 E-03 1.17 E-04 0.00E+00 5.65E-05 2.06E 03 l Page 58 of 120

NUCLEAR POWER BUSINESS UNIT . ODCM_ o OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT i December 2,1997 -

OFFSITE DOSE CALCULATION MANUAL ;

- Table 5,1 2 -

Dose factor airborne release pathway (mrem /Ci released) ,

I-l32 Bone' Liver T. Body- Thyroid Kidney Lungs ; + GI LLI - Skin

~

Adult 1.46E 03 2.53E 03 4.21 E-03 3.71E 01 4.4 t E-03 0.00E+00 2.14E 03 4.19E 03 Teen 1.49E 2.52E-03 4.21 E-03 3.53E 01 4.42E 03 0.00E+00 1.75E 4.19E-03 Child 1 2.87E 03 3.55E-03 4.78 E-03 6.61E 01 5.91E 03 - 0.00E+00 1.35E-03 4.19E 03 Infar't 3.16E 03 4.59E-03 4.79E-03 8.37E 01 5.40E 03 0.00E+00 7.45 E-04 4.19E 03 -

Dose factor a;rborne release pathway (mrem'Ci released) ;

l134 Bone <Liverg T. Body Thyroid - Kidney Lungsv GI LLI Skin Adult . l .91 E-05 5.13E-05 6.45E 04 8.85E 04 8.17E 05 0.00E+0') 2.99E 08 7.45 E-04 Teen 2.63 E-05 6.88 E-05 6.52E 04 1.17c-03 1 1.09E 04 0.00E+00 6.05E 07 7.45E 04 Child 3.48E 05 - 6.41E 05 6.57 E-04 1.50E 03 9.79E-05 0.00E+00 2.83 E-05 7.45E 04 -

Infant 2.73E 05 5.57E-05 6.47 E-04 1.32E-03 6.19E 05 - 0.00E+00 3.83E-05 7.45E-04 Dose factor airborne release pathway (mrenvCi released) l135 Bone -Liver T. Body Thyroid - Kidney ; -Lungsi . Gi-LLI - Skin Adult 9.31E 05 2.43i' 04 3.64E 03 1.56E-02 3.87E-04 0.00 E+00 1.96E-04 4.14E 03 Teen- 1.22E 3.12E 04 3.66E 03 2.05E 02 4.92E-04 0.00E+00 2.41 E-04 4.14E 03 Child , 1.69E 04 3.00E-04 3.69E 03 2.72E 02 4.61E 04 0.00E+00 1.63E 04 4.14E-03 Infant 1.23 E-04 2.43 E-04 3.64E 03 2.22E 02 l 2.70E-04 0.00E+00 6.06E 05 4.14E-03 Dose f actor - airbome release pathway (mrem /Ci released)

Cs-134 Bone: Liver T. Body , Thyroid > i Kidney- : Lungsi LGI LLI. Skin 4

Adult 6.68E+00 1.59E+0i 2.26E+01 0.00E+00 5.15E t00 1.71E+00 2.78 E-01 1.12E+01 Teen- 1.06E+0'! 2.49E+01 2.12E+01 0.00E+00 7.90E+00 3.02E+C0 3.09E-01 1.12E+01 Child ' 2.39E+01 3.93 E+01 1.79E+01 0.00E+00 1.22E+01 4.37E+00 2.12E-01 1.12E+0 !

Infant : 1.96E+0 ! 3.66E+01 1.33 E+01 0.00E+00 9.42 E+00 3.86E+00 9.94 E-02 1.12E+01 Dose facto airborne release pathway (mrem /Ci released) j< Cs-134m Bone ; Liver.- T. Body Thyroid : = Kidney ELungs: GILLi~ Skin C Adult - 8.36E-04 1.76L-03 9.4 l E 04 - 0.00E+00 9.54 E-04 1.50E-04 6.19E-04 6.90E-05 Teen 1.40E 03 2.89E-03 1.53 E-03 0.00E+00 1.61 E-03 2.83 E-04 1.92 E-03 6.90E 05 Child - 3.30E-03 4.89E 03 3.24E 03 0.00E +00 2.58 E-03 4.27E-04 6.18 E-03 6.90E-05 Infant 5.48 E-06 8.72E 06 - 4.70E-05 0.00E+00 3.53F 06 1 8.31E-07 4.82E-06 6.90E-05 Page 59 of 120 -

. - m. _ _ . _ . . _ . _ _ _ .u_. ._ , _- _ -

. NUCLEAR POWER BUSINESS UNIT -ODCM OFFSITE DOSE CALCULATION MANUAL ' ' Revision i1 DRAFT December 2,1997' OFFSITE DOSE CALCULATION MANU/.L Table 5.12 I

Dose factor airborne release pathway (mrem /Ci released)-

Cs136-Bone ~ Liver . T. Body. Thyroid -

. Kidney - -Lungs- . GI LLI _- Skin Adult -- 3.31E 01 1.3lE+00 1.28E+00 0.00E+00 7.27E 01 9.97E 02 1.48E 01 4.73E 01

' Teen, 5.12 E-01 2.02E+00 1.70E+00 0.00E+00 1.10E+00 1.73E 01 1.62E-01 4.73E 01 Child - 1.14E+00 3.14 E+00 2.38E+00 0.00E+00 1.67E+00 2.49E 01 1.10E-01 4.73E 01 Infant 3.54E 01 104 E+00 7.33E 01 0.00E+00 4.15E 01 8.48E-02 1.58E 02 4.73E-01 l Dose factor . airbome release pathway (mrenVCi released)

Cs-137 Bone > Liver T. Body Thyroid ; Kidney - Lungs. .GI LLI Skin Adult 9.32E+00 1.30E+01 2.30E+01 0.00E+00 4.42 E+00 1.47 E+00 2.52E 01 1.69E+01 Teen 1.57E+01 2.09E+01 2.18E+01 0.00E+00 7.12 E+00 2.77E+00 2.97E-01 1.69E+01 Child - 3.73E+01 3.57E+0i 1.97E+01 0.00E+00 1.16E+01 4.18E+00 2.23E 01 169E+01- !

Infant = 2.99 E+01 3.49E+0 i 1.70E+01 0.00E+00 9.38 E+00 3.80E+00 l .09E-01 1.69E+0 !

Dose factor - airborne release pathway (mrem /Ci released)

Cs-138 -

Bone Liver T. Body Thyroid Kidney . Lungs GI-LLI - Skin Adult 2.17E 03 4.28 E-03 2.70E 03 0.00E+00 3.14E 03 3.10E 04 1.82E-08 4.39E-03 Teen 3.69E 03 7.08 E-03 4.13 E-03 0.00E+00 5.23 E-03 6.08E-04 3.21 E-06 4.39E-03 Child 8.O E-03 0.00E+00 8.73 E-03 9.40E 04 5.71E 03 4,39E-03 8.93E-03 ~

1.24 E-02 Infant 1.50E-05 2.32E 05 5.97E N 0.00E+00 1.22E-05 1.94 E-06 2.60E-05 4.39E-03 ;

q Dose factor - airborne release pathway (mrem /Ci released) l !

Ba 139 j

. Bone . Liver T. Body. Thyroid - Kidney - Lungs < . GI-LLI - Skin Adult x 3.78E-03 2.69E 06 1.38 E-04 0.00E+00 2.52E 06 4.62E 05 6.71E 03 6.76E-03 Teen' 6.56E-03 4.61 E-06 2.18E 04 0.00E+00 4.35 E-06 8.00E-05 5.86 E-02 6.76E-03 Child - 1.6 i E-02 8.50E 06 4.95 E-04 0.00E+00 7.5 i E-06 7.37E 05 9.31 E-01 6.76E 03 Infant - 1.76E 08 1.17E Il 2.75E 05 0.00E+00 7.04E 12 7.07E 05 6.06E 04 6.76E-03 _

Dose factor airbome release p*hway (mrem /Ci released) -

Ba140-Bone. : Liver T. Body Thyroid --- Kidney -LungsF

x GI-LLI - Skin Adult 1.09E-01 1.37E-04 3.60E-02 0.00E+00 4.67E-05 3.78E 2.29E-01 3.29E 02 Teenc 1.19E-01 1.46E-04 3.65 E-02 0.00E+00 4.94E-05 6.04E 1.88E-01 3.29E 02 Child ' 2.29E 01 2.10E * $E . 0.00E+00 6.83 E 5.18E-02 1.23E 01 3.29E-02 Infam . 4.46E-02 4.46E 3a E-02 0.00E+00 1.06E-05 4.74E-02 1.17E-02 3.29E-02 Page 60 of 120

- NUCLEAR POWER BUSINESS UNIT? ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT

< December 2,1997__ 1

. OFFSITE DOSE CALCULATION MANUAL :

-Table 5.1-2 r Dose factor . airborne release pathway (mrem /Ci released)

Ba 141 -

Bone T. Body. 'Ihyroid . Kidney Lungs GI-LLI - Skin

. Liver Adult - 1.83 E-03 1.39E 06 2.01E 04 0.00E+00 1.29E-06 2.38 E-05 8.66 E-13 1.53E-03 {

Teen 3.16E 03 2.36E 06 2.45E 04 0.00E+00 2.19E 06 4.07E 05 6.75E 09 1.55E-03 ';

j Child ' 7.79E-03 4.36E-06 3.92E-04 0.00E+00 3.77E 06 6.03 E-05 4.44 E-03 1.55E-03 Infant - 1.86E-09 1.28E 12 1.39E 04 0.00E+00 7.72E 13 3.53E-05 5.64E 05 1.55E-03 l

Dose factor . airborne release pathway (mrem /Ci released)

La 140

-Bone -Liver T. Body _ D yroid Kidney. Lungsf 1GI LLI Skin Adult - 1.17E-05 5.91E 06 2.70E 02 0.00E+00 0.00E+00 4.04E 03 6.96E-02 3.06E 02 i 4- Teen- 1.57E 05 7.7 l E 06 2.70E 02 0.00E+00 0.00E+00 6.36E-03 5.51 E-02 3.06E-02 l Child = 2.18E 05 7.60E 06 2.70E-02 0.00E+00 0.00E+00 5.42E 03 3.26 E-02 3.06E 02 l Infant - 1.56E 05 6.17E-06 2.70E 02 0.00E+00 0.00 E+00 4.98E-03 5.27E 03 3.06E 02 l Dose factor airborne release pathway (mrem /Ci released)

La 142 -

F Bone Liver T. Body: D yroi'. Kidney . Lungs GI-LLI Skin Adult - 4.98E-06 2.27 E-06 1.97E 03 0.00E+00 0.00E+00 7.52E 05 1.65 E-02 9.71 E-03 Teen 8.44 E-06 3.75 E-06 1.97E. 03 0.00E+00 0.00E+00 1.tlE-04 1.14 E-01 9.71 E-03 Child 2.04E 05 6.50E 06 ' 97E G3

. 0.00E+00 0.00E+00 1.03E 04 1.29E+00 9.71E 03 Infant 1.22 E-08 4.48 E-09 1.97E-03 0.00E+00 0.00E+00 9.77E 05 7.07E-04 9.71 E-03 i~

4 Dose factor airborne release pathway (mrem /Ci released)

Cc 141 Bone' _ Liver = -- T. Body . Thyroid 7 Kidney > L Lungsa iGI LLI Skin

~

Adult '. 7.38E 04 5.0lE-04 1.93 E-02 0.00E+00 2.32E 04 1.07E-02 3.84 E-01 2.16E-02 .

Teen- 1.05 E-01 7.02E 04 1.93E-02 0.00E+00 3.29E 04 1.82E 02 4.02 E-01 2.16E 02 Child , 1.65E 03 8.20E-04 1.93E-02 0.00E+00 3.59E 04 1.61E 02 3.02E-01 2.16E-02

~

Infant 3.32E-0 4 5.00E-04 1.92E-02 0.00 E+00 1.58E-04 1.53 E-02 3.79E-03 2.16E 02 Dose factor - airborne release pathway (mrem /Ci released)

Cc143

^

Bone- : Liver iT. Body- Thyroid' Kidney ; Lungs- GI LLI - Skin

~

Adult + 6.71 E-05 4.80E-02 4.80E 03 0.00E+00 2.18 E-05 9.48E 1.80E+00 6 60E 02 Teen - 1.15 E-04 8.10E-02 4.81 E-03 0.00E+00 3.74 E-05 1.55E.03 2.44E+00 - 6.60E-02 Child 2.77E 1.48 E-01 4.82E-03 0.00E+00 6.31 E-05 1.37E-03 2.17E+00 6.60E-02 infant 3.55E-06 5.06E 05 ,4.80E-03 0.00E+00 6.85E-07 1.38E-03 8.73 E-04 6.60E-02 Page 61 of 120

l NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor airborne release pathway (mrem /Ci released)

Cc-144 Bone _ Liver T. Body Thyroid - Kidney Lungs GI LLI Skin .

Adult ' l.26E 01 5.24 E-02 1.04E-01 0.00E+00 3.10E 02 2.31 E-01 8.05E+00 1.13E 01 Teen 1.83 E-01 7.56E-02 1.07E-01 0.00E+00 4.51 E-02 3.96E-01 9.46E+00 1.13E 01 Child 2.91 E-01 9.10E-02 1.13E-01 0.00E+00 5.04 E-02 3.55E 01 7.37E+00 1.13E-01 Infant 1 9.58 E-02 3.64 E-02 1.03E 01 0.00E+00 1.61 E-02 2.92E-01 6.97E-02 1.13 E-01 Dose factor airborne release pathway (mrem /Ci released)

Pr 143 Bone- Liver - T. Body - Thyroid Kidney Lungs- GI-LLI Skin Adult' 5.IIE-04 2.05E 04 2.53 E-05 0.00 E+00 1.18E 04 3.34 E-03 1.75E+00 3.77E-01 Teen- 8.14E-04 3.25E 04 4.05 E-05 0.00E+00 1.89E-04 5.74E 03 2.16E+00 3.77E 01 Child . l.82E 03 5.46E-04 9.02 E-05 0.00E+00 2.96E-04 5.15E 03 1.73 E+00 3.77E-01 Infant 1.67E-04 6.23 E-05 8.32E 06 0.00E+03 2.35E-05 5.14E-03 5.83E 04 3.77E 01 Dose factor airborne release pathway (mrem /Ci released)

Pr144 Bone . Liver T. Body Thyroid Kidney- Lungs. - GI-LLI Skin Adult 8.93E 10 3.70E-10 2.58E-06 0.00E+ 00 2.09E 10 3.01 E-05 639E 16 2.96E 06 Teen. 1.27F 'a 5.22E 10 2.58E 06 0.00E+00 2.99E 10 5.20E 05 6.98E 12 2.96E 06 Child 1.77E-63 5.48E 10 2.58 E-06 n 00E+00 2.90E 10 4.64 E-05 5.84 E-06 2.96E-06 Infant 1.42E-09 5.48E 10 2.58E 06 l 0.00E+00 1.99E 10 4.78 E-05 1.27E-04 2.96E 36 Dcsc factor airborne release pathway (mrem /Ci released)

Nd 147 Bone Liver T. Body. Thyroid Kidney Lungs ;GI-LLI Skin Adult: 8.95 E-05 1.03 E-04 2.00E-02 0.00E+00 6.04E 05 2.62E 03 1.51E 01 2.00E 01 Teen 1.22E 04 1.33 E-04 2.00E 0.00E+00 7.80E-05 4.42E-03 1.15E 01 2.00E 01 Child 1.85E 04 1.49E-04 2.00E 02 0.00E+00 8.22E-05 3.90E-03 7.33E-02 2.00E-01 Infant 9.45 E-05 9.69E-05 2.00E-02 0.00E+0? 3.75 E-05 3.83E 03 4.73 E-04 2.00E-01 Dose factor airborne release pathway (mrem /Ci released)

Eu-152 Bone . Liver T. Body. Thyroid 3 . Kidney - Lungs _ GI-LLI . Skin Adult 3.32E 02 2.45 E-01 3.62E+01 0.00 E+00 4.67E-02 3.261' 12 1.38E+00 6.86E+0!

Teen- 4.20E-02 1.02E-02 3.62E+0 ] 0.00E+00 4.73E-02 4.76E-02 1.23 E+00 6.86E+01 Child 6.02E-02 1.10E-02 3.62E+01 0.00Et00 4.64 E-02 3.96E-02 8.25E-01 6.86E+01 Infant - 1.30E-02 2.95E 03 3.62E+01 0.00E+00 9.90E-03 2.46E-02 5.31E 04 6.86E+01 Page 62 of 120

. NUCLEAR' POWER BUSINESS UNIT ' ODCM 0FFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 0FFSITE DOSE CALCULATION MANUAL ;

Table 5.12 i

-. 4 Dose factor airborne release pathway (mrem!Ci released; W.187. ,.

