ML20212A026
| ML20212A026 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/13/1987 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20211R050 | List: |
| References | |
| PROC-870113, NUDOCS 8703030269 | |
| Download: ML20212A026 (126) | |
Text
{{#Wiki_filter:- ODCM
. .- Rev. 8 Page 1 of 126 O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) REV. 8 DOCKET NO. 50-282 and 50-306 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA
- 8703030269 870228 l PDR ADOCK 05000282 R ppg .
OPERATIONS COMMITTEE FINAL REVIE ATE: '//-/// 96 REVIEWED .
/_ , #d # DATE: / [c2O d REVIEWED BY: \ DATE: / 7 3ehera Supt (J1a^ Prot & Chem APPROVED,BY: '
( DATE: /- 9'[7 Supt Rad Prot IBM 1
7
~
o' , OUCH Rsv. 8 Page 2 TABLE OF CONTENTS
) Section Title '
. Page
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Table of Contents........................ . . . . . . . .?. 2 I f List of Figures.......... ........................,.3 List of Tab 1es..................................... 4 4 Record of Revisions................................ 5 e
/
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1.0 INTRODUCTION
................................................. 6 . i 6 2.0 LIQUID EFFLUENTS............................................. 2.1 Monito'r Alarm Setpoint Determination.................... 6 2.2 Liquid Effluent Concentration - Compliarce with 10 CFR 20......................................... 14 2.3 Liquid Effluent Doses - Compliarce with 10 CFR 50.........................,..................... 15 References............................................. 19 O 3.0 GASEOUS ErFtuENTS....................................... ... 22 3.1 Monitor Alarm Setpoint Determination................... 22 3.2 Gaseous Effluent Dose Rate - Compliance with
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1 0 ' C F R' 2 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9 3.3 Gaseous Effluent Doses - Compliance with 1 10 CFR 50.............................................. 32 References............................................. 37 4.0 INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141............ 58 5.0 RADIATION ENVILdNMENTAL MONITORING PROCRAM... ...,.......... 60 , i APPENDIX A - Meteorological Dispersion Parameters........... 68 I APPENDIX B - Joind(Frequency Distribution Table'4. . . . . . . . . . . 107 APPENDIX C - Dose Parameter-s for Radiciodines, Particulates and Tritium........... .......... 115 i i f IBM L
- - ~- -- - - , - , - - -,------,.--c-.. , - , - . --,,,--.-r- - - - - - , . . - -
ODCM Rev. 8 Page 3 LIST OF FIGLTES
- 1. Page Figure i 5.1-1 Prairie Island Nuclear Generating Plant .t Radiation Environmental Monitoring Program........ 65 5.1-2 Site Boundary TLD Locations....................... 66 t
s 5.1-3 4-5 Mile Ring, Control, and Special Interest TLD Locations............................ 67 i! k O l I I I I ( i I 9
~)
IBM e
g o ODCM Rev. 8 Page 4 LIST OF TABLES
? Page s
v
'v s '; Tables
. s y 2.1'-1 Liquid Source Terms for PNGP...................... 13
; 2.3-1 Ag Value s fo r the ' PNGP . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0
, 3.l'-l Monitor Alarm Se'tpoint Determination for PNGP..... 26 s
3.1-2 Gaseous Source Terms for PNGP . . . . . . . . . . . . . . . . . . . . . 27 3.1-3 ' Dose Factors and Constants........................ 27 3.2-1 Pg Values for the PNGP............................ 31 . 3.3-1 Dose Factors for Noble Gases and Daughters........ 38 3.3-2 R g Values for the PNGP - Ground, All Ages......... 39 i 3.3-3 R Values for the PNGP - Vegetable, Adult......... 40
) g 3.3-4 ,
R g Values for the PNGP - Vegetable, Teen.......... 41 3.3-5 R. Values for the PNGP - Vegetable, Child......... 42 1 3.3-6 R. Values for the PNGP - Meat, Adult.............. 43 1 3.3-7 R. Values for the PNGP - Meat, Teen............... 44 1 3.3-8 R. Values for the PUGP - Meat, Child.............. 45 1 3.3-9 R. Values for the PNGP - Cow Milk, Adult.......... 46 ()
- 3.3-10 3.3-11 R Values for the PNGP - Cow Milk, Teen........... 47 R. Values for the PNGP - Cow Milk, Child.......... 48 1
+
3.3-12 R Values for the PNGF - Cow Milk, Infant......... 49
; g
! 3.3-13 \' R. Values for the PNGP - Goat Milk, Adult......... 50 1
3.3-14 < R. Values for the PNGP - Goat Milk, Teen.......... 51 1 3.3-15 ' HR Values for the PNGP - Goat Milk, Child......... 52 g 3.3-16 R. Values for the PNGP - Goat Milk, Infant........ 53 1 3.3-17 R. Values for the PNGP - Inhalation, Adult........ 54 1 3.3-18 R. Values for the PNGP - Inhalation, Teen......... 55 1 3.3-19 R. Values for the PNGP - Inhalation, Child........ 56 1 l 3.3-20 R. Values for the PNGP - Inhalation, Infant....... 57 l 1
, 5.1-1 PNGP - Radiation Environmental Monitoring Program Sampling Locations........................ 61 l
l ! \ IBM
'~ = . _ _
ODCM j Rev. 8 Page 5 RECORD OF REVISIONS Revision No. Date Reason for Revision Original June 7, 1979 1 April 15, 1980 Incorporation of NRC Staff comments and correction of miscellaneous errors 2 August 6, 1982 Incorporation of NRC Staff comments 3 February 21, 1983 Change in milk sampling location 4 November 14, 1983 Change in milk sampling location and change in cooling tower blowdown 5 March 27, 1984 Change Table 3.2-1 6 February 14, 1986 Change in location to collect cultivated crops (leafy green veg.) and removal of meat animals from the \_ land use census. 7 July 31, 1986 Retype and format ODCM. No change in content. 8 January 8, 1987 Addition of Discharge Canal Monitor Setpoint calculation. O IBM
ODCM Rev. 8 Page 6
1.0 INTRODUCTION
This Offsite Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Prairie Island Nuclear Generating Plant (PNGP) to assure compliance with certain portions of PNGP's Operating Technical Specification. These portions are those related to liquid
- and gaseous radiological effluents. They are intended to show compliance with 10 CFR 20, 10 CFR 50.36A, 10 CFR 50,
' Appendix A (GDC 60 & 64) and Appendix I, and 40 CFR 190. This ODCM is based on " Radiological Effluent Technical Specifications for PWR's (NUREG-0472, October, 1978),"
" Preparation of Radiological Effluent Technical Specifica-tions for Nuclear Power Plants' (NUREG-0133, October 1978),"
and other inputs from the Nuclear Regulatory Commission (USNRC). Specific plant procedures for implementation of this manual are provided elsewhere. These procedures will be utilized by the operating staff of the PNGP to assure compli-ance with the Technical Specifications. Also included in thic manual is information related to the Radiological Environmental Monitoring Program (REMP) in the form of Figures 5.1-1, 5.1-2, 5.1-3 and Table 5.1-1. These figures and table designate specific sample types and locations currently used to satisfy the technical specification require-l ments for the REMP. They are subject to change based on the results of the periodic land use census. Although the ODCM has been prepared as generically as possible in order to minimize the need for future revisions, some changes to the ODCM may be required in the future. Any such changes will be properly reviewed and approved as required by the PNGP Technical Specifications. 2.0 LIQUID EFFLUENTS 2.1 Monitor Alarm Setpoint Determination
;- This procedure determines the monitor alarm setpoint that indicates if the concentration of radionuclides in l
- the liquid effluent released at the site boundary exceeds the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other
- than dissolved or entrained noble gases or exceeds a i
concentration of 2 x 10-4 pCi/ml for dissolved or i entrained noble gases. Monitor high alarm or isolation setpoints will be established in one of these ways: ! ( a. Monthly calculation of setpoints using the methodology of Sections 2.1.1 and 2.1.3. i IBM
ODCM i Rev. 8 ' Page 7
- b. Calculation of alarm setpoint based on analysis prior to discharge using methodology of Section 2.1.2.
- c. Alarm setpoint determined using methodology of Sections 2.1.1 and 2.1.3 assuming all radionuclides [
have an MPC of IE-7 pCi/ml. No recalculation of setpoints is necessary unless an increase in alarm setpoint is desired.- PWR GALE Code source terms (Table 2.1-1) may be used if there were no detectable isotopes in the previous month or in the analysis prior to release. If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value. 2.1.1 Liquid Effluent Monitor Setpoints The following method applies when determining the isolation setpoints for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid Monitor - Unit 1 (lR-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19) during all operational conditions when the radwaste discharge flow rate is maintained g-] constant at the maximum design flow rate. (_j 2.1.1.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.
- a. Determine the liquid source terms that are representative of the
" mix" of the liquid effluent.
Liquid source terms are the total curies of each isotope released during the previous month. Table 2.1-1 source terms may be used if there have been no liquid releases.
- b. De'termine S. (the fraction of the
' total radiolctivity in the liquid effluent comprised by radionuclide "i") for each individual radionuclide in the liquid effluent. A i S i=1 i A. 1 (2.1-1) () Af = The radioactivity of radionuclide "i" in the liquid effluent. IBM
ODCM Rev. 8 Page 8 2.1.1.2 Determine C (the maximum acceptable
total radio 3ctivity concentration of all (N radionuclides in the liquid effluent prior to dilution (pCi/ml)).
C = F t f' S i (2.1-2) MPC. 1 i F = Dilution water flow rate (gpm)
= 67,300 gpm from cooling tower blowdown f = The maximum attainable discharge flow rate prior to dilution (gpm)
= 60 gpm from the ADT tank pump (2)
= 100 gpm from the CVCS tank pump (2)
= 60 gpm from the SGBD tank pump (2)
MPC. = The liquid effluent radioactivity O, 1 concentration limit for radionuclide "i" (pCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1, obtained from Reference 3. 2.1.1.3 Determine C (the maximum acceptable total radioIctivity concentration of the radionuclides (minus tritium) in the liquid discharge prior to dilution (pCi/ml)). C, = C t - (C tg S) (2.1-3) SH =inThe fraction of the total radioactivity the liquid effluent contributed l by tritium and other radionuclides that do not emit gamma or X-ray radiation. l 2.1.1.4 Determine C.R. (the calculated monitor count rate above background attributed - to the radionuclides (nepm)). C.R. is obtained by using the applicable ,! Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate that corresponds to the " adjusted" i total radioactivity concentration (C,). IBM
-- , , , - . - , , . . . . _, ,,.m _ . ,. . , , . _ , . _ _ , , . _ . , . , . _ _ . _ - , _ _ . _ _ _ _ _ - _ e ,_._ -,._ ._.- - _ ,. _..-_.... ,..- .._ ,. -.. . .-
ODCM Rev. 8 Page 9 2.1.1.5 Determine HSP (the monitor high alarm setpoint above background (nepm)).
)
HSP = T,C.R. (2.1-4) , T* = the Fraction of the radioactivity from site that may be released via each release point to ensure that the site boundary dose rate limit is not exceeded due to simultaneous releases from several release points.
= 0.90 for the Waste Effluent Liquid Monitor (R-18) ,
= 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 1 (lR-19)
= 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19) 4
. T values may be revised from the 4 vIlues given above. The summation of all the T values for active release points shall not be greater than unity.
- ( '
- 2.1.1.6 The monitor high alarm setpoint above background (nepm), shall be set at or below the HSP value.
2.1.2 Setpoint Based on Analysis of Liquid Prior to Discharge (Optional) This method may be used in lieu of the method in Section 2.1.1 to determine the setpoints for the maximum acceptable discharge flow rate prior to i dilution and to determine the associated high alarm setpoint based on this flow rate for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid Monitor - Unit 1 (lR-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19), during all operational conditions. , 2.1.2.1 Determine f (the maximum acceptable discharge flow rate prior to dilution (gpm)). f = 0.8 F T, C (2.1-5) MPC f 1 4 1BM
ODCM Rev. 8 Page 10 F = Dilution water flow rate (gpm) (} = 67,3000 gpm from cooling tower blowdown C. = Concentration of radionuclide "i" in 1 the liquid effluent prior to dilution (pCi/ml) from analysis of the liquid effluent to be released. MPCf = The liquid effluent radioactivity concentration limit for radionuclide "i" (pCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1 from Reference 3. T" = Fraction of the radioactivity from the site that may be released via each release point to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points. Refer to
- Section 2.1.1.5.
2.1.2.2 Determine the monitor setpoint based on the radionuclide mix of the liquid effluent. () a. Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (nepm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate point that corresponds to the " adjusted" to.tal radioactivity concentration (C,). l C" = The total radioactivity concen- ! tration of the radionuclides (minus tritium and other radionuclides that are only beta emitters) in the liquid discharge prior to dilution (pCi/ml) as determine using Equation 2.1-3. (C and S beingdeterminedbhanalyNis of undiluted liquid effluents.) IBM
l ODCM Rev. 8 I Page 11
- b. Determine HSP (the monitor high alarm setpoint above background
() (_j (ncpm)). HSP = C.R. (2.1-6) g 0.8 = A correction factor to increase the monitor setpoint to prevent spurious alarms caused by deviations in the mixture of radionuclides that affects monitor response.
- c. The monitor high alarm setpoint above background shall be set at or below this HSP value when this optional method is selected. The maximum discharge flow shall not exceed the value of f as determined in Section 2.1.2.1 when this optional method is selected.
2.1.3 Discharge Canal Monitor The following method determines the high alarm setpoint for the Discharge Canal Monitor (R-21) O during all operational conditions. 2.1.3.1 Determine the " mix" (radionuclides and composition) of the liquid effluent.
- a. Determine the liquid source terms that are representative of the
" mix" of all liquids released into the discharge canal. Liquid source terms are the total curies of each isotope released during the previous month. Table 2.1-1 source terms may be used if there have been no liquid releases,
- b. Determine Si (the fraction of the total radioactivity of all liquids released into the discharge canal
- comprised by radionuclide "i") for each individual radionuclide released into the discharge canal.
Si = Ai I Ai O Ai = The radioactivity of radionuclide "i" released into the discharge canal. 7 1BM
ODCM Rev. 8 Page 12 2.1.3.2 Determine Cd (the maximum acceptable
'~N diluted radioactivity concentration of m- ) .
all radionuclides released into the discharge canal (pCi/ml)). Cd = 1 Si j[MPCi i MPCi = The liquid effluent radioactivity concentration limit for radionuclide "i" (pCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1, obtained from reference 3. ' 2.1.3.3 Determine Cm (the maximum acceptable total radioactivity concentration of the radionuclides (minus tritium) released into the discharge canal (pCi/ml)). Cm = The fraction of the total radioactivity released into the discharge canal comprised of tritium and other radionuclides that do not emit gamma or X-ray radiation.
- 2.1.3.4 Determine C.R. (the calculated monitor s_-
count rate above background attributed to the radionuclides (ncpm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor
! Calibration file. C.R. is the count l
rate that corresponds to the " adjusted" total radioactivity concentration (Cm). 2.1.3.5 The monitor high alarm setpoint above background (nepm) shall be set at or above the C.R. value. O IBM
ODCM Rev. 8 Page 13 p TABLE 2.1-1 LIQUID SOURCE TERMS WASTE EFFLUENT (0) SGBD I) RADIONUCLIDE MPC (pCi/ml)(2) (A.)(Ci/Yr) , (A.)(Ci/Yr) Mo-99 4E-5 6.42E-3 1.415E-2 1-131 3E-7 3.061E-2 4.11E-2 Te-132 2E-5 2.12E-3 3.61E-3 1-132 8E-6 2.83E-3 1.88E-2 1-133 lE-6 2.365E-2 4.856E-2 Cs-134 9E-6 1.464E-1 4.047E-2 1.792E-2 1-135 4E-6 4.84E-3 Cs-136 6E-5 5.743E-2 1.862E-2 Cs-137 2E-5 8.214E-2 2.69E-2 All Others lE-7 0 2E-5 H-3 3E-3 1.89E2 1.41E2 Noble gases 2E-4 - - Total 1.894E2 1.412E2 t O l l I O IBM
ODCM Rev. 8 Page 14 2.2 Compliance With 10 CFR 20 In order to comply with 10 CFR 20, the concentrations of radionuclides in liquid effluents will not exceed the maximum permissible concentrations (MPC) as defined in Appendix B, Table II of 10 CFR 20. For continuous releases, the alarm trip setpoints discussed in Section 2.1 will assure that these concentrations are not exceeded. For batch releases, concentrations of radioactivity in effluents prior to dilution will be determined, providing protection in addition to the alarm trip setpoint discussed in Section 2.1 Concentration in diluted effluents will be calculated using these results. 2.2.1 Continuous Releases Continuous liquid releases can occur from PNGP through steam generator blowdown. The alarm trip setpoints discussed in Section 2.1 will assure that releases from this pathway will not exceed the limits of 10 CFR 20. Other minor releases of a continuous nature have occurred at PNGP through the turbine building sump system. These releases were minor and are not expected to occur in the future. However, a continuous composite sampler will be maintained (("N) at the discharge from the turbine building sump with samples being taken and analyzed weekly. If these samples indicate detectable levels of radionuclides, the methodologies given in Section 2.2.2 will be applied to the turbine sump weekly releases and the limit in Equation 2.2-2 will be lowered to account for this source term. 2.2.2 Batch Releases To further show compliance with 10 CFR 20, the radioactivity content of each batch release will be determined prior to release. The concentration of the various radionuclides in the batch release prior to dilution, is divided by the minimum dilution flow to obtain the concentration at the site boundary. This calculation is shown in the following equation: C R Conc.1 = f (2.2-1) MDF . O IBM
- l
ODCM Rev. 8 Page 15 where A (_,/ Concg = concentration of radionuclide i at the site boundary, pCi/ml; C. = concentration of radionuclide i in the 1 potential batch release, pCi/ml; R = release rate of the batch MDF = minimum dilution flow (=67,300 gpm) The projected concentration at the site boundary is compared to the MPCs in Appendix B, Table 11 of 10 CFR 20 which are given in Table 2.1-1. Before a release may occur, Equation 2.2-2 must be met for all isotopes. y Conc u i
~
< 0.9 (2.2-2) i MPC f
MPC f
= Maximum permissible concentration of radionuclide i from Appendix B, Table II of 10 CFR 20. pCi/ml V
The summation has been reduced from 1.0 to 0.9 to account for simultaneous continuous releases from steam generator blowdown as given in Section 2.1.1.5. As noted earlier, this fraction may be adjusted based on experience. The summation of all source terms shall not be greater than 1.0 of the 10 CFR 20 limit. 2.3 Liquid Effluent Doses - Compliance with 10 CFR 50 Doses resulting from liquid effluents will be calculated monthly to show compliance with 10 CFR 50. A cumulative i summation of total body and organ doses for each calendar quarter and calendar year will be maintained as well as projected doses for the next month. The limits of 10 CFR 50 are on a per reactor unit basis. The liquid radwaste system at PNGP is shared by both reactor units making it impossible to separate the - releases of the two units. The releases that can be l separated by unit, steam generator blowdown and turbine building sump releases, contribute a very small portion Os of the total liquid releases from PNGP. Therefore, for compliance with 10 CFR 50 the releases from both units will be summed and the limits of Appendix I will be doubled. IBM ( l _ _ - . . , , _ . . _ _. __ - _ _ _ _ _ _ _ . _ , .- _. . - _ _ . - . - , , _ . , _ , , _ - .- _~
ODCM Rtv. 8 Page 16 2.3.1 Determination of Liquid Effluent Dilution (9 s To determine doses from liquid effluents the near field average dilution factor for the period of release must be calculated. This dilution factor must be calculated for each batch release and each continuous release mode. The dilution factor is determined by: Rk F = (2.3-1) k X ADF k where R k
= release rate of the batch or continuous releases during the period, k, gal; ADF = actual dilution flow during the k time period of release k, gal.
The value of X is the site specific factor for the mixing effect of the PNGP discharge
/T operating in This structure. value is the closed 10 for cycle PNGP cooling while (1) mode. \-s/
TheproductofXandADFuislimitedto1000 gpm). Therefore, since blowdown cfs (4.5 x 10
- flow in closed cycle is 150 cfs, the denominator 5 of Equation 2.3-1 is always 4.5 x 10 in closed cycle. In once through or helper mode, the value of X is reduced to 1.0.
2.3.2 Dose Calculations The dose contribution from the release of liquid effluents will be calculated monthly. The dose contribution will be calculated using the following equation: where: Dr = IIA gt t k ik F k ( * ~} k1 I where: i Dt = the dose commitment to the total body or any organ I, from the liquid effluents for the period O of release, mrem; I l IBM
i ODCM Rev. 8 Page 17 C = the average concentration of ik radionuclide, i, in undiluted O_, s liqpid effluent for liquid release k, pCi/ml;
= the site related ingestion dose A*1 commitment factor to the total ' body or any organ I for each identified principal gamma and beta emitter, mrem /hr per pCi/ml; F = the near field average dilution k factor for C during liquid
- effluentrelkIsek,
- t = the duration of release k, hours.
, k The dose factor A was calculated for an adult for each isotope bIing the following equation:
i
$ Ag = 1.14 x 105 [21BF g DFf7) (2.3-3) where:
6 pCi x 10 3 r 1.14 x 10 5 = 10 ml x 1 yr ; pCi I 8760 hr O 21 = adult fish consumption, Kg/yr; i
- BF i
= bioaccumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1 (5) pCi/Kg per.pCi/1; i
DF iT
= dose conversion factor for
! radionuclide i for adults for a particular organ I from Table l E-11 of Regulatory Guide 1.109 Rev. 1, (5) mrem /pCi. values for an adult at the PNGP A table of A *in Table 2.3-1. arepresenteb Mississippi River water is not used as a potable water supply i within 300 miles downstream of the PNGP. Wells ' are used for irrigation downstream of the plant. 2.3.3 Cumulation of Doses u l Doses calculated monthly will be summed for i comparison with quarterly and annual limits. The monthly results should be added to the doses l cumulated from the other months in the quarter of interest and in the year of interest for the combined releases of both reactor units. The following relationships should hold: IBM 1 _ . . - - . - _ - . - . - . - - - . _ , - , - - . - , . - - _ _ - - . . - _ ~ . . . . . - - - - - . _ . . - - - - - - _ - . -
ODCM Rev. 8 Page 18 For the quarter, ( D t
< 3.0 mrem total body (2.3-4)
D 7
< 10 mrem any organ (2.3-5) o For the calendar year, D
7
< 6.0 mrem total body (2.3-6)
D 7
< 20 mrem any organ (2.3-7)
The quarterly limits given above represent one half of the annual design objective. If these quarterly or annual limits are exceeded, a special report should be submitted to the USNRC identifying the cause and corrective action to be taken. If twice the quarterly or annual limits are exceeded, a special report shall be submitted showing compliance with 40 CFR 190. 2.3.4 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly. If A the projected doses for the month exceed 2 (_) percent of Equation 2.3-6 or 2.3-7, additional components of the liquid radwaste treatment system will be used to process waste. The projected doses will be calculated using Equation 2.3-2. The dilution factor, F will becalculatedbyreplacingthetermADFh,in Equation 2.3-1 with the term MDF from Equation 2.2-1. The totaf source term utilized for the most recent dose calculation should be used for the projections unless information exists indicating that actual releases could differ significantly in the next month. In this case, the source term would be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month. O IBM
ODCM Rev. 8 Page 19 REFERENCES O 1. " Prairie Island Final Environmental Statement," USAEC, May, 1973, p. V-26.