Bone. 1 Liver - T. Body: Thyroid . Kidney Lungsu GI LLIy Skin Adult 4.08E 03 3.41 E-03 7.22E 03 - 0.00E+00 0.00E+00 3.45E 04 1.12E+00 2.79E 02 ,

Teen- 6.98E 03 5.69E 03 8.03 E-03 0.00E+00 0.00E+00 5.63E 04 1.54E+00 2.79E 02 Child 1.69E-02 1.00E-02 1.05 E.02 0.00Et00 0.00E+00 4.88E-04 1.41 E +00 2.79E 02 infant e 1.13E-05 7.88 E-06 6.04E 03 0.00Ev00 0.00E+00 4.71E 04 8.79E 04 2.79E 02 -

Dose factor airborne release pathway (mrem /Ci released)

U-235

v. Bone. . Liver- -T. Body Thyroid : Kidney . ' Lungs ;GI LLI . Skin Adult . 4.06E+0 i 0.00E+00 1.04E+01 0.00E+00 9.47E+00 4.65E+00 3.87E+00 1.06E+01 -

Teen 6.45E+01 0.00E+00 1.19E+01 0.00E+00 1.5 l E+01 8.03E+00 4.59E+00 1.06E+01 l Child- 1.54 E+02 0.00E+00 1.73 E+0! 0.00E+00 2.53E+01 7.17E+00 3.58E+00 1.06E+01 l Infant - 1.17E+0i 0.00E+00 8.84 E+00 0.00E+00 2.49E+00 5.46E+00 1.90E-01 1.06E+01 l Dose factor - airborne release pathway (mrem /Ci released)

U 238 Bone Liver T. Body . Thyroid . Kidney- Lungs .GI-LLI Skin Adult - 3.88 E+01 0.00E+00 2.33 E+00 0.00E+00 8.86E+00 4.36E+00 2.72 E+00 2.47E-01 Teen.- 6.17E+01 0.00E+00 3.70E+00 0.00E+00 1.41 E+01 7.50E+00 3.23E+00 2.47E-01 Child 1.48E+02 0.00E+00 8.79E+00 0.00E+00 2.37E+01 6.73 E+00 2.53 E+00 2.47E-01 Infant - 1.12E+01 0.00E+00 8.63E-01 0.00E+00 2.33 E+00 5.09E+00 1.34E-01 2.47E 01 Dose factor airborne release pathway (mren'Ci released)

Np 239

. Bone Liver T. Body- - Thyroid - Kidney -Lungsc . GI-LLI . s Skin Adult 5.00E 4.92 E-06 5.54E-03 0.00E+00 1.53 E-05 4.47E 04 9.55E 01 9.52E-03 Teen- 8.79E-05 8.29E 06 5.55 E-03 0.00E+00 2.60E-05 7.71 E-04 1.27E+00 9.52E-03 Child 2.llE 04 1.52E 05 5.55E-03 0.00E+00 4.39E 05 6.91 E-04 1.10E+00 9.52E-03 Infant - 4.42E-06 3.95E-07 5.54E-03 0.00E+00 7.88E-07 7.07E-04 3.14 E-04 9.52E-03 Dose factor airborne release pathway (mrem /Ci released)

Am-24 I

Bone ;Liverj .T. Body _ PThyroid :- Kidney ' Lungs, . GI-LLI. . Skin Adult : 1.34 E+02 4.76E+01 1.03E+01 0.00E+00 6.70E+01 5.76E+00 3.48 E+00 2.94 E+00 Teen- 1.46E+02 5.59E+01 1. l l E+01 0.00E+00 7.31 E&01 9.99E+00 4.12E+ 00 2.94 E+00 Child ' l .37E+ 02 6.14E+01 1.llE+01 0.00E+00 5.98 E+01 8.8SE+00 3.22 c +00 2.94 E+00 Infant ' 3.07E+0 i 1.4tE+0i 3.56E+00 - 0.00E+00 1.32 E+0! 6.76E+00 2.58 E-02 2.94E+00 Page 63 of 120

NUCLEAR POWE ,.USINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 5.1.3 Atmospheric Release Mode: Noble Gases

- The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix 1 dose limits for noble gases released to the atmosphere will be done in the manner similar to the liquid release dose calculations described in Section 5.1.1. The total doses to the air, skin, and whole body resulting from the release of noble gases is compared to the corresponding Appendix limits.

Noble gases released in liquids are to be added to the atmospherically released noble gases for Appendix I dose compliance calculations.

Tlv: doses are calculated using the following formula:

API = E Doset; = I(TDF iix C )i $ K mrem i where API = the Appendix I dose for compliance evaluation in mrem Doset; = the dose to the applicable target (t) from radionuclide (i)

TDF;t = total dose factor from Table 5.1-3 in mrem /Ci for the specific target (t) from radionuclide (i) based on the maximum annual average x/Q at the site boundary Ci =

curies of radionuclide (i) released K = c.e noble gas Appendix I dose limit for target (t)

The methodology used to obtain the TDF values are given in Appendix C.

Instead of using the precalculated total dose factors, the Appendix I dose calculation may be modified to reflect actual x/Q values during the release using the methodology of Appendix C, Page 64 of 120

. NUCLEAR POWER BUSINESS UNIT. :ODCM OFFSITE DOSE CALCULATION MANUAL : Revision 11 DRAFT --

December 2,~ 1997 - .

OFFSITE DOSE CALCULATION MANUAL 2 .

4

=

1 TABLE 5.1-3 ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES -

(Highest Annual Averagex/Q) 1Nuclide_ ;.. Beta Air ; . Gamma Air ,

Skin .Whole Body

? '(mrad /Ci)L (mrad /Ci)" 1(mrem /Ci)4 1(m^r em/Ci)L

- AR-41 1.56E-04 4.42E-04 -2.94E-04 4.72E-04 KR-83M 1.37E-05 9.18E-07 2.52E-09 7.13E-07 KR-85M 9.37E-05 5.85E-05 - 3.89E-05 1.15 E-04 '

f 8.18E-07 5.36E-07 6.44E-05 '

KR 9.27E-05 KR-87 4.90E 2.93E-04 .1.97E-04 6.91E-04

' KR 1.39E-04 7.23E-04 4.89E-04 6.74E-04 KR-89. 5.04E 8.23E-04 5.53E-04 1.12E-03 KR-90 3.72E-04 7.75E-04 5.19E-04 9.49E-04 XE-131M - 5.28E-05 7.42E-06 3.05E-06 2.84E-05 XE-133M 7.04E-05 1.55E-05 8.35E 06 5.93E-05 XE-133 4.99E-05 1.68E-05 9.79E-06 2.76E-05 XE-135M 3.51E-05 1.60E-04 1.04E-04 1.58E-04 XE-135 1.17E-04 9.13 E-05 6.02E-05 1.59E-04 XE-137 6.04E 04 7.18E-05 4.73E-05 6.36E-04 XE-138 2.26E-04 4.38E-04 2.94E-04 5.37E-04 L

Page 65 of 120

-. , x.

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 6.0 R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirements for the PBNP environmental monitoring program are detailed in Technical l Specification 15.7.8.3. A complete description of the PBNP radiological environmental monitoring program, including procedures and responsibilities, is contained in the PBNP Environmental Manual. The latter is hereby incorporated into the Offsite Dose Calculation Manual (ODCM) by reference.

7.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE DISPOSAL The methodology for determining the radiological impact of contaminated sewage treatment sludge is presented in this section. The evaluation must be made prior to every land application of sewage treatment plant (Si P) sludge that contains licensed material. Sludge and other STP material which does net contain licensed rnaterials may be disposed of by any legal method without prior radiological analysis.

7.1 Basis. Commitments. and Actions 7.1.1 Basis With the discovery that the PBNP STP sludge contained licensed material, Wisconsin Electric applied for NRC approval to dispose of the sludge by land application on land within the PBNP site boundary pursuant to 10 CFR 20.302(a). Wisconsin Electric committed to gamma isotopic analysis (GI A) of the sludge to measure the concentrations oflicensed material in the STP sludge and to compare the results to concentration limits prior to each disposal [ letter dated October 8,1987 (VPNPD-87-430, NRC-87-104)]. In addition, the dose to the maximally exposed individual of tne general public and to the inadvertent intruder would be evaluated for the appropriate exposure pathways. ,

7.1.2 Basis for NRC Commitment Modification Pursuant to NRC guidance, the sludge is clean if no licensed materials are found when analyzed under conditions necessary to achieve the environmental LLDs (NRC HPPOS 221). Clean sludge is not under NRC jurisdiction and may be disposed of by any legal method without prior radioanalyses.

Therefore, if the sludge is clean and there is no pathway to the STP from the RCA, or pathways are administratively controlled to prevent the transfer of licensed materials to the STP, there is no need to analyze the sludge prior to any disposal.

Page 66 of 120 1

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE C ALCULATION MANUAL Revision 11 DRAFT OFFSITE DOSE CALCULATION MANUAL' Since the 1987 commitment, engineering modifications and administrative controls have eliminated the pathways from the RCA to the STP, Three subsequent sludge GI As (a total of eight STP samples) utilizing the analytical parameters required to achieve environmental lower limit of detection (LLD) found only naturally occurring radionuclides. In each analysis, the licensed matcrials were below the minimum detectable activity for thi particular measurement and below the required LLDs. These results verify the efficiency of the modifications and administrative controls in eliminating pathways from the RCA to the STP. Therefore, because there is no longer any reason to believe that the PBNP STP sewage contains licensed msterial and there are no pathways from the RCA to the STP, the sewage may be disposed of by any legal method without GIA prior to each disposal.

7.1.3 Modification Periodic gamma isotopic analyses (GIA) of the STP sludge shall occur at a frequency set forth in the Environmental Standing Orders (ES0). This may include analyses prior to disposal depending on the results from the periodic analyses. The GIA of tbc STP sludge shall meet the LLD criteria of normal liquid effluents. Th detection of any licensed material in the sludge during the periodi- GIA shall necessitate returning to the GIA prior to disposal in order to evaluate the radiological consequences of the disposal. The GIA prior to each disposal shall continue until such time that the sludge can be shown, using environmental LLD criteria, not to contain licensed material.

Also, re-initiation of the 1987 commitment to analyze the STP sludge prior to each disposal shall be required if plant conditions change in a manner which would lead one to believe that the STP sludge may be contaminated. An -

example of such a condition is the opening of valve STP-009 which is controlled by a danger tag. Again, reversion to an ESO controlled frequency can occur only upon verification that no licensed material is in the sludge pursuant to the environmental LLD criteria.

7.1.4 Exposure Evaluations If the sludge contains licensed material, the 1987 commitment requires that the appropriate exposure pathways be evaluated prior to each application of sludge to insure that the dose to the maximally exposed member of the general public is maintained at less than 1 mrem / year and that to the inadvertent c intruder, at less than 5 mrem / year. Also, the measured concentration shall be {

l compared to the liquid maximum effluent concentrations of Appendix B to 10 CFR 20.

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. OFFSITE DOSE CAL.CULATION MANUAL I f

'The exposure pathways evaluated for the maximally exposed individual are the .

l

- following-I

1. Extemal whole body exposure due to a ground plane source of radionuclides.-

2. Milk ingestion pathway from cows fed alfalfa grown on plot.

3. Meat ingestion pathway from cows fed alfalfa grown on plot.

i

! 4. Vegetable ingestion pathway from vegetables grown on plot.

5. Inhalation of radioactivity resuspended in air above plot,

6. Pathways associated with a release to Lake Michigan. These pathways are .

ingestion of potable water at the Two Livers, Wisconsin municipal water supply,-

ingestion of fish from edge ofinitial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water from Lake Michigan, ;

ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at the edge of the initial mixing zone, and shoreline deposits.

The exposure pathways evaluated for the inadvertent intruder are the same as items 1,4, 5, and 6 identified above for the maximally exposed individual.

7.2 Procedure -

The following steps are to be performed by the responsible Radiological Engineer for each contamihated sewage treatment sludge disposal:

7.2.1 Obtain from PBNP-Chemistry the radionuclide concentrations in each representative sewage treatment sludge sample. The minimum number of representative samples required is three from each sludge storage tank. The average of all statistically valid concentration determinations will be utilized in determining the sludge storage tank concentration values.

7.2.2 Ver:fy that the concentration of each radionuclide meets the concentration and activity limit criteria. The methodology for determining compliance with the concentration and activity li.mit criteria are contained in Appendix E.

' Page 68 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 7.2.3 Verify that the proposed disposal of the sewage treatment sludge will maintain doses within the applicable limits. This calculation will include radionuclides disposed ofin previous sludge applications. The activity from these prior disposals will be corrected for radiological decay prior to performing dose calculations for the meat, milk, and vegetable ingestion pathways, the inhalation of resuspended radionuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrated, if applicable, for the mixing of radionuclides in the soil prior to performing extemal exposure calculations.

Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perform shielding and dose rate analyses. QAD will be used to calculate the dose rate due to standing on a plot ofland utilized for sludge disposal in which the radionuclides from prior disposals have been incorporated into the plot by plowing. This calculated dose rate will be used to assess the radiological consequences from prior disposals with the consequences of proposed future disposals. The total radiological dose consequence of the past and the proposed disposal will be compared to the applicable limits to insure the dose is maintained at or below the limits.

The methodology for calculating the radiological impact of the sewage treatment sludge disposal is contained in Appendix E.

7.2.4 Inform PBNP - Chemistry that the sewage treatment sludge disposal may proceed after verifying that the sewage treatment sludge meets the concentration, activity, and dose limits.

7.2.5 Forward all calculations to PBNP - Chemistry to be included with the sewage-treatment sludge disposal record.

7.3 Administrative Reauirements 7.3.1 Complete records of each contaminated disposal shall be kept as follows:

a. Radionuclide concentration of the sludge.

b. Total volume of sludge disposed.

c. The identity of the plot used for the disposal.

d. Dose calculation results.

e. Results of annual chemical composition detemiination.

Page 69 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 7.3.2 Modifications to the October 8,1987, NRC submittal

a. Modification 1 - Appendix F Section 3.2 of Attachment II of the submittal states that physical and chemical properties of the sludge would be determined prior the each land application. Pursuant to a change in the PBNP WPDES Permit, non radiological properties are now determined annually instead of per applicativa. The frequency for radiological characterization did not change.

b. Moditication 2 - Appendix G In Section 3.3 of Attachment II of the submittal letter, the annual disposal rate was "... limited to 4,000 gallons / acre, provided WDNR chemical composition, NRC dose guidelines and activity limits are maintained...."

Modification 2 removes the 4,000 gallon limit and makes the application unlimited provided the WDNR and NRC constraints are met,

c. Modification 3 - Appendix H In Section 3.2 of Attachment II of NRC submittal letter dated October 8,1987, Wisconsin Electric committed to gamma isotopic analysis (GIA) to determine the concentration oflicensed material in sewage treatment plant (STP) sludge prior to each disposal. Pursuant to NRC HPPOS-221 guidance, the sludge has been shown to be clean on three different occasions after pathways from the RCA to the STP were eliminated by plant modifications and administrative controls. Pursuant to HPPOS, the sludge analyses were done under the conditions necessary to achieve the environmental LLDs. Only naturally occurring radionuclides were found and licensed material was below the minimum detectable concentration. This indicates that the former pathways from the RCA to the STP had been eliminated. Therefore, there is not need to continue the analyses because there is no RCA to STP pathway and there is no reason to believe that the sewage contains licensed material. Hence, the commitment to analyze STP sludge prior to every disposal is modified and replaced with periodic analyses at a frequency set by ESO-104. However, if plant conditions change in a manner which places tne STP sewage outside the guidance parameters which allowed for the discontinuance of analyses, the sewage must be analyzed prior to each disposal until it again is shown not to contain licensed material.

Page 70 of 120

NUCLEAR POWER BUSINESS UNIT ODCtJ OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,-1997 OFFSITE DOSE CALCULATION MANUAL l i:

-l APPENDIX A DERIVATION OF LIQUID RELEASE PATHWAY EFFEC'.IVE MAXIMUM EFFLUENT CONCENTRATION Page 71 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL A.I.0 Derivation of Liauid Release Effective Maximum Efnuent Concentration A.l.1 Source Tem 1 The effective maximum ef0uent concentration is calculated from the annual releases via liquids for the years 1985-1991 (Table A-1). Although Na-24 was discharged in 1985, it was excluded from the isotopic mixture because it is not a radionuclide which would be normally found in PBNP effluent. Na 24 appears in the efnuent because it was used for tests run on the steam system.

Tritium also was omitted from the initial calculation because its production is largely independent from the appearance of the fission products in the ef0uent.

A.I.2 Effective Maximum Efnuent Concentration The effective maximum effluent concentration (EMEC) was calculated using the formula given in Section 3.6 EMEC =

IC i / I(C /MEC)i or IC *i 1/COF where:

SOF = I C /MEC isi the summation of fractions for the annual efnuent isotopic release C i ,= concentration of radionuclide "i" (pCi/ml) in efnuent (annual discharge / total volume of discharge)

MECi

= maximum effluent concentration for unn stricted areas from Appendix B, Table 2, Column 2 of the revised 10 CFR 20.

The SOF for radionuclides in liquid effluent for the years 1985 through 1991 were calculated with and without H-3 and used to calculate the EMEC for the same years (Table B-2). The average EMEC without H-3 is 4.29E-06 pCi/cc.

This is the maximum concentration of non H-3 radionuclides in a mixture that could be released in liquid efnue it without the SOF exceeding one (1).

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OFFSITE DOSE CALCULATION MANUAL- Revision 11 DRAFT .

- December 2,1997; ;

t OFFSITE DOSE CALCULATION MANUAL'-

However, the 10 CFR 20 Appendix B criterion is'that the SOF for all 1

radionuclides, including H 3 which can not be measured bp the liquid effluent- 1 Nal RMS monitors, be less than or equal to one (1). Therefore, the above .

equation, modified by a factor of 0.70 to account for H 3, becomes .

7

- EMEC. = 0.70 ICi / I(C /MEC;) i or IC *i 0.70/SOF.

The EMEC becomes EMEC- -=- 0.70

4.29E-05. = 3.00E-06 pCi/cc.

LOnly three radionuclides identified in PBNP liquid effluent have a lower MEC

_ (10 CFR 20,- Appendix B, Table 2). They are I-131 (1E-06), Cs-134 (9E-07),

and Cs-137 (IE 06).

By restricting the non-tritium radionuclides to 70% of their calculated EMEC, .

the H 3 concentration can be discharged at 30% ofits MEC or -

3.00E-04 pCi/cc without exceeding the SOF criterion of 10 CFR 20, Appendix B for the total liquid effluent isotopic mixture, 1

4

~

{.

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_ -. _. . - _ , . . ~ - . _ . ~ . . . _ . ._ _ - . _ . . _ - _._ -. . -

NUCLEAR POWER BUSINESS UNIT ODCM i l

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT l December 2,1997 -

OFFSITE DOSE CALCULATION MANUAL - . .

TABl.E A l CURIES RELEASED IN LlOUIDS ElQUID RELEASES .

NUCLIDE . : MEC = .-1985 1986 1987. 1988. -1989 . 1990 -- .1991 uCi/cc -

11 3 l 00E 03 8O!E+02 8.11E+02 7.09E+02 3.57E+02 5.59E+02 8 72E+02 7.87 E+02 ;

l 131 1.00E 06 1.02E-01 3.74L 02 104E 02 1.40E 03 1.77E 03 1.53 E-N 1.83E 03 1 132 - 1.00E-04 615E-02 7.25E-02 5 82E 02 1.03E 03 8.15E 04 4 45E 0$ 9 4tE 03 7.00E-06 1.27E 01 1.49E 01 1.04E 01 1.2 t E-02 8. l l E-03 3.01E 03 1.01E 02 1-133 i !!4 4.00E44 318E 439E 02 3 97E-02 2.29E-04 6.83E 04 1 135 3 00E-05 1.04E Ol IJ4E 01 1.23E-Oi 4.48E-04 8.2 t E 04 AG-il0M 6.00E 06 2.55E 05 2.84E 04 3 09E-03 9.85E 04 4.70E44 1.71E 04 4.06E 04 BA 133 2.00E 05 BA 139 2 00E-04 8 63E-06 2.4 7 E-04 HA 140 8 00E-06 6.90E 06 4.45E 05 6.13E 05 CD-109 6.00E 06 6JJ E-05 4 3tE 04 CE 139 7.00E-05

< CE141 3 00E-05 131E 03 7 50E 04 IJ7E-03 2 08E 03 4.76E 04 1.59E 04 9.47E-06 9.64E 06 CE 144 3.00E 06 CO-56 6 00E 06 CO-57 6 00E 05 2.52E 03 133E 04 3.2iE 04 5.07E-05 6.90E 07 4.08E 06 CO 58 2.?)E-05 4 0$E 01 9 02E 03 JJ6E-02 6.81 E-03 3.12E 03 3.25E 04 2.93E 03 C0-60 3 00E 06 2.88E 01 2.85E 02 6J4E 02 2.04E 02 1.54 E-02 1.4 t E 03 5.53E 03 3 CR SI 5 00E 04 2.7 t E-02 316E 04 1.58E 02 5.31E 4.44E-04 8.71E 05 CS-134 9 00E 07 4.76E-02 6,92E 03 1.48E 03 4.96F 04 1.49E 03 CS 134M 2.00E-03 3.59E 04 $.97E 06 4 67E-04 t %136, 6 00E 06 1.00E-06 9 60E 02 2.llE 02 7.54 E-03 8 63E-03 180E-03 1.94E 03 8.93E 03 CS 137 4 CS 138 4 00E 04 4.llE 03 5,48E 03 3.24E 03 F-18 7.00E 04 100E-02 l.67E 02 7.56E 04 1.66E 03 2.26E 03 4.06E-04 IE 59 I.00E 05 2.76E-04 EA 640 9.00E 06 MN-54 3 00E-05 7.46E 03 1.18E-03 4 65E 03 1.54E 04 2.68E-04 3.10E-05 1.96E N M0-99 2.00E 05 3.70E-05 NH-95 3 00E-05 6 28E-03 A65E-04 3.21 E-03 1.61E 04 233E 06 8.68E 05 N D-97 3.00E 04 1J5E 03 5.22E 04 6.16E-05 1.06E-05 3.90E 06 8.40E 06 5J0E 06 RB 88 4 00E 04 8.46E-05 1.llE 02 JJ3E 03 RD 89- 9 00E-04 7.98E M 2J4E M J- RU103 3.00E 05 3.59E43 1.68E 06 8.4 t E 04 5.86E-05 RU-lon 3 00E-06 8 07E 04 2.88E-03 7J3E-03 1.04E M SB-124 7 00E 06 3 86E 02 2.96E 04 1.42E 04 2.34E 04 SB-125 3.00E 05 1.12E 02 1.20E-03 4.95E 03 1.00E 03 2.12E 02 1.28E 05 1.C8E 02 SN ll3 3.00E 05 1.07E-03 4 20F 05 5.13E 04 3.2iE M 3.07E 06

- SR 89 8.00E-06 2.27E 04 3.46E 05 3 89E 03 2.68E-03 8 69E 06 SR 90 5.00E 07 1.29E-03 2.28E 04 - 2.80E 04 3.50E M 2.55E 04 1C-99M 1.00E-03 1.75E 05 - 3.75E 06 330E-05 1C-101 2.00E 03 1.10E 05 11'-134 8.00E-05 7.98E 05 TE 132 9.00E-06 $.83E 07 6.94E-05 2.74E-05 7.19 E-06 1.74E N bl87 3.00E 05 3.4 t E-05 Y-9iM 2.00E-03

} $ 15E-05 ZN-65 5.00E-06 4R 2.00E 05 7.95E 05 - 2.61E44 2.45E 03 1.58E-05 4

^

iR 97 9 00E 06 1.49E 06 3 0vE-06 1.74 E-05 TOTAL CI 40eE+02 812E+02 7.10E *02 3.57E+02 5.59E+02 8.72E+02 7.8 7 E+02 TOTAL W/O H-3 137E+00 539E 01 512 E-O L $ 99E 02 5 65E-02 9 57E 03 5 42E-02 Page 74 Of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL TABLE A 2 FRACTIONAL MEC IN LIQUID EFFLUENT NUCLIDE MLC 1985 1986 1987 1988 1989- 1990 -1991 uCi/cc :

H-3 100E-03 1.27E43 1.2 S E-03 1.04L 03 S.17E 04 M6E 04 1.26E 03 1.22E 03 1 131 1.00E 06 8 61E 04 5.75E 0$ l.52E 05 2.03E 06 2.6$E 06 2.21E47 2.84E 06 l 132 1 00E 04 9.70E 07 1.12E 06 8 $3E-07 1.49E-08 1.22E 08 6.43E 10 146E 07 l 133 7 00E-06 2.86E 0$ 3.27E 0$ 2.18E 05 2.$lE 06 1.73E 06 6.21E 07 2.24E 06 1 134 4 00E 04 I.2SE 07 1.69E 07 4.46E-07 8J0E 10 2 65E 09 l 13$ 3 00E-0$ 5.47E 06 6 87E 06 6.Olt 06 2.16E 08 424E 08 AO il0NI 6 00E46 6.70E 09 7.28 E-08 7.$$E-07 2.38E 07 1.17E 07 4.12E 08 t=0$E 07 BA 133 2.00E 05 UA 139 2.00E-04 6 33E Il 1.79E-09 UA 140 8 00E 06 IJ6E 09 0 00L+00 8.16E 09 1.llE 08 CD-109 6.00E 06 1 62E 08 3.16E 08 ]

CE 139 7.00E 0$

CE-141 3 00E 0$ 6 89E 08 3 67E 08 CE-144 3 00E-06 7.03 E-07 1.02E 06 2.30E 07 7.92E 08 4.56E 09 4 98E-09 CO-56 6 00E 06 C0-57 6.00E-0$ 6 62E 08 3 4 t E 09 7.84E 09 1.22E 09 1.72E Il 9.83E Il 3.19E-0$ 6 94E-07 2.46E 06 4.93E 07 2.33E-07 2 35E 08 2,27E 07 0 0-$8 2.00E 05 CO-60 3.00E 06 1.$1E 04 1.46E 05 3.l0E 0$ 9 86E 06 7 67E416 6.79E 07 2.86E 06 CR-$ 1 500E-N 8 $$E 08 9 72E 10 4.63E-08 1.54E 10 1.33E 09 2.52E 10 CS-134 9 00E 07 8 34E 0$ 1.18E 0$ 1.92 E .06 ~T99E 07 2.$7E 06 CS-134Nt 2 00E 03 2 60E 10 4.46E 12 3 62E 10 CS 136 6 00E 06 C3137 1.00E-On I.$1E-04 3.23E 0$ l. l l E -0S 1.2SE 05 4.19E 06 2.80E 06 1.38E43 CS-138 4 00E 04 4J8E 09 2.llE 08 1.19E-08 F 18 7 00E 04 2.20E 08 3 $0E 08 1.5 7E 09 3 $4E 09 4.67E 09 8.99E 10 iE-39 100E 05 4 0$E-08 LA 140 9 00E 06 MN434 3.00E-05 3 92E 07 6 0$E 08 2 29E 07 7.44E 09 IJ4E 08 1.49EO 101E 08 M0 99 2.00E-05 2.68E-09 Nil 95 3.00E 0$ 330E 07 3 4 t E 08 1.5 7 E-0 7 7.78E 09 1.16E 10 4.18E 09 N1597 3.00E M 7.10E 09 2 68E-09 101E 10 3.12E Il 1.94E il 4.24E il 2.74E ll RB 88 4 00E 04 3 34E 10 4.27 E-08 1.22E-08 RB-89 9 00E 04 136E-09 3 81E 10 RU 103 3 00E 05 1.89E 07 8 62E LI 4.1lE 08 2.83E 09 RU 106 100E 06 4 24E 07 1.48 E-06 3 $8E 06 5.02E 08 SD-124 7.00E 06 8.70E 06 6.5 t E 05 2.97E-08 4.84E 08 SD 125 3 00E 03 $ 89E 07 6.1$E 08 9.33E 08 4.83 E-08 1.06E 06 6.17E 10 3.58E 07 SN-il) 3.00E 0$ $ 63E Da 2.15 E-09 2.5 t E 08 1.$$E 08 1.59E 10 SR 89 8 00E-06 4 48E 08 6.65E 09 7.13E 07 4 86E 07 1.62E 09 S R-90 $ 00E 07 4 07E 06 7.02E 07 8.2 t E-07 1.0!L 06 7.62E 07 IC-99NI l.00E 03 2.76E-Il 5 77E-12 4.78E ll IC 101 2 00E 03 8 06E 12 T E-13 I 8.00E-05 1.45E 09 TEl32 9.00E 06 1.02E-10 1. l9E e* 4.46E 09 1.16E 09 100E-08

% 187 100E 05 1.6$E 09 Y 91M 2.00E 03 LN 6$ $.00E46 1.5 L E-08 ZR 93 2.00E-05 627E 09 2.0lE-08 1.50E-07 1.14E 09 ZR 97 9 00E.Oe 2.6 t h 10 $.28E-10 2 80E 09 Page 75 of 120

l NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT ;

~

December 2,1997 OFFS 11E DOSE CALCULATION MANUAL TABLE A 2,(cont )

FRACTIONAL MEC IN LIQUID EFFLUENT i 1985 1986 1987 1988 1989 1990 1998.

ANNUAL VOLICCs) 6 34E+ 44 6 50E+14 6 82E+l4 6 90L+ 14 6 6vl+14 6 92E+ 14 6 45E*l4

'lO T F RAC'llON l 90E 03 141E 03 1.14f: 03 5 48E 04 8 54E 04 1.26E-03 12$ E-03 f RACI W/0 fi 3 6 29E 04 16lE 04 9 83E 05 3 04E 05 8.85E-0$ 4 41E-06 2.35E45 IOI AL Cl 8 06E+02 812E+02 7.10E+02 3.5 7 E+02 559E+02 8 72E+02 7 87E+02

'lOTAL %/0 t13 1.37E+00 539E-Oi 5.12E-01 5.99E-02 5 65E-02 9 57E 03 $ 42E42 101 CONC (uCvCCl 1.27E v6 1.2 $ E-06 1.04E 06 5.17E-07 8.36E-07 1.26E-06 1.22 E46 l

' ICON W/O . i > 2,16E-09 8 30E-10 7.5lE 10 8 69E Il 8 44E ll 1.38E Il 8.40E.ll l.

EMIC 6 70E 04 8 86E-04 914E 04 9 45E 04 9 78E 04 9 97E-04 9 8U044 l EMEC W/O ti 3 3 43E 06 514E 06 7.64 E-06 2.83E 06 4 $6E 06 3.14 E-06 3.30E 06 l Page 76 of 120

NUCLEAR POWER BUSINESS UNIF ~

oODCM I OFFSITE DOSE CALCULATION MANUAL . Revision 11 DRAFTL- ,

December 2,199_7 - ,

OFFSITE DOSE CALCULATION MANUAL- j

l

-)

I c) 6

-APPENDIX B c ,

?

a DERIVATION OF ATMOSPHERIC RELEASE MODE -

EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION t

b t

/-- - _

r r.

L Page 77 of120 -

_s . . _. , .-.; . . , - - . , _ . _ . = . - . . . - .'

NUCLEAR POWER BUSFNESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL _-

B.1.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration Bl .1 Source Term The effective maximum effluent concentration (EMEC) for atmosphecie ernuents is calculated from the annual releases for the years 1985 1991 (Table B-1). Unlike liquid releases, tritium was not omitted from the EMEC calculation. Instead, the EMEC was calculated with H 3 and then modified by the fraction of non-tritium radionuclides in the efnuent.

Bl.2 Effective Maximum Effluent Concentration The maximum concentration of a radionuclide mixture that is allowable at the site boundary is called the effective maximum efnuent concentratior. (EMEC).

The EMEC for an ef0uent mir.ture is defined by the equation EMEC = IC; / I(C i/ MEC i) where Ci

= concentration of radionuclide "i" MFC i = maximum effluent ;oncentration for radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column i I(C i/ MEC i) = sum,mation of fractions (SOF), as discussed in Section 3.6, applied to atmospheric releases The EMEC is calculated from the reference radionuclide mixture which is the radionuclides released during the years 1985 - 1991. The average annual site boundary conce;" ration for each year was calculated using the highest annual 3

average x/Q of 1.56E-06 sec/m . Then the total EMEC was calculated for each year (Table C-2). The average total EMEC is 8.04E-08 1.31E-08 Ci/cc with a range of 5.84E-08 to 9.50E-08 pCi/cc. Next, the annual EMEC was modified for the presence of H-3, which is not detected by the atmospheric RMS, by multiplying each EMEC by the ratio of the non H-3 concentration to the total concentration. The annual H-3 corrected EMECs were averaged to obtain a value of 1.92E-08 1.23E-08 pCi/cc with a range of 5.02E-09 to 3.70E-08 Ci/cc.

Page 78 of 120

. NUCLEAR POWER BUSINESS UNIT. ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL TADLE D-i CURIES IN ATMOSPliERIC EFFLUENT

' NUCEIDE MEC 1985_ 1986 .1987 l988 1989 1990 1991 uCi/mi 11 3 100E-07 6 71L+01 1.20E+02 1.18E+02 1.26E +02 142E+02 1.28E+02 1.13 E+ 02 AR41 1.00L*08 1.27E+00 6 81E 01 2.17E+00 1.96E+00 1.57E+00 1.IIE+00 1.07 E +00 KR 85M l.00E 07 l84E+01 6 77E 01 1.18L+00 7JtE-01 2 24E-01 4.85 E-01 1.03E 01 LR-85 7.00E 07 1.67E+01 IJ2L+00 7. ll E-01 9 84E-0 4 3.580 01 1.78 E-01 2.74 E-01 AR 87 2,00E 08 4.78E+00 1.01E+00 237E+00 1.48E+00 4 94E 01 4 0$E 01 2J1E 01 130E+00 2.72E+00 169E+00 5 64E Ol 4 49E-01 2,56E 01 LR 88 9 00E 09 3.73 E + 00 AE 13tM 2.00E 06 8 $4E-02 AL 133M 6 00L-07 JJOE On IJ 8E-01 2.12E-01 335E-On 4 94E-03 2.0eE-02 3.97E 02 AL 133 $ 00E-07 3.45L+0! 1.53 E+01 2.0t,E +0! 6 04L+01 7.$4E+00 1.96E+00 160E+0!