- 2. "NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis - Supplement No. 1 - Docket No. 50-282 and 50-306,"
Table 2.1-1.
- 3. "10 CFR 20," Appendix B, Table II, Column 2.
- 4. "NSP - Prairie Island Nuclear Generating Plant, Appendix 1 Analysis - Supplement No. 1 - docket 50-282 and 50-306," July 21, 1976, Table 2.1-2.
o
- 5. U. S. Nuclear Regulatory Commission, " Regulatory Guide 1.109
- Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10 CFR 50, Appendix 1," Rev. 1, 1977.
O I I O 1 I IBM
. - _ _- _ - __ - . - - .-- . - - - - - = . . - - - . - _ . - -_
CDCM Rev. 8 Page 20 I, l TABLE 2.3-1 i i l \
/
A" VALUES FOR THE(MREM PRAIRIE /HR ISLAND PER pCI/ML) NUCLEAR GENERATING PLANT h'JCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l 1H 3 0.00E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 ,
! 6C 14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 l 4 11NA 24 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 24CR 51 0.00E-01 0.00E-01 1.27E 00 7.61E-01 2.81E-01 1.69E 00 3.20E 02
! 25MN $4 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 i 25MN 56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.51E 03 , ! 26FE 55 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 l t 26FE 59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03 i t 27CO 58 0.00E-01 8.92E 01 2.00E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 ) 27CO 60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81E 03 28NI 63 3.11E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 : l i 28NI 65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 l , 29CU 64 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51E 01 0.00E-01 8.50E 02 [ ! 30ZN 65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 30ZN 69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 ! l 1 35BR 83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 1 i 35BR 84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 '
! 35BR 85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 1.01E-15 37RB 86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 1 37RB 88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 37RB 89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11
- 38SR 89 2.21E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 38SR 90 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 -
l 1.94E 03 ' 1 38SR 91 4.07E 02 0.00E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01
! 38SR 92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 '
3.06E 03 39Y 90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 39Y 91M 5.44E-03 0.00E-01 2.11E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 39Y 91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 . 39Y 92 5.06E-02 0.00E-01 1.48E-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 l 39Y 93 1.60E-01 0.00E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 40ZR 95 2.40E-01 7.70E-02 3.21E-02 0.00E-01 1.21E-01 0.00E-Oi 2.44E 02 l 1 40ZR 97 1.33E-02 2.68E-03 1.22E-03 0.00E-01 4.04E-03 0.00E-01 8.30E 02 41NB 95 4.47E 02 2.'8E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 { i' 42MO 99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 I 43TC 99M 8.87E-03 2.51E-02 3.19E-01 0.00E-01 3.81E-01 1.23E-02 1.48E 01 , l 43TC101 9.12E-03 1.31E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95E-14 44RU103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.69E 01 0.00E-01 5.17E 02 44RU105 3.69E-01 0.00E-01 1.46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 44RU106 6.58E 01 0.00E-01 8.33E 00 0.00E-01 1.27E 02 0.00E-01 4.26E 03 , l 4.84E-01 0.00E-01 1.60E 00 0.00E-01 3.33E 02
- 47AG110M 8.81E-01 8.15E-01 j 52TE125M 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.02E 04
! 52TE127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 ! 52TE127 1.05E 02 3.78E 01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03 i 52TE129M 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 l l 52TE129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 52TE131M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.04E 04 52TE131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.00E-01 2.67E 00 l 52TE132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.38E 04 53I 130 2.71E 01 8.01E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01
. 53I 131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 IBM (
ODCM f
' Rev. 8 Page 21 1
TABLE 2.3-1 (CONT.)
'O \
A g VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT (MREM /HR PER pCI/ML) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 53I 132 7.29E 00 1.95E 01 6.82E 00 6.82E 02 3.11E 01 0.00E-01 3.66E 00 53I 133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01
- 53I 134 3.81E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01E-03 53I 135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 l 55CS134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 55CS136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.38E 03 1.40E 04 4 55CS137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 55CS138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 56BA139 9.29E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 56BA140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 56BA141 4.51E-01 3.41E-04 1.52E-02 0.00E-01 3.17E-04 1.93E-04 2.13E-10 56BA142 2.04E-01 2.10E-04 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.37E-19 57LA140 1.50E-01 7.54E-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 i 57LA142 7.66E-03 3.48E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 58CE141 2.24E-02 1.52E-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 58CE143 3.95E-03 2.92E 00 3.23E-04 0.00E-01 1.29E-03 0.00E-01 1.09E 02 58CE144 1.17E 00 4.88E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 i
- 59PR143 5.51E-01 2.21E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41E 03 59PR144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04 0.00E-01 2.59E-10 60ND147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2.54E-01 0.00E-01 2.09E 03
{ 0.00E-01 0.00E-01 8.10E 04 74W 187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 4 93NP239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-01 5.75E 02 i l \ b i O l IBM
ODCM Rev. 8 Page 22 3.0 GASEOUS EFFLUENTS (O s,) 3.1 Monitor Alarm Setpoint Determination This procedure determines the monitor alarm setpoint that indicates if the dose rate at or beyond the site boundary due to noble gas radionuclides in the gaseous effluent released from the site exceeds 500 mrem / year to the whole body or exceeds 3000 mrem / year to the skin. Monitor high alarm or isolation setpoints will be established in one of the following ways:
- a. Monthly calculation of setpoint using the methodology of Section 3.1.1 for continuous releases using previous month releases as source term.
- b. Prior to each containment purge, recalculation of the setpoint using the methodology of Section 3.1.1 based on the sample taken prior to purging.
- c. In lieu of (a) and (b) above, alarm setpoints may be established using the methodology of Section 3.1.1 using conservative assumptions (e.g., 100%
Kr-89). No recalculation of setpoints is necessary unless an increase is desired. PWR GALE Code source terms (Table 3.1-2) may be used if s_) there were no detectable isotopes in the previous month or in the analysis prior to purging. If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value. 3.1.1 Effluent Monitors The following method applies when determining the isolation or high alarm setpoint for the monitors listed in Table 3.1-1. 3.1.1.1 Determine the " mix" (noble gas radio-nuclides and composition) of the gaseous effluent.
- a. Determine the gaseous source terms that are representative of the gaseous effluent. Gaseous source terms are the total curies of each noble gas released during the previous month or a repre-sentative analysis of the gaseous effluent.
p)s (_ Table 3.1-2 source terms may be used if the releases for the previous month were below the lower limits of detection . (LLD). IBM
ODCM Rev. 8 Page 23
- b. Determine S (the fraction of the totalradiokctivityinthegaseous O effluent comprised by noble gas radionuclide "i") for each individual noble gas radionuclide in the gaseous effluent.
i i (3.1-1) 1A i 1 Ag = The radioactivity of noble gas radictuclide "i" in the gaseous effluent from Table 3.1-2. 3.1.1.2 Determine Q total releaIe(the maximum acceptable rate of all noble gas radionuclides in the gaseous effluent (pCi/sec)) based upon the whole body exposure limit. Qt = 500 (3.1-2) (x/Q) 1 KS gg O (x/Q) = The highest calculated annual average relative concentration of effluents released via the plant vents for any area at or beyond the site boundary for all sectors (sec/m8 ) from the "x/Q" column in Table 3.1-1. K. = The total whole body dose factor due 1 to gamma emissions from noble gas 3 radionuclide "i" (mrem / year /pCi/m ) from Table 3.1-3. 3.1.1.3 Determine Q g based upon the skin exposure limit. Qt = 3000 (3.1-3) (X/9} 1 (Li+l1M} i S i i
= The total skin dose factor L1 + 1.1 Mg due to emissions from noble O gas radionuclide "i" (mrem /
year /pci/m3 ) from Table 3.1-3. IBM
OC ^" Rcv. 8 Page 24 3.1.1.4 Determine C (the maximum acceptable total radiohetivity concentration of all
/'") noble gas radionuclides in the gaseous
(_/ effluent (pCi/cc)). C e
= 2.12 E-3 9 t ,(3.1-4)
F NOTE: Use the lower of the Q E values obtained in Sections 3.1.1.2 and 3.1.1.3. F = The maximum effluent flow rate at the point of release (cfm) from the " Effluent Flow Rate" column in Table 3.1-1. 2.12 E-3 = Unit conversion constant to convert pCi/sec/cfm to pCi/cc. 3.1.1.5 Determine C.R. (the calculated monitor count rate above background attributed to the noble gas radionuclides (nepm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate point that corresponds to the total radioactivity concentration (C g). 3.1.1.6 Determine HSP (the monitor high alarm setpoint above background (ncpm)). HSP = T ,C.R. (3.1-5)
= Fraction of the total radioactivity T* from the site that may be released via each release point to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points from the " Release Fraction" column in Table 3.1-1.
3.1.1.7 The isolation or high alarm setpoints above background (nepm) for the monitors should be set at or below the HSP values. 3.1.2 Air Ejector Monitors Radiation monitors 1R-15 and 2R-15 provide an (i (_) indication of gross noble gas activity at the main condenser air ejector of Unit 1 and Unit 2, respectively. These monitors are provided to IBM
. _ _ _ - _ _ . _ . _ . - _____ -_ _. _ . _ _ - . _ _ - . . _ . _ . . . ~ . _ _- -
ODCM s Rev. 8 l Page 25 give rapid indication of steam generator tube
/
leakage. They are not effluent monitors since the air ejectors are vented to the auxiliary building vents during normal plant operation and l releases are monitored by the auxiliary building i vent monitoring system. ) I, i e l i i 4 i 1 r
^
l t k i e i 1 l l t i l l 4 r 3 i I I l }, i IBM i
_ _ _ _ _ . . _ . _ __ . _ . - _ _ _ _ _ _ _ _ . _ ~ . . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ - 4
~
l4 O O - Rev. 8 O Page 26 ] ] TABLE 3.1-1 MONITOR ALARM SETPOINT DETERMINATION FOR PNGP , l l l SOURCE l SOURCE l l EFFLUENT l RELEASE l l l RELEASE l OF l TERMS (A.) l l FLOW RATE l FRACTleN l I l MONITOR POINT RELEASE (TABLE 3.11 2)l y/Q(sec/m ) (F) (cfm) l (Tm) l l l I l { l 1R-30 l Aux. Bldg. l Aux. Bldg. - l l l l l j l and l Vent - Unit 1 l Unit 1 Exhaust l Aux. Bldg. 3.38E-5 l 2.9Et4 l 0.2 l
! l 1R-37 l l Air Ejector l Air Ejector 3.38E-5 l 2.9E*4 l l l l l Unit 1 l l l 1 l l '
I I l l 2R-30 l Aux. Bldg. l Aux. Bldg. - l l l l l ]j l and l Vent - Unit 2 l Unit 2 Exhausti Aux. Bldg. l 3.38E-5 4.1E*4 l 0.3 l l
; l 2R-37 l l Gas Decay Tanks l Xe-133 (100%){ l.32E-4 4.lE*4 l l l l l l l l l l Air Ejector Air Ejector 3.38E-5 4.lEt4 l l
, l l Unit 2 l l i
! l l I l j l 1R-12 l Shield Bldg. l Cont. - Units l Shield Bldg. l 1.32E-4 l 3.2E*4 l 0.3 l [
j l and l Vent - Unit il 1&2 Purge, l l l (Note 2) l l t l 1R-22 l l Unit ! Inserv-l l l l l j l l l ice Purge l
! l l l l l 4
l 2R-12 l Shield Bldg. I Cont.-Unit 2 l Shield Bldg. l 1.32E-4 l 4.6E+3 l 0.3 l r l and l Vent - Unit 21 Inservice l l l l l l 2R-22 l l Purge l l i i l l I I l j l R-35 l Radwaste l Radwaste l Aux. Bldg. l 3.38E-5 l 6.1Et3 l 0.1 l ; { l l Bldg. Vent -Bldg. Exhaust l l l
! l 1 l l l l l R-25 l Spent Fuel l Spent Fuel l Aux. Bldg. l 3.38E-5 l 1.8E*4 l 0.1 l J l and l Pool l Pool Air l l l l l [
I l R-31 l Air Vent l Exhaust l l l l l i NOTES: i 1. Values listed for T are nominal values only. They may be adjusted as necessary to allow a reasonable j
! margin to the monit ,or setpoint. Duplicate values of T are assigned to both Shield Building vents since l only one containment will be purged at any one time. The assigned T , values of all active release points ,
j shall not be greater than unity. a l 2. When purging the Unit I containment via the inservice purge system, the monitor setpoints may be based j on 4.6Et3 cfm for the duration of the release.
ODCM Rev. 8 Page 27 TABLE 3.1-2 GASEOUS SOURCE TERMS (1) AUX. BLDG SHIELD BLDC. AIR EJECTOR RADIONUCLIDE (Ag ) (Ci/Yr) (Ag ) (Ci/Yr) (A1 ) (Ci/Yr) Kr-85m 3E0 - 2E0 Kr-85 2E0 2.2E1 - Kr-87 LEO - - Kr-88 SEO LEO 3E0 Xe-131m 2E0 2.1El LEO Xe-133m SEO 2E1 3E0 Xe-133 3.7E2 2.7E3 2.3E2 Xe-135 8E0 6EO SEO Xe-138 1EO - - Total 3.97E2 2.77E3 2.44E2
" " indicates that the release is less than 1 Ci/yr.
O O IBM
CDCM
- Rev. 8 Page 28 TABLE 3.1-3
/ DOSE FACTORS AND CONSTANTS i SKIN TOTAL WHOLE BODY DOSE FACTOR DOSE FACTOR (Kg) (mrem /yr/pCi/m 3)
(L. + 1.lM ) 3 (mrlm/yr/pC1/m) RADIONUCLIDE Kr-83m 7.56E-2 2.12E1 Kr-85m 1.17E3 2.81E3 Kr-85 1.61El 1.36E3 i Kr-87 5.92E3 1.65E4 I Kr-88 1.47E4 1.91E4 Kr-89 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4 Xe-131m 9.15El 6.48E2 Xe-133m 2.51E2 1.35E3 Xe-133 2.94E2 6.94E2 Xe-135m 3.12E3 4.41E3 Xe-135 1.81E3 3.97E3
- Xe-137 1.42E3 1.39E4 Xe-138 8.83E3 1.43E4 i Ar-41 8.84E3 1.29E4 4
i I j O IBM i
ODCM Rev. 8 Page 29 3.2 Gaseous Effluent Dose Rate - Compliance with 10 CFR 20 () Dose rates resulting from the release of noble gases, and radioiodines and particulates must be calculated to show compliance with 10 CFR 20. The limits of 10 CFR 20 must be met on an instantaneous basis at the hypothetical worst case location, and apply on a per site basis. 3.2.1 Noble Gases The dose rate at the site boundary resulting from noble gas effluents is limited by 10 CFR 20 to 500 mrem /yr to the total body and 3000 mrem /yr to the skin. The setpoint determinations discussed in the previous section are based on the dose calculational method presented in NUREG-0133.(2) They represent a backward solution to the limiting dose equations in NUREG-0133. Setting alarm set trip points in this manner will assure that the limits of 10 CFR 20 are met for noble gas releases. Therefore, no routine dose calculations for noble gases will be needed to show compliance with this part. Routine calculations will be made for doses from noble gas releases to show compliance with 10 CFR 50, Appendix I as discussed in Section 3.3.1. (_), 3.2.2 Radioiodine, Radioactive Particulates, and Other Radionuclides The dose rate at the site boundary resulting from the release of radiciodines and particulates with half lives greater than 8 days is limited by 10 CFR 20 to 1500 mrem /yr to any organ. Calculations showing compliance with this dose rate limit will be performed for batch releases prior to the release and weekly for all releases. The calculations will be based on the results of sample analyses obtained pursuant to the PNGP Technical Specifications. To show compliance, Equations 3.2-1 will be evaluated for I-131, tritium, and radioactive i particulates with half-lives greater than eight days. I Pg (X/Qy ) h iy < 1500 mrem /yr (3.2-1) i I I where - - P i = infant critical organ dose parameter for radionuclide i for the inhalation pathway, () = mrem /yr per pCi/m 3 (Table 3.2-1); annual average relative deposition for (x/Q)v long 3 term release (Appendix at the A-4); A, Table critic al location, sec/m , IBM l L
y
~j ODCM s
R;v. 8 i Page 30
- 1
- annual aversge relative deposition for (D/Q)V
(T (m ,/ long-term release at the critical location, 1/m2 (Appendix A, Table A-5); Q iv = the. total release rate of radionuclide i from all vents from.hoth units for tne batch or week of intererc, pCi/sec; Radioiodines , tricium, and' radion'etive particulates ' will be releasad from up to six tndividual vents all within 300 feet of each other. For snowing com-pliance with 10 CFR 20, calculations based on Equa- . tion 3.2-1 will;be made once per week. The source terms'(Qgy) will be determined from the results' of ar.alysis of vent particulate filters and charcoal canisy.crs and vent ' flow rate. These source terms incluce all, gaseous releases from PNGP. Significant short-term batch releases of long-lived. , radibactive particulates and tritium uill result from containment purges. Calculations will be made for t'aese < releases separately to further assure compliance with 10 CFR Part 20 prior to release.- These calculations will 'oe used' only to determine whether or not the purge release will be ' ' - allowed'to occur. Source terms will be determined from tha (~T results of isotopic analyses of samples from containment' ( ,) prior to release. Equatior. 3.2.1 will be used in conjunction with the following relatioaship to demonstrate that the bat:h release does not exceed the dose rate limit:
- BL = 1500 - (Dy -
D) p (3.2-2) where BL = limiting dose' rate for the batch, mreu/yr; D V
= previous week's doses from all vent releases, mrem /yr; D
p
= previous week's doses from all purge releares mrem /yr.
3.2.2 critical Receptor; Identification Tac atmospheric dispersion parameters given in Appendix A will be used to identify the critic 11 receptor. Compliance with Part 20 will always be shown at the site boundary location with the highest %/Q. As discussed prev' ion 91r,. Weekly and batch dcae calculations will be performed at this ('")
\_,/
location. The critical site boundary location, based upon long term groun<i level releases x/C i l (Table A-3), is 0.36 miles in the WNW sector. 9 IBM ' '
s' ODCM Rev. 8 Page 31 TABLE 3.2-1 p Values for Infant il i l l mrem /yr l l ISOTOPE l P ty pCi/m 3 ; l 1 l l H-3 l 6.47 E 2 l l Cr-51 l 1.28 E 4 l ! l Mn-54 l 1.00 E 6 l 1 l Fe-59 l 1.02 E 6 , l l Co-58 l 7.77 E 5 l 4 l Co-60 l 4.51 E 6 l l Zn-65 l 6.47 E 5 l l Rb-86 l 1.90 E 5 l l Sr-89 l 2.03 E 6 l l Sr-90 l 4.09 E 7 l - l Y-91 l 2.45 E 6 l () l l Zr-95 Nb-95 l l 1.75 E 6 4.79 E 5 l l l l- Ru-103 l 5.52 E 5 l l l Ru-106 l 1.16 E 7 l l l Ag-110m l 3.67 E 6 l7 \ l l Te-127m i 1.31 E 6 l ! l Te-129m l 1.68 E 6 l
- l Cs-134 l 7.03 E 5 l i l Cs-136 l 1.35 E 5 l l Cs-137 l 6.12 E 5 l l Ba-140 l 1.60 E 6 l l Ce-141 l 5.17 E 5 l l Ce-144 l 9.84 E 6 l l 1-131 l 1.48 E 7 l l 1 I .
O IBM
*r:'e -
y---_ .---m"
,c y ,-------w.--m.- -. ----er-w-,w,+ +w--- - - - - - - - -m
CDCM Rev. 8 Page 32 Gaseous Effluents - Compliance with 10 CFR 50 ( 3.3 Doses resulting from the release of noble gases, and radioiodines and particulates must be calculated to show compliance with Appendix 1 of 10 CFR 50. The calculations will be performed monthly for all gaseous effluents. The limits of 10 CFR 50 are on a per reactor unit basis. The gaseous radwaste treatment system and the auxiliary building at PNGP is shared by both reactor units making it impossible to separate the releases of the two units. The releases that can be separated by unit contribute a very small portion of the total gaseous releases from PNGP. Therefore, for compliance with 10 CFR 50 the releases from both units will be summed and the limits of Appendix I will be doubled. 3.3.1 Noble Gas 3.3.1.1 Dose Equations The air dose at the critical receptor due to noble gases released in gaseous effluents is determined by Equations 3.3-1 and 3.3-2. The critical receptor will be identified as described in Section 3.3.4. For gamma radiation: , 3.17 x 10-8 7 3 (xjg) giv (xjq)vq iv 1 . .
< 10 mrad for any calendar quarter
< 20 mrad for any calendar year (3.3-1)
For beta radiation: 3.17 x 10-8 I Ng ('x/Q)y Q1y + (x/q)yggy
< 20 mrad for any calendar quarter
< 40 mrad for any calendar year (3.3-2) where:
M. = The air dose factor due to gamma emission 1 for each identified noble gas radionuclide i, mrad /yr per pCi/m3 ; (Table 3.3-1) N.1 = the air dose factor due to beta emissions for each identified noble gas radionuclide i l i, mrad /yr per pCi/m3 ; (Table 3.3-1) IBM
CDCM
- Rev. 8 Page 33
= the annual average relative concentration
(~N(,) (X/Q)V for areas at or beyond the restricted area boundary for long-term vent releases (greater than 500 hr/ year), sec/m 3 (Appendix A, Table A-4); (X/q)y = the relative concentration for areas at or beyond the restricted area boundary for short-term vent releases (equal to or less than 500 hrs / year), sec/m 3 (Appendix A, Table A-7); q.lV = the total release of noble gas radionuclide i in gaseous effluents for short-term vent releases from both units (equal to or less than 500 hrs / year), pCi; Q.lV = the total release of noble gas radionuclide i in gaseous effluents for long-term vent releases from both units (greater than 500 hrs /yr), pCi; 3.17 x 10-8 = the inverse of the number of seconds in a year. Noble gases will be released from PNGP from up to O nine vents. Long-term X/Q's were given in Appendix A. Short-term X/q's were calculated using the USNRC computer code "XOQDOQ" assuming 100 hours per year short term releases and are given in Appendix A (Table A-7). Values of M and N were calculated using the methodology presented in NUREG-0133 and are given in Table 3.3-1. 3.3.1.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits. The monthly results will be added to the doses cumulated from the other months in the quarter of interest in the year of interest and compared to the limits given in Equations 3.3-1 and 3.3-2. If these limits are exceeded, a special report will be submitted to the USNRC in accordance with the PNGP Technical Specifications. If twice the limits are exceeded, a special report showing compliance with 40 CFR 190 will r)s (_ be submitted. IBM
ODCM
- Rev. 8 Page 34 3.3.2 Radiciodine. Particulates, and Other Radionuclides yq t
(_-) 3.3.2.1 Dose Equations The worst case dose to an individual from I-131, tritium, and ra'dioactive particulates with half-lives greater than eight days in gaseous effluents released to unrestricted areas is determined by the following expressions: During any calendar quarter cnr year-3.17 x 10-8 R ijak W9v iv + "v41v J1
< 15 mrem (per quarter) -
< 30 mrem (per calendar year)
(3.3-3) where: Q fV = release of radionuclide i for long-term vent releases from both units (greater than 500 hrs /yr), pCi; qIV = release of radionuclide i for short term purge releases from both units (equal to ()x (s , or less than 500 hrs /yr); pCi; W v
= the dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases (greater than 500 hrs /yr);
w v
= the dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hrs /yr);
3.17 x 10-8 = the inverse of the number of seconds in a year; R the dose factor for each identified ijak = radionuclide i, pathway j, age grcup a, and organ k, m 2 mrem /yr per pCi/sec or mrem /yr per pCi/m 3. The above equation will be applied to each combination of age group and organ. Values of R.. have been calculated using the methodology f-gl48 h in NUREG-0133 and are given in Tables 3.3-2 through 3.3-20. Dose factors for isotopes not ( listed will be determined in accordance with the methodology in Appendix C. Equation 3.3-3 will be applied to a controlling location residence, which will l have one or more of the following: ! IBM n-. . . . , ,, - - - .
ODC.M
. -Rev . 8 Page 35 vegetable garden and milk animal. The selection of the actual receptor is discussed in Section
{s')/ 3.3.4. The source terms and dispersion parameters in Equation 3.3-3 are obtained in the same manner as in Section 3.2. The W 3 values are in terms of X/Q(sec/m ) for the inhalation pathways and for tritium (Tables 2 A-4 and A-5) and in terms of D/Q(1/m ) for all other pathways (Tables A-7 and A-8). 3.3.2.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits. The monthly results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest and compared with the limits in Equation 3.3-3. If these limits are exceeded, a special report will be submitted in accordance with the PNGP Technical Specifications. If twice the limits are exceeded, a special report showing compliance with 40 CFR 190 will be submitted.
, f-'s 3.3.3 Projection of Doses
' V Doses resulting from the release of gaseous effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month. In this case the source terms will be adjusted to reflect this information and the justification for the adjustment noted. If the projected release of noble gases for the month exceeds 2 percent of the calendar year limits of equation 3.3-1 or 3.3-2, additional waste gas treatment will be provided. If the projected release of I-132, tritium, and radioactive particulates with half-lives greater than 8 days exceeds 2 percent of the calendar year limit of equation 3.3-3, operation of the ventilation exhaust treatment equipment is required if not currently in use. 3.3.4 Critical Receptor Identification The critical receptors for compliance with 10 CFR 50, Appendix I will be identified. For the c g noble gas specification the critical location will be based on the beta and gamma air doses l only. This location will be the offsite location with the highest long term vent X/Q and will be selected using the X/Q values given in Appendix A, IBM
ODCM
- Rev. 8 Page 36 Table A-3. This location will remain the same unless
('T3 meteorological data is reevaluated or the site boundary V changes. The critical location for the 1-131, tritium, and long-lived particulate pathway will be selected once each year. The selection will follow the annual land use census performed within 5 miles of the PNGP. Each of the following locations will be evaluated as potential critical receptors prior to implementation of the Radioactive Effluent Technical Specifications:
- 1. Residence in each sector
- 2. Vegetable garden producing leafy green vegetables
- 3. All identified milk animal locations Following the annual survey, doses will be calculated using Equation 3.3-3 for all new identified receptors and those receptors whose characteristics have changed significantly. The calculation will include appropriate information about each new location. The dispersion parameters given in this manual should be employed. The total releases reported for the previous calendar
(~N year should be used as the source terms.
'v) l l
l l I IBM
4 ODCM
- Rev. 8 '
Page 37 2 4 REFERENCES i i (1) "NSP-Prairie Island Nuclear Generating Plant, Appendix I ' Analysis - Supplement No. 1 - Docket No. 50-282 and 50-306", i Table 2.1-4. e 3 l i i l 1 l i i l IBM
ODCM i Rev. 8 - Page 38 4 TABLE 3.3-1 ' ~ DOSE FACTORS FOR NOBLE GASES AND DAUGIITERS* j j Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K. 3 L 3 H. 3 N. 3 (mrem /yr'per pCi/m ) I (mrad /yr*per pCi/m ) Radionuclide (mrem /yr per pCi/m ) (mrad /yr'per ECi/m, ) Kr-83m 7.56E-02** --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23EiO3 1.97E*03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92Et03 9.73E+03 6.17E+03 1.03E404 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E*03 Kr-89 1.66E+04 1.01EiO4 1.73E+04 1.06Et04 Kr-90 1.56E+04 7.29E403 1.63E+04 7.83E+03 Xe-13Im 9.15E101 4.76Et02 1.56E+02 1.IIE*03 Xe-133m 2.51Et02 9.94Et02 3.27E+02 1.48E+03 Xe-133 2.94E102 3.06Et02 3.53E+02 1.05Et03 Xe-135m 3.12Et03 7.11E+02 3.36E+03 7.39E+02 l Xe-135 1.81Et03 1.86E*03 1.92E+03 2.46E+03 Xe-137 1.42E103 1.22EiO4 1.51E+03 1.27E+04 Xe-138 8.83E403 4.13Et03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28Et03
- Tlie listed dose factors are for radionuclides tinat may be detected in gaseous effluents. All otliers are 0.
_2
** 7.56E-02 = 7.56 x 10 .
- O O :5" e Page 39 CL -
TABLE 3.3-2 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATilWAY = GROUND
) NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN I I I I I I I I I HN 54 1 1.34E 09 1 1.34E 09 l 1.34E 09 1 1.34E 09 1 1.34E 09 l 1.34E 09 1 1.34E 09 l 1.57E 09 I l l l 1 I I I I I
- I I I I I I I I I FE 59 l 2.75E 08 1 2.75E 08 1 2.75E 08 l 2.75E 08 1 2.75E 08 1 2.75E 08 l 2.75E 08 I 3.23E 08 I I I I I _I I I I I I CO 58 1 3.79E 08 I 3.79E 08 1 3.79E 08 1 3.79E 08 1 3.79E 08 1 3.79E 08 I 3.79E 08 1 4.44E 08 I I 1 1 1 I I I I I l CO 60 1 2.15E 10 1 2.15E 10 1 2.15E 10 1 2.15E 10 1 2.15E 10 1 2.15E 10 1 2.15E 10 1 2.52E 10 I i
l l l l I I
- I I I I I I
! SR 89 1 2.23E 04 1 2.23E 04 1 2.23E 04 1 2.23E 04 1 2.23E 04 I 2.23E 04 1 2.23E 04 1 2.58E 04 I I I i 1 1 1 1 i l i I I I 131 1 1.72E 07 l 1.72E 07 1 1.72E 07 1 1.72E 07 l 1.72E 07 l 1.72E 07 l 1.72E 07 1 2.09E 07 I I i l I I I I I I I CS134 I 6.82E 09 I 6.82E 09 I 6.82E 09 I 6.82E 09 I 6.82E 09 I 6.82E 09 1 6.82E 09 I 7.96E 09 I l 1 1 1 I I I I I I I I I l CS137 1 1.03E 10 1 1.03E 10 1 1.03E 10 1 1.03E 10 1 1.03E 10 1 1.03E 10 1 1.03E 10 1 1.20E 10 I l l l l l l l I I I
- R VALIIES IN llNITS OF HREH/YR PER pCI/M FOR INilALATION AND TRITIUH, AND IN UNITS OF H -HREH/YR PER pCl/SEC FOR ALL OTIIERS
M C C e lC e a e C e C e C W e I - C s C 8
-hf 2
=
Ca2 co f.a2 O
- s2 C
W C Ca2 C f.s2 C W C C Ca2 C f.a2 C j M C. C. C. C. C. C. y} N. O. C. C. N O C C C C C C C C M
- - - - - - - -- - ga; L
M - N - a ch m gg; C C C C C C C C C .C > e e e a e e N O Ca2 Ca2 Ca2 ta2 Ca2 Ca2 ta! Ca2 Ca2 ta2 E 2 co C N O C C C C @ N Ca2
- - CE:
y G N. O. O. C. C. C. C. O. z a co C C C C C - N O N a A - -- E C k 2 C
. M - - C -
A C C C C C C C - C C U2 E.sg. >w $ e B I I I I I H C M C sa2 Ca2 Ca2 Ca2 Ca3 C
&a2 C
Ca2 C Ca3 00 Ca3 C Ca2 C 2 c0 < sa2 E co C C C 2 >= 6 C. Q N. C. C. C. C. C. C. C. E *U gas = N O C C C C C M C C 2 C H . 0 > 50 C O c4 cz: -- C O cm r < -- - - - - - - - - 2 Ca2 J < U M N - - ** - - co e m D > C C C C C C C C C C = 2 C.2 e e e e a E 2 Ca2 Ca2 Ca2 Ca2 Ca2 Ca2 Ca2 f.s2 ta2 Ca2 D C3 ::2 co ch C C C C C co ch co 2; - < C. 6e as; M N. C. C. C. C. C. C. ch. . s i3 N Ch C C C C C - M M W. t-*
.U2 e
- - - -- -- :=
Ca2 2
== *C cz: m co co N co - - co o ch
- C C C C C C C C - C 2
< sk: I I C m r.a2 Ca2 Ca2 Ca2 Ca2 &a2 Ca2 C
Es2 C Ca2 Ca2 co Ca2 N E.= A >
*-8 co e M ch @
@ C C i.n
- C y N. C. Ch. Ch. . * * *
- C. -
ta2 m.2
= N M N N - O C - - ch <
i-. 2 2 gg; -- - - - - - - ----- - C Cz: W C
= - co - - C - N Ch ch Cf3 C C C C C - - C C C W Ca2 Ca2 e a e D 2 ta2 Ca2 Ca2 Ca2 ta2 Ca2 ta2 Ca2 Ca2 Ca2 M m.2 O C C < C C C C N < M E
< ClC 4 @ N
;;> C. C. N. O. C. C. N. C. . -
C C - C C - @ oc 4 @ U Ck: 1
- - - - - ---- - -- gg; ta2 M r i
f-. M ce co ce ch ch C N co co M. O C C C C C C - C C C QC M < > Ca2 ta2 Ca2 Ca2 f.a2 ta2 la2 La2 Ca2 Ca2 N Ca2 C.t: 6= co @ m N N O M < ch @ E m2 I N - @ co. Ca2 cz: N. M. . O. . . m. C. N. g
< C N m Ch @ M *
- M -
- E Cf3 CX:
6=. E== 4 :a2 3 m --- - ----- -- - --- - c ::::: O H-
< >= M N co N cc co - N cn ch to.
6- C C C C C C C C - C C C =n2 Cf 22 6-* w} CQ O Ca2 Ca2 ta2 Ca2 Ca2 Ls2 Ca2 Ca2 Ca2 Ca2 O =0 Ca2 < cc M N - N N < - M < CO . - N @ co @ @ C3 2 CM: N. cc. = * * . . Ch. == 0 Ca2 C'$4 .
@ co e W
> sa2 N m - @ M N -
CC
- - -- ga; O HA - - - ---- - -
C Ca2
=2 m.2 CC
> c Ca2 <N
< C: C - N ;> -
~3t C .A.* M 4 ch cc C ch 4 g ll: . m e e @ C22 m M M M=
U 2l; 1 H Ca2 U
< C 22 2 Ca2 C C C2: ol: CC CC U
A < 24 2:2 Z W U U CC V2 >-= U .!
llillIllillIIlill IllIll1 3 0 1 0 1 0 1 0 1 0 0 1 IIl1_Il1 0 1 0 1 0 1 0 N E E E E E E E E E E I t 0 0 0 0 0 0 0 0 0 K 6 0 0 0 0 0 0 0 0 0 S 0 2 0 0 0 0 0 0 0 0 R ll lIll lIIl l l l lIlll E P 3 1 8 1 1 1 1 1 9 9 R 0 0 0 0 0 0 0 0 0 0 Y
- - - - - - /
G E E E E E E E E E E H
- N 1 0 0 0 0 0 0 0 7 6 E T U 6 0 3 0 0 0 0 0 9 8 R N L H 0 0 0 0 0 0 1 1 -
A 2 1 L H P ll l l l1Il l liIl LIl Illl F G O N 1 1 1 1 0 1 1 I 3 1 1 T D 0 0 0 0 0 0 0 1 0 0 S A I - - - - - - - - T 1 R O E E E E E E E E E E I E R 1 0 0 0 0 0 0 4 0 0 N 84 N Y 6 0 0 0 0 0 0 1 0 0 U e E H . 0 0 N G T 2 0 0 0 0 0 0 3 Vg I a R lIIlIIl ll D P A 1l l l l l l N E A L C 3 8 1 1 1 1 1 8 9 9 U Y 0 0 0 0 0 0 0 0 0 0 , N E - - - - - M N E E E E E E E E E E U D D 1 2 0 0 0 0 0 5 6 8 I N I 6 3 0 0 0 0 0 8 1 7 T I A K . 4 R L 2 1 0 0 0 0 0 1 5 S T I illll l l l l1Il l 1 lI D E N I A R 3 8 8 7 8 1 1 8 0 0 I 0 0 0 0 0 0 0 0 1 1 N A R - - O R E E E E E E E E E E E I P V 1 3 4 5 7 0 0 7 2 1 T I 6 4 1 2 4 0 0 0 6 4 A E L . L l i 2 4 4 4 2 0 0 1 1 1 A l T i N l1lll I R IlIIl I l l liIl11l O R F 1 1 8 1 1 0 1 7 9 0 O S 0 0 0 0 0 1 1 0 0 1 F E E - - - - E E E U N E E E E E E E L O 0 0 7 0 0 2 2 8 0 6 M A B 0 0 7 0 0 5 3 6 9 0 / I V 8 7 6 1 C 0 0 1 0 0 1 p R IlJIl]1l l lI1l l l l ll R 4 E
- P 3 T 3 8 8 8 9 9 0 7 8 8 C 0 0 0 0 0 0 1 0 0 0 R 3 A Y
- R E E E E E E E E E E / E T 1 9 8 5 2 1 3 3 2 0 H _ L - 6 0 7 8 2 8 3 1 0 0 E R B I A G 2 9 9 5 3 1 2 2 2 2 HS T R N FE E IllIl llIl l1 ll ' ll1lIIlll1l Oi l E T T SO Y 3 7 8 7 8 8 1 7 9 9 T D 0 0 0 0 0 0 1 0 0 0 I L SO NL TLB E E E E E E E E E E UA EA 1 9 0 9 7 6 5 7 4 0 GU . 6 7 6 7 5 3 0 7 5 9 NR EQT I O VE 2 8 1 9 5 4 2 5 7 4 F S
=P Il l[1liIllIl1ll - l lLIllIll EC UE U _ LS YOE A/
ARD 4 7 VI WGI 3 4 9 8 0 9 0 1 l L 5 5 5 6 8 9 3 3 3 C i 1 Rp TEC R 1 1 S S AGU N E O O R PAN I I H F C C S S 1 C C
- lj !
, i' ll
IlIIlIIlIIlIllIIlIIlIIlIIlIIlI 3 1 1 1 1 1 1 _ 1 1 1 0 0 0 0 0 0 0 0 0 0 O N E E E E E E E E E E I 4 0 0 0 0 0 0 0 0 0 K 0 0 0 0 0 0 0 0 0 0 S 4 0 0 0 0 0 0 0 0 0 R IliIlIIlIIlIllIIlIIl1IlIIllIlI E P 3 1 8 1 1 1 1 1 9 9 R 0 0 0 0 0 0 0 0 0 0 Y
- - - - - - /
G E E E E E E E E E E H
- N 4 0 4 0 0 0 0 0 4 0 E T U 0 0 8 0 0 0 0 0 8 8 R N L H A 4 0 1 0 0 0 0 0 2 2 -
L M P IliIl1IlIIl1ll l l lIIl ' lI G F N O I 3 1 1 1 1 1 1 0 1 1 T D 0 0 0 0 0 0 0 1 0 0 S A I - - - - - - - - T 2 R O E E E E E E E E E E I E R 4 0 0 0 0 0 0 5 0 0 N N Y 0 0 0 0 0 0 0 7 0 0 U I . e E I 0 N L4 G T 4 0 0 0 0 0 0 4 0 g I a R llIlIIlIIII D
;P A Il IIl1Il l1ll l N
E A L 1 1 8 9 9 C 3 8 1 1 1 U Y 0 0 0 0 0 0 0 0 0 0 , N E - - - - - M N E E E E E E E E E E U D D 4 2 0 0 0 0 0 6 3 8 I N I 0 8 0 0 0 0 0 3 9 7 T
. I A K 2 7 7 R L 4 1 0 0 0 0 0 S T I
Il1Il1Il l l ' l llIl l lI D E N I A _ 0 8 1 8 0 O 8 8 7 1 R 3 0 0 0 1 1 N I 0 0 0 0 0 A R - - O R E E E E E E E E E E E I P V 4 9 6 7 6 0 0 4 6 9 T _ I 0 4 3 2 7 0 0 4 5 3 A L L _ E . 0 2 2 A l i 4 6 6 6 3 0 1 I T I N lIIl l1 I
. R Il l l11l l1IlIIl O R F 2 8 0 0 O 1 1 8 1 1 0 S 0 0 0 0 0 1 1 0 1 1 F E E - - - -
E E E U N E E E E E E E L O 0 0 3 0 0 2 8 3 6 9 M A B 0 0 9 0 0 6 3 4 5 4 / I V 0 3 1 1 1 2 C 0 0 3 0 p R Il1Il1Il l1ll liIl lIIllIl1 R E 5 P 3 T 3 8 8 8 9 9 0 7 8 8 C 0 0 0 0 0 0 1 0 0 0 R A Y 3 E E E E / R E E E E E E E T 4 4 2 6 8 0 6 8 8 0 H L - 0 4 6 6 0 4 8 2 3 5 E R B 1 1 1 1 1 HS A G 4 5 6 3 2 1 D R T FE L l1IllIll OI I l Il l1Ill1llll1IllIl l T l C SO Y 3 8 8 8 9 9 1 7 9 9 T D 0 0 0 0 0 0 1 0 0 0 I L SO NL TLB E E E E E E E E E E UA 2 3 9 6 0 2 EA 4 3 7 l 0 4 1 4 5 NR GU . 0 7 1 9 l EQT . . . . I O 1 3 8 5 3 F VE 4 1 3 1 1 S
= P Il l l l l llI1 l liIll EC U UE YOE LS O ARD WGI l
iTEC AGU L 3 4 5 N 9 5 E 8 5 O 0 6 O 9 8 R 9 R 0 1 3 1 4 3 S 1 7 3 1 S A/ Vl Rp C PAN 1 1 H F C C S S I C C *
, l l; l ll i '
a a O O ::= s Page 43 O.. I TABLE 3.3-6 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- 1 PATIIWAY = HEAT AGE GROUP EQUALS ADULT NilCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN I I I I I I I I I 11 3 l 3.27E 02 l 3.27E 02 l 0.00E-01 l 3.27E 02 l 3.27E 02 l 3.27E 02 l 3.27E 02 l 3.27E 02 l 1 J l i I I I i l l HN 54 l 8.98E 05 l 1.44E 07 l 0.00E-01 1 4.71E 06 l 1.40E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l l 1 1 1 1 I I I I I I I I FE 59 l 1.12E 08 l 9.73E 08 l 1.24E 08 l 2.92E 08 l 0.00E-01 l 0.00E-01 l 8.16E 07 l 0.00E-01 l 1 1 1 I I I I I I I I I I I CO 58 l 1.95E 07 l 1.76E 08 l 0.00E-01 l 8.68E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l
[ [ l i I I I I I I CO 60 l 8.87E 07 l 7.55E 08 l 0.00E-01 l 4.02E 07 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 1 I l I I I I I I I I l l l l SR 89 l 4.12E 06 l 2.30E 07 l 1.43E 08 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l l 1 I I I I _I I I I I I I l SR 90 l 1.76E 09 l 2.07E 08 l 7.17E 09 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 1 1 I I 1 1 I I I I I I I I 131 l 4.33E 06 l 1.99E 06 l 5.28E 06 1 7.55E 06 l 1.29E 07 l 2.48E 09 l 0.00E-01 l 0.00E-01 l 1 1 1 I i 1 1 l -l l I I I I I I I I CS134 l 6.68E 08 l 1.43E 07 1 3.43E 08 l 8.17E 08 l 2.64E 08 l 0.00E-01 l 8.78E 07 l 0.00E-01 l 1 1 1 J l I I I I I I I I I I I CSl37 l 4.33E 08 l 1.28E 07 l 4.83E 08 l 6.61E 08 1 2.24E 08 l 0.00E-01 l 7.46E 07 l 0.00E-01 l l l l l l l I I _I
- R VALUES IN UNITS OF HREH/YR PER pCI/M FOR INilALATION AND TRITIUH, AND IN UNITS OF M -NREH/YR PER pCI/SEC FOR ALL OTilERS