XE 135M 4.00E 08 S.76E+00 1.270+00 3 68L+00 2.54E+00 7J7E 01 6 49E-01 3 44E-01 XE 1)$ 7 00E 08 1.19E+01 3 21L+00 564E+00 3.53 E+00 108E+00 109E+00 6.0)E 01 AL 138 2 00E 08 1.65E+0L 2 91E+00 8 87E+00 7.19 E+00 2 45E+00 199E+00 1.06E+00 _

i.0-l 10M l.00f>10 2)lE 07 flA 133 9 00E 10 BA 139 4.00E 08 t.17E 07 IIA 140 2.00E 09 3 41E 07 CD-109 2 00E-10 8 92L-06 1.26E-00 2.28E 04 CE 139 9 00E 10 CE 141 8 00E 10 8 48L 09 CE 144 2 00E-11 2 WE 06 3.92E 07 3.94E 09 2.52E*il 4.13E 08 1.23E-06 4 80E 07 i C0-57 9.00E-10 2.10E 07 CO-58 100E 09 1.5)E 04 1330 05 1. ole-04 3.39E-0$ 169E 04 2.745-05 3.8 Alo 0 0-60 5 00E Il 7.94E 0$ l llE 04 1.18E 0$ 3 64E 04 163E 04 3 $6E Oo 1.06 E-04 CR 51 3.00E 08 5.28E 04 7.58E 09 CS 134 2.00E-10 1.18E 03 9 49E 04 5 soE-05 7.27E 05 1.10E 03 CS 136 9 00E 10 CS 137 2.00E-10 4 02E 03 2.94E 04 3 08E 04 6 74E 04 2.10E-03 19lE 04 4.90E 03 C5-138 8 00E-08 9 64L 07 l.92E 00 1.85E 03 t .26E-07 3 44E-06 1.92E-02 F 18 100E 07 1.08E 03 2.52E-04 3 87E-05 JJ1E 04 1.10E 05 6 60E-04 FE+$9 7.00E 10 4 87E 09 l

MN 54 1.00E 09 1.99E Oo 1.70:1-06 4.SoE 03 MO-99 2 00E-09 7.27E 09 2.71 E-08 NA 24 7 00E 09 1.39E-04 4J2E-04 4.29E-04 Nil 95 2 00E 09 2 32E-06 7.70E-07 $.97E 07 6.2$E-08 9.SoE 10 ND-97 1.00E 07 1.60E 08 _ l.65E 09 RD 88 9.00E 08 4 63E-05 3 46E 0$ l.03E 02 4.00E-06 _ 1.81E 05 1.62E-01 RB-89 2.00F 07 4.30E@

RU 103 9.00E 10 1.91E 08 1.89E-05 SU 125 7.00E iJ 1.25E 07 3.68E 06 939E 08 5N il) 8.00E 10 2.16E 08 4 80E-10 SR 89 2.00E 10 4 87E 08 1.54E Oo 7 70E-07 3.71E 06 SR 90 6 00E 12 1.68E 10 430E 06 SWI 5.00E 09 IC99h 3 00E 07 6 43E 03 2.20E 07 9.24 E-07 TC-101 5.00E 07 l'E 132 9.00E 10 3 07E-Oo 733E-08 2 34E-06 Y 88 - 3 00E 10 1.23E 10

/N 63 4 00E 10 9.27E Oo ZR 95 4.00E-10 IJ1E-00 3.56E-09 7.4)E 10 ZR 97 2.00E 09 . 2.9 '% t o l-Page 79 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL TABLE D 1,(cont )

CURIES IN ATMOSPHERIC EFFLUENT

.1989 .YO 1991 NOC' b

~

MEC 195$ 1986 1987 1988 j uCi/ml 3 44E43 l.llE 03 3 05E 03 $ 43E-04 3.18E44 7.8 $ E-0$ 3 46E 04 1 131 2 00E lb 1 132 2%E08 3 7$E 03 1.79E 03 2 42E 03 4 78E-04 4 20E-0$ l.090-05 2.95E 0$

1.0Cm r9 8.37E-03 6 80E44 3 04E 0) 1.53E 03 1.tvE-03 1.13E-04 1.13E 04 l 133 1-134 6 00E 08 i 33E 0$ 9 32E44 126E 05 315 E-08 1.$$E 0$

1-135 6.000 09 5.7vE 04 I WE-04 2.lvE-03 3 916E 05 I

Page 80 of 120 l

. NUCLEAR POWER BUSINESS UNIT- -ODCM

OFFSITE DOSE CALCULATION MANUAL) Revision 11 DRAFT December 2,1997 e

OFFSITE DOSE CALCULATION MANUAL L TABLE B 2 -

Fractional MEC for Atmospheric Efiluent -

S 1986 1987 1988 1989 1990- 1991 NUCl>lDE

$.38E 05 11 3 ))1983 20E43 $.71E 0$ $.62E-0$ 6.00E 0$ 6.76E-05 6.10E 03 A R-4 l - 6.0$E 06 3 24E 06 1.03E 03 9.33Ed 7.48E 06 $.2 4 06 5.10E 06 AR 83M 8 7bE-06 3220 07 $.621407 3 48E 1.07E 07 8 81E 08 4.90E 08 KR 85 1.14E 06 8 98E48 4.84E 08 6.69E-08 2.44E-08 1.2 t E 08 1.86E 08 KR 87 1.14E 0$ 2.40E 06 $ 64E-06 3.$2E 06 1.18E-06 9.64E 07 $.50E 07 KR 88 3.03E 0$ 6.88E 06 1.44E-0$ 8 94E 06 2.98E 06 238E 06 IJ$E 06 XE-13 t M 2 03E 09 -

XE 133M 2.62E 08 l.10E48 1.68E 08 2.66E 08 3.92E 10 1.63E 09 3.1$E43 XE13) 3.29E 06 1.46E 06 - 1.96E 06 $ ,3E 06 7.18E 07 1.87E 1.32E 06 4 38E-06 3 02E 06 8 77E 07 7,73E 07- 4.10E 07 XE 133M 6 86E46 1.5 t E 06 .

XE133 8.10E-Oo 2.18E Os 3.84E 06 2.40E-06 7.35E 07 7.41 E-07 4.10E 07 XE 138 3,93E 0$ 6 93ts 06 2.!!E 05 1.71E 0$ $ 83E 06 4 74E 06 , 2.52E46 AG110M 1.10E 10 tiA 139 IJ9E 13 ilA 140 8.12E 12 CD-109 2.12E-09 100E 10 $.43E 08 CE141 $ 0$E 13 CE-144 4 86E 09 9.33E l0 938E 12 IJ3E 13 6.5 t E I l 2,$4E fl CO-57 1.IIE Il $.98E 13 CO 58 7.48 E-09 6J3E lo 4 81E 09 1.7 t E 09 8 0$E 09 130E-09 1.83E l0 Co-60 7.36E 08 l .06E-07 1.12E 08 3 47E-07 1.$$E 07 3 39E 09 1.01E 07 C R-$ 1 838E 10 1.20E 14 CS-134 2.81E 07 2.26E 07 1.40E 08 1.73E 08 2.62E 07 -

CS-136 CS-137 9.57E 07 7.00E 08 7.33E 08 1.60E 07 $ 00E 07 4.S$E 08 4.52E 07 CS-138 $.74E 13 1. l4E-12 1.10E 09 7.50E 14 2.0$E 12 1.14E 08 F 18 $.14E 12 1.20E 10 1.84E Il 1.58E-10 $.24E-12 3.14E 10 IE 59 3JIE 13 MN34 9.48E Il 810E Il 231E 09 MO-99 1.73E 13 6.43E 13 NA 24 9 46E 10 2.94 E-09 2.92E 09 s ND 95 6 00E ll 1.83 E-I l 1.42E Il 1.49E 12 228E14 NB-97 7.62E l$ 7.86E 16 R11-88 2.45E ll . 83E-Il 3.43E 09 2.12E 12 9.58:1-12 8.$7E 08

~

RB-89 1.02E 15 RU-103 -. 1.0lE 12 1.00E 09 SB 12$ 8.50E 12 2.$0E-10 6.39E 12 SN il) 1.29E 12 1.86E l4

$R 89 - I 16E Il 3 67E lo 1.83E-10 8 83E-10 SR 90 IJ3El2 3 41E 08 SR 91 TC-99M l.02E 14 3.49E-14 1.4 7E-13 tc ioi

. . _ IE 632 l.62E 10 3.88E 12 1.24E lu Y 88 - 2.03E 14 4N 63 1.10E-09 ZR 93 1.56E-10 4.24E-13 8 83E-14 l ZR-97 7.07E 13 Page 81 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL - Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL TABLE 112.(cont )

FRACTIONAL MEC FOR ATMOSPilERIC LFFLUENT NUCLlDE 1985 1986 1987 1988 1989 1990 1991 1 131 819E 07 2 64E 07 733E47 1.29E47 7.57E 08 1.87E 08 8.24E-08 1-132 8 93E 09 4.26E 09 $ 76E 09 1.14E 09 1.00E-10 2.60E-I l 7.02E Il 1 13) 6.32E 08 3 24E 08 1.45L 07 7.29E 08 5.67E*18 5.38E 09 $.35E 09 l-134 106E Il 7 40E 10 1 1)$ 4.60E-09 8 6$E 10 1.74E48 7.29E 10 1.00E.O 2.50E 13 1.25E-10

'lul Ali RAC 1.4VE 04 8.29E 05 1.20E 04 1.11L 04 8.83E 05 7 62E-05 6 67E 0$

IOFAE fl3 1.17E 04 2.5 7 E-05 634E0$ $ 13E 03 2 07E-05 1.52E 05 1.29E-03

$ 84E 08 8.49E-08 6 62E 08 8 83E-08 8 46E 08 8.30E 08 9 50E 08 l elf MEC 3 70t.08 i bOE.08 i m.08 3.46t.08 8 ice 09 3 02t.09 uu3 i mo li.3 t

Page 82 of 120

. -... . ... . . - ~ . . ~ - , . . . .- . . . . - . _...__.-.-

NUCLEAR POWER BUSINESS UNIT; .ODCM< :

f0FFSITE DOSE CALCULAT10N MANUAO

. Revision iI DRAFT ( ,. j

. December 2,1997 ! '

~

OFFSITE DOSE CALCULATION MANUAL [

J N i

O e

i u 5 t

.Y

^

. APPENDIX C CALCULATION OF TOTAL DOSE FACTORS ->

USING -

REGULATORY GUIDE 'l.109, REV.1 :

f i

.~_

a x -

w e

a

.'Page 83 of.120

. ~a - .. . . __

i NUCLEAR POWER BUSINESS UNIT ODCM !

0FFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT -l

" December 2,1997 0FCSITE DONE CALCULATION MANUAL I

> C,1.0 CMeulation of Total Dose Factors Usine Revidgory Guide 1.109 Methodolocy C.l 1 Lkuid Release Dose Fnctog The equations and values used to calculate the total dose to th, ximum .

I cxposed individual for each of the liquid release mode pathways evaluated according to Regulatory Guide 1.109, Rev.1,1977 mebdology is shown below. The total dose factor in mrem /Ci released is the sum of all pathway doses in mrem /Ci for the following pathways: milk, meat, fish, potable water, :

and shoreline deposits. The results for an organ is summed for each pathway ,

and the total presented by age group and target organ in a matrix format for cach radionuclide in Section 5. Table 5.1.1. The deri,ation of dilution factors used in the calculations is presented in Appendix D. The highest dose in each !

niatrix is used as the dose tracking factor to be used for the monthly tracking !

of release doses. These values are found in Sectioit 5. Table 5.2. i C l .l .1 Aauatic Foods The dose from the eating of fresh fish caught at the edge of the initial 3 mixing zone was calculated using the equation:

= 1100 P "P 4'4 Dose.g Qi ;pB D ,;p,e where:

Dose,p) = the dose to the organj of an individual of age group

- a from all of the nuclides i in pathway p,in mrem / year; i

l100 = a factor to convert from Ci sec/yr f[ to pCi/ liter; [

Mp = the mixing ratio (reciprocal of the dilution factor) at the point of han*est of aquatic food, dimensionless; ,

U,p = a usage factor that spechies the intake rate for an iodividual of age group a associated with ; ,

pathway p,in kglycar; F = the flow rate of the liquid effluent, in ff/see; ;

Page 84 of 120

-- _ -~ - . . . _ .., .. _ _ . _ _ . - __

NUCLEAR POWER HUSINESS UNIT ODChi OFFSITE DOSE CALCULATION hlANUAL Revision 11 DRAFT i December 2.1997 i OFFSITE DOSE CALCULATION h1ANUAL Qi

= the release rate of nuclide i, in Ci/ year; !

B ip = the equilibrium bioaccumulation factor for nuclide 1 l 19 pathway p, expressed as the ratio of the j concentration in biota (in pCl/kg) to the radionuclide concentration in water (in pCL/l), in liters /kg; 4

D,ip) = the dose fauor, specific to a given age group a, r nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a 1

nuclide,in mrent'pCl;

= the radioactive decay constant c 'nuclide i, in day ^ t Ai l t

the average transk time required for nuclides to 4

tp =

reach the point of exposure. For intemal dose, pt is l the total time elapsed between release of the nuclides and the inges bn of the water,in days.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseo,i , g;g ht, U., .g

- Q, I-The values used in the equation above are:

hi p =

0.1136 (Point of harvest of the fresh fish is taken at a ;

point 1000 m downstream. The plume centerline dilution factor at this location is 8.8 using RO 1.111 methodology. The dilution factor calculations are attached. The factor ofhilowed for current reversals was not used.); ,

U,p = Infant - 0, Child - 6.9, Teen - 16, and Adult - 21 kglyear;' ,

3 F = 1507 ft /sec. (677000 gpm);

B;p

= Values used are taken from Table A 1 of RO 1.109; .

Page 85 of 120

. . . _ _ _ . - . - , _ . . _ _ _ _ _ _ . _ __ _ m._ _ _

NUCLEAR POWER llUSINESS UNIT ODChi [

OFFSITE DOSE CALCULATION h1ANUAL Revision l a DRAFT !'

December 2,1997 OFFSITE DOSE CALCULATION h1ANUAL j

+

Dgg = Values used are taken from Tables E 11 through E 14 of RO 1.109; j i

tp = 0.5 days.

l C1.1.2 Irricated Foods (hteatfrom Watered Cattle) [

2 The dose from the ingestion of meat from cattle whlen have been given contaminated water was calculated using the equation:

i hip Q Dose.,, = 1100 Q F D.wc "

l .f ^*

where:

i Dosen g = the dose to the organj of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; .

1100 = factor to convert from Cl.sec/yr ft' to pCi/ liter; i

U,p = a usage factor that specifies the intake rate for an ;

individual of age group a associated with pathway p, in kg/ year; Mp = the' mixing ratio (reciprocal of the dilution factor) at the l point of exposure, dimensionless;

' ~

Q3w

= consumption rate of contamina.ed water by an animal, in liters / day; P = the flow rate of the liquid effluent,in ft'/sec; Qi

= the release rate of nuclide 1, in Ci/ year;

= the stable element transfer coefficient that relates the Fig

? daily ini ... ate by an animal to the concentration in an edible portion of animal product, in pCi/ liter of meat :

per pCi/ day; page 86 of 120

k NUCLEAR POWER BUSINESS UNIT ODCM i OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT l December 2,1997 OFFSITE DOSE CALCULATION MANUAL D,;p) -- the dose factor, specific to a given age group a, nuclide i, pathway p, and organ J, which is used to !

calet. late the radiation dose from an intake of a nuclide, i

in mrem /pCl; d

A = the radioactive decay constant of nuclide i, in day ;

t, = the average time from slaughter to consumption, in days. j To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose.'"' = Il00 M,U,0* F D.n e *d' Q, F The values used in the equation above pre-Mp =

0.1111 (Point at which water is taken trum the lake is taken as plume centerline 1 mile downstream. The plume centerline dilution factor at this location is 9 using RO 1.111 methodology.);

U,p = Infant - 0, Child 41, Teen - 65, and Adult 110 kg/ year; QAw

= 60 liters / day; 3

F = 1507 ft /see. (677000 gpm);

= Values used are taken from Table E 1 of RO 1.109; Fi3 D,ip)

= Values used are taken from Tables E-11 through E 14 of RO 1,109; t, = 20 days.

i Page 87 of 120 ;

NUCLEAR POWER BUSINESS UNIT ODCh!

OFFSITE DOSE CALCULATION hiANUAL Revision 11 DRAFT :

December 2,1997 0FFSITE DOSE CALCULATION hfANUAL .!