lIII lll 9Il 2 0 IIlllliIlIIlIIl1IlI_Il 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 N E E E E E E E E E E C' I K S 5 9 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 R il lJll l ' l l l1IliIlI1lI E P 2 1 7 1 1 1 1 1 7 7 R 0 0 0 0 0 0 0 0 0 0 Y
- - - - - - /
G E E E E E E E E E E N N 0 1 0 0 0 0 0 9 6 E
- 5 3 0 0 0 0 0 7 0 R T U 9 0 . H N L 0 7 7 -
A 1 0 7 0 0 0 0 L H P ilIIlIlliIl1Il ' 1 l lII1IllI F G O N 1 1 1 1 9 1 1 I 2 1 1 S T D 0 0 0 0 0 0 0 0 0 0
- - - - - - - T A I -
E E E E E E E E I 4 R O E E 0 0 N E R 5 0 0 0 0 0 0 9 s4 N Y 9 0 0 0 0 0 0 7 0 0 U E H
=g
- a e G R
T 1 0 0 0 0 0 0 1 0 0 N I l1Il1Il lIllI D
- P A IllIl1lliIl l N
E A L 1 1 7 8 8 C 2 6 1 1 1 U Y 0 0 0 0 0 0 0 0 0 0 , N E - - - - - M N E E E E E E E E E E U 0 0 0 0 6 4 2 I D D 5 7 0 0 0 0 8 T N I 9 0 0 0 0 0 I A K 0 2 1 R L 1 1 0 0 0 0 1 S T I l1IliIl1llI D Il' l lIIl lIIl E N I A 6 8 6 7 1 1 6 8 8 R 2 N O- I 0 0 0 0 0 0 0 0 0 0 R - - O A E E E E E E E E I R E E E 2 4 T P V 5 9 2 9 2 0 0 4 I 9 5 3 6 1 0 0 1 4 3 A E L . . L t i 1 3 2 6 3 0 0 6 6 5 A l i T N l1Il lllll I R Il1Ili1l1Il l l O R F 1 8 9 6 8 8 O 1 1 7 1 0 0 0 0 0 0 0 0 0 0 F S E E - - - - E E E U N E E E E E E E L O 0 0 3 0 0 1 4 9 3 1 H A B 0 0 9 0 0 2 6 3 7 0 /
. 1 V 0 4 4 2 4 C 0 0 9 0 1 p
R Il l l l1IllIl l1IllIlllll R 7 E P 3 T 2 6 8 7 8 7 8 6 6 6 C 0 0 0 0 0 0 0 0 0 0 R Y 3 A E E E E E / R E E E E E E T 5 7 8 2 6 4 0 2 9 9 H L - 9 3 4 2 0 4 3 2 9 5 E B I R A G 1 7 5 9 4 1 1 1 7 7 HS _ R T FE N E Il lIlllIl llIl lLI l 1IIll Oi l T E SO T 7 7 6 9 6 8 8 T Y 2 5 7 0 0 0 0 I L D 0 0 0 0 0 0 NL SO E E E E E E UA LB E E E E 6 3 7 5 0 8 TA 5 2 5 4 0 4 1 3 9 8 NR AU . 9 1 9 5 I O EQT . 7 3 1 3 2 1 F HE 1 7 8 1 S 1lllIIll EC
=P Il l}ll[Il l1IllIl UE U LS YOE A/
O ARD WGI l i TEC AGU L 3 4 5 N 9 5 E 8 5 O C 6 0 O C 9 8 R S 0 9 R S 1 3 1 i 4 3 1 S C 7 3 S C 1 Vl Rp C PAN 1 1 H F
llIIIill1ll11llllIIlIIlIIllIli 1 1 1 1 1 1 1 2 1 1 0 0 0 0 0 0 0 0 0 0
N E E E
E E E E E E E n\ - I K S 6 3 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 R ll l l l llll l l ll;lI E P 2 1 7 1 1 1 1 1 7 7 R 0 0 0 0 0 0 0 0 0 Y 0 - - / G E E E E E E E E E E H 6 0 0 0 0 0 8 9 E
- N 6 0 2 0 0 0 0 0 7 2 R T U 3 0 H N L 0 0 0 8 8 -
A 2 0 8 0 0 g L M P IlIIlIll lllllIl l!IlIIl lI F G O N 1 1 1 1 9 1 1 I 2 1 1 0 0 S T D 0 0 0 0 0 0 0 0
- - - - - - - - T A I E E E E E E E E I 5 R O E E 0 0 N E R 6 0 0 0 0 0 0 1 84 Y 3 0 0 0 0 0 0 7 0 0 U N l E N
.e G i
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=P Il1IlIll l l IlIl l l ll EC U UE YOE LS A/
O ARD NGI L I TEC AGU 3 4 5 N 9 5 E 8 5 O C 0 6 O C 9 8 R S 0 9 R S 1 3 1 4 3 1 S C 7 3 1 S C V1 R p C PAN 1 1 H F 1 1 < < l' I
lllll1IlIlllll1IlIIl1llllliIl1 1 2 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 N E E E E E E E E E E 9 0 0 0 0 0 0 0 0 0 Gs I K 6 0 0 0 0 0 0 0 0 0 S 7 0 0 0 0 0 0 0 0 0 R lllll l l l l l l l1Ill E P 2 1 6 1 1 1 1 1 8 8 R 0 0 0 0 0 0 0 0 0 0 Y
- - - - - - /
G E E E E E E E E E E H
- N 9 0 0 0 0 0 0 0 4 1 E T U 6 0 1 0 0 0 0 0 5 3 R N L . N A 7 0 9 0 0 0 0 0 7 6 -
L M P l l1ll l l l l l ll Il G F N O I 2 1 1 1 1 1 1 0 1 1 T D 0 0 0 0 0 0 0 1 0 0 S A I - - - - - - - - T 6 R O E E E E E E E E E E I 84 E R 9 0 0 0 0 0 0 2 0 0 N N Y 6 0 0 0 0 0 0 8 0 0 U E H N G T 7 0 0 0 0 0 0 6 0 0
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- P 3 T 2 7 8 7 8 8 8 7 8 8 C 0 0 0 0 0 0 0 0 0 0 R 3 A Y R E E E E E E E E E E /
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ODCM , Rev. 8 Page 48 I TABLE 3.3-11 R VALUES FOR TIIE PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATilWAY = COW HILK AGE GR0llP EQUAL.S CIIILD
, NUCLIDE T. HODY GI-TRACT BONE LIVER KIDNEY TilYROID LUNG SKIN l l l l l l l l l l
- 11 3 l 1.58E 03 1 1.58E 03 l 0.00E-01 1 1.58E 03 l 1.58E 03 1 1.58E 03 l 1.58E 03 l 1.58E 03 l I I i 1 I I i i I i
HN 54 l 2.87E 06 l 9.04E 06 l 0.00E-01 l 1.08E 07 l 3.02E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l i 1 I i 1 1 I I I I I I FE 59 l 4.52E 07 l 9.45E 07 l 5.61E 07 I 9.08E 07 1 0.00E-01 1 0.00E-01 l 2.63E 07 l 0.00E-01 l . I 1 1 l I I I I I I I I I I CO 58 l 1.77E 07 l 3.37E 07 l 0.00E-01 l 5.77E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 1 1 1 1 l 1 I I I I I I l CO 60 1 6.81E 07 l 1.28E 08 l 0.00E-01 l 2.31E 07 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 I I I l I I I I I SR 89 l 8.93E 07 l 1.21E 08 1 3.13E 09 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l I I I I 1 l 1 I I I I I I I SR 90 l 1.63E 10 l 8.68E 08 l 6.44E 10 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 1 I I I .I I I I I l i I 131 1 3.66E 08 l 5.73E 07 l 6.40E 08 l 6.44E 08 l 1.06E 09 l 2.13E 11 l 0.00E-01 l 0.00E-01 l 1 1 1 I 1 1 I I I I I l CS134 1 4.09E 09 l 1.05E 08 l 1.18E 10 l 1.94E 10 l 6.01E 09 l 0.00E-01 l 2.16E 09 l 0.00E-01 l I I I l I 1 1 I I I I l l 1 l I CS137 l 2.52E 09 l 1.07E 08 l 1.79E 10 1 1.71E 10 l 5.57E 09 l 0.00E-01 l 2.00E 09 l 0.00E-01 l l l l l l 1 l l l 3 2
- R VALUES IN UNITS OF HREH/YR PER pC1/H FOR INilALATION AND TRITIUM, AND IN UNITS OF M -HREH/YR PER pCI/SEC FOR ALL OTilERS
m i. - .= - - C C C C C C C C C C 0 e i 5 e e 5 9 I 2 ta: W Ca: Ca2 ts: W W W r.a: hj - C Ca2 C C C C C C C C C
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---- --- --- gas L
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/
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. ll l l l l l lllllll ll E P
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. L l
i L . 2 2 1 A T 1 5 4 2 1 0 0 l i N R l l l lllll I O ll l l l l F R S 1 1 5 1 1 9 0 8 9 0 O 0 0 0 0 1 0 0 1 F E 0 0 U E - - - - E E E 3 L N E E E E E E E A O 0 0 0 0 0 4 7 4 5 3 M B 8 0 0 4 6 7 8 2 / V 0 0 I 0 0 0 1 5 1 8 1 C R 0 1 p 3 Il llIll1l l l l llIll1ll R 1 E P 6 6 6 7 8 9 7 8 8 3 T 3 0 0 0 0 0 0 0 R C 0 0 0 Y . 3 A E E E E E E / R E E E E 5 H E 6 8 1 4 9 9 T 7 9 1 4 9 3 6 5 6 2 E L - 5 5 4 R l I l A G 1 1 1 5 1 2 1 6 3 3 HS R T T FE L l1Illll lllll Oi l U Il l l l l T - D SO A 5 6 7 0 8 0 0 T K Y 3 4 5 I L L D 0 0 0 0 0 0 1 0 1 1 NL I SO E E E E E E UA HLB E E E E 0 3 2 3 9 3 2 TA 7 9 6 2 0 3 1 3 4 7 1 NR AU . 5 8 . . . I O OQT 6 2 4 1 1 1 1 F GE 1 9 1 S llIl l ll EC
=P Il1ll l l llIl UE U LS YOE A/
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- PAN I H F C C S S I I
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- - - - - - /
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P M l l l lllll G ll l1ll l l F N O I 1 1 1 1 1 1 1 1 T 3 1 A D 0 0 0 0 0 0 0 1 0 0 S R I - - - - - - - - T 1 E O E E E E E E E E E E I N R 4 0 0 0 0 0 0 9 0 0 N 85 E Y 0 0 0 0 0 0 0 2 0 0 U e G H 0 0 0 0 N T 2 0 0 0 0 1 vg R I a A l l lllll D P E ll l l l l l N L A C 1 1 1 8 0 0 U 3 5 1 1 N Y 0 0 0 0 0 0 0 0 1 1 E - - - - - M D N E E E E E E E E E E U N D 4 8 0 0 0 0 0 3 5 l I A I 0 5 0 0 0 0 0 6 1 T
. O. I L K 0 1 R S 2 2 0 0 0 0 7 1 I T E Il l l l l l l l l ll D I
N R A I 3 5 5 5 6 1 1 8 0 0 A 0 0 0 0 0 0 0 0 1 1 N R R - - O P E E E E E E E E E E E I V 4 4 4 3 8 0 0 3 2 6 T E I 0 6 3 5 7 0 0 4 6 9 A H L L T 2 8 7 4 1 0 0 4 3 2 A l i R N l l ll I O l l l l l l Il F R S 1 1 5 1 1 9 0 8 0 0 O E 0 0 0 0 0 0 1 0 1 1 F U E - - - - E E L N E E E E E E E E A O 0 0 4 0 0 5 1 7 4 2 M V B 0 0 1 0 0 6 0 1 5 2 /
. . l R 0 0 3 0 0 2 8 3 1 2 C p
4 Il l l l l l1ll llll ll R 1 E
- P 3 T 3 6 6 6 7 8 9 7 8 8 C 0 0 0 0 0 0 0 0 0 0 R 3 A Y
_ R E E E E E E E E E E / - E T 4 7 4 5 2 6 S 7 0 1 N L - 0 7 7 2 3 1 2 7 5 2 E B I . . . R - A G 2 1 1 6 2 3 2 8 4 4 HS - T R N FE E Il l l l l l l l1ll ll Oi l E T T SO K Y 3 5 5 6 6 7 0 8 0 0 T L D 0 0 0 0 0 0 1 0 1 1 I L I S9 NL _ HLP E E E E E E E E E E UA 2 9 8 8 8 3 TA 4 1 3 4 0 5 9 3 6 0 NR AU . 0 7 8 0 I O OQT . 2 4 7 1 2 1 1 F GE 2 1 1 S
=P Il1IllIl l l lllllll l ll EC U UE YOE LS ARD A/
WGI 3 4 9 8 0 9 0 1 4 7 VI l L 5 5 5 6 8 9 3 3 3 C i 1 1 Rp TEC R 1 S S AGU N E O O R PAN 1 1 M F C C S S 1 C C
- Ii .' i
l ODCM Rev. 8 Page 52 TABLE 3.3-15 R VALUES FOR TIIE PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATilWAY = C0ATHILK AGE GROUP EQUALS CllILD NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY TIIYROID LING SKIN I I I I I I I I I 11 3 l 3.23E 03 1 3.23E 03 l 0.00E-01 l 3.23E 03 l 3.23E 03 l 3.23E 03 l 3.23E 03 l 3.23E 03 l I I i 1 1 j l I
, I I I I I I I HN 54 l 3.44E 05 l 1.08E 06 l 0.00E-01 l 1.29E 06 l 3.62E 05 l 0.00E-01 l 0.00E-01 l 0.00E-01 l . ) l I I ' I
. I I FE 59 l 5.88E 05 l 1.23E 06 l 7.29E 05 l 1.18E 06 l 0.00E-01 l 0.00E-01 l 3.24E 05 l 0.00E-01 l
! I I I I I I 0.00E-01 l CO 58 l 2.12E 06 l 4.04E 06 l 0.00E-01 l 6.92E 05 l 0.00E-01 l 0.00E-01 l l 0.00E-01 l I I I I 1 i l i I I i I CO 60 1 8.17E 06 l 1.53E 07 l 0.00E-01 l 2.77E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l I I 1 1 I I I I
; SR 89 l 1.87E 08 l 2.54E 08 l 6.56E 09 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 I l 1 1 l l l l l l
l SR 90 1 3.43E 10 l 1.82E 09 l 1.35E 11 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 1 0.00E-01 l 4 1 1 I 1
- 1 I I I
! I 131 l 4.39E 08 l 6.88E 07 l 7.68E 08 l 7.72E 08 l 1.27E 09 l 2.55E 11 l 0.00E-01 l 0.00E-01 l l I I I l [ i i i I I CS134 l 1.23E 10 l 3.14E 08 l 3.55E 10 l 5.82E 10 l 1.80E 10 l 0.00E-01 l 6.47E 09 l 0.00E-01 l l 1 I I l l 1 1 1 I I I I I I I CS137 l 7.57E 09 l 3.21E 08 l 5.36E 10 l 5.13E 10 l 1.67E 10 l 0.00E-01 1 6.01E 09 l 0.00E-01 l l l l 1 I I I l l
- R VALUES IN UNITS OF HREH/YR PER pCI/M FOR INIIALATION AND TRITIUM, AND IN UNITS OF M -HREH/YR PER pCI/SEC FOR AI.L OTilERS
8 Page 53 ] TABLE 3.3-16 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATIIWAY = GOATHILK AGE GROUP EQUALS INFANT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY TilYROID LUNG SKIN I I I I I I I I I 11 3 l 4.90E 03 l 4.90E 03 l 0.00E-01 l 4.90E 03 l 4.90E 03 l 4.90E 03 l 4.90E 03 l 4.90E 03 l
. 1 I I I I I I I l l l l l l l l HN 54 l 5.45E 05 l 8.83E 05 l 0.00E-01 l 2.40E 06 l 5.33E 05 l 0.00E-01 l 0.00E-01 l 0.00E-01 l l 1 I I I I I I FE 59 l 9.37E 05 l 1.14E 06 l 1.36E 06 l 2.38E 06 l 0.00E-01 l 0.00E-01 l 7.03E 05 l 0.00E-01 l l l 1 I I I I I I l i I I I CO 58 1 3.45E 06 l 3.45E 06 l 0.00E-01 l 1.38E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l I I 1
- I I I CO 60 l 1.34E 07 1 1.35E 07 l 0.00E-01 l 5.65E 06 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l l 1 1 I I I I I I I l I l l SR 89 l 3.58E 08 l 2.57E 08 l 1.25E 10 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1 1 1 1 I I I I I I SR 90 1 3.75E 10 l 1.84E 09 l 1.47E 11 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 0.00E-01 l l l t i 1 I I I I I I I I 131 1 8.31E 08 l 6.74E 07 l 1.60E 09 l 1.89E 09 l 2.21E 09 l 6.21E 11 l 0.00E-01 l 0.00E-01 l l l l [ l l I I I I I I I I I I CS134 l 1.08E 10 l 2.89E 08 l 5.71E 10 l 1.07E 11 l 2.74E 10 l 0.00E-01 l 1.12E 10 l 0.00E-01 l l I l 1 I I I 1
i i l l I I I I I i CS137 l 7.10E 09 l 3.13E 08 l 8.55E 10 l 1.00E 11 l 2.69E 10 l 0.00E-01 1 1.09E 10 l 0.00E-01 l l l I I I I I I I l l
- R VALUES IN llNITS OF HREH/YR PER pCI/H FOR INilALATION AND TRITIUM, AND IN UNITS OF M -HREH/YR PER i
pCI/SEC FOR ALL OTilERS i l l
A h ODCH Rev. 8 Page 54 TABLE 3.3-17 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATilWAY = INIIAL AGE GROUP EQUALS ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY TIIYROID LUNG SKIN l
I I I I I I I I I 11 3 l 1.26E 03 l 1.26E 03 l 0.00E-01 l 1.26E 03 1 1.26E 03 l 1.26E 03 l 1.26E 03 l 1.26E 03 l 1 I I I I I 1 I I I I I I I HN 54 l 6.29E 03 l 7.72E 04 l 0.00E-01 1 3.95E 04 l 9.83E 03 l 0.00E-01 l 1.40E 06 l 0.00E-01 l 1 1 1 1 I i 1 I I I I I I l l l FE 59 l 1.05E 04 l 1.88E 05 l 1.17E 04 l 2.77E 04 l 0.00E-01 l 0.00E-01 l 1.01E 06 l 0.00E-01 l 1 I I 1 1 I I I I I CO 58 l 2.07E 03 l 1.06E 05 l 0.00E-01 l 1.58E 03 l 0.00E-01 l 0.00E-01 l 9.27E 05 l 0.00E-01 l I I I I l 1 I I I I I l CO 60 l 1.48E 04 l 2.84E 05 l 0.00E-01 l 1.15E 04 l 0.00E-01 l 0.00E-01 l 5.96E 06 l 0.00E-01 l I I I I 1 I I I I I SR 89 l 8.71E 03 l 3.49E 05 l 3.04E 05 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1.40E 06 l 0.00E-01 l I I
! I I I I I SR 90 l 6.09E 06 l 7.21E 05 l 9.91E 07 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 9.59E 06 l 0.00E-01 l I I I 1 1 1 I I I I I I I 131 l 2.05E 04 l 6.27E 03 l 2.52E 04 l 3.57E 04 l 6.12E 04 l 1.19E 07 l 0.00E-01 l 0.00E-01 l l l l I I 1 l I I I I I l I CS134 l 7.27E 05 l 1.04E 04 l 3.72E 05 l 8.47E 05 l 2.87E 05 l 0.00E-01 l 9.75E 04 l 0.00E-01 l 1 I I I I l 1 1 I I I I I I CS137 l 4.27E 05 l 8.39E 03 l 4.78E 05 l 6.20E 05 l 2.22E 05 l 0.00E-01 l 7.51E 04 l 0.00E-01 l l l I I I I I I i
- R VALilES IN UNITS OF HREN/YR PER pC1/H FOR INIIALATION AND TRITIUM, AND IN UNITS OF M -HREH/YR PER pCI/SEC FOR ALL OTilERS
ODCH Rev. 8 Page 55 TABLE 3.3-18 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATilWAY = INIIAL AGE GROUP EQUALS TEEN
- NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY TIIYROID LUNG SKIN i l I I i l l l l l l 11 3 l 1.27E 03 l 1.27E 03 l 0.00E-01 l 1.27E 03 l 1.27E 03 l 1.27E 03- l 1.27E 03 l 1.27E 03 l I
I HN 54 l 8.39E 03 l 6.67E 04 l 0.00E-01 1 5.10E 04 l 1.27E 04 l 0.00E-01 l 1.98E 06 l 0.00E-01 l ! l l l l l l FE 59 l 1.43E 04 l 1.78E 05 l 1.59E 04 l 3.69E 04 l 0.00E-01 l 0.00E-01 l 1.53E 06 l 0.00E-01 1
- 1 I I I
! I I I l
- CO 58 l 2.77E 03 l 9.51E 04 l 0.00E-01 l 2.07E 03 l 0.00E-01 l 0.00E-01 l 1.34E 06 l 0.00E-01 l
- I l
CO 60 l 1.98E 04 l 2.59E 05 l 0.00E-01 1 1.51E 04 l 0.00E-01 l 0.00E-01 l 8.71E 06 ! 0.00E-01 l [ l I I I I SR 89 l 1.25E 04 l 3.71E 05 l 4.34E 05 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 2.41E 06 l 0.00E-01 l l 1 I I I I i SR 90 l 6.67E 06 l 7.64E 05 l 1.08E 08 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1.65E 07 l 0.00E-01 l l I 4 I 131 l 2.64E 04 l 6.48E 03 l 3.54E 04 l 4.90E 04 l 8.39E 04 l 1.46E 07 l 0.00E-01 l 0.00E-01 l 1 I I I I l l 1 1 I CS134 l 5.48E 05 l 9.75E 03 l 5.02E 05 l 1.13E 06 l 3.75E 05 l 0.00E-01 l 1.46E 05 l 0.00E-01 l I i _I I I I CS137 l 3.llE 05 l 8.47E 03 l 6.69E 05 l 8.47E 05 l 3.04E 05 l 0.00E-01 l 1.21E 05 l 0.00E-01 l 1 l l l l l l l l l
- R VALUES IN UNITS OF HREH/YR PER pCI/H FOR INilALATION AND TRITIUN, AND IN UNITS OF H -HREH/YR PER pC1/SEC FOR ALL OTilERS 1
O d ODCH Rev. 8 h D - Page 56 i l TABLE 3.3-19 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- PATilWAY = INilAL AGE GROUP EQUALS CIIILD NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN I I I I I I I I I
; 11 3 l 1.12E 03 l 1.12E 03 l 0.00E-01 l 1.12E 03 l 1.12E 03 l 1.12E 03 l 1.12E 03 l 1.12E 03 l i l I I I I I I HN 54 l 9.50E 03 l 2.29E 04 l 0.00E-01 l 4.29E 04 l 1.00E 04 l 0.00E-01 l 1.57E 06 l 0.00E-01 l 1
l 1 I FE 59 l 1.67E 04 l 7.06E 04 l 2.07E 04 l 3.34E 04 l 0.00E-01 l 0.00E-01 l 1.27E 06 l 0.00E-01 l l l I I CO 58 l 3.16E 03 l 3.43E 04 l 0.00E-01 l 1.77E 03 l 0.00E-01 l 0.00E-01 l 1.10E 06 l 0.00E-01 l l 1 1 I I l I I I i i i CO 60 l 2.26E 04 l 9.61E 04 l 0.00E-01 l 1.31E 04 l 0.00E-01 1 0.00E-01 l 7.06E 06 l 0.00E-01 l l 1 l I I I SR 89 l 1.72E 04 l 1.67E 05 l 5.99E 05 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 2.15E 06 l 0.00E-01 l l l l 1 SR 90 l 6.43E 06 l 3.43E 05 l 1.01E 08 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1.47E 07 l 0.00E-01 l 1 I I I I 131 l 2.72E 04 l 2.84E 03 l 4.80E 04 l 4.80E 04 l 7.87E 04 l 1.62E 07 l 0.00E-01 l 0.00E-01 l I [ l 1 1 1 1 I l l I I I l CS134 l 2.24E 05 l 3.84E 03 l 6.50E 05 l 1.01E 06 l 3.03E 05 1 0.00E-01 l 1.21E 05 1 0.00E-01 l I I I 1 1 I I I I l CS137 l 1.28E 05 l 3.61E 03 l 9.05E 05 l 8.24E 05 l 2.82E 05 1 0.00E-01 l 1.04E 05 1 0.00E-01 l l l l l l l l l 4 l
- R VALUES IN UNITS OF HREH/YR PER pCI/H FOR INilALATION AND TRITIUM, AND IN UNITS OF M -HREH/YR PER pC1/SEC FOR ALL OTilERS
ODCH Rev. 8 Page 57 i ' TABLE 3.3-20 R VALUES FOR Tile PRAIRIE ISLAND NUCLEAR GENERATING PLANT * ! PATIIWAY = INIIAL AGE GROUP EQUALS INFANT 4 NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY TilYROID LUNG SKIN I I I I I l l l l l li 3 l 6.46E 02 l 6.46E 02 l 0.00E-01 l 6.46E 02 l 6.46E 02 l 6.46E 02 l 6.46E 02 l 6.46E 02 l l 1 I I I l I I I I . NN 54 1 4.98E 03 l 7.05E 03 l 0.00E-01 l 2.53E 04 l 4.98E 03 l 0.00E-01 l 9.98E 05 l 0.00E-01 l ' i 1 l i I I I I I I I I I l l l
- FE 59 l 9.46E 03 l 2.47E 04 l 1.35E 04 l 2.35E 04 l 0.00E-01 l 0.00E-01 l 1.01E 06 l 0.00E-01 l i I I I I i I
'i I I I I I I I CO 58 l 1.82E 03 l 1.IIE 04 l 0.00E-01 l 1.22E 03 l 0.00E-01 l 0.00E-01 l 7.76E 05 l 0.00E-01 l 1 I J l i I I I I I I I I l Co 60 l 1.18E 04 l 3.19E 04 l 0.00E-01 l 8.01E 03 l 0.00E-01 l 0.00E-01 l 4.50E 06 l 0.00E-01 l . l i I I I I SR 89 l 1.14E 04 l 6.39E 04 l 3.97E 05 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 2.03E 06 l 0.00E-01 l I I
- 1
. I I I SR 90 l 2.59E 06 l 1.31E 05 l 4.08E 07 l 0.00E-01 l 0.00E-01 l 0.00E-01 l 1.12E 07 l 0.00E-01 l I I I I I I 1
I I I I I I I I 131 l 1.96E 04 l 1.06E 03 l 3.79E 04 l 4.43E 04 l 5.17E 04 l 1.48E 07 l 0.00E-01 l 0.00E-01 l 1 1 1 I l I I I I I CS134 l 7.44E 04 l 1.33E 03 1 3.96E 05 l 7.02E 05 l 1.90E 05 l 0.00E-01 l 7.95E 04 l 0.00E-01 l
' I I I 1 I I I l i I I I I I J CS137 l 4.54E 04 l 1.33E 03 l 5.48E 05 l 6.11E 05 l 1.72E 05 l 0.00E-01 l 7.12E 04 1 0.00E-01 l l l I I I !