Cl.lJ Irricated Foods (hlilk From Watered Cattle)

The dose from the ingestion of milk from cows which have been given contaminated water was calculated using the equation:

Dosem = 1100 bN*p Q Fa D.w e"

where:

t Dose,p;

= the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; 3

1100 = factor to convert from Cl sec/yr ft to pCilliter; hi p = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; U,p = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in liters / year; Q3w

= consumption rate of contaminated water by an animal, in liters / day; 3

F = the flow rate of the liquid effluent,in ft /sec; Qi

= the telease rate of nuclide i, in Ci/ year; Fg i

= the stable element transfer coeflicient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/ liter of ,

milk per pCi/ day; D,ipj = the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to i calcula:e the radiation dose from an intake of a nuclide,in mrem /pCi; Ai

= the radioactive decay constant of nuclide i, in day'I ;

tr

= the average transport time of the activity from the feed into the milk and to the receptor, in days.

' Page 88 of 120-

NUCLEAR POWER 13USINESS UNIT ODCM OFFSITE DOSE cal.CULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose *

= l100 M' * ** Fa D.,p,e*

Q, F The values used in the equation above are:

Mp = 0,1111 (Foint at which water is taken from the lake is taken as plume centerline 1 mile downstream. The plume centerline dilution factor at this location is 9 using RG 1.111 methodology. the dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used. This is a conservative assumption.);

U,p = f r.fant - 330, Child - 330, Teen 400, and Adult - 310 liters / year; Q3w

= 60 literr/ day; 3

F = 1507 ft /sec. (677000 gpm);

= Values used are taken from Table E 1 of RG 1.109; Fai D,ip) = Values used are taken from Tables E-11 through E 14 of RG 1.109;

= 2 days.

tt Page 89 of 120

l ODCN1 ;

NUCLEAR POWER 11USINESS UNIT '

OFFSITE DOSE CALCULATION A1ANUAL Revision 11 DRAFT I

December 2,1997 OFFSITE DOSE CALCULATION h!ANUAL l C l .l .4 Potable Water [

t The dose from ingestion of water was calculated using the equation:

4 U." Q, D..,3 e%

Dose.p, = 1100 i

where:

Dose,p;

= the dose to the organj of an individual of age group a from all of the nuclides i in nthway p, in mrem / year; 1100 = a factor to convert from Ci sec/yr ft' to pCi/ liter:

hi p - the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, i dimensionless; U,p = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in 1/ year; 3

F = the flow rate of the liquid efiluent, in ft /sec; Qi

= the release rate of nuclide i, in Ci/ year;

D,;p;

= the dose f::ctor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intaxe of a i

nuclide, in mrent /pCi;

-- the radioactive decay constant of nuclide i, in day *I; li t-p

= the average transit time required for nuclides to reach the point of exposure, For intemal dose, tp is the -

total time elapsed between release of the nuclides and the ingestion of the water. in days.

Page 90 of 120 -

NUCLEAR POWER BUSINESS UNIT ODChi l OFFSITE DOSE CALCULATION htANUAL Revision 11 DRAFT !

December 2,1997 OFFSITE DOSE CALCULATION h!ANUAL +

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide, The rearranged equation is shown below:

L Dose.o . = 1100 ' D.ine*'

Q F f i

The values used in the equation above are: ;

i hi p = 0.0384 (Withdrawal point is taken as the Two Rivers municipal water intake located a distance of 12 miles ;

downstream le plume centerline dilution factor at this location is 26 using RG 1.111 methodology and

the factor of 2 allowed for current reversals. The dilution factor calculations are uttached.);

U,p = Infant 330, Child - 510, Teen - $10, and Adult . 730 7

liters / year; 3

F = 1507 ft /sec. (677000 gpm);

D,ip; = Values used are taken from Tables E 11 through E 14 of RG 1.109 l 1

tp = 2 days (This was calculated using a current speed of 12.2 cm/s plus 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to reflect the transport of the water through the water purification pladt and distribution system.)

i J

i Page 91 of 120

- __ _. . - - - - . = _ - - - - . . - ._._- _--_.- .- . _ . _-

NUCLEAR POWER BUSINESS UNIT ODCM [

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT - l December 2,1997 OFFSITE DOSE CALCULATION MANUAL Cl.l.S Shoreline Dennsits .

The dose from exposure to radioactive materials deposited on the shoreline of the lae was calculated using the equation:

Dose. = 110000 Q. tid,cie'%(1 c*)

where:

a Dose,p)

= the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; ,

110000 = a factor to convert from Cl.sec/yr.ft' to pCi/ liter and f to account for the proportionality constant used in the sedinient radioactivity model; Mp = the mixing ratio (reciprocal of the dilution factor) at !

the point of exposure, dimensionless; U,p = a usage factor that specifies the exposure time for an individual of age group a associated with pathway p, in hours / year; W = shoreline width factor, dimensionless;

3 '

F = the flow rate of the liquid effluent, in ft /sec;

't Qi

= the release rate of nuclide i, in Ci/ year; Ti

= the radioactive halflife of nuclide i, in days; D,ip)

= the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide,in mrem /pCi;-

A;. = the radioactive decay constant of nuclide i, in day'I ;

I Page 92 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, pt is the total time elapsed between release of the nuclides and the ingestion of the water,in days; tb

= the period of time for which the sediment or soil is exposed to the contaminated water, in days.

To calculate the dose per curie released, the equation above was rearranged and the :alculation performed for each nuclide. The rearranged equation is shown below:

M, U. W Dose""i = 110000 F

B,Ti D.nie*'(1 e**)

Q The values used in the equation above are:

Mp = 0.01821 (Point of exposure is taken as the Point Beach State Park beach which is located 8000 meters downstream. The plume shoreline dilution factor at this location is 54.9 using RO 1.111 methodology.

The dilution factor calculations are attached. The -

factor of 2 allowed for current reversals was not used.);

U,p = Infant - 0, Child - 14, Teen - 67, and Adult - 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months / year; W = 0.3; B ip = Values used are taken from Table A 1 of RG 1.109; F = 1507 fd/sec. (677000 gpm);

D,ip;

= Values used are taken from Table E-6 of RG 1.109; tp = 0.5 day; tb

= 5458 days.

Page 93 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL C 1.2 - Atmospheric Release Dose Factors: Non-Gaseous j The equations and values used to calculate the total dose to the maximum exposed individual factors for non gaseous radionuclides released to the <

atmosphere using Regulatory Guide 1.109, Rev.1,1977 is shown below. The ,

total dose factor in mrem /Ci released is the sum of all airborne efauent doses in mrem /Ci for the following pathways: milk, meat, leafy vegetables, potable water, and shoreline deposits. A summary of totals is presented by age group and target organ in matrix format for each radionuclide in Section 5, Table 5 1. The highest dose in each matrix is used as the dose tracking factor to be used for the monthly tracking of release doses. These values are found in Section 5, Table 5 2.

C l .2.1 inhalation of Nuclides in Air The dose from the inhalation of nuclides in the air was calculated using the equation:

r s Dose,. = 3.17 E+ 04 R. 1 QiDFlw

where:

Dosep = the annual dose to organ j of an individual of age group a due to inhalation,in mrem / year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year; R, = the annual air intake for individuals in the age group a, ,

3 in m / year; y/Q = the annual average atmosphere dispersion factor, in 3

sec/m (The location at which the dose was calculated was the site boundaiy in the south sector - a distance of 1270 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; DFI;p = the inhalation dose factor for radionuclide i, organ j, !

and age group a, mrem /pCl.

Page 94 of 120

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT ;

December 2,1997 OFFSITE DOSE CALCULATION MANUAL i Te calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below: 4 Dosen. =

1, DFl.;.

3.17 E+ 04 R.

Q, \Q) t The values used in the equation above are:

r R, = Infant 1400, Child - 3700, Teen - 8000, and 3

Adult 8000 m / year; y/Q =

9.36E-07 seconds /m3 (This value taken from Table 1.4-2 of the FSAR, release mode IB, annual average, site boundary.);

DFI;;, = Values used are taken from Tables E-7 through E-10 of RG 1.109.

Cl.2.2 Annual Orean Dose From External irradiation From Nuclides

Denosited On the Ground 4

The organ dose from external irradiation from nuclides deposited on the ground was calculated using the equation:

Q'(1 Dose, = IE+12 (8760) Si Sr e*'*) DFGo where:

Dose;

= the annual dose to the organ j, in mrem / year; 1E+12 = the number of pCi per Ci; 8760 = - the number of hours in a year; Si = the annual average relative deposition of nuclide i, considering depletion of the plume during transport, in ,

2 m ,(The location at which the dose is calculated is the site boundary in the south sector - a distance of -

1300 meters.);

Page 95 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997: l 1 OFFSITE DOSE CALCULATION MANUAL Sr

= the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless; Q; = the release rate of nuclide i, in Ci/ year; 4 d

A; a the radioactive decay constant of nuclide 1, in day ;

tb

= the time period over which the accumulation is evaluated,in days; DFGy = the open field ground plane dose conversion factor for 8

organj from nuclide i, in mrem m /pci hour.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

~

Dose o

= IE+12 (8760) Si Sr DFO,3 Q. Ai The values used in the equation above are:

Si

= 31E-09 m' (This value taken from Table 1,4 2 of the FSAR, release mode 10, annual average, site boundary.);

Sr

= 1 (No structural shielding is assumed.);

tb

= 5479 days (15 years);

DFOg= Values used are taken from Table E-6 of RG 1.109.

Page 96 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Raision !! DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL C l .2.3 Annual Orcan Dose From Atmostsherically Released Nuclidetig Mills 7

The organ dose from atmospherically released nuclides in milk was calculated using the equation:

Dosej. = 2.7 E+ 09 U.Qr6i Q, Fm, DFI,;.e*'" {f, f. + e%1 - f, fiy

'r (1 4 x<

c *) + B,,(1 - e*d')' >

Yvlu PA4 ,

where: ,

Dosej, a the annual dose to the organj of an individual in age group a from a dietary intake of atmospherically released nuclides, in mrem / year; 2.7E+09 = the number of pC' per Ci divided by the number of days per year; U, = the ingestion rate of milk for individuals in age groun a, in liters / year; Qp = the amount of feed consumed by a cow per, in kg/ day; Si = the annual average relative deposition of nuclide i, considering depletion of the plume during transport,in m# (The location , !

at which the dose is calculated is the nearest animal location in the south southeast sector a distance of 1300 meters.);

Qi

= t'e release rate of nuclide i, in Ci/ year; d

li = the radioactive decay constant of nuclide i, in day ;

tb

= the time period over which the accumulation is evaluated, in days; DFl),i

= the dose conversion factor for the ingestion of nuclide i, organj, and age group u, in mrem /pCi; Page 97 of 120

NUCLEAR POWER BUSINESS UNIT ODChi OFFSITE DOSE CALCULATION hlANUAL Restion 11 DRAFT December 2,1997 .

OFFSITE DOSE CALCULATION h!ANUAL Fm i

- the average fraction of the animal's daily intake of nuclide i i which appears in each liter of milk, in days / liter; tr

= the average transport time of the activity from the feed into the milk and to the receptor,in days; fp = the fraction of the year that the animals graze on pasture, l dimensionless; f, = the fraction of the daily feed that is pasture grass when the animal grazes on pasture, dimensionless; J

r = the fraction of the deposited activity retained on crops.

- dimensionless; 7

A El = the effective removal rate constant for nuclide i from crops, in I

days, where Agi- A! + A w, and A wis the removal rate

> constant for physical loss by weathering; Aw = 0.0504 day;

t, = the time period that crops are exposed to contamination during the growing season,in days; 2

Yv = the agricultural productivity, in kg (wet weight)/m ;

B;y = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCl/kg) to the nuclide concentration in water (in pCi/ liter),

in liters /kg; 2

P = the effective surface density for soil, in kg (dry soil)/m ,

For iodines, this factor is changed to 1.4E+09.

Page 98 of 120

NUCLEAR POWER BUSINESS UNIT ODChi !

OFFSITE DOSE CALCULATION hlANUAL Revision 11 DRAFT December 2,1997 !

OFFSITE DOSE CALCULATION h1ANUAL i To calculate the dose per curie released, the equation above was rearranged f and the calculation performed for each nuclide. The rearranged equation is ;

shown below: ,

E 5'"' = 2.7 E+ 9 U.Q,6. F DFlu.c" ]fr f. + c**'(1 - f, f.N ed') + B ,(1 - c'*^)'

X <f r(1 .

YvAn PAi .

7 The values used in the equation above are: ,

U, = Infant-330, Child 330 Teen 400, and Adult 310 liters / year; QF

= 50 kg/ day; ,

63 = 18.8E-09 m 2 (This value taken from Table 1.4 2 of the FSAR, release mode 1 B, grazing season, site boundary.);

= Values used are taken from Table E 1 of RG 1.109; Fm i DFlj,i = Values used are taken from Tables E 11 through E 14 of RG 1.109; tr

= 2 days; fp = 0.5; f, = 0.5; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14;

= ;

t, 30 days; 2

Yv = 0.7 kg/m ;

Biv

= Values used are taken from Table E 1 of RG 1.109; P = 240 kg/rn ;

tb

= 5458 days (15 years). ;

Page 99 of 120

. - . . - . . - - - ---- . - . - - - ~ . - . . - . - . - . --

NUCLEAR POWER BUSINESS UNIT ODCM f OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT l December 2,1997 !

OFFSITE DOSE CALCULATION MANUAL i C l .2.4 Annual Orean Dose From Atmospherically Released Nucildes In :

hkal ;

The organ dose from atmospherically released nuclides in meat was calculated ,

using the equation: ;

Dose, = 2.7 E+ 9 U.Q,6, Q, Fir DFlc.c f, f. + e91 f, f.[ ,

x f r(1 - e**) + a,(1 - e**) t YvAu P Ai ,

where:

a the annual dose to the organJ of an individual in age group a !

Dosej, from a dietary intake of atmospherically released nuclides, in mrent lyear; 2.7E+9' - the number of pCi per Ci divided by the number of days per year; U, = the ingestion rate of meat for individuals in age group a, in literdyear; QF

= the amount of feed consumed by a cow per, in kg/ day; 1

1 5; = the annual average relative deposition of nuclide i, considering depletion of the plume during transport, in m# ,

(The location at which the dose is calculated is the nearest animallocation in the south southeast sector a distance of t

1300 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; ,

= the radioactive decay constant of nuclide i, in day 9; Ai 1

tb

= the time period over which the accumulation is eva!uM.4, in days;

- DFl;, i

= the dose conversion factor for the ingestion of nuclide i, organj, and age group a, in mrent/ pCi; page 100 of120

NUCLEAR POWER BUSINESS UNIT ODCM ;

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL i Fri = the average fraction of the animal's daily intake of nuclide i l which appears in each kilogram of flesh, in days &g; l i

t, = the average time from slaughter to cortsumption, in days; i

fp = .the fraction of the year that the animals graze on pasture, dimensionless; ;

f, = the fraction of the daily feed that is pasture grass when the '

animal grazes on pasture, dimensionless; r = the fraction of the deposited activity retained on crops, l dimensionless; ,

= the effective removal rate constant for nuclide i from crops, !

) Aa in days", where Agi = Ai + A w , and Aw is the removal rate constant for physical loss by weathering; t, = the time period tha crops are exposed to contamination during the growing season,in days; i

2 Yv = the agricultural productivity, in kg (wet weight)/m ;

Biy = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCi/ liter),in liters /kg; 2

P = the effective surface density for soil, in kg (dry soil)/m , ;

For iodines, this factor is changed to 1.4E+09. [

l

- Page 101 of 120 ;

p w , -.

- - . . , . '~ +4. ....-.-,rm,y_~+- --.m- - - , ,

- - . _ - _ _ . .._ - _ .___ _-._ - ~ . _ _ _ - _ . - . .._ .-

NUCLEAR POWER BUSINESS UNIT ODCh1 OFFSITE DOSE CALCULATION h!ANUAL Revision 11 DRAFT i, December 2,1997 -

0FFSITE DOSE CALCULATION htANUAL 1 1

To calculate the dose per curie released, the equation above was rearranged ;

and the calculation perfomied for each nucl!de. The rearranged equation is l l

shown below:

$'"- - f,f.h q, 2.7 E+ 9 U.0,6, J F,r DFlo,e*' jf,f, + e91

'r (i . e.x,...) + a,(i . c.u.)' -

x<

Yv).o P ).i ,

The values used in the equation above are:

U, = Infant 0, Child 41, Teen 65, and Adult - 110 kg/ year; Qr

= 50 kg/ day; 53 = 18.8E 09 m : (This value taken from Table 1,4 2 of the FSAR, release mode 1B, grazing season, site boundary.);

= Values used are taken from Table E-1 of RG 1.109; Fri DFlij , = . Values used are taken from Tables E-ll through E 14 of RG 1.109; a 20 days; t,

fp = 0.5; f, = 1.0; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon 14, t-e

= 30 days; B;y = Values used are taken from Table E-1 of RG 1,109; 2

Yy . = 0.7 kg/m ;

2 P = 240 kg/m ;

d

).w = 0.0504 day ;

tv = 5458 days (15 years).

Page 102 of 120

NUCLEAR POWER llUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Cl .2.5 Annual Orean Dose From Atmosr>herically Released Nuclides in Produce The organ dose from atmospherically released nuclides in produce was calculated using the equation:

'r (i . , ~,) + a,(i . .o.);

Dose,. = 2.7 E+ 9 U, f,Si Q,DFlw e <

YvAn PL ,

where:

Dosej, = the annual dose to the organ J of an individual in age group a from a dietary intake of atmospherically released nuclides, in miem/ year; 2.7E+9 = the number of pCi per Ci divided by tne number of days per year; U, = the ingestion rate of produce for individuals in age grot.p a, in

' ivear; f, = tra .aon of produce ingested grown in garden ofinterest, dimensionless; Si

- = the annual average relatis e depositi n of nuclide i, considering depletion of the plume dunng transport, in m'2 (The location at which the dose is calculat rd is the nearest garden location in the south southwest sector . a distance of 1460 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; d

Ai

= the radioactive decay constant of nuclide i,in day ;

tb

= the time period over which the accumulation is evaluated, in

- days; DFlj,i

= the dose conversion factor for the ingestion of nuclide i, organj, and age group a, in mrem /pCi; Page 103 of 120

NUCLEAR POWER DUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL th

= the holdup time that represents the time interval between harvest and consumption of the food,in days; r - the fraction of the deposited activity retained on crops, dimensionless; Agg = the effective removal rate constant for nuclide i from crops, in days, where Agi = Ai + )m, and ), is the removal rate constant for physical loss by_ weathering; t, = the time period that crops are exposed to contamination during the growing season,in days; 2

Yv = the agricultural productivity,in kg (wet weight)/m ;

Bjy - the concentration factor for the uptake of nuclide iln pathway p, exp used as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCi/ liter),

in liters /kg; 2

P = the effective surface d:nsity for soil,in kg (dry soil)/m .

For iodines, this factor is changed to 1.4E+09.

Page 104 of 120.

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 0FFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below;

'r Dose.,.

= 2.7 E+ 9 U. f,5. DFl.;. e*^ < (1 - e'**) + IL (1e-^>)

Q ,

YvAo P A. ,

The values used in the equation above are:

U, e infant 0, Child $20, Teen 630,and Adult 520 kglycar; fg = 0.76; 63 = 18.8E 09 m 2 (This value taken from Table 1,4 2 of the FSAR, release mode lu, growing season, site boundary.):

DFig, = Values used are taken from Tab;es E ll through E 14 of RO 1.109;-

= 60 days; th r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, anu carbon 14;

).w = 0.0504 day *I; a t, = 60 days; 2

Y = 0.7 kg/m ;

By = Values used are taken from Table E 1 of RG 1.109; 2

P = 240 kg/m ;

tb

= 5458 days (15 years),

e Page 105 of 120

NUCLEAR POWER BUSINESS UNIT ODCM i Revision 11 DRAFT ;

OFFSITE DOSE CALCULATION MANUAL '

December 2.1997 i

OFFSITE DOSE CALCULATION MANUAL Cl.2.6 Annual Orean Dose From Atmospherically Released Nuclides In f I eafv Vecetables ;

The organ dose from atmospherically released nuclides in leafy vegetables was calculated using the equation.

{

~

4

= Q, DFl.3 e4d' <

'r(1 c "') + Ba(1 e*")

Dosep 2.7 E+ 9 U. fiS4 i, van PL ,

svhere: ,

Dosej,

= the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides,in mrem / year; 2.7E+9' = the number of pCi per Ci divided by the number of days per year; 1

U, = the ingestion rate of produce for individuals in age group a, in kg/ year; fi a fraction ofleafy vegetables ingested grown in garden of interest, dimensionlesa; Si = the annual average relative deposition of nuclide i, considering depletion of the plume during transport,in m 2 (The location at ,

which the dose is calculated is the nearest garden location in the south-southwest sector a distance of 1460 meters.);

= the release rate of nuclide 1, in Ci/ year; Qi d

Ai

= the radioactive decay constant of nuclide 1, in day ; {

tb

= . the time period over which the accumulation is evaluated, in days; DFlj, i

= the dose conversion factor for the ingestion of nuclide i, organj, and age group a, in mrem /pCi; ;

Page 106 of120

NUCLEAR POW 11R DUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT ,

December 2,19M! !

OFFSITE DOSE CALCULATION MANUAL ,

th

= the holdup time that represents the time interval between '

harvest and consumption of the food, in days; r a the fraction of the deposited activity retained on crops, dimensionless; ,

= the effective removal rate constant for nuclide i from crops, in

).ti days *I, where ).ci = ).i + A, and A is the removal rate constant for physicalloss by weathering; ;

t, = the time period that crops are exposed to contamination during f the growing season, in days; 2

Yv

= the agricultural productivity, in kg (wet weight)/m ; l Bjy = the concentration factor for the uptake of nuclide i in I

pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCl/ liter),

in liters /kg; 2

P = the effective surface density for soil, in kg (dry soil)/m ,

For iodines, this factor is changed to 1.4E+09. ;

[

Page 107 of 120

., ,. .. ,s .m., . . , . ._ . , --_# _ . , , . . _ . .

NUCLEAR POWER BUSINESS UNIT ODCM ;

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT ,

December 2,1997 i l

0FFSITE DOSE CALCULATION MANUAL ,

i To calculate the dose per curie released, the equation above was rearranged and the calculation perfonned for each nuclide. The rearranged equation is shouri below:

4 Dose,;,

= 2.7 E+ 9 U. fi6, 4 DFli,.e <

r (!

e46'*) + IL (1e ^)'

Q, YvAu PAi ,

The values used in the equation above are:

U, = Infant 0, Child-26, Teen 42,and Adult 64 kg/ year; .;

f = 1; Si = 18.8E 09 rn'2 (This value taken from Table 1.4 2 of the FSAR, .

release mode 1B, growing scason, site boundary.);

DFlp i

= Values used are tf:n from Tables E lI through E 14 of RO 1.109; th

= 1 day; r = 0.25,1.0 for lodines, and 0.20 for noble gases, tritium, and carbon-14; Aw = 0.0504 day;

t, = 60 days; 2

Yv = 0.7 kg/m ;

= Values used are taken from Table E l of RO 1.109; Div 2

P = 240 kg/m ;

tb

= 5458 days (15 years).

Page 108 of 120. l

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT '

December 2.1997 j

OFFSITE DOSE CALCULATION MANUAL Cl.3 Almospheric Release Dose Factors: Noble Gases j The equations arad values used to calculate the total dose factors for noble ,

gases released to the atmosphere using Regulatory Guide 1.109, Rev.1,1977 I is shown below. The dose factor in mrem /Ci and mrad /Ci released for each i

radionuclide is presented in Section 5, Table 51.

Cl..t.1 Annual Gamma and Reta Air Dose From All Noble Gas Releases The dose from the submersion ofindividuals in air containing noble gases was calculated using the equation' 1 es l 8 = 3.17 E+ 04 1 [Q, Dose' or Dosc (Q/ , DFl Or DFff where:

^

Dosci or 0 = the annual gamma and beta air dose, in Dose mradlyear; 3,17E+04 = the number of pCl/Ci divided by the number of sec/ year; y./Q = the annual average atmosphere dispersion factor, 3

in sec/m (The location at which the dose was

- calculated was the site boundary in the south ',

sector a distance of 1270 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; DFf or DF,0 = the gamma and beta air dose factors for a unifomi semi infm' ite cloud of radionuclide i, in 3

mrad m /pCi year.

Page 109 of120 L

NUCl EAR POWER BUSINESS UNIT ODCM '

OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT Decernber 2,1997 :

, OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was ;

rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose [ or Dose'-

0 'y'

= 3.17 E+ 04 - 'DFY i or DF,y Q4 sQs6 ,

t The values used in the equation above are: ;

yfQ =

9.36F 07 seconds /m3 (This value taken from Table 1.4 2 of the FSAR, release mode IB, intennittent, annual average, site boundary.);

DE[ or DFni

= Values used are taken from Table B 1 of RO l.109.

C l .3.2 Annual Skin Dose From All Noble Gas Releases The skin dose from the submersion ofindividuals in air containing -

noble gases was calculated using the equation: ;

f 5f 3 Dose = 3.17 E+ 04 1 1.lls, Q, DFl + Q,DFS,

<Qsr >

where:

Dose = the annual skin dose due to immersion in a semi infinite cloud, in mrem / year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year; 1.11 = the average ratio of tissue to air energy absorption coefficients; Sr

= the attenuation factor that accounts for the dose reduction ,

due to shielding provided by residential structures, dimensionless; Page 110 of120

.. -. - - _ . _ ..._ _.- . _ .2 -_

NUCLEAR POWER 13USINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 -

OFFSITE DOSE CALCULATION MANUAL POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 0FFSITE DOSE CALCULATION MANUAL i

WISCONSIN ELECTRIC POWER COMPANY December 2,1997 Revision 11 i

i

.- - . .--e

, UCLEAR POWEli BUSINESS UNIT - ODCM-K OFFSITE DOSE CALCULATION MANUAL ? Revision 11 DRAFT 1

. December 2;1997. 'i j OFFSITE DOSE CALCULATION MANUAL

=. ,

.. .i

. . TABLE OF CONTENTS ?

g-i

1.0 DEESITE DOSE CALCUL ATION M ANUAL ADMINISTRATION................................................1 -

i 1.1 Purpose..........................................................................................................................................1- .

l 1.2 G e neral Respo nsib i l i ties . . . .. . .. ... . . . . . . ... .. .. . . . . . . . . .. . .. . . . . . .. . . . . . .. . . . . . . . . .. .. . .. . .. . .. ... .. . . . .. .. . ... . . . . .

x 1 . 3 M an u al R e v i s i o n s . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

a 2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING ..................................... 2

. 3.0 M ETHODOLOGY FOR DETER. MINING AL ARM SET POINTS ............................ ...................... 7 3.1 introduction....................................................................................................................................7 3,2 Objective.......................................................................................................................................7 3 . 3 A l ert S e t Po i n t G u id e l in es . .. . . . . . . . . .. . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . .. .. .. .. . ... . . . . . .... . . .... . . . .

3.4 Alarm or T rip S et Point G uidelines ...... .. . ..... . .... .. . .. ... . ... ......... ..... ......... ......... . .. ... ... .............. .. .. ... 8 t

3.5 Monier Calibration a.,d Calibration Constant Determinaticn ................................ ................. .. ... 8 '

3,6 Determination of the Effective Maximum EHluent Concentration (EMEC) for Liquid Releases... 9

. ; 3.7 Determination of Liquid Effluer.t Monitor Abrm Set Point ................................................... ......11 e

s 3.8 Determination o f EM EC for Atmospheric Relenses...................................................... ................16 3.9 Determination of Gaseaus EfDuent Monitor Alarm Set points ................ ...... ..............................17 i -4.0 DEMONSTRATING COMPLI ANCE WITF 10 CFR 50. APPENDIX ! ......................................... 24 e

- 4.1 I n tro d u e ti o n . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. , . . . . . .. . . . .. . . . . . . .. . . . . . .. . . . . .. .. . . . . . . . . . . . . . . . .. 2 4

4 .2 D o s e L i mi ts ; . . . . . . . . . .. . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . . . . 2 4 I

i .43 Re l eas e L i m i ts . . . . . .. . .. . . . . ... . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . .

2 14.4 E PA Re g u l ati o ns . . . . . . . .. . . . . . . .. . ., . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. .. . . . ,

4 f'

y isvam-u- -- se af t N -*f W f- -- -P- b- T--V d' *Nt' P-smw h- =* e1mr-" 1 #--

W-b--TW"t '-7s-'*'-'

NUCLEAR POWER BUSINESS UNIT =ODCM-OFFSITE DOSE CALCULATION MANUAL- Revision 11 DRAFT I

December 2,1997 OFFSITE DOSE CALCULATION MANUAL t

'5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS.... 26 i .

5.1 A ppe nd i x ! Dose Calc ul atio n s ... . .. .. . . . . .. . .. .. . . . . . . . .. . ... . ... . . .. . .. . . .... .. . . . . . ... . . . .. . . . .. ... .. . . . . ..;

15 .1. I Li qui d Rel ease M od e . . . . . .. . . . .. . .. .. . . . . . .. . . .. . . .. . . .. . . . .. . . . .. . . .. . .. . . . .. . . . ... .. . .. . . . .. . . .. .

5.1.2 Atmospheric Release Mode: Radioiodine, Tritium, and Particulates......... ........................... 45

- 5.1.3 Atmospheric Release Mode: Noble Gases .............................................................................. 64 .

16.0 RADIOLOGIC AL ENVIRONMENTAL MONITORING PROGRAM ...................... .................... 66 7.0 R_ ADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE DISPOSAL 66 7.1 B a sis, Commitmen ts, an d Ac ti ons . . . . . . .. . .. . . . . . . . . . . . . . . . .. . ... .. . . . .. . . . . . . . . . . . . . . .. . . .. . . . . .. .. . .. .. . .

7;1.IBasis.........................................................................................................................................66 ,

7.1.2 Basis for NRC Commitment Modification . ........ ........................................ ....................... .. 66 7.1.3 M o d i fi c a ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . .

d 7'.1.4 E x posure E val ua tie s . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . .. . . . ... . . . . . . . . .. . . . . . . . . .

7.2 Procedure...................................................................................................................................68 7.3 Ad m i ni st; ati ve R eq ui re m e nts . ... . . . . .. . . ... . . . . ... . .. . .. .. . . . . . .. . . . . . . . . . . . .. . .. . . . .. . .. . . ... . . . . . . . . .. ..

7.3.1 Complete records of each contaminated disposal shall be kept as follows: ..... . ... ............... 69 -

- 7.3.2 Moditications to the October 8,1987, NRC submittal ....... ... ................ .............. .......... .... 70 4

APPENDIXA....................................................................................................................................71 A.l.0 Dsrivation of Liquid Release Effective Maximum Eftluent Concentration......... ...... ............. 72 l

. A . I .1 S o urc e Term .'.. .. .. . . ... ...... . . . . . ....... . ... . . ... . .... . . . .....................................................................72 2

2 A.1.2 Effective Maximum Effluent Concentration;.............. ............. ............................................. 72

~APPENDIXB...................................................................................................................................77 4

. B.I.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration ..................... 78 B 1.1 S o u rc e Te rm . . . . . .. ... . . . .. ... . ... .. . . . . . . . . .. . .. ... . ... . . .. .. . . . . .. . . . ... ...........................................78 B1.2 Effeetive Maximum Effluent Concentration.... ............ . ..............................................78 f

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NUCLEAR POWER BUSINESS UNIT ODCM

. OFFSITE DOSE CALCULATION MANUAL Revision i1 DRAFT December 2,1997 OFFSiTE DOSE CALCULATION MANUAL ~

l A P P EN D I X C .. .. . . . .. . . . . . . . . .. . . . .. .. . . . . . . . . . . . . . . . . . . . . ...................................................83 C.I.0 Calculation of Total Dose Fcctors Us 4 mlvo- Guide 1.109 Methodology. . ... . ...... ... 84 C.1.1 Liquid Relcase Dose Factors... . ...... .......................................................84 C 1.1.1 Aquatic Foods ..... ..... .. ..... .............. .........................................................84 C 1.1.2 Irrigated Foods (Mcat From Watered Cattie)..... ..... .......................... .. ..... ..... .............. 86 C1.1.3 Irrigated Foods (Milk From Watered Cattle) ........ .... . ........................ . ...................88 C 1.1. 4 P o t a b l e Wa t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

C 1.1. 5 S h o re l i n e D e posi ts. . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

C1.2 Atmospheric Release Jose Factors: N o n G aseo us . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . ... . . . . .

C 1.2.1 o halation o f N uc lides I n Air .. .. .... .. . .. . .. .. . . . . . . ... . . .. . . .. ... ... . .. . . ..... .. . . . .. .. .. .... . .. ... ..