l l l 3 2
- R VALUES IN UNITS OF HREH/YR PER pCI/H FOR INilALATION AND TRITIUH, AND IN UNITS OF M -HREH/YR PER pCI/SEC FOR ALL OTilERS l
ODCM'
- Rev.'8 Page'58 4.0 INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141 -
The PNGP Technical Specifications indicate that if twice the per unit limits of 10 CFR 50, Appendix 1 are exceeded, a special report is required. Therefore, if twice the annual .
~ limits of Equations 2.3-6, 2.3-7, 3.3-1, 3.3-2 or 3.3-3 are {
exceeded, the licensee shall prepare and submit a Special Report to the Commission and limit subsequent releases such that the dose or dose commitment'to a rea] Lndividual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over 12 consecutive months. This special Report is to include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous j effluent pathways and direct radiation) are less than the standards in 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations. If analysis indicates that releases resulting in doses that exceed the 40 CFR 190 Standard may have occurred, then a. variance from the Commission to permit such releases will be obtained. The Standard Technical Specificatichs 3.11.1.2, 3.11.2.2 and 3.11.2.3 consider doses to a real individual and apply to each reactor but do not include any other portion.of the uranium fuel cycle or dirset shine from the , reactor. () The " Uranium fuel cycle" is defined in 40 CFR Part 190.02(b) as:
" Uranium fuel cycle means the operations of miliing of -
uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel,
- generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use.
utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive macerial in support of these operations, and l ) the reuse of recovered non-uranium special nuclear and l by-product materials from the cycle." l l The Special Report will contain:
- 1) A determination of which uranium fuel cycle facilities or operations, in addition to the nuclear power reactor units at the site, contribute to the annual dose to the maximum exposed member of the public. Only those other
' fuel cycle facilities within 5 miles of PNGP need be considered; No such facilities exist or are planned at present. i ('N
\_)
l l IBM
ODCM
- - Rev. 8 !
Page 59
- 2) A determination of the maximum exposed member of the
,s public as given for determining compliance with 10 CFR
( ,) 50, Appendix 1.
- 3) A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents using the methodologies described for compliance with 10 CFR 50, Appendix 1 in this ODCM.
Where additional information on pathways and nuclides is needed, the best available information will be used and documented.
- 4) A determination of the dose resulting from direct radiation from the plant and storage facilities.
The various organ doses resulting from liquid effluents from the PNGP will be summed with the organ doses resulting from releases of noble gases, radioiodines and particulates. These doses will be based upon releases from the PNGP during the past 3 quarters and from the quarter in which twice the specification was exceeded. The doses from the PNGP will be summed with the doses to the maximum exposed individual contributed from other operations of the uranium fuel cycle. The direct dose components will be determined by either calculation or actual measurement. The N-16 component of direct radiation may be calculated using SKYSHINE. A Computer (') Procedure Evaluating Effects of Structure Design on N-16 Gamma-Rav Dose Rates. Radiation Research Associates, Inc. Report RRA-T7209, November 1972. (Available in the NSP-NSS Library). The calculation or actual measurement will be documented in this Special Report. If the quarterly or annual doses due to liquid releases exceed the values, listed in Section 2.3.3, a special report shall be submitted to the USNRC and shall include information related to 40 CFR 141 such as analysis of , Mississippi River water tad an analysis of possible impacts through the drinking weker pathway. l \ r IBM
= > - -----
[ ODCM
. P. Rev. 8 r Page 60 5.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling Table 5.1-1 and Figures 5.1-1, 5.1-2, and 5.1-3 specify
' the current. sampling locations based on the latest land
; use census.
If it is learned from an annual census that milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously. sampled, the new milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable. Sample locations'(except the control) having lower calculated doses may be dropped from the program at the end of the grazing or growing season (October 31) to keep the total number of sample locations constant. 5.2 Interlaboratorv Comparison Program Analyses shall be performed on radioactive samples supplied by the EPA crosscheck program. This program involves the analyses of samples provided by a control laboratory and comparison of results with those of the rs control laboratory as well as with other laboratories 1,) which receive portions of the same samples. Media used in this program (air, milk, water, etc.) shall be limited to those found in the radiation environmental monitoring program. The.results of analyses performed as a part of the crosscheck program shall be included in the Annual Radiation Environmental Monitoring Report. V i i l I i i !O IBM
ODCM
. Rev. 8 Page 61 TABLE 5.1-1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Code Collection Site Location River Water P-Sc Upstream of Plant 0.6 mi @ 60 /ENE River Water P-6 Lock & Dam #3 1.6 mi @ 129 /SE Drinking Water P-11 City of Red Wing 7.1 mi 0 135 /SE Well Water P-25c Kinneman Farm 11.1 mi @ 331 /NNW Well Water P-6 Lock & Dam #3 1.6 mi @ 129 /SE Well Water P-8 Kinney Store 2.0 mi @ 280*/W Well Water P-9 Plant Well #2 0.3 mi @ 306 /NW C
Sediment-River P-5 Upstream of Plant 0.6 mi @ 60 /ENE Sediment-River P-6 Lock & Dam #3 1.6 mi @ 129 /SE Sediment-Shoreline P-12 Recreation Area 3.4 mi @ 116 /ESE Periphyton or P-5c Upstream of Plant 0.6 mi @ 60 /ENE () Macroinvertebrates Fish P-6 P-Sc Lock & Dam #3 Upstream of Plant 1.6 mi @ 129 /SE 0.6 mi @ 60 /ENE Fish P-6 Lock & Dam #3 1.6 mi @ 129 /SE Milk P-25 c Kinneman Farm 11.1 mi @ 331 /NNW Milk P-14 Gustafson Farm 2.2 mi @ 168 /SSE Milk P-16 Johnson Farm 2.6 mi @ 60 /ENE Milk P-17 Place Farm 3.5 mi @ 25 /NNE Milk P-18 Christensen Farm 3.7 mi @ 88 /E IBM
ODCM Rev. 8 Page 62 TABLE 5.1-1 (Continued) iQ V PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS i Type of Sample Code Collection Site Location Cultivated Crops (Leafy Green Veg) P-25c Kinneman Farm 11.1 mi-@ 331 /NNW P-24 Suter Residence 0.6 mi @ 158 /SSE (Corn) P-25 C Kinneman Farm 11.1 mi @ 331 /NNW P-14 Gustafson Farm 2.2 mi @ 168 /SSE c Particulates and P-l Air Station P-1 16.5 mi @ 348 /NNW Radiciodine (air) Particulates and P-2 Air Station P-2 0.5 mi @ 294 /WNW Radiciodine (air) Particulates and P-3 Air Station P-3 0.8 mi @ 313 /NW Radiciodine (air) Particulates and P-4 Air Station P-4 0.4 mi @ 359 /N Radioiodine (air) Particulates and P-6 Air Station P-6 1.6 mi @ 129 /SE Radioiodine (air) Direct Radiation (TLD) P0lA Property Line 0.4 mi @ 359 /N Direct Radiation (TLD) P02A Property Line 0.3 mi @ 19 /NNE Direct Radiation (TLD) P03A Property Line 0.5 mi @ 183 /S Direct Radiation (TLD) PO4A Property Line 0.4 mi @ 204*/SSW Direct Radiation (TLD) POSA Property Line 0.4 mi @ 225 /SW O IBM
ODCM
- Rev. 8 Page 63 TABLE 5.1-1 (Continued) b U
PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Code Collection Site Location Direct Radiation (TLD) P06A Property Line 0.4 mi @ 249 /WSW Direct Radiation (TLD) P07A Property Line 0.4 mi @ 268*/W Direct Radiation (TLD) P08A Property Line 0.4 mi @ 291 /WNW Direct Radiation (TLD) P09A Property Line 0.7 mi @ 317 /NW Direct Radiation (TLD) P10A Property Line 0.5 mi @ 333 /NNW Direct Radiation (TLD) PolB Tom Killian Res. 4.7 mi @ 355 /N Direct Radiation (TLD) P02B Roy Kinneman Farm 4.8 mi @ 17 /NNE Direct Radiation (TLD) P03B Wayne Anderson Farm 4.9 mi @ 46 /NE Direct Radiation (TLD) PO4B Nelson Drive (Road) 4.2 mi @ 61*/ENE l Direct Radiation (TLD) P05B County Rd E & Coulee 4.1 mi @ 97 /E l Direct Radiation l (TLD) P06B William Houschildt Res. 4.4 mi @ 112 /ESE Direct Radiation (TLD) P07B Red Wing Service Center 4.7 mi @ 140 /SE i Direct Radiation (TLD) P08B David Wnuk Res. 4.1 mi @ 165 /SSE l l Direct Radiation (TLD) P09B Hwy 19 South 4.2 mi @ 187 /S Direct Radiation k (TLD) P10B Cannondale Farm 4.9 mi @ 200*/SSW l IBM r
ODCM Rev. 8 Page 64 TABLE 5.1-1 (Continued) PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1 RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Code Collection Site Location Direct Radiation (TLD) P11B Wallace Weberg Farm 4.5 mi @ 221 /SW Direct Radiation (TLD) P12B Roy Gergen Farm 4.5 mi @ 247*/WSW Direct Radiation (TLD) P13B Thomas O'Rourke Farm 4.4 mi @ 270 /W Direct Radiation (TLD) P14B David Anderson Farm 4.9 mi 0 306 /NW Direct Radiation (TLD) P15B Holst Farms 4.2 mi 0 347 /NNW Direct Radiation (TLD) P01S Federal Lock & Dam #3 1.6 mi @ 129 /SE Direct Radiation (TLD) P02S Charles Suter Res. 0.5 mi @ 155 /SSE Direct Radiation (TLD) P03S Carl Gustafson Farm 2.2 mi @ 168 /SSE Direct Radiation (TLD) P04S Richard Burt Res. 2.0 mi @ 228*/SW Direct Radiation (TLD) PO5S Kinney Store 2.0 mi @ 270 /W Direct Radiation (TLD) P06S Earl Flynn Farm 2.5 mi @ 299 /WNW Direct Radiation (TLD) P01C Robert Kinneman Farm 11.1 mi @ 331 /NNW
* "c" denotes control location. All other locations are indicators.
The letters after numbered TLD's are as follows:
"A" denotes locations in the general area of the site boundary.
"B" denotes locations about 4 to 5 miles distance from the plant.
l "S" denotes special interest locations. IBM
ODCM - Rev. 8 - Page 65
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ODCM Rev. 8 Page 68
- APPENDIX A - METEOROLOGICAL ANALYSES O Table A-1 Release Conditions Table A-2 Unrestricted Area Boundaries Table A-3 Long Term - Ground Level - Unrestricted Area Boundary - X/Q and D/Q.
Table A-4 Long Term -Ground Level - Standard Distances - X/Q Table A-5 Long Term - Ground Level - Standard Distances - D/Q Table A-6 Short Term - Ground Level - Unrestricted Area Boundary - X/q and D/q Table A-7 Short Term - Ground Level - Standard Distances - X/q Table A-8 Short Term - Ground Level - Standard Distances - D/q lO l e J l IBM i
ODCM
- Rev. 8 Page 69 APPENDIX - A Ch V Summary of Dispersion Calculational Procedures Undepleted, undecayed dispersion parameters were computed using the computer program XOQDOQ (Sagendorf and Goll, 1977).
Specifically, sector average X/Q and D/Q values were obtained for a sector width of 22.5 degrees. Building wake corrections were used to adjust calculations for ground-level releases. Standard open terrain recirculation correction factors were also applied as available as default values in XOQDOQ. Dispersion calculations were based on ground level releases for the shield buildings, turbine building, and auxiliary building (hereafter referred to as the plant complex). A summary of release conditions used as input to XOQDOQ is presented in Table A-1 and controlling unrestricted boundary distances are defined in Table A-2. Computed X/Q and D/Q values for unrestricted area boundary locations (relative to release points) and for standard distances (to five miles from the source in 0.1 mile increments) are presented in Tables A-3 through A-8. Onsite meteorological data for the period April 1, 1977 through March 31, 1978 (as presented in Appendix B) were used as input to XOQD0Q. Data were collected and AT stability classes were O. defined in conformance with NRC Regulatory Guide 1.23. Dispersion
^
calculations for the plant complex were based on AT 42.7-12.2m and 12.2 meter wind data (joint data recovery of 96 percent). i I l V IBM
ODCM Rev. 8
- Page 70 R_EFERENCES
- O 1. Sagendorf, J.F. and Goll, J.T., XOQDOQ Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG-0324, U.S. Nuclear Regulatory Commission, September 1977.
i i lO l l O IBM
ODCH Rev. 8 Page 71 i TABLE A-1 Prairie Island Release Conditions I I l l l I l l Shield Buildings l Auxiliary Building l Turbine Building l l 1 I I I I I I l l l Type Release l Ground Level l Ground Level l Ground Level l l l (Long Term and Short Term) l (Long Term) l (Long Term) l l l l l l
- I l l l l l Release Point Ileight (m) l 56.4 l 24.4 l 33.6, 12.2 l l l l l l l Adjacent Building Ileight l 62.2 l 62.2* l 62.2* l l l l l l l Relative Location to l Adjacent to l Adjacent to l Adjacent to l l Adjacent Structures l Auxiliary Building l Auxiliary Building l Auxiliary Building l l l l l l l Exit Velocity (m/sec) l N.A. l N.A. l N.A. l
- l l l l l i l Internal Stack Diameter (m) l N.A. l N.A. l N.A. l l l l l l
- l Building 2 Cross-Sectional l l l l
! l Area (m ) l 2,170 l 2,170** l 2,170** l l l l l l l Purge Frequency ***(times /yr)l 20 l N.A. l N.A. l l l l . l l l Purge Duration ***(hours / l l l l l l release) l 5 l N.A. l N.A. l l l l l l
- Ileight of Shield Buildings
** Shield Building cross-sectional area j *** Applied to short-term calculations only l
i
l ODCM Rev. 8 Page 72 TABLE A-2 Distances (Miles) To Controlling Unrestricted Area Boundary Locations , l As Measured from Edge of Plant Complex Sector Distance N 0.28 NNE 0.26 NE 0.84* ENE 0.62*
,.. E 0.59*
ESE 0.61* SE 0.67 SSE 0.43 l A S 0.43 1 U SSW 0.40 SW 0.40 WSW 0.37 i W 0.36 l I WNW 0.36 l NW 0.43 I NNW 0.48
- Over-water distances O
IBM
ODCH Rev. 8 Page 73 TABLE A-3
~
i l Prairie Island Dispersion Parameters for Long Term Ground Level Releases > 500 llrs/Yr or > 150 lirs/QTR
- for Unrestricted Area Boundary Locations (identified in Table A-2) l Unrestricted Area 2 3
Boundary Sector )(/Q (sec/m ) D/Q (1/m ) i N 1.82E-05 1.18E-07 i NNE 1.52E-05 8.55E-08 l NE 1.83E-06 7.74E-09 l ENE 3.25E-06 1.84E-08 , E 1.05E-05 4.23E-08 i j ESE 1.86E-05 7.30E-08 i SE 1.67E-05 6.80E-08 i ] SSE 1.95E-05 6.81E-08 l S 8.12E-06 3.19E-08 l SSW 7.08E-06 2.55E-08
- SW 7.66E-06 2.77E-08
- ' WSW 1.13E-05 3.53E-08 l W 2.66E-05 7.63E-08 1
WNW 3.38E-05 1.42E-07 ] l NW 2.13E-05 9.02E-08 NNW 1.11E-05 5.43E-08 i I i i 1 Period of Record: 4/1/77 - 3/31/78 i IBM
8 Page 74 TABLE A-4 - Prairie Island Dispersion Parameters (X/Q), sec/m , for Long Term Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Heasured from Edge of Plant Complex) Miles Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 N 1.20E-04 3.44E-05 1.66E-05 1.02E-05 7.04E-06 5.29E-06 4.13E-06 NNE 8.53E-05 2.44E-05 1.18E-05 7.20E-06 4.93E-06 3.67E-06 2.83E-06 NE 8.18E-05 2.35E-05 1.14E-05 6.87E-06 4.69E-06 3.49E-06 2.69E-06 ENE 7.88E-05 2.26E-05 1.10E-05 6.70E-06 4.62E-06 3.46E-06 2.69E-06 E 2.40E-04 6.89E-05 3.34E-05 2.02E-05 1.38E-05 1.02E-OS 7.88E-06 ESE 4.52E-04 1.30E-04 6.28E-05 3.80E-05 2.59E-05 1.92E-05 1.48E-05 SE 4.85E-04 1.39E-04 6.74E-05 4.07E-05 2.77E-05 2.04E-05 1.56E-05 SSE 2.59E-04 7.44E-05 3.60E-05 2.17E-05 1.48E-05 1.10E-05 8.44E-06 S 1.08E-04 3.09E-05 1.49E-05 9.06E-06 6.20E-06 4.62E-06 3.58E-06 SSW 8.60E-05 2.46E-05 1.19E-05 7.19E-06 4.91E-06 3.66E-06 2.83E-06 SW 9.19E-05 2.62E-05 1.26E-05 7.72E-06 5.31E-06 3.98E-06 3.09E-06 WSW l.17E-04 3.35E-05 1.61E-05 9.80E-06 6.70E-06 4.97E-06 3.83E-06 W 2.64E-04 7.56E-05 3.66E-05 2.22E-05 1.51E-05 1.12E-05 8.61E-06 WNW 3.42E-04 9.80E-05 4.75E-05 2.88E-05 1.98E-05 1.47E-05 1.14E-05 NW 2.91E-04 8.35E-05 4.05E-05 2.46E-05 1.68E-05 1.25E-05 9.67E-06 NNW I.76E-04 5.04E-05 2.45E-05 1.50E-05 1.03E-05 7.70E-06 5.99E-06 Period of Record: 4/1/77 - 3/31/78 IBM
. _ ~ . _ _ _ - - - _ _ - - . . . - _ . - - _- -_
8 Page 75 TABLE A-4 (Cont.) 3 j Prairie Island Dispersion Parameters (X/Q), sec/m , for Long Term Ground Level Releases > 500 lirs/Yr or > 150 Hrs /QTR i for Standard Distances (As Heasured from Edge of Plant Complex) l Hiles i i Sector 0.8 0.9 1.0 1.I 1.2 1.3 1.4 f ! N 3.18E-06 2.39E-06 1.87E-06 1.51E-06 1.24E-06 1.04E-06 8.80E-07 ! NNE 2.17E-06 1.62E-06 1.27E-06 1.02E-06 8.33E-07 6.95E-07 5.90E-07 l NE 2.06E-06 1.54E-06 1.20E-06 9.60E-07 7.86E-07 6.56E-07 5.56E-07 j ENE 2.07E-06 1.55E-06 1.21E-06 9.72E-07 7.98E-07 6.66E-07 5.65E-07 I E 6.02E-06 4.51E-06 3.52E-06 ' 2.82E-06 2.31E-06 1.93E-06 1.64E-06 i ESE 1.13E-05 8.44E-06 6.58E-06 5.28E-06 4.33E-06 3.62E-06 3.07E-06
- SE 1.19E-05 8.92E-06 6.96E-06 5.58E-06 4.58E-06 3.82E-06 3.25E-06
- SSE 6.45E-06 4.82E-06 3.76E-06 3.01E-06 2.47E-06 2.06E-06 1.75E-06 S 2.74E-06 2.06E-06 1.61E-06 1.29E-06 1.06E-06 8.88E-07 7.54E-07 l SSW 2.17E-06 1.63E-06 1.27E-06 1.02E-06 8.36E-07 6.99E-07 5.93E-07 SW 2.38E-06 1.78E-06 1.39E-06 1.12E-06 9.17E-07 7.66E-07 6.50E-07 t WSW 2.93E-06 2.19E-06 1.71E-06 1.37E-06 1.12E-06 9.35E-07 7.93E-07 4
W 6.57E-06 4.91E-06 3.83E-06 3.07E-06 2.51E-06 2.10E-06 1.78E-06 I WNW 8.77E-06 6.58E-06 5.14E-06 4.13E-06 3.39E-06 2.83E-06 2.41E-06 NW 7.40E-06 5.56E-06 4.35E-06 3.50E-06 2.88E-06 2.41E-06 2.05E-06 f NNW 4.60E-06 3.46E-06 2.71E-06 2.18E-06 1.79E-06 1.50E-06 1.28E-06 I 1 I { Period of Record: 4/1/77 - 3/31/7f f IBM
8 j Page 76 i TABLE A-4 (Cont.) - ) Prairie Island Dispersion Parameters (X/Q), sec/m , for Long Term Ground Level Releases > 500 lirs/Yr or > 150 lirs/QTR l for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 l N 7.57E-07 6.59E-07 5.79E-07 5.13E-07 4.59E-07 4.14E-07 3.76E-07 l NNE 5.07E-07 4.41E-07 3.87E-07 3.43E-07 3.07E-07 2.77E-07 2.52E-07 NE 4.77E-07 4.15E-07 3.64E-07 3.23E-07 2.89E-07 2.61E-07 2.38E-07 ! ENE 4.86E-07 4.23E-07 3.71E-07 3.29E-07 2.94E-07 2.65E-07 2.41E-07 E 1.41E-06 1.23E-06 1.08E-06 9.55E-07 8.56E-07 7.75E-07 7.05E-07 I ESE 2.64E-06 2.30E-06 2.02E-G6 1.79E-06 1.61E-06 1.46E-06 1.32E-06 l SE 2.79E-06 2.43E-06 2.14E-06 1.90E-06 1.70E-06 1.54E-06 1.40E-06 1 SSE 1.50E-06 1.31E-06 1.15E-06 1.02E-06 9.12E-07 8.25E-07 7.5!E-07 ] l S 6.49E-07 5.65E-07 4.97E-07 4.41E-G7 3.95E-07 3.56E-07 3.24E-07 l SSW 5.10E-07 4.44E-07 3.90E-07 3.46E-07 3.10E-07 2.80E-07 2.54E-07 l SW 5.59E-07 4.87E-07 4.27E-07 3.79E-07 3.39E-07 3.06E-07 2.78E-07 1 ] WSW 6.82E-07 5.93E-07 5.21E-07 4.61E-07 4.13E-07 3.74E-07 3.40E-07 j W l.53E-06 1.33E-06 1.17E-06 1.04E-06 9.29E-07 8.40E-07 7.64E-07 l WNW 2.07E-06 1.80E-06 1.59E-06 1.41E-06 1.26E-06 1.14E-06 1.03E-06 1 ) NW 1.76E-06 1.54E-06 1.35E-06 1.20E-06 1.08E-06 9.72E-07 8.83E-07 NNW 1.10E-06 9.59E-07 8.43E-07 7.47E-07 6.69E-07 6.04E-07 5.49E-07 l 1 l Period of Record: 4/1/77 - 3/31/78 i ! 2 i IBM v - - - _ _
V 8 . Page 77 l TABLE A-4 (Cont.) - 3 Prairie Island Dispersion Parameters (X/Q), sec/m , for Long Term Ground Level Releases > 500 IIrs/Yr or > 150 Ilts/QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 2.2 2.3 2.4 2.5 2.6 2.7 2.8 1 N 3.42E-07 3.14E-07 2.89E-07 2.67E-07 2.47E-07 2.30E-07 2.15E-07 I NNE 2.30E-07 2.llE-07 1.94E-07 1.80E-07 1.67E-07 1.56E-07 1.45E-07 NE 2.17E-07 1.99E-07 1.84E-07 1.70E-07 1.58E-07 1.47E-07 1.38E-07 ENE 2.20E-07 2.01E-07 1.85E-07 1.71E-07 1.59E-07 1.48E-07 1.38E-07 E 6.44E-07 5.92E-07 5.46E-07 5.05E-07 4.70E-07 4.38E-07 4.09E-07 . ESE 1.21E-06 1.11E-06 1.03E-06 9.51E-07 8.84E-07 8.25E-07 7.71E-07 SE 1.28E-06 1.18E-06 1.09E-06 1.01E-06 9.37E-07 8.74E-07 8.17E-07 SSE 6.86E-07 6.31E-07 5.82E-07 5.39E-07 5.01E-07 4.67E-07 4.37E-07 S 2.96E-07 2.71E-07 2.50E-07 2.31E-07 2.15E-07 2.00E-07 1.87E-07 ! SSW 2.32E-07 2.13E-07 1.96E-07 1.82E-07 1.69E-07 1.57E-07 1.47E-07 SW 2.53E-07 2.32E-07 2.14E-07 1.98E-07 1.83E-07 1.71E-07 1.59E-07 WSW 3.IIE-07 2.85E-07 2.63E-07 2.43E-07 2.26E-07 2.11E-07 1.97E-07 W 6.99E-07 6.42E-07 5.93E-07 5.49E-07 5.10E-07 4.76E-07 4.45E-07 WNW 9.44E-07 8.67E-07 7.99E-07 7.39E-07 6.86E-07 6.39E-07 5.97E-07 NW 8.07E-07 7.41E-07 6.83E-07 6.32E-07 5.87E-07 5.47E-07 5.12E-07 NNW 5.01E-07 4.59E-07 4.23E-07 3.91E-07 3.63E-07 3.38E-07 3.15E-07 i i Period of Record: 4/1/77 - 3/31/78 IBM
, 8 -
Page 78 1 TABLE A-4 (Cont.) l Prairie Island Dispersion Parameters (X/Q), sec/m , l for Long Term Ground Level Releases > 500 lirs/Yr or > 150 Hrs /QTR ! for Standard Distances (As Measured from Edge of Plant Complex) i
' Miles i Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5 I
i N 2.01E-07 1.88E-07 1.77E-07 1.67E-07 1.58E-07 1.49E-07 1.42E-07 l NNE 1.36E-07
- 1.28E-07 1.20E-07 1.14E-07 1.07E-07 1.02E-07 9.65E-08 NE 1.29E-07 1.21E-07 1.14E-07 1.08E-07 1.02E-07 9.69E-08 9.20E-08 ENE 1.29E-07 1.21E-07 1.14E-07 1.07E-07 1.01E-07 9.60E-08 9.IIE-08 E 3.84E-07 3.61E-07 3.40E-07 3.21E-07 3.04E-07 2.88E-07 2.74E-07 ESE 7.23E-07 6.80E-07 6.41E-07 6.05E-07 5.73E-07 5.43E-07 5.16E-07 SE 7.67E-07 7.21E-07 6.80E-07 6.42E-07 6.08E-07 5.77E-07 5.48E-07
) SSE 4.10E-07 3.85E-07 3.63E-07 3.43E-07 3.24E-07 3.08E-07 2.92E-07 j S 1.75E-07 1.64E-07 1.55E-07 1.46E-07 1.38E-07 1.31E-07 1.24E-07 SSW l.38E-07 1.29E-07 1.22E-07 1.15E-07 1.09E-07 1.03E-07 9.77E-08 SW l.49E-07 1.40E-07 1.32E-07 1.24E-07 1.17E-07 1.llE-07 1.05E-07 ) WSW l.85E-07 1.74E-07 1.64E-07 1.54E-07 1.46E-07 1.39E-07 1.32E-07 W 4.17E-07 3.92E-07 3.70E-07 3.49E-07 3.30E-07 3.13E-07 2.98E-07 ) WNW 5.60E-07 5.26E-07 4.95E-07 4.67E-07 4.42E-07 4.19E-07 3.98E-07 NW 4.79E-07 4.50E-07 , 4.24E-07 4.00E-07 3.79E-07 3.59E-07 3.41E-07 i i NNW 2.95E-07 2.77E-07 2.61E-07 2.46E-07 2.32E-07 2.20E-07 2.09E-07 l l Period of Record: 4/1/77 - 3/31/78 l i l IBM
ODCM , Rev. 8 Page 79 TABLE A-4 (Cont.) 3 Prairie Island Dispersion Parameters (X/Q), sec/m , 'i for Long Term Ground Level Releases > 500 llrs/Yr or > 150 Hrs /QTR
- for Standard Distances (As Heasured from Edge of Plant Complex) i Hiles
- Sector 3.6 3.7 3.8 3.9 4.0 4.1 4.2 i
i N 1.35E-07 1.28E-07 1.22E-07 1.16E-07 1.11E-07 1.07E-07 1.02E-07 1
; NNE 9.18E-08 8.74E-08 8.34E-08 7.97E-08 7.62E-08 7.30E-08 7.00E-08 NE 8.75E-08 8.34E-08 7.96E-08 7.61E-08 7.28E-08 6.98E-08 6.70E-08 j ENE 8.66E-08 8.24E-08 7.86E-08 7.50E-08 7.17E-08 6.86E-08 6.58E-08 I E 2.60E-07 2.48E-07 2.37E-07 2.26E-07 2.17E-07 2.08E-07 1.99E-07 i ESE 4.91E-07 4.68E-07 4.47E-07 4.27E-07 4.09E-07 3.92E-07 3.76E-07
! SE 5.22E-07 4.97E-07 4.75E-07 4.54E-07 4.35E-07 4.17E-07 4.00E-07 j SSE 2.78E-07 2.65E-07 2.53E-07 2.42E-07 2.32E-07 2.22E-07 2.13E-07 S 1.18E-07 1.12E-07 1.07E-07 1.02E-07 9.79E-08 9.38E-08 8.99E-08 . SSW 9.29E-08 8.85E-08 8.44E-08 8.07E-08 7.72E-08 7.39E-08 7.09E-08 SW l.00E-07 9.54E-08 9.10E-08 8.69E-08 8.31E-08 7.95E-08 7.62E-08 WSW l.25E-07 1.19E-07 1.14E-07 1.09E-07 1.04E-07 9.98E-08 9.57E-08 W 2.83E-07 2.70E-07 2.58E-07 2.47E-07 2.36E-07 2.26E-07 2.17E-07 i WNW 3.78E-07 3.60E-07 3.44E-07 3.28E-07 3.14E-07 3.01E-07 2.89E-07 j NW 3.24E-07 3.09E-07 2.95E-07 2.82E-07 2.70E-07 2.58E-07 2.48E-07 I NNW l.99E-07 1.89E-07 1.80E-07 1.72E-07 1.65E-07 1.58E-07 1.51E-07 i i
! Period of Record: 4/1/77 - 3/31/78 IBM
! 8 l Page 80 i
TABLE A-4 (Cont.) i Prairie Island Dispersion Parameters (X/Q), sec/m ,3 I
- for Long Term Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /QTR
{ for Standard Distances (As Heasured from Edge of Plant Complex) l li Hiles 5 j Sector 4.3 4.4 4.5 4.6 4.7 4.8 4.9 j l N 9.79E-08 9.41E-08 9.04E-08 8.71E-08 8.39E-08 8.09E-08 7.81E-08 ? NNE 6.72E-08 6.46E-08 6.22E-08 5.99E-08 5.77E-08 5.57E-08 5.38E-08 NE 6.43E-08 6.18E-08 5.95E-08 5.74E-08 5.53E-08 5.34E-08 5.16E-08
- ENE 6.31E-08 6.06E-08 5.83E-08 5.62E-08 5.41E-08 5.22E-08 5.04E-08 E 1.91E-07 1.84E-07 1.77E-07 1.71E-07 1.65E-07 1.59E-07 1.54E-07 ESE 3.62E-07 3.48E-07 3.35E-07 3.23E-07 3.11E-07 3.01E-07 2.91E-07 l
SE 3.85E-07 3.70E-07 3.56E-07 3.44E-07 3.31E-07 3.20E-07 3.09E-07 SSE 2.05E-07 1.97E-07 1.90E-07 1.83E-07 1.76E-07 1.70E-07 1.65E-07 S 8.63E-08 8.30E-08 7.98E-08 7.69E-08 7.41E-08 7.15E-08 6.91E-08 1 SSW 6.81E-08 6.55E-08 6.30E-08 6.07E-08 5.85E-08 5.65E-08 5.46E-08 SW 7.32E-08 7.03E-08 6.76E-08 6.51E-08 6.28E-08 6.06E-08 5.85E-08 ] WSW 9.19E-08 8.84E-08 8.51E-08 8.20E-08 7.91E-08 7.64E-08 7.38E-08 l W 2.09E-07 2.01E-07 1.93E-07 1.86E-07 1.80E-07 1.73E-07 1.68E-07 l WNW 2.77E-07 2.66E-07 2.56E-07 2.47E-07 2.38E-07 2.30E-07 2.22E-07 NW 2.38E-07 ,2.29E-07 2.20E-07 2.12E-07 2.05E-07 1.97E-07 1.91E-07 NNW 1.45E-C7 1.39E-07 1.34E-07 1.29E-07 1.24E-07 1.20E-07 1.16E-07 Period of Record: 4/1/77 - 3/31/78 l I IBM i
i 8 j Page 81 l TABLE A-4 (Cont.)
'l 3 ; Prairie Island Dispersion Parameters (X/Q), sec/m , ) for Long Term Ground Level Releases > 500 Ifrs/Yr or > 150 Hrs /QTR j for Standard Distances (As Measured from Edge of Plant Complex)
I Hiles 4 i l j Sector 5.0 i N 7.54E-08 NNE 5.20E-08 i NE 4.99E-08 ENE 4.87E-08 E 1.49E-07
. ESE 2.81E-07 1
] SE 2.99E-07 j SSE 1.59E-07 S 6.68E-08 SSW 5.27E-08
- SW 5.65E-08
! WSW 7.14E-08 i W l.62E-07 I WNW 2.15E-07 l NW l.84E-07 l 1.12E-07 4 NNW i i .i l Period of Record: 4/1/77 - 3/31/78 I I i l IBM i
ODCH ' Rev. 8
- Page 82 TABLE A-5 Prairie Island Dispersion Parameters (D/Q), 1/m for Long Term Ground Level Releases > 500 lirs/Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) l Hiles l
i Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 ! N 5.38E-07 2.01E-07 1.09E-07 6.97E-08 4.87E-08 3.62E-08 2.81E-08 i NNE 3.39E-07 1.27E-07 6.87E-08 4.39E-08 3.07E-08 2.28E-08 1.77E-08 I NE 2.21E-07 8.28E-08 4.49E-08 2.87E-08 2.01E-08 1.49E-08 1.16E-08 i i ENE 2.88E-07 1.08E-07 5.85E-08 3.73E-08 2.61E-08 1.94E-08 1.51E-08 E 6.15E-07 2.30E-07 1.25E-07 7.97E-08 5.57E-08 4.14E-08 3.22E-08 l ESE 1.12E-06 4.19E-07 2.27E-07 1.45E-07 1.02E-07 7.54E-08 5.86E-08 SE 1.22E-06 4.55E-07 2.47E-07 1.58E-07 1.10E-07 8.19E-08 6.36E-08 ) SSE 5.81E-07 2.17E-07 1.18E-07 7.53E-08 5.27E-08 3.91E-08 3.04E-08 j S 2.72E-07 1.02E-07 5.53E-08 3.53E-08 2.47E-08 1.83E-08 1.42E-08 ) SSW 2.00E-07 7.47E-08 4.06E-08 2.59E-08 1.81E-08 1.34E-08 1.04E-08 1 i SW 2.16E-07 8.06E-08 4.38E-08 2.79E-08 1.95E-08 1.45E-08 1.13E-08 WSW 2.39E-07 8.93E-08 4.85E-08 3.09E-08 2.16E-08 1.61E-08 1.25E-08 i V 5.00E-07 1.87E-07 1.01E-07 6.47E-08 4.53E-08 3.36E-08 2.61E-08 WNW 9.50E-07 3.55E-07 1.93E-07 1.23E-07 8.60E-08 6.39E-08 4.96E-08 NW 7.95E-07 2.97E-07 1.61E-07 1.03E-07 7.20E-08 5.35E-08 4.15E-08 NNW 5.54E-07 2.07E-07 1.12E-07 7.17E-08 5.02E-08 3.72E-08 2.89E-08 i l Period of Record: 4/1/77 - 3/31/78 IBM
~
8
- Page 83 TABLE A-5 (Cont.)
Prairie Island Dispersion Parameters (D/Q), 1/m for Long Term Ground Level Releases > 500 IIrs/Yr or > 150 lirs/QTR for Standard Distances (As Heasured from Edge of Plant. Complex) l Hiles j Sector 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1 N 2.13E-08 1.56E-08 1.19E-08 9.32E-09 7.47E-09 6.10E-09 5.07E-09 f NNE 1.34E-08 9.84E-09 7.49E-09 5.87E-09 4.70E-09 3.84E-09 3.19E-09 NE 8.76E-09 6.43E-09 4.90E-09 3.83E-09 3.07E-09 2.51E-09 2.09E-09 ENE 1.14E-08 8.37E-09 6.37E-09 4.99E-09 4.00E-09 3.27E-09 2.72E-09 E 2.43E-08 1.79E-08 1.36E-08 1.07E-08 8.54E-09 6.98E-09 5.80E-09 ESE 4.43E-08 3.26E-08 2.48E-08 1.94E-08 1.56E-08 1.27E-08 1.06E-08 j SE 4.81E-08 3.54E-08 2.69E-08 2.1IE-08 1.69E-08 1.38E-08 1.15E-08 $ SSE 2.30E-08 1.69E-08 1.29E-08 1.01E-08 8.07E-09 6.59E-09 5.48E-09 l S 1.08E-08 7.92E-09 6.03E-09 4.72E-09 3.78E-09 3.09E-09 2.57E-09 SSW 7.91E-09 5.81E-09 4.42E-09 3.46E-09 2.77E-09 2.27E-09 1.88E-09 SW 8.53E-09 6.26E-09 4.77E-09 3.73E-09 2.99E-09 2.45E-09 2.03E-09 i WSW 9.45E-09 6.94E-09 5.28E-09 4.14E-09 3.32E-09 2.71E-09 2.25E-09 j ) W 1.98E-08 1.45E-08 1.10E-08 8.65E-09 6.93E-09 5.67E-09 4.71E-09 WNW 3.76E-08 2.76E-08 2.10E-08 1.64E-08 1.32E-08 1.08E-08 8.95E-09 NW 3.14E-08 2.31E-08 1.76E-08 1.38E-08 1.10E-08 9.02E-09 7.49E-09 NNW 2.19E-08 1.61E-08 1.22E-08 9.59E-09 7.68E-09 6.28E-09 5.22E-09 i i Period of Hecord: 4/1/77 - 3/31/78 1 1 l IBM
O O =" Rev. 8 O Page 84 l I TABLE A-5 (Cont.) ! l Prairie Island Dispersion Parameters (D/Q), 1/m for Long Term Ground Level Releases > 500 lirs/Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) i Miles i Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 4 N 4.27E-09 3.65E-09 3.14E-09 2.73E-09 2.40E-09 2.12E-09 1.89E-09 NNE 2.69E-09 2.30E-09 1.98E-09 1.72E-09 1.51E-09 1.33E-09 1.19E-09 l NE 1.76E-09 1.50E-09 1.29E-09 1.13E-09 9.87E-10 8.72E-10 7.76E-10 ] 1.01E-09 l ENE 2.29E-09 1.95E-09 1.68E-09 1.46E-C9 1.28E-09 1.14E-09 , E 4.88E-09 4.17E-09 3.59E-09 3.13E-09 2.74E-09 2.42E-09 2.16E-09 ESE 8.90E-09 7.59E-09 6.54E-09 5.69E-09 4.99E-09 4.41E-09 3.93E-09 SE 9.66E-09 8.25E-09 7.11E-09 6.18E-09 5.43E-09 4.79E-09 4.27E-09 SSE 4.61E-09 3.94E-09 3.39E-09 2.95E-09 2.59E-09 2.29E-09 2.04E-09 S 2.16E-09 1.85E-09 1.59E-09 1.38E-09 1.21E-09 1.07E-09 9.55E-10 ] 8.91E-10 7.87E-10 7.00E-10 l SSW 1.59E-09 1.35E-09 1.17E-09 1.02E-09 I SW 1.71E-09 1.46E-09 1.26E-09 1.10E-09 9.61E-10 8.49E-10 7.56E-10 a WSW 1.90E-09 1.62E-09 1.40E-09 1.21E-09 1.06E-09 9.41E-10 8.37E-10 W 3.97E-09 3.39E-09 2.92E-09 2.54E-09 2.23E-09 1.97E-09 1.75E-09 1 WNW 7.54E-09 6.44E-09 5.55E-09 4.83E-09 4.23E-09 3.74E-09 3.33E-09 l I NW 6.31E-09 5.39E-09 4.64E-09 4.04E-09 3.54E-09 3.13E-09 2.79E-09 NNW 4.40E-09 3.75E-09 3.23E-09 2.81E-09 2.47E-09 2.18E-09 1.94E-09 a l 1 Period of Record: 4/1/77 - 3/31/78 l j IBM
g Page 85 TAELE A-5 (Cont.) Prairie Island Dispersion Parameters (D/Q), 1/m for Long Term Ground Level Releases > 500 Ilts/Yr or > 150 ifrs/QTR for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 2.2 2.3 2.4 2.5 2.6 2.7 2.8 N 1.69E-09 1.52E-09 1.37E-09 1.25E-09 1.14E-09 1.04E-09 9.58E-10 1.06E-09 9.56E-10 8.65E-10 7.86E-10 7.17E-10 6.57E-10 6.03E-10 NNE NE 6.95E-10 6.25E-10 5.65E-10 5.13E-10 4.69E-10 4.29E-10 3.94E-10 9.04E-10 8.14E-10 7.36E-10 6.68E-10 6.10E-10 5.59E-10 5.13E-10 ENE 1.93E-09 1.74E-09 1.57E-09 1.43E-09 1.30E-09 1.19E-09 1.10E-09 E 3.16E-09 2.86E-09 2.60E-09 2.37E-09 2.17E-09 2.00E-09 ESE 3.51E-09 3.44E-09 3.11E-09 2.82E-09 2.58E-09 2.36E-09 2.17E-09 SE 3.82E-09 1.82E-09 1.64E-09 1.48E-09 1.35E-09 1.23E-09 1.13E-09 1.04E-09 SSE 8.55E-10 7.69E-10 6.95E-10 6.32E-10 5.77E-10 5.28E-10 4.85E-10 S 6.27E-10 5.64E-10 5.10E-10 4.63E-10 4.23E-10 3.87E-10 3.56E-10 SSW 6.09E-10 5.50E-10 5.00E-10 4.56E-10 4.18E-10 3.84E-10 SW 6.76E-10 6.74E-10 6.10E-10 5.54E-10 5.06E-10 4.63E-10 4.26E-10 WSW 7.49E-10 1.41E-09 1.28E-09 1.16E-09 1.06E-09 9.68E-10 8.90E-10 W 1.57E-09 2.68E-09 2.42E-09 2.20E-09 2.01E-09 1.84E-09 1.69E-09 WNW 2.98E-09 2.24E-09 2.03E-09 1.84E-09 1.68E-09 1.54E-09 1.42E-09 NW 2.49E-09 1.56E-09 1.41E-09 1.28E-09 1.17E-09 1.07E-09 9.86E-10 NNW 1.74E-09 Period of Record: 4/1/77 - 3/31/78 111H
. I ODCM i. Y w Rsv. 8 '~3 Page 86
. J ', ~
TABLE A-5 (Cont.) . 2 4: xPrairie Island Dispersion Parameters (D/Q)) 'l/m for Long Term Ground L.evel Releases > 500 lirs/Yr oc > 150 Ilts/QTR for Standard DistEnces (As Measured from Edge of Plant Complex) '
~
~
Miles j sy Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5 N 8.84E-10 8.17E-10 7.58E-10 7.05E-lu 6.57E-10 6.14E-10 5.75E-10 _ NNE 5.56E-10 5.15E-10 4.77E-10 4.44E-10 4 '11.E-10 3.87E-10 - -- 3.62E-10 3.12E-10 2.90E-10 2.70E-10 2.53D~10 2 2.37E-10 NE 3.64E-10 3.36E-10 ENE 4.73F.-10 4.38E-10 -4.06E-10 3.78E-10 ~ 3.$2E-10 . 3.29E-10 J3.0h.5-10 . E - _l.01E-09 9.34E-10 '3.67E-10 8.06E-10 7.51E-10 7.02E-lo 6.57E-10
.. ~
- 1.20E-09 ESE . .