Cl.2.2 Annual Organ Dose From External Irradiation From Nuclides Deposited On the Ground 95 Cl.2.3 Annual Organ Dose From Atmospherically keleased Nuclides In Milk. ..... .. . ... , ..... 97 Cl.2.4 Annual Organ Dose From Atmospherically .: leased Nuclides In Meat ....... . ... ... .. 100 Cl.2.5 Annual Organ Dose From Atmospherically Released Nuclides In Produce... ... . . ... 103 Cl.2.6 Annual Organ Dose From A mospherically Released Nuclides In Leafy Vegetables.. .106 Cl.3 Atmospheric Release Dose Factors: Noble Gases..... . . ...... . . . . . . . . . . . ..................109 Cl.3.1 Annual Gamma and Beta Air Dose 1.am All Noble Gas Releases. . ......................109 C1.3.2 Annual Skin Dose From All Noble Gas Releases. ... ..... .. ...............................110 C1.3.3 Annual Total Body Dose From All Noble Gas Releases... . .. . .. ..... .... .. ..............112 APPENDIXD........................................................,................,..........................I14 D1.0 Liauid Emuent Dilution Factor Calculations . . .. .... . .... . .. . .. ...................... ... 115 D 1.1 Methodology .. ... . .. .. ... ... ...... . ........................................... ... ....... 1 15 DI.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake . . . . ... . 118

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision il DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL APPENDlX E NRC Submittal: Radiologicalimpact Evalu ition o f Sewage Treatment SIudge ............................................... ...... .. ............E-1 APPENDIXF......................................................................................................................F1 M odi fication # 1 to N RC S ubmit tal .. .. . ... . . ... . . ... .. . . . ... .... . ... . .. .. . .. ... . . .... . . ... . .. .. . . .... . ... ... ... .. ... . . ... . ...

APPENDIXG............................................................................................................G1

- M od i fi c a t i o n # 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

APPENDLXI1..............................................................................................................................H1 M odilication #3 to NRC S ubmittal . . ... . .. . .. .. ... . . .. . . . .. . ... . . . ........ .. . . .. ..... . .. .. .... . ..... .. .. . . . ........ .. . .. H-2 C hang e to Ori g i nal S u b m i tt al . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. .. . . . .. . . . . . . .. . . . . . . . . . .. . . .

B a s i s/Ex pl ana ti o n . .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . .. . .. .. . . . . . . . . . . . . . . . . . . . . . .

NUCLEAR POWER BUSINESS UNIT ODCM-OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES AND FIGURES Pace SECTION 2.0 TABLE 21 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS. ....... . . ............... .. 3 TABLE 2 2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS ... ... ..... .............. 4 FIGURE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS........ ... . .. ....... .. . 5 i FIGURE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS. ........ .. .... . .... 6 SECTION 3.0 f TABLE 3.7-1

SUMMARY

OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES.............................................................................................................!3 TABLE 3.7-2 LIQUID PATHWAY MONITOR CALCULATED DEFAUI.T SET POINTS ......13 TABLE 3.91

SUMMARY

OF GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATES...........................................................................................................I7 TABLE 3.9 2 ATMOSPHERIC PATHWAY MONITOR DEFAULT RMS SET POINTS...... ...18 SECTION 5.0 TABLE 5.I-1 LIQUID EFF LUENT DOS E FACTOR... ........ .. . ... ....................... . ..... ... ......... 28 TABLE 5.1-2 AIRBORNE EFFLUENT DOSE F ACTOR... . ...... .. ... . ... ... .. .... . ... , . .. .... 47 TABLE 5.1 ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES ... . . .. 65 APPENDIX A TABLE A-1 CU RIES RE LEASED IN LIQUIDS.. .. ................... . ... . .. .......... .. . . .. ............74 TABLE A-2 FRACTIONAL MEC IN LIQUID EFFLUENT.... ..... ........ . . ... ..... . ... .. ..... 75 APPENDIX B TABLE B-1 CURIES IN ATMOSPHERIC EFFLUENT..... ....................... ... ...... ... .. . ....... 79 TABLE B-2 FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT .. ...... . .. ....... . . . .. 81 APPENDIX D TABLE D 1 SURFACE DILUTION FACTORS LIQUID EFFLUENTS IN A LARGE LAKE .. ... . .... .. . .. ...... ................. .. ... ....I16 FIGURE D-1 DILUTION FACTOR AT SURFACE. . . . . . . . . . . . . . . . ........ ....I17 t

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL _

x/Q = the annual average atmosphere dispersion factor, in 3

sec/m (The location at which the dose was calculated was the site boundary in the south sector - a distance of 1270 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; DF[

= the annual gamma air dose factor for a uniform 3

semi-infinite cloud of nuclide i, in mrad m /pCi-year; DFSi = the beta skin dose factor for a semi-infmite cloud of 2 nuclide i, which includes the attenuation by 7 ing/cm og 3

skin,in mrem m /pCi-year.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

< s Dose' = 3.17 E+ 04 1 (1.11 SrDFT + DFSi)

Q, sQs The values used in the equation above are:

Sr

= 1 (No structural shielding is assumed.);

x/Q =

9.36E-07 seconds /m3 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

= Values used are taken from Table B-1 of RG 1.109; DFf DFS; = Values used are taken from Table B-1 of RG 1.109.

Page111of120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997

- OFFSITE DOSE CALCULATION MANUAL C1.3.3 Annual Total Body Dose From All Noble Gas Releases The total body dose from the submersion ofindividuals in air containing noble gases was calculated using the equation:

r 8 Dose = 3,17 E+04 Sr 1 Q DFB,

<Qi where:

Dose = the annual total body dose due to immersion in a semi-infinite cloud, in mrem / year; L 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year; SF = the attenuation factor that accotmts for the dose reduction due to shielding provided by wsidential structures, dimensionless; y/Q = the annual average atmosphere dispersion factor, in 3

sec/m (The location at which the dose was calculated was the site boundary in the south s etor - a distance of 1270 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; DFB i = the total body dose factor for a uniform semi-infinite cloud of nuclide i, which includes the attenuation of 2 3 i 5 g/cm of tissue,in mrem-m /pCi-year.

Page 112 of 120

i ODCM ;

NUCLEAR POWER BUSINESS UNIT OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT I

OFFSITE DOSE CALCULATION hlANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The

- rearranged equation is shown below:

e Dose' = 3. 7 E+ 04 Sr 1>

Q, \Q)DFB The values used in the equation above are:

Sr

= 1 (No structural shielding is assumed.),

yjQ = 9.36E-07 seconds /m3 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

DFB i = Values used are taken from Table B-1 of RG 1.109.

Page 113 of 120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 ;

i OFFSITE DOSE CALCULATION hlANUAL APPEllDIX D DERIVATION OF DILUTION FACTORS USING REGULATORY GUIDE 1.113 Page 114 of 120

NUCLEAR POWER BUSINESS UNIT ODChi OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December: '997 OFFSITE DOSE CALCULATION hlANUAL Dl.0 Liauid Effluent Dilution Factor Calculations Dl.1 Methodoloev The dilution factors used for calculating the doses from liquid effluent released to Lake Michigan were calculated using the methodology of Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose ofImplementing Appendix 1." The parameters used in the calculation and the results of the calculation are given in Table D i. The results are presented graphically in Figure D 1.

r The centerline and shoreline values were calculated using Reg Guide 1.113 formulae 17 and 18 which apply to discharges to the Great Lakes. (The formulae are not presented here. See Section 5 of the PBNP FSAR for the formulae and origin of values used.) These results are applied as calculated for fish caught near PBNP. But for other pathways, an extra factor of two (2) is applied to account for current reversals which occur in Lake Michigan as described in the Appendix 1, Section 5, of the PBNP FSAR.

Page 115 of 120

i NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION hlANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL TABI E D-1 j SURFACE DILUTION FACTORS LIQUID EF FLUENTS IN A LARGE LAKE Dow nstream Distance Plume Centerline Shorelme (meten) l 10 8 8l 20 8 81 30 8.81 40 8 81 50 8 81 60 8.81 70 8.81 80 8.81 90 8 81 100 8.81 200 8 81 300 8 81 400 8 81 500 8.81 600 8 81 700 8 31 800 8 81 900 8.81 1000 8 8l 122000 2000 8 86 1758 3000 9 01 401 4000 9.25 186 5000 9 53 l16 6000 9 85 83 5 7000 10.2 65 9 8000 10 5 54 9 9000 10 8 474 10000 11.1 42.I 20000 14 0 24 3C000 16 1 20.1 40000 17.7 18.7 50000 18.8 18 3 60000 19 6 I 8.2 70000 2tf3 18 3 80000 20.9 18 6 90000 21.4 15 9 100000 21.9 19 2 200000 25,9 23.2 h0000 29.2 26.9 400000 323 30.3 500000 35.2 33.3 600000 37.8 36 0 700000 40 2 38.6 800000 42 6 41.0 900000 44 8 43.3 1000000 46 9 45.5 NOTD These values we~e calculated using the equation dessribed in Section 3.2 of the PBNP FSA R and thefollowing values:

e, = 900 c,m' hec :, = 0 meten

e. = 2 cm' hec d = 10 meters n' = 12.2cndec h = 10 meten b = 305 meten y, = 132.5 meten and a discharge rate of 42.2 m'/sec.

Page 116 of 120

e m

m as

m n to p Dilution Factor at Surface 5

m o 0 -c mo .

L.iquid Effluents .in a Large Lake

M

> :o E E@

DF per Unit Release Rate @ %m .

1.0E+0 6 = >- >Z '

5 d .d ?

o- om

)

~

...<,3. aoe m 2i...

1.0E+05 g .,,c,3 2 .m 2,... ama iia. -

5- [q '

- e

12.2 sm/ s.o

- Y t e)

18 2.8 m 7 7 C C T Z(si = 0 m >

r

@ 1.0E+04 g d;g = g

- I b = 305 m c Disoh.rs, est.

42.2 m 3 / s.o 2 1.0E+03 = c 8 5 1.0E+0 2 i ei.m. c.. .,u.. %

N /

1.0E+01 ;

7 '

E

PW@

g 5. n 1.0E+00 hk5 1.0E+ 01 1.0E+ 02 1.0E+03 1.0E+ 04 1.0 E+ 05 1.0E+06 _O C Downstream Distance (in meters) @y '

Area source, width 305 m and height 10 m ' ~m --I

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 1

1 DI.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water intake !

1 The dilution factor used at the Two Rivers water intake twelve miles downstream from PBNP included the factor of two described in Section DI.l.

Ilowever, instead of using the straight centerline dilution factor shown in Table 1, the weighted average dilution factor calculated over the width of the plume was used.

This approach was used for the following reasons. Firs, the path that the current takes to reach the Two Rivers water intake is not straight. In order to reach Two Rivers, the water must flow southeast around Point Beach State Park, which juts into Lake Michigan, and then curves back 90 degrees towards Two Rivers. As a result of this deviation from straight line flow, any part of the plume or possibly none of the plume would impinge upon the intake structure.

Second, there is a ditTerence in the distance offshore of the PBNP discharge and the Two Rivers water intake. The Two Rivers water intake is located 5080 feet offshore. By contrast, PBNP discharges close to the shoreline through two flumes, one directed north and one directed south, and is modeled as a source that extends 1000 feet out into the lake from the shoreline.

Based on these two considerations,it was concluded that the weighteo average dilution across the width of the plume as it diverges while flowing south would constitute a better estimate of the dilution factor instead of the calculated for the centerline of an area source as is assumed for the FS AR calculation, The calculation and the values used are shown below.

The average dilution factor at l2 miles downstream was calculated in the following manner:

4

1. The standard deviation of the radionuclide concentration in the y direction at 12 miles downstream on the surface of the lake was calculated. This calculation used the following formula:

=

2 x cy xx cy u

where 2

ey = lateral turbulera diffusion coefficient in cm /sec x = the downstream distance in cm u- = current in cm/sec Page 118 of120

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Substituting the values for ey, x, and u of 900 cm /sec,19308 m, and 12.2 cm/sec, respectively, into the equation yields C*

2 x 900 x 19308 m x 100 '"

see m 12.2 sec oy = = 168.8 meters 100 -

m

2. At distances of 0.10,0.2a, etc., off the plume centerline, the dilution factor vas calculated using the equation shown in Section 5.2 of the PBNP FSAR. The distances off the plume centerline, the calculated dilution factor, and the fraction of the area under the normal distribution curve is listed below.

Distance Off Plume Centerline Fraction of Equivalent Fraction of Total Standard Distance Area Under the Deviation (m) Curve for Interval Dilution Factor 0.1a 16.9 0.080 13.8 0.2a 33.8 0.080 14.0 0.3c 50.6 0.078 14.3 0.4a 67.5 0.075 14.7 0.5a 84.4 0.072 15.2 0.6a 101.3 0.068 15.8 0.7o 118.1 0.065 16.6 0.8o 135.0 0.060 17.6 0.9a 151.9 0.056 18.8 1.0a 168.8 0.051 20.2 1.la 185.6 0.046 21.9 1.20 202.5 0.042 23.9 1.3o 219.4 0.037 26.3 1.4a 236.3 0.032 29.2 1.5o 253.2 0.028 32.6 1.75c 295.4 0.053 44.7 2.0c 337.6 0.035 64.7 2.25o 379.8 0.021 98.4 2.5a 421.9 0.012 158.4 3.0c . 506.3 0.010 482 Totals 1.00 Page 119 of 120

- NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 11. DRAFT!

December 2,1997 OFFSITE DOSE CALCULATION MANUAL

It is assumed that the standard deviation of the radionuclide concentrations across the plume can be represented by a normal distribution curve. The fraction of the total area under the curve is that fraction of the area under the curve that lies between, for example, the interval 0.1o and 0.2o which also includes the area of the curve in the interval -0.le and -0.2a.

The average dilution factor over the width of the plume was calculated by multiplying the dilution factor at each of the locations off of the plume centerline by the fraction of the total area of the curve occupied by that interval and then summing over all the intervals. An average dilution actor of 29 was calculated, d

i Page 120 of 120

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fNUCLEhR POWER BUSINESS UNIT. LODCML lj v _ : OFFSITE DOSE CALCULATION MANUALS : Revision 11 DRAFT d

~

December 2,1997 j OFFSITE DOSE CALCULATION MANUAL :l j

~

l i

l

~

APPENDIX E - ]

f } }

.'

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'~

'4- W

? isconsin Electric submittal to the United States Nuclear Regulatory Commission, dated ;

.. October 8,1987 (VPNPD-87-430, NRC-87-104)

-The submittal consists of the letter and two Attachments, Attachment Il contains LAppendices A G. f s

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Page E-1

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APPENDIX G'

.r CALCULATIONAL METHODOLOGY FOR s!TERMINING

.i.

EXTERNAL' DOSE RATES FROM RADIONUCLIDES l AFTER-INCORPORATION INTO S0IL It 1 1 A

k) e W

' , y

'Ce 5 4_l

Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perform shielding and cose rate analyses. The QAD computer code utilizes a point kernel methodology to calculate the dose rate at a specified point due to a given source of radiation.

QAD will be used to calculate the dose rate due to standing on a plot of land utilized for sludge disposal after the radionuclides have been incorporated into the plot by plowing. The following parameters will be used in the caicu1stion:

The total Activity from all previous disposals will be corrected for radiological decay and used as the radio-nuclide source term.

Appropriate values wil' be used to represent the surface area of the plot.

The radionuclides will be assumed to be incorporated uniformly into the top six inches of soil. .

The dose rate will be calculated at a height of I seter above the ground plane at a depth of 5 centimeters in tissue. (Regulatory Guide 1.109 values).

The density of the soil will be assumed to be 1.3 grams /

cubic centimeter.

This calculated dose rate will be used to assess the radiological consequences of past disposals in conjunction with the consequences of proposed future disposals. The total radiological dose consequence of the past and the pro-posed disposal will be cor. pared to the applicable limits to insure the dose is maintained at or below the limits.

6 E-52

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N ~ NUCLEAR POWER BUSINsSS UNIT , 'ODCM-

=- OFFSITE DOSE CALCULATION MANUAL; ' Revision 11 DRAFT -

December 2,1997 - - .j i

-. OFFSITE DOSE CALCULATION MANUAlL

-J J

-- APPENDIX F - ,

}

- Modifications to the Wisconsin Dectric submittal to the United States Nuclear Regulatory

' Commission dated October 8,1987 (VPNPD-87-430, NRC-87-104), Disposal by Land ::

. Application of Sewage Sludge Coataining Minute Quantities of Radioactive Material.

t

+

A 4

W A.

4 }

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NUCLEAR POWER BUSINESS UNIT ODCM i OFFSITE DOSE CALCULATION MANUAL _ Revision 11 DRAFT .!

December 2,1997 j y OFFSITE DOSE CALCULATION MANUAL l Modification #1 to NRC Submittal .

CHANGE TO ORIGINAL SUBMITTAL Section 3.2, Disposal Procedure (page 3) j Section 3.3, Adrainistrative Procedure (page 4)

The requirements for sludge characterizatian (t'ae de'.ermination of the chemical and physical properties of the sludge' con'.ained in the sections referenced above are modified to allow characteru.ation of the sludge on an annual basis. '

BASIS / EXPLANATION The October 8,1987 submittal to the USNRC for permission to dispose of sevage treatment sludge containing minute quantities of radioactive material requires that, " prior to disposal the vaste stream vill be monitored to determine the physical and chemical properties of the sludge. ... " Subsequent to the sub-mittal and the approval by the NRC, a new Wisconsin Pollutant Discharge Elimination System (WPDES) permit was issued to the Point Beach Nuclear Plant by the Wisconsin Department of Natural Resources on November 30, 1988. Both the new WPDES permit and the Point Beach Nuclear Plant Sludge Management Plan specify an annual required frequency for the evaluation of the sludge characteristics.