1.84E-09 1.70E-09 IM8E-09 1.47E-c9 .l.37E-09 ~ - T.28E-De-SE 2~.00E-09 1.85E-09 1.'71E-09 1.59E-09 s 1.49h-09'- 1.39E 1.30Ce09_ ; [ 6.21E-10
~
SSE 9.'55E-10 8.83E-10 8.19E-10 7.61E-1A"*g 7.10E-10 6.63E-10
~ i-S 4.47E-10 4.le-10 3.84E-10 3.57E-10 '3.33E-10 n , 3.11E-10 1 ", "- 2.91E-10 :
- 2. li,E- 10 SA'- _
3.28E-10 3.04E-10 2.82E-10 2.62E-10 2.44E-10 ~ L28E.10 4
!" ' 3.54E-10 3.27E-10 3.04E-lO.' 2.82E-10 2.63E-10 2.4sf.-10 2.30G10 WSW .'3.92E-lo' 3.63E-10 3.37E-10 ,
3.13E-10 2.92E-10 2 73E-10 2.5SE-10 _ g 6.10E-10 5.70E-10 5.34E-10 W _ 8.20E-10 -'7.59E-10 7.04E-10 6.54E-10 WNW. 1.56E-09 J.44E-09 1.34E-09 1.24E-09 1.16E-09 1.08E-09 ~ 1.0IE-09 , NW l.31E-09 1.212-09
~
1.12E-09 1.04E 9.7 E-10 ^ N 9.07E-10 v - 8.49f.- 10 '
~
NNW 9.09E-10 8.41E-10 7.80E-10 7'.25E-10 6.76E-10 6.32E-10 $5.92E-107
~
- - ~- -. - ,
- ~ t -
Period of Record: 4/1/77 - 3/31/78 - N_ - g-- ,
. , x IBM -
_ T [, -[ ,v i
~_.u
ODCM-Rev. 8 - Page 87 TABLE A-5 (cont.) 2 Prairie Island Dispersion Parameters (D/Q), 1/m for Long Term Ground Level Releases > 500 ifrs/Yr or > 150 Hrs /QTR for Standard Distances (As Heasured from Edge of Plant Complex) 1 Miles Sector 3.6 3.7 3.8 3.9 4.0 4.1 4.2 N 5.40E-10 5.07E-10 4.78E-10 4.51E-10 4.26E-10 4.03E-10 3.82E-10 NNE 3.40E-10 3.19E-10 3.01E-10 2.84E-10 2.68E-10 2.54E-10 2.41E-10 NE 2.22E-10 2.09E-10 1.97E-10 1.86E-10 1.75E-10 1.66E-10 1.57E-10 ENE 2.89E-10 2.72E-10 2.56E-10 2.42E-10 2.28E-10 2.16E-10 2.05E-10 E 6.17E-10 5.80E-10 5.46E-10 5.16E-10 4.87E-10 4.61E-10 4.37E-10 ESE 1.12E-09 1.06E-09 9.95E-10 9.39E-10 8.87E-10 8.40E-10 7.96E-10 SE 1.22E-09 1.15E-09 1.08E-09 1.02E-09 9.64E-10 9.12E-10 8.65E-10 i SSE 5.83E-10 5.48E-10 5.16E-10 4.87E-10 4.60E-10 4.36E-10 4.13E-10 S 2.73E-10 2.57E-10 2.42E-10 2.28E-10 2.16E-10 2.04E-10 1.94E-10
! 2.00E-10 1.88E-10 1.78E-10 1.67E-10 1.58E-10 1.50E-10 1.42E-10 SSW SW 2.16E-10 2.03E-10 1.92E-10 1.81E-10 1.71E-10 1.62E-10 1.53E-10 2 WSW 2.40E-10 2.25E-10 2.12E-10 2.00E-10 1.89E-10 1.79E-10 1.70E-10 W 5.0lE-10 4.71E-10 4.44E-10 4.19E-10 3.96E-10 3.75E-10 3.55E-10 9.53E-10 8.96E-10 8.44E-10 7.96E-10 7.52E-10 7.12E-10 6.75E-10 WNW ~
7.97E-10 7.50E-10 7.06E-10 6:66E-10 6.29E-10 5.96E-10 5.65E-10 NW 5.55E-10 5.22E-10 4.92E-10 4.64E-10 4.38E-10 4.15E-10 3.93E-10 NNW Period of Record: 4/1/77 - 3/31/78 IBM
. 8 i Page 88 TABLE A-5 (Cont.) - Prairie Island Dispersion Parameters (D/Q),1/m 2 for Long Term Ground Level Releases > 500 lirs/Yr or > 150 Hrs /QTR - for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 4.3 4.4 4.5 4.6 4.7 4.8 4.9 N 3.63E-10 3.45E-10 3.28E-10 3.13E-10 2.99E-10 2.85E-10 2.73E-10 NNE 2.29E-10 2.17E-10 2.07E-10 1.97E-10 1.88E-10 1.80E-10 1.72E-10 NE 1.49E-10 1.42E-10 1.35E-10 1.29E-10 1.23E-10 1.17E-10 1.12E-10 i ENE 1.94E-10 1.85E-10 1.76E-10 1.68E-10 1.60E-10 1.53E-10 1.46E-10 l ! E 4.15E-10 3.94E-10 3.75E-10 3.58E-10 3.41E-10 3.26E-10 3.12E-10 ESE 7.56E-10 7.18E-10 6.84E-10 6.52E-10 6.22E-10 5.94E-16 5.68E-10 l SE 8.21E-10 7.80E-10 7.45E-10 7.08E-10 6.75E-10 6.45E-10 6.17E-10 SSE 3.92E-10 3.73E-10 3.55E-10. 3.38E-10 3.23E-10 3.08E-10 2.94E-10 S 1.84E-10 1.75E-10 1.'66E-10 1.58E-10 1.51E-10 1.44E-10 1.38L-10. SSW 1.35E-10 1.28E-10 1.22E-10 1.16E-10 1.11E-10 1.06E-10 1.01E-10 ' SW l.45E-10 1.38E-10 1.32E-10 1.25E-10 1.20E-10 1.14E-10 1.09E-10
~
WSW 1.61E-10 1.53E-10 1.46E-10 1.39E-10 1.33E-10 1.27E-10 1.21E-10 W 3.37E-10 3.20E-10 3.05E-10 2.91E-10 2.77E-10 2.65E-10 2.53E-10 WNW 6.41E-10 6.09E-10 5.80E-10 5.52E-10 5.27E-10 5.03E-10 4.81E-10 NW 5.36E-10 5.10E-10 4.85E-10 4.62E-10 4.41E-10 4.21E-10 4.03E-10 NNW 3.75E-10 3.55E-10 3.38E-10 3.22E-10 3.07E-10 2.93E-10 2.80E-10 Period of Record: 4/1/77 - 3/31/78 IBM e
ODCM Rev. 8 Page 89
~
TABl.E A-5 (Cont.) 2 I Prairie Island Dispersion Parameters (D/Q), 1/m for Long Term Ground Level Releases > 500 IIrs/Yr or > 150 lirs/QTR for Standard 1)istances (As Heasured from Edge of Plant Complex) { i Miles Sector 5.0 i N 2.61E-10 NNE 1.64E-10 NE 1.07E-10 ENE 1.40E-10 E 2.98E-10 i ESE 5.43E-10 SE 5.90E-10 SSE 2.82E-10 l S 1.32E-10 SSW 9.69E-11 SW 1.05E-10 WSW 1.16E-10 W 2.42E-10 WNW 4.61E-10 l i NW 3.85E-10 NNW 2.68E-10 l Period of Record: 4/1/77 - 3/31/78 l l IllM i
O O ;55 Page 90 O TABLE A-6 - Prairie Island Dispersion Parameters for Short Term Ground Level Releases < 500 Ilrs/Yr or < 150 lirs/Qtr for Unrestricted Area Boundary Locations (identified In Table A-2) Unrest.ricted Area Boundary Sector 2 Sector X/q (sec/m3) D/q (1/m ) N 7.09E-05 4.60E-07 NNE 7.32E-05 4.11E-07 NE 1.60E-05 6.77E-08 ENE 1.97E-05 1.11E-07 , E 4.92E-05 1.99E-07 ESE 6.40E-05 2.52E-07
- SE 5.98E-05 2.43E-07 SSE 8.79E-05 3.08E-07 S 5.18E-05 2.04E-07 SSW 5.26E-05 1.89E-07 SW 5.25E-05 1.90E-07 WSW 7.83E-05 2.44E-07 W 1.32E-04 3.78E-07 WNW 1.10E-04 4.61E-07 NW 7.67E-05 3.25E-07 NNW 4.79E-05 2.34E-07 i
Period of Record: 4/1/77 - 3/31/78 IBM
g Page 91 1 I TABLE A-7 ! Prairie Island Dispersion Parameters (X/9), sec/m , for Short Term Ground Level Releases 5 500 lirs/Yr or 5150 lirs/Qtr I for Standard Distances (As Heasured from Edge of Plant Complex) l Miles Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 N 3.76E-04 1.13E-04 6.59E-05 4.39E-05 3.15E-05 2.47E-05 1.90E-05 NNE 3.35E-04 1.05E-04 5.94E-05 3.93E-05 2.77E-05 2.19E-05 1.65E-05 NE 4.38E-04 1.33E-04 7.71E-05 4.94E-05 3.39E-05 2.68E-05 2.12E-05 ENE 3.27E-04 1.02E-04 5.93E-05 4.01E-05 2.80E-05 2.19E-05 1.69E-05 E 8.12E-04 2.43E-04 1.39E-04 8.80E-05 6.16E-05 4.84E-05 3.78E-05 i ESE 1.17E-03 3.52E-04 1.98E-04 1.27E-04 8.80E-05 6.84E-05 5.32E-05 SE 1.27E-03 3.85E-04 2.06E-04 1.31E-04 9.32E-05 7.34E-05 5.67E-05 SSE 5.30E-04 2.82E-04 1.57E-04 9.85E-05 6.75E-05 5.39E-05 4.30E-05 S 5.01E-04 1.57E-04 8.75E-05 5.74E-05 3.97E-05 3.11E-05 2.51E-05 SSW 4.54E-04 1.43E-04 8.26E-05 5.34E-05 3.60E-05 2.85E-05 2.31E-05 SW 4.46E-04 1.44E-04 8.25E-05 5.30E-05 3.58E-05 2.85E-05 2.35E-05 WSW 6.10E-04 1.95E-04 1.08E-04 6.78E-05 4.59E-05 3.67E-05 3.05E-05 W 1.00E-03 3.10E-04 1.74E-04 1.10E-04 7.59E-05 6.07E-05 4.89E-05 WNW 8.70E-04 2.65E-04 1.50E-04 9.70E-05 6.86E-05 5.33E-05 4.17E-05 NW 8.41E-04 2.50E-04 1.38E-04 8.89E-05 6.37E-05 4.97E-05 3.84E-05 NNW 5.69E-04 1.71E-04 9.73E-05 6.28E-05 4.54E-05 3.55E-05 2.78E-05 Period of Record: 4/1/77 - 3/31/78 IBM
8 Page 92 TABLE A-7 (Cont.) 3 Prairie Island Dispersion Parameters (X/q), sec/m , for Short Term Ground Level Releases < 500 Ilrs/Yr or < 150 llrs/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 0.8 0.9 1.0 1.1 1.2 1.3 1.4 N 1.57E-05 1.26E-05 1.06E-05 8.97E-06 7.73E-06 6.76E-06 5.91E-06 NNE 1.35E-05 1.11E-05 9.26E-06 7.87E-06 6.81E-06 5.96E-06 5.27E-06 NE 1.74E-05 1.44E-05 1.21E-05 1.02E-05 8.57E-06 7.50E-06 6.63E-06 ENE 1.39E-05 1.14E-05 9.46E-06 8.04E-06 6.83E-06 5.97E-06 5.27E-06 E 3.llE-05 2.51E-05 2.11E-05 1.80E-05 1.53E-05 1.33E-05 1.18E-05 4.35E-05 3.58E-05 2.98E-05 2.54E-05 2.19E-05 1.91E-05 1.71E-05 ESE 4.65E-05 3.79E-05 3.18E-05 2.71E-05 2.32E-05 2.03E-05 1.81E-05 SE 3.53E-05 2.87E-05 2.41E-05 2.05E-05 1.72E-05 1.51E-05 1.35E-05 SSE i 2.05E-05 1.66E-05 1.38E-05 1.17E-05 1.01E-05 8.83E-06 7.81E-06 S 1.89E-05 1.54E-05 1.29E-05 1.10E-05 9.05E-06 7.93E-06 7.02E-06 SSW 1.54E-05 1.30E-05 1.12E-05 9.19E-06 8.05E-06 7.21E-06 SW l.95E-05 2.51E-05 2.05E-05 1.72E-05 1.47E-05 1.21E-05 1.06E-05 9.41E-06 WSW 3.24E-05 2.70E-05 2.30E-05 1.89E-05 1.65E-05 1.46E-05 W 4.01E-05 2.75E-05 2.31E-05 1.96E-05 1.68E-05 1.48E-05 1.31E-05 WNW 3.44E-05 2.57E-05 2.17E-05 1.85E-05 1.60E-05 1.40E-05 1.24E-05 NW 3.15E-05 1.86E-05 1.54E-05 1.31E-05 1.12E-05 9.85E-06 8.82E-06 NNW 2.28E-05 Period of Record: 4/1/77 - 3/31/78 IBM ,
O O "8 Page 93 O - I TABLE A-7 (Cont.) 1 - . 3 Prairie Island Dispersion Parameters (X/q), sec/m , , for Short Term Ground Level Releases 5 500 lirs/Yr or $ 150 Hrs /Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Miles Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 N 5.27E-06 4.74E-06 4.30E-06 3.91E-06 3.59E-06 3.32E-06 3.07E-06 NNE 4.70E-06 4.22E-06 3.82E-06 3.47E-06 3.18E-06 2.97E-06 2.75E-06 ] NE 5.89E-06 5.30E-06 4.80E-06 4.37E-06 4.01E-06 3.69E-06 3.42E-06 ENE 4.67E-06 4.21E-06 3.80E-06 3.45E-06 3.16E-06 2.91E-06 2.70E-06 E 1.06E-05 9.52E-06 8.66E-06 7.90E-06 7.25E-06 6.74E-06 6.25E-06 ESE 1.52E-05 1.38E-05 1.25E-05 1.13E-05 1.04E-05 9.72E-06 9.03E-06 SE 1.62E-05 1.46E-05 1.33E-05 1.21E-05 1.llE-05 1.03E-05 9.59E-06 SSE 1.20E-05 1.09E-05 9.84E-06 8.96E-06 8.23E-06 7.58E-06 7.04E-06 S 6.97E-06 6.27E-06 5.68E-06 5.18E-06 4.75E-06 4.36E-06 4.04E-06 SSW 6.28E-06 5.66E-06 5.14E-06 4.69E-06 4.31E-06 3.92E-06 3.64E-06 SW 8.43E-06 5.78E-06 5.24E-06 4.77E-06 4.37E-06 3.90E-06 3.62E-06 WSW 8.41E-06 7.58E-06 6.87E-06 6.27E-06 5.77E-06 5.17E-06 4.80E-06 W l.30E-05 1.17E-05 1.06E-05 9.62E-06 8.83E-06 8.33E-06 7.73E-06 WNW l.17E-05 1.05E-05 9.65E-06 8.80E-06 8.08E-06 7.42E-06 6.89E-06 l NW l.IIE-05 1.00E-05 9.09E-06 8.30E-06 7.63E-06 7.13E-06 6.62E-06 l NNW 7.89E-06 7.llE-06 6.47E-06 5.89E-06 5.41E-06 5.01E-06 4.64E-06 i l Period of Record: 4/1/77 - 3/31/78 IBM
g . Page 94 i *
! TABLE A-7 (Cont.)
Prairie Island Dispersion Parameters (X/q), sec/m3, for Short Term Ground Level Releases 5 500 lirs/Yr or i 150 Ifrs/Qtr - for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 2.2 2.3 2.4 2.5 2.6 2.7 2.8
) N 2.87E-06 2.67E-06 2.50E-06 2.32E-06 2.27E-06 1.94E-06 1.84E-06 l NNE 2.56E-06 2.39E-06' 2.24E-06 2.09E-06 2.03E-06 1.76E-06 1.66E-06 NE 3.19E-06 2.98E-06 2.79E-06 2.63E-06 2.57E-06 2.24E-06 2.11E-06 ENE 2.51E-06 2.34E-06 2.19E-06 2.05E-06 1.97E-06 1.74E-06 1.64E-06
, E 5.82E-06 5.44E-06 5.10E-06 4.89E-06 4.75E-06 4.14E-06 3.92E-06 ESE 8.41E-06 7.87E-06 7.38E-06 7.16E-06 7.09E-06 6.11E-06 5.78E-06 SE 8.93E-06 8.35E-06 7.82E-06 7.70E-06 7.60E-06 6.62E-06 6.26E-06 SSE 6.56E-06 6.14E-06 5.76E-06 5.55E-06 5.36E-06 4.73E-06 4.47E-06 I S 3.76E-06 3.51E-06 3.29E-06 3.18E-06 3.06E-06 2.73E-06 2.59E-06 SSW 3.39E-06 3.16E-06 2.96E-06 2.89E-06 2.75E-06 2.42E-06 2.28E-06 SW 3.37E-06 3.15E-06 2.95E-06 2.84E-06 2.70E-06 2.44E-06 2.30E-06 WSW 4.47E-06 4.18E-06 3.92E-06 3.85E-06 3.67E-06 3.28E-06 3.10E-06 W 7.21E-06 6.74E-06 6.32E-06 6.45E-06 6.03E-06 5.30E-06 5.02E-06 WNW 6.42E-06 6.00E-06 5.65E-06 5.32E-06 5.23E-06 4.55E-06 4.30E-06 NW 6.16E-06 5.76E-06 5.40E-06 5.16E-06 5.03E-06 4.37E-06 4.13E-06 NNW 4.31E-06 4.02E-06 3.76E-06 3.57E-06 3.46E-06 3.00E-06 2.83E-06 l Period of Record: 4/1/77 - 3/31/78 IBM
ODCH Rev. 8 Page 95 TABLE A-7 (Cont.) Prairie Island Dispersion Parameters (X/q), sec/m , for Short Term Ground Level Releases 5 500 llrs/Yr or 5150 Ilts/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Hiles I Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5 N 1.74E-06 1.66E-06 1.58E-06 1.50E-06 1.43E-06 1.37E-06 1.31E-06 NNE 1.57E-06 1.50E-06 1.43E-06 1.36E-06 1.30E-06 1.24E-06 1.19E-06 NE 2.00E-06 1.90E-06 1.81E-06 1.73E-06 1.65E-06 1.58E-06 1.51E-06 ENE 1.55E-06 1.48E-06 1.40E-06 1.33E-06 1.27E-06 1.21E-06 1.16E-06 E 3.71E-06 3.51E-06 3.34E-06 3.19E-06 3.04E-06 2.91E-06 2.79E-06 ESE 5.48E-06 5.18E-06 4.93E-06 4.70E-06 4.49E-06 4.29E-06 4.11E-06 SE 5.93E-06 5.63E-06 5.36E-06 5.11E-06 4.87E-06 4.66E-06 4.46E-06 SSE 4.24E-06 3.97E-06 3.78E-06 3.60E-06 3.44E-06 3.29E-06 3.15E'06 S 2.45E-06 2.25E-06 2.14E-06 2.04E-06 1.94E-06 1.85E-06 1.77E-06 SSW 2.16E-06 1.96E-06 1.87E-06 1.78E-06 1.70E-06 1.63E-06 1.56E-06 2.18E-06 2.03E-06 1.93E-06 1.84E-06 1.75E-06 1.67E-06 1.60E-06 SW 2.70E-06 2.57E-06 2.45E-06 2.34E-06 2.24E-06 2.14E-06 WSW 2.94E-06 4.76E-06 4.34E-06 4.13E-06 3.95E-06 3.77E-06 3.61E-06 3.47E-06 W 4.07E-06 3.86E-06 3.67E-06 3.50E-06 3.34E-06 3.20E-06 3.06E-06 WNW 3.69E-06 3.51E-06 3.35E-06 3.20E-06 3.06E-06 2.94E-06 NW 3.92E-06 2.53E-06 2.40E-06 2.28E-06 2.18E-06 2.08E-06 1.99E-06 NNW 2.68E-06 Period of Record: 4/1/77 - 3/31/78 IBM
ODCH Rev. 8 . ] Page 96 TABLE A-7 (Cont.) - y Prairie Island Dispersion Parameters (X/q), sec/m ,3 for Sliort Term Ground Level Releases 5 500 lirs/Yr or 5150 llrs/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Miles i Sector 3.6 3.7 3.8 3.9 4.0 4.1 4.2 N 1.25E-06 1.20E-06 1.15E-06 1.10E-06 1.06E-06 1.02E-06 9.88E-07 NNE 1.14E-06 1.09E-06 1.05E-06 1.01E-06 9.73E-07 9.37E-07 9.04E-07 I NE 1.45E-06 1.39E-06 1.34E-06 1.29E-06 1.24E-06 1.20E-06 1.16E-06 I ENE 1.11E-06 1.07E-06 1.02E-06 9.83E-07 9.46E-07 9.11E-07 8.79E-07 2.47E-06 2.38E-06 2.29E-06 2.21E-06 2.13E-06 E 2.67E-06 2.57E-06 ESE 3.94E-06 3.78E-06 3.64E-06 3.50E-06 3.38E-06 3.26E-06 3.15E-06 SE 4.27E-06 4.10E-06 3.94E-06 3.79E-06 3.65E-06 3.52E-06 3.39E-06 i SSE 3.02E-06 2.90E-06 2.79E-06 2.68E-06 2.59E-06 2.50E-06 2.41E-06 i S 1.70E-06 1.63E-06 1.57E-06 1.51E-06 1.45E-06 1.40E-06 1.35E-06 SSW 1.50E-06 1.44E-06 1.38E-06 1.33E-06 1.29E-06 1.24E-06 1.20E-06 SW 1.53E-06 1.47E-06 1.41E-06 1.36E-06 1.29E-06 1.25E-06 1.20E-06 WSW 2.06E-06 1.98E-06 1.90E-06 1.83E-06 1.76E-06 1.70E-06 1.64E-06 W 3.33E-06 3.20E-06 3.08E-06 2.97E-06 2.87E-06 2.77E-06 2.68E-06 WNW 2.93E-06 2.81E-06 2.70E-06 2.60E-06 2.51E-06 2.42E-06 2.33E-06 NW 2.82E-06 2.71E-06 2.60E-06 2.50E-06 2.41E-06 2.32E-06 2.24E-06 NNW 1.91E-06 1.83E-06 1.76E-06 1.69E-06 1.63E-06 1.57E-06 1.52E-06 Period of Record: 4/1/77 - 3/31/78 IBM
'g /7 ODCM O V Rev. 8 Page 97 b ,
TABLE A-7 (Cont.) , Prairie Island Dispersion Parameters (x/q), sec/m , for Short Term Ground Level Releases 5 500 lirs/Yr or 5 150 lirs/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Miles Sector 4.3 4.4 4.5 4.6 4.7 4.8 4.9 N 9.59E-07 9.27E-07 8.97E-07 8.68E-07 8.41E-07 8.16E-07 7.92E-07 NNE 8.73E-07 8.44E-07 8.16E-07 7.90E-07 7.65E-07 7.42E-07 7.20E-07 NE 1.12E-06 1.08E-06 1.05E-06 1.01E-06 9.81E-07 9.51E-07 9.23E-07 ENE 8.47E-07 8.18E-07 7.91E-07 7.66E-07 7.41E-07 7.18E-07 6.97E-07 E 2.06E-06 2.00E-06 1.93E-06 1.87E-06 1.82E-06 1.76E-06 1.71E-06 ESE 3.04E-06 2.94E-06 2.85E-06 2.76E-06 2.67E-06 2.60E-06 2.52E-06 SE 3.27E-06 3.16E-06 3.06E-06 2.97E-06 2.88E-06 2.79E-06 2.70E-06 SSE 2.34E-06 2.26E-06 2.19E-06 2.12E-06 2.07E-0( 2.01E-06 1.95E-06 S 1.30E-06 1.26E-06 1.22E-06 1.18E-06 1.15E-06 1.11E-06 1.08E-06 SSW 1.16E-06 1.12E-06 1.09E-06 1.05E-06 1.02E-06 9.94E-07 9.66E-07 SW 1.16E-06 1.12E-06 1.09E-06 1.05E-06 1.02E-06 9.91E-07 9.62E-07 WSW l.59E-06 1.54E-06 1.49E-06 1.44E-06 1.39E-06 '.35E-06 1 1.31E-06 W 2.59E-06 2.51E-06 2.43E-06 2.36E-06 2.29E-06 2.23E-06 2.17E-06 WNW 2.25E-06 2.18E-06 2.llE-06 2.04E-06 1.98E-06 1.92E-06 1.86E-06 NW 2.16E-06 2.09E-06 2.01E-06 1.95E-06 1.89E-06 1.84E-06 1.79E-06 ! NNW 1.46E-06 1.41E-06 1.36E-06 1.32E-06 1.28E-06 1.24E-06 1.20E-06 Period of Record: 4/1/77 - 3/31/78 IBM
v 8
; Page 98 TABLE A-7 (Cont.)