The original requirement to perform the characterization of the chemical and physical properties of the sewage sludge prior to each disposal has proven time consuming and costly for Wisconsin Electric Lab Services. Preparation of special analytical standards are required to complete the characterization study. The preparation of these standards, sample preparation, and the actual analyses are all manpower intensive and difficult to perform on a timely basis. This has led to requiring overtime for Lab Services personnel and support from outside companies. In order to better utilize the resources of Lab Services while maintaining the requirements of the WPDES permit, the frequency of sludge characterization in the October 8,1987 submittal to the NRC should be changed to an annual requirement. -

This change in the required frequency for determination of the sludge characteristics does not change the requirement to analyze the sewage sludge for radionuclide content or perfona dose evaluations ' prior to each disposal, ,

Page F-2

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y NUCLEIR POWER BUSINESS UNIT ODCM :,

- OFFSITE DOSE CALCULATION.MANUALL- Revision 11 DRAFTJ- ;

December 2,1997 - i OFFSITE DOSE CALCULATION MANUALi i 1

e-L APPENDIX Cr i

i Modifications to the Wisconsin Electi ' submittal to the United States Nuclear Regulatory- l Commission dated October 8,1987 (VPNPD-87-430, NRC 87-104), Disposal by Land -

Application of Sewage Sludge Containing Minute Quantities of Radioactive Material.

l 4

4 1

k' S

~

m. -

t

_E e

4

7

'. Page G-1

= - - . _ _ _ . - _ . . _ _ . _ _ . ._ . _ _ . .

i

~ NUCLEAR POWER BUSINESS UNIT _ . ODCM l

[OFFSITE DOSE CALCULATION MANUAL 1 Revision ll DRAFT 1

~

December 2,1997 l OFFSITE DOSE CALCULATION MANUAL--- -l y

Modification #2

,k

- CHANGE TO ORIGINAL SUBMITTALL :},

Section 3.3, Administrative Procedures (Page E-10) j y

I Thh limitation on the annual volume of sludge disposal per acre contained in the section referenced above is modified to allow unlimited disposal provided the other requirements of this 1 submittal are met, 1

BASIS / EXPLANATION The October 8,1987, submittal to the USNRC for permission to dispose of sewage treatment c sludge containing minute quantities of radioactive material requires that "the annual disposal rate-

_- for each of the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR ,

! chemical composition, NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values,"

The original requirement to limit sewage sludge disposal to 4,000 gallons per acre is basea on the assumption that the sewage sludge is contaminated with Co-58 at a concentration that is ten percent of the 10 CFR Part 20 Appendix B Table 2 Column 2 value Past sewage sludge disposal experience has shown that the sludge may or may not be contaminated and, ifit is, at concentrations far below ten percent of the performed prior to each sewage sludge disposal.

With the removal of some of the land spread sites due to their use as a storage site for dry storage of spent fuel, this requirement is limiting our ability to dispose of the sewage sludge on the remaining approved land spread sites.

This removal of the annual volume of sewage sludge that may be disposed of per acre on approved land spread sites does not change the requirement to analyze the sewage sludge for radionuclide content or perfonn dose evaluations prior to each disposal, This change was evaluated under SER 95 057, " Removal oflicensee Commitment Involved

- With Sewage Sludge Disposal," 4/20/95, 5

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NUCLEAR l'OWER BUSINESS UNIT ODCM .

OFFSITE DOSE CALCULATION MANUAL- Revision 11 DRAFT

' December 2,1997 -

OFFSITE DOSE CALCULATION MANUAL l MODIFICATION #2

Depth to f,roundwater and bedrock shall be greater than 3 feet from the land surface elevation during use of any site.

Sludge shall not be land spread in a floodway.

Sludge shall not be land spread within 50 feet of a property line road-or ditch unless the sludge is incorporated with the soil, in which case a sinimum separation distance of at least 25 feet is required,

The pH of the sludge soil sixture shall be siaintained at 6.5 or higher.

Low areas of the appreved fields, subject to seasonally high ground-water levels, are excluded from the sludge application.

~ Crops for human consumption shall not be grown on the land for up to one year following the application of the sludge.

The sludge shall be plowed, disked, infected or otherwise incorporated into the surface soil layer at appropriate intervals.

. The flexibility implied in the latter provision for soil incorporation is intended to allow for crops which require more than a one year cycle.-

For the Point Beach disposal sites, alfalfa is a common crop which is harvested for several years after a single planting. Sludge disposal on an alf alfa plot constitutes good fertilization, but tha plot cannot be plowed without destroying the crop. The alfalfa in this case sids in binding the layer of sludge on the surface of the plot. At a minimum, however, plowing (or disking or other method of injection and mixing to a nominal depth of 6 inches) shall os done prior to planting any new crop, regardless of the crop.

3.3 Administrative Procedures Complete records of each disposal will be maintained. These records will include the concentration of radionuclides in the sludge, the total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical co0 position determinations, and all dose calculations.

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-The annyal disposal rate for each of the approved land spread sites wi l l be 'Hohed " ' ^^^ - " -- '- - - provided WDNR chemical compost- -

tion NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values.

The farmer leasing the site used for the disposal will be notified of the applicable restrictions placed on the site due to the land spreading cf sewage sludge.

4.0 Evaluation of Environmental Impact 4.1 Site Characteristics 4.1.1 Site Topocraphy The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc CoJnty,. Wisconsin, on the E-10 Page G-3

C NUCLEAR POWER BUSINFSS UNIT -ODCM--

g LOFFSITE DOSE CALCULATION MANUAL :. ,

Revision 11 DRAFT 1

- December 2,1997 :

~ OFFSITE DOSE CALCULATION MANUAL --

k

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_4._

' APPENDIX H-:-

Modifications to the. Wisconsin Electric submittal to the US Nuclear Regulatory Commission dated

October'8,1987 (VPNPD-87 430,-NRC 87104),- Disposal by Land Application of Sewage Sludge 1 Containing Minute Quantities of Radioactive Material.

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NUCLEAR POWER BUSINESS UNIT ODChi

~ OFFSITE DOSE CALCULATION h1ANUAL - Revision 11 DRAFT December 2,1997 g _

OFFSITE DOSE CALCULATION NIANUAL h!odiGcation #3 to NRC Submittal Chance to Oricinal Submittal Section 3.2 of Attachment II of the October 8,1987 letter to the NRC contains the commitment to perform a gamma isotopic analysis of sewage sludge samples prior to every sludge disposal on land surrcunding PBNP. The analytical results are to be used to evaluate the dose consequences of die radionuclides entering the environmer t via this disposal pathway. As described in ODChi Section 7, the requirement for a radioisotopic analysis of the sewage sludge prior to every disposal on land surrounding PBNP is modined if the sludge has been shown to be clean and there is no reason to believe that the sludge is contaminated.

Dasis/Exritanation Small Ci quantities of PBNP licensed materials (Co-58/60, Cs-134/137, Cr-51, and hin-54) were found in PBNP sewage treatment plant (STP) sludge. Pursuant to of 10 CFR 20.302(a), Wisconsin Electric applied to the NRC for permission to dispose of the licensed material by applying the sludge to Wisconsin Electric land surrounding PBNP. In the October 8,1987 ipplication letter, Wisconsin Electric committed to ganuna isotopic analysis of the sludge prior to every disposal in order to evaluate the dose consequences of this disposal and to compare radionuclide concentrations to the 10 CFR 20, Appendix B, maximum emuent concentrations. However, such analyses are not required if the sludge does not contain licensed material. If there is no reason to believe that the sludge is contaminated and if there is no pathway from the RCA to the STP, then there is no reason to analyze the sludge for radionuclides once it has been shown to be clean. Administrative controls and engineering modiGeations to PBNP have removed the pathway from the RCA to the STP as verified by subsequent analyses of the sludge under conditions required to obtain the environmental LLDs. These analyses have not revealed radionuclif s attributable to PBNP. Pursuant to NRC HPPOS-221, a substance is clean if analyses under analytical parameters necessary to achieve the environmental LLDs does not f'

reveal any licensed material. These LLDs define how hard you have to look. Below this detection level,

. . .the probability of undetected radioactivity is negligible and can be disregarded when considering the practicality of detecting such potential radioactivity from natural background. . ." (Docket No. 50-206, letter to J. E. Dyer from L. J. Cunningh:m dated September 6,1991). Therefore the NRC criteria are met and there is tro longer any reason to believe that the STP sludge is contaminated. However if plant conditions should change in a manner compromising the NRC criteria, radiological analysis must be made prior to each STP sludge land application until such time that the clean criteria are satisfied pursuant to subsequent NRC guidance.

Page H 2

Attachment to NPL 97-0804 Page1of1 ATTACH 51ENT 4 SUPPLE 51ENT TO TSCR id2 The proposed amenoments in TSCR 182 allow additional management flexibility in meeting our commitments to ANSI N18.1-1971 as modified by the Technical Specifications for the Health Physics hianager position This proposed amendment, as described in letter dated November 17, 1995, changed the position title from Health Pnysics hianager to Health Physicist. By letter dated July 29,1996, we clarified our proposed amendment to stipulate that the Health Physicist must be a line supervisor.

A simplified version of the current Heath Physics organization chart is attached. As shown on that figure, the Health Physicist is also the acting radiation protection manager responsible for directly supervising the Health Physics operational staff. The Health Physicist's responsibilities include daily oversight and technical direction to Health Physics supersisors and specialists on the implementation of the PBNP radiation protection program. The Health Physicist performs continuous assessment of the radiation protection program to meet regulatory and technical requirements. The Health Physicist is a member of the hianager's Supersisory Staff and the Exposure Reduction committee. The professional requirements for the Health Physicist,just as they were for the Health Physics hianager, will continue to be delineated in Technical Specification 15.6.3.2.

Additionally, we identified another reference in the specifications to the title " Health Physics hianager" which should have been included in the proposed amendment. This reference appears in specification 15.6.5.1.3. This change is editorial in nature, and consistent with the original amendment request.

The additional edited Technical Specification page with the proposed revision is attached.

We have reviewed the Safety Evaluation and Determination of No Significant Hazards included as attachments to our November 17,1995 request and have determined that this modification to our submittal does not modify the conclusions contained in the evaluations. These evaluations remain applicable to this change. The proposed amendments continue to be administrative only and continue to meet the categorical exclusion criterion set forth in 10 CFR 51.22(c)(10).

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? NUCLEAR POWER BUSINESS UNIT:- ..-

Point Beach Nuclear Plant! ..

Health Physics

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. PLANT MANAGER 'a t.__.-__3-_______

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IIEAliff PilYSICS {.

The Acting Radiadon Protection MANAGER l .p Manager reports directly to the Plant !

Manager for issues relauve to Die Radiation Protection Program at Point -

Beach tJuclear Plant. . 1 ttE Allll PilV SICisT (Actirig itsdiation Protecbtei Marsager)

HEALTH PHYSICS '

OPERATIONAL .

STAFF f

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.; s 15.6.4 TRAINING 15.6.4'.1 ' A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

15.6.5 REVIEW AND AUDIT 15.6.5.1 Manager's Supervisory Staff

-15.6.5.1.1 The Manager's Supervisory Staff (MSS) shall function to advise the Manager on all matters related to nuclear safety.

15.6.5.1.2 The Manager's Supervisory Staff shall be selected and designated by the Manager from a list of qualified individuals in the following disciplines:

Operations Maintenance Health Physics Engineering Licensing Training Chemistry 15.6.5.1.3 Each individual representing a MSS discipline shall meet or exceed the qualification requirements specified in Section 4.2 of ANSI N18.1-15'71, except as described in Specification 15.6.3.2 for the Health Php!= P=ger Physicist.

Unit 1 Amendment No.170 15.6.4/5-1 January 8,1997 Unit 2 - Amendment No.174

Attachmut to NPL 97 0804 Page1ofI ATTACll51ENT S SUPPI.EhlENT TO TSCR 195 ,

Technical Specifications change request (TSCR) 195, as described in letters from Wisconsin Electric to the Nuclear Regulatory Commission (NRC) dated October 16,1996, proposes to chang Technical Specifications for the radiation protection program to update the references to specific sections of 10 CFR 20 to the new paragraph numbers in the revised Part 20. In a letter dated August 15,1997, the NRC provided a request for additional information that included two questions pertaining to this Technical Specifications change request. These questions are stated as follows:

8. New guidance (Attachment D) was provided to NEl on Aprii 9,1997, on TS administrative control for a high radiation area. This new guidance includes 10 CFR 20 changes. Please review the new guidance and revise your submittal as appropriate.

9. If you choose not to revise your submittal per the new guidance, please describe how your program complies with the new Part 20 requirements for high radiation ara with dose rates greater than 1.0 rem / hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads / hour at I meter from the radiation source or from any surface penetrated by the ridiation.

Based on a review of the guidance contained in Attachment D of the NRC request for additional information we conclude that the new guidance is sufficiently consistent with the current Technical Specifications contained in Section 15.6.11 that we propose to directly incorporate this guidance into the PBNP Technical Specifications.

The additional edited Technical Specification pages with the proposed revisions are attached.

We have reviewed the Safety Evaluation and Determination of No Significant liazards included as attachments to our October 16,1996, request and have determined that this mo'dification to our submittal does not modify the conclusions contained in the evaluations. These evaluations remain applicable to this change. The proposed amerdments continue to be administrative only and continue to meet the categorical exclusion criterion set fonh in 10 CFR 51.22(c)(10).

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i '15.6.11 RADIATION PROTECTION PROGRAM i Specification . -l Radiological control procedur6s shall be written and made available to all !

station personnel and shall state pemissible radiation exposure levels.

The radiation protection program shall meet the requirements of 10 CFR 20.

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Parnerach 20.160L - centrol of - Accean to Mich Radiatien Areas..

As provWed in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be "

applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

High Radiation Areas with Dose Rates Not Exceeding 1.0 renvhour at 30 Centimeters from f the Radiation Source or from Any Surface Penetrated by the Radiation;

s. Each entryway to such an area shall be barricaded and conspleuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment. !

i

b. Access to, and aWities in, each such area shall be controlled by means of i Radiation Work . mit (RWP) or equivalent that includes specification of f f radiation dose rates in the immediate wt,rk area (s) and other appropriate

't radiation protection equipment and measures,

c. Individuals qualified in radiation protection procedures (e.g., health physics r technicians) and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are following plant radiation protection

procedures for entry to, exit from, and work in such area.

d. Each individual or group entering such an area shall possess:

, 1. A radiation monitonng device that continuously displays radiation dose rates in the area; or

2. A radiation monitonng device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarrn setpoint is reached, with an oppropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose to a remote receiver monitored by radiation protection l personnel responsible for controlling personnel radiation exposure within the area, or 1

- Unit 1 Amendment 15.6.11-1 -

~

Unit 2' Amendment ..

1

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic ,

dosimeter) ,and, (i) Be under the survel"ance, as specified in the RWP or i equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation ;

monitoring device that continuously displays radiation dose rates In the area; who is responsible for controlling personnel exposure )

within the area, or t

e (ii) Be unAr the surveillance as spec!fied in the RWP or equivalent, while in the area, by means of closed circuit television, of l personnel qualified in radiation protection procedures, -

responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individualin the area.

e. Except for individuals qualified in radiation protection procedures, entry into such areas shall be made onry after dose rates in the area have been ,

determined and entry personnel are knowledgeable of them.

High Radiation Areas with Dose Rates Greater than 1.0 rem / hour at 30 Centimeters from the h Radiation Source or from Any Surface Penetrated by the Radiation, but less than 500 rads / hour at 1 Meter from the Radiation Source or from Any Surface Penetrated by the Radiation: :

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the :

administrative control of the shift supervisor, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel

or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that locludes specification of radiation dose rates in the ,

immediate work area (s) and other appropriate radiation protection equipment [

and measures.

~

- c. Individuals qualified in radiation protection procedures may be exempted from tha requirement for an RWP or equivalent while performing radiation surveys in .;

such areas provided that they are following plant radiation protection 4 procedures for entry to, exit from, and work in such areas.

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d. Each individual or group entering sucii an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is i reached, with an appropriate alarm setpoint, or

2. A radiation monitodng device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in .

, radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlkng personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, wh!!e in the area, by means of closed circuit television, of personnel qualified in radiatien protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and contro; every individualin the area, or

4. In those cases where options (2) an (3), above, are impractical or determined to be inconsistent with the *As Low As is Reasonably Achievable" principle, a radiation monitonng device that continuously displays radiation dose rates in the area.

e. Except for individual qualified in radiation protection procedures, entry into such areas shall be made only after dose rwio. ;r, the area have been determined and entry personnel are knowledgeable of them,

f. Such individual areas that are within a larger area that is centrolled as a high radiation area, where no enclosure exists for the purpose of locking and where no enclosure can reasonably ise constructed around the individual area need not be controlled by a locked door or gate, but shall be barricaded and conspicuous, clearly visible flashing light shall be activated at the area as a waming device.

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ML20203K323

Text

SUMMARY

SUMMARY

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