, Prairie Island Dispersion Parameters (X/q), sec/m 3 3 for Short Term Ground I.evel Releases < 500 lirs/Yr or < 150 ifrs/Otr
- for Standard Distances (As Heasured from Edge of Plant Complex) 1 l Miles Sector 5.0 1
N 7.67E-07 NNE 6.99E-07 NE 3.97E-07 ENE 6.76E-07 E 1.67E-06 ESE 2.45E-06 SE 2.62E-06 SSE 1.89E-06 S 1.05E-06 SSW 9.39E-07 SW 9.35E-07 WSW l.27E-06 W 2.IIE-06 WNW l.81E-06 NW l.74E-06 NNW l.17E-06 Period of Record: 4/1/77 - 3/31/78 IBM
V 8 . Page 99 TABLE A-8 2 Prairie Island Dispersion Parameters (D/q), 1/m ' for Short Term Ground Level Releases 5 500 lirs/Yr or 5150 lirs/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 i i N 1.68E-06 6.63E-07 4.32E-07 3.00E-07 2.18E-07 1.69E-07 1.29E-07 l NNE 1.33E-06 5.43E-07 3.46E-07 2.40E-07 1.72E-07 1.36E-07 1.03E-07 i NE 1.19E-06 4.68E-07 3.05E-07 2.06E-07 1.45E-07 1.14E-07 9.10E-08 ENE 1.20E-06 4.86E-07 3.17E-07 2.23E-07 1.58E-07 1.23E-07 9.49E-08 E 2.08E-06 8.09E-07 5.21E-07 3.46E-07 2.49E-07 1.96E-07 1.54E-07 ESE 2.90E-06 1.14E-06 7.17E-07 4.85E-07 3.45E-07 2.69E-07 2.llE-07 SE 3.20E-06 1.26E-06 7.54E-07 5.08E-07 3.71E-07 2.94E-07 2.31E-07 SSE 2.09E-06 8.24E-07 5.16E-07 3.41E-07 2.40E-07 1.92E-07 1.55E-07 S 1.27E-06 5.18E-07 3.24E-07 2.23E-07 1.58E-07 1.23E-07 1.00E-07 SSW l.06E-06 4.33E-07 2.82E-07 1.92E-07 1.33E-07 1.05E-07 8.51E-08 SW l.05E-06 4.42E-07 2.85E-07 1.91E-07 1.31E-07 1.04E-07 8.55E-08 l WSW l.24E-06 5.19E-07 3.24E-07 2.14E-07 1.48E-07 1.19E-07 9.94E-08 W l.90E-06 7.65E-07 4.83E-07 3.22E-07 2.27E-07 1.82E-07 1.48E-07 WNW 2.42E-06 9.62E-07 6.10E-07 4.14E-07 2.99E-07 2.31E-07 1.81E-07 NW 2.30E-06 8.91E-07 5.49E-07 3.72E-07 2.73E-07 2.12E-07 1.65E-07 NNW l.79E-06 7.01E-07 4.46E-07 3.01E-07 2.21E-07 1.72E-07 1.34E-07 Period of Record: 4/1/77 - 3/31/78 IBM
) ODCH v Rev. 8 v -
Page 100 TABl.E A-8 (Cont.) 2 Prairie Island Dispersion Parameters (D/q), 1/m
- l for Short Term Ground Level Releases 5 500 lirs/Yr or 5150 lirc/Qtr for Standard Distances (As Heasured from Edge of Plant Complex)
Miles l Sector 0.8 0.9 1.0 1.1 1.2 1.3 1.4 N 1.05E-07 8.25E-08 6.73E-08 5.55E-08 4.66E-08 3.99E-08 3.41E-08 l NNE 8.35E-08 6.76E-08 5.48E-08 4.55E-08 3.85E-08 3.29E-08 2.85E-08 NE 7.39E-08 5.99E-08 4.95E-08 4.08E-08 3.35E-08 2.87E-08 2.49E-08 ] { ENE 7.67E-08 6.15E-08 4.97E-08 4.13E-08 3.42E-08 2.93E-08 2.53E-08 E 1.25E-07 9.96E-08 8.17E-08 6.79E-08 5.63E-08 4.82E-08 4.18E-08 f ESE 1.71E-07 1.38E-07 1.12E-07 9.32E-08 7.87E-08 6.71E-08 5.86E-08 l l SE 1.88E-07 1.50E-07 1.23E-07 1.02E-07 8.55E-08 7.34E-08 6.38E-08 SSE 1.26E-07 1.01E-07 8.26E-08 6.86E-08 5.63E-08 4.83E-08 4.22E-08 S 8.06E-08 6.40E-08 5.16E-08 4.29E-08 3.60E-08 3.07E-08 2.66E-08 SSW 6.87E-08 5.49E-08 4.50E-08 3.73E-08 3.00E-08 2.57E-08 2.23E-08 l SW 7.00E-08 5.41E-08 4.47E-08 3.73E-08 3.00E-08 2.57E-08 2.25E-08 l WSW 8.llE-08 6.49E-08 5.32E-08 4.44E-08 3.59E-08 3.08E-08 2.67E-08 l W l.21E-07 9.57E-08 7.80E-08 6.48E-08 5.22E-08 4.46E-08 3.86E-08 ! WNW l.47E-07 1.15E-07 9.45E-08 7.80E-08 6.54E-08 5.61E-08 4.86E-08
- NW l.34E-07 1.07E-07 8.78E-08 7.30E-08 6.13E-08 5.23E-08 4.53E-08 l NNW l.08E-07 8.62E-08 6.96E-08 5.74E-08 4.82E-08 4.12E-08 3.60E-08 Period of Record
- 4/1/77 - 3/31/78 IBM
( ~) O i ODCM Rev. 8 V' . Page 101 TABLE A-8 (Cont.) 2 1 Prairie Island Dispersion Parameters (D/q), 1/m ' for Short Term 0round Level Releases 5 500 lirs/Yr or $ 150 lirs/Qtr i for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 N 2.98E-08 2.62E-08 2.33E-08 2.08E-08 1.87E-08 1.70E-08 1.54E-08 NNE 2.49E-08 2.20E-08 1.95E-08 1.74E-08 1.56E-08 1.43E-08 1.30E-08 NE 2.17E-08 1.92E-08 1.70E-08 1.52E-08 1.37E-08 1.23E-08 1.12E-08 ENE 2.20E-08 1.94E-08 1.72E-08 1.54E-08 1.38E-08 1.25E-08 1.13E-08 E 3.66E-08 3.24E-08 2.89E-08 2.58E-08 2.32E-08 2.11E-08 1.91E-08 ESE 5.12E-08 4.53E-08 4.03E-08 3.60E-08 3.23E-08 2.95E-08 2.68E-08 SE 5.61E-08 4.96E-08 4.41E-08 3.95E-08 3.55E-08 3.21E-08 2.92E-08 SSE 3.70E-08 3.27E-08 2.91E-08 2.60E-08 2.34E-08 2.10E-08 1.91E-08 S 2.32E-08 2.05E-08 1.82E-08 1.63E-08 1.46E-08 1.31E-08 1.19E-08 SSW 1.95E-08 1.73E-08 1.54E-08 1.38E-08 1.24E-08 1.10E-08 1.00E-08 SW 1.97E-08 1.74E-08 1.54E-08 1.38E-08 1.24E-08 1.08E-08 9.86E-09 WSW 2.34E-08 2.07E-08 1.84E-08 1.65E-08 1.49E-08 1.30E-08 1.18E-08 W 3.37E-08 2.97E-08 2.64E-08 2.36E-08 2.12E-08 1.95E-08 1.77E-08 WNW 4.26E-08 3.76E-08 3.38E-08 3.02E-08 2.72E-08 2.44E-08 2.22E-08 NW 3.97E-08 3.51E-08 3.12E-08 2.80E-08 2.52E-08 2.30E-08 2.09E-08 NNW 3.15E-08 2.78E-08 2.48E-08 2.22E-08 1.99E-08 1.81E-08 1.64E-08 Period of Record: 4/1/77 - 3/31/78 IBM
- ODCM Rev. 8 -
Page 102 - TABLE A-8 (Cont.) 2 j Prairie Island Dispersion Parameters (D/q), 1/m ' i for Short Term Ground Level Releases 5 500 ifrs/Yr or 5150 Ilrs/Qtr for Standard Distances (As Measured from Edge of Plant Complex) l Hiles i Sector 2.2 2.3 2.4 2.5 2.6 2.7 2.8 l N 1.41E-08 1.29E-08 1.19E-08 1.09E-08 1.05E-08 8.80E-09 8.23E-09
- NNE 1.18E-08 1.08E-08 9.96E-09 9.12E-09 8.70E-09 7.42E-09 6.90E-09 NE 1.02E-08 9.34E-09 8.58E-09 7.92E-09 7.61E-09 6.51E-09 6.05E-09
] ) ENE 1.03E-08 9.45E-09 8.69E-09 7.99E-09 7.58E-09 6.56E-09 6.10E-09 E 1.74E-08 1.60E-08 1.47E-08 1.38E-08 1.32E-08 1.13E-08 1.05E-08 ESE < 2.44E-08 2.24E-08 2.05E-08 1.96E-08 1.90E-08 1.61E-08 1.50E-08 SE 2.66E-08 2.43E-08 2.24E-08 2.16E-08 2.09E-08 1.79E-08 1.66E-08 f SSE 1.74E-08 1.60E-08 1.47E-08 1.39E-08 1.32E-08 1.14E-08 1.06E-08 j S 1.09E-08 9.97E-09 9.17E-09 8.70E-09 8.23E-09 7.22E-09 6.73E-09 j SSW 9.14E-09 8.37E-09 7.70E-09 7.37E-09 6.91E-09 5.96E-09 5.54E-09 SW 9.00E-09 8.25E-09 7.60E-09 7.18E-09 6.72E-09 5.98E-09 5.56E-09 j WSW 1.08E-08 9.89E-09 9.09E-09 8.77E-09 8.21E-09 7.20E-09 6.69E-09 W 1.62E-08 1.48E-08 1.36E-08 1.36E-08 1.25E-08 1.08E-08 1.00E-08 WNW 2.02E-08 1.86E-08 1.71E-08 1.59E-08 1.53E-08 1.31E-08 1.22E-08 NW l.90E-08 1.74E-08 1.60E-08 1.51E-08 1.44E-08 1.23E-08 1.14E-08 NNW l.50E-08 1.37E-08 1.26E-08 1.17E-08 1.12E-08 9.53E-09 , 8.86E-09 l Period of Record: 4/1/77 - 3/31/78 IBM 1
ODCM Rev. 8 Page 103 TABLE A-8 (Cont.) 2 Prairie Island Dispersion Parameters (D/q),1/m ' for Short Term Ground Level Releases 5 500 Ilrs/Yr or 5150 ifrs/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Hiles Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5 N 7.68E-09 7.22E-09 6.76E-09 6.35E-09 5.97E-09 5.63E-09 5.31E-09 NNE 6.44E-09 6.04E-09 5.66E-09 5.32E-09 5.00E-09 4.72E-09 4.46E-09 NE 5.64E-09 5.27E-09 4.94E-09 4.64E-09 4.36E-09 4.llE-09 3.89E-09 ENE 5.69E-09 5.33E-09 5.00E-09 4.69E-09 4.41E-09 4.16E-09 3.92E-09 E 9.78E-09 9.10E-09 8.52E-09 8.00E-09 7.52E-09 7.09E-09 6.69E-09 ESE 1.39E-08 1.30E-08 1.21E-08 1.14E-08 1.07E-08 1.01E-08 9.53E-09 SE 1.55E-08 1.44E-08 1.35E-08 1.27E-08 1.19E-08 1.12E-08 1.06E-08 SSE 9.88E-09 9.llE-09 8.52E-09 8.00E-09 7.52E-09 7.08E-09 6.69E-09 S 6.27E-09 5.67E-09 5.31E-09 4.98E-09 4.68E-09 4.41E-09 4.16E-09 SSW 5.16E-09 4.61E-09 4.32E-09 4.06E-09 3.82E-09 3.61E-09 3.41E-09 SW 5.18E-09 4.74E-09 4.45E-09 4.17E-09 3.93E-09 3.70E-09 3.50E-09 WSW 6.24E-09 5.64E-09 5.28E-09 4.96E-09 4.67E-09 4.40E-09 4.16E-09 W 9.36E-09 8.39E-09 7.87E-09 7.40E-09 6.97E-09 6.58E-09 6.22E-09 WNW l.13E-08 1.06E-08 9.92E-09 9.31E-09 8.76E-09 8.27E-09 7.81E-09 NW l.07E-08 9.88E-09 9.26E-09 8.70E-09 8.19E-09 7.72E-09 7.3]E-09 NNW 8.26E-09 7.66E-09 7.17E-09 6.73E-09 6.33E-09 5.97E-09 5.63E-09 Period of Record: 4/1/77 - 3/31/78 IBM
D ODCH (V Rev. 8 Page 104 d - TABLE A-8 (Cont.) 2 Prairie Island Dispersion Parameters (D/q), 1/m ' for Short Term Ground Level Releases 5 500 Ilrs/Yr or 5150 Ilrs/Qtr for Standard Distances (As Heasured from Edge of Plant Complex) Miles Sector 3.6 3.7 3.8 3.9 4.0 4.1 4.2 N 5.01E-09 4.75E-09 4.50E-09 4.28E-09 4.07E-09 3.88E-09 3.70E-09 NNE 4.22E-09 4.00E-09 3.79E-09 3.60E-09 3.42E-09 3.26E-09 3.11E-09
! NE 3.68E-09 3.49E-09 3.31E-09 3.15E-09 3.00E-09 2.85E-09 2.72E-09 ENE 3.71E-09 3.51E-09 3.33E-09 3.17E-09 3.01E-09 2.87E-09 2.74E-09 E 6.33E-09 6.00E-09 5.69E-09 5.41E-09 5.15E-09 4.91E-09 4.68E-09 i
ESE 9.02E-09 8.54E-09 8.10E-09 7.70E-09 7.32E-09 6.98E-09 6.66E-09 SE 9.99E-09 9.46E-09 8.96E-09 8.51E-09 8.09E-09 7.70E-09 7.33E-09 SSE 6.33E-09 5.99E-09 5.68E-09 5.40E-09 5.14E-09 4.90E-09 4.67E-09 S 3.94E-09 3.73E-09 3.54E-09 3.36E-09 3.20E-09 3.05E-09 2.91E-09 SSW 3.23E-09 3.06E-09 2.91E-09 2.77E-09 2.64E-09 2.51E-09 2.40E-09 SW 3.31E-09 3.14E-09 2.98E-09 2.83E-09 2.66E-09 2.53E-09 2.42E-09 WSW 3.94E-09 3.73E-09 .3.54E-09 3.37E-09 3.21E-09 3.06E-09 2.92E-09 W 5.89E-09 5.59E-09 5.31B-09 5.05E-09 4.81E-09 4.59E-09 4.38E-09 WNW 7.39E-09 7.00E-09 6.64E-09 6.31E-09 6.00E-09 5.72E-09 5.45E-09 NW 6.93E-09 6.56E-09 6.23E-09 5.92E-09 5.63E-09 5.36E-09 5.11E-09 NNW 5.33E-09 5.05E-09 4.79E-09 4.58E-09 4.34E-09 4.13E-09 3.94E-09 Period of Record: 4/1/77 - 3/31/78 IBM l
- ~ . - .
ODCH [ , Rev. 8 - Page 105 TABLE A-8 (Cont.) - 2 Prairie Island Dispersion Parameters (D/q),1/m ' 3 for Short Term Ground Level Releases 5 500 lirs/Yr or $ 150 lirs/Qtr l for Standard Distances (As Heasured from Edge of Plant Complex)
] Hiles j
1
) Sector ,, 4.3 4.4 4.5 4.6 4.7 4.8 4.9 u ! N 3.55E-09 3.40E-09 3.26E-09 3.12E-09 2.99E-09 2.87E-09 2.76E-09 NNE 2.97E-09 2.84E-09 2.71E-09 2.60E-09 2.49E-09 2.39E-09 2.30E-09 NE 2.60E-09 2.48E-09 2.37E-09 2.27E-09 2.18E-09 2.09E-09 2.01E-09 ENE 2.61E-09 2.49E-09 2.39E-09 2.29E-09 2.19E-09 2.10E-09 2.02E-09 E 4.48E-09 4.28E-09 4.10E-09 3.93E-09 3.77E-09 3.62E-09 3.47E-09 ESE 6.35E-09 6.07E-09 5.81E-09 5.57E-09 5.34E-09 5.13E-09 4.92E-09 SE 6.99E-09 6.68E-09 6.38E-09 6.12E-09 5.86E-09 5.62E-09 5.38E-09 SSE 4.48E-09 4.28E-09 4.10E-09 3.93E-09 3.78E-09 3.63E-09 3.48E-09 i S 2.78E-09 2.65E-09 2.54E-09 2.43E-09 2.34E-09 2.24E-09 2.15E-09 ! SSW 2.30E-09 2.20E-09 2.llE-09 2.02E-09 1.94E-09 1.86E-09 1.79E-09 j SW 2.31E-09 2.21E-09 2.12E-09 2.03E-09 1.95E-09 1.87E-09 1.80E-09 j WSW 2.79E-09 2.67E-09 2.55E-09 2.45E-09 2.33E-09 2.24E-09 2.15E-09 l W 4.19E-09 4.01E-09 3.84E-09 3.69E-09 3.54E-09 3.40E-09 3.27E-09 l WNW 5.20E-09 4.98E-09 4.76E-09 4.57E-09 4.38E-09 4.21E-09 4.04E-09
! NW 4.88E-09 4.66E-09 4.44E-09 4.25E-09 4.08E-09 3.92E-09 3.77E-09
; NNW 3.76E-09 3.60E-09 3.43E-09 3.29E-09 3.16E-09 3.03E-09 2.91E-09 Period of Record: 4/1/77 - 3/31/78 IllM
ODCM Rev. 8 -
- Page 106 TABLE A-8 (Cont.)
2 1 Prairic Island Dispersion Parameters (D/q),1/m l for Short Term Ground Level Releases 1 500 ifrs/Yr or $ 150 IIrs/QTR j for Standard Distances (As Heasured from Edge of Plant Complex) l ! Hiles i l Sector 5.0 l N 2.65E-09 NNE 2.21E-09 NE 1.93E-09 ENE 1.94E-09 E 3.34E-09 I ESE 4.73E-09 SE 5.17E-09 SSE 3.35E-09 S 2.07E-09 SSW l.73E-09 SW l.73E-09 WSW 2.07E-09 W 3.15E-09 WNW 3.89E-09 NW 3.63E-09 I NNV 2.80E-09 i i a Period of Record: 4/1/77 - 3/31/78 IBM
. _ . = .
7- _.._-_. ~, - , S ODCM 4 - - Rev. 8 , Page 107 4 i-i- -! i 1 4 1 i 1- . F i l i t l- ! !- i t APPENDIX - B f h Prairie Island 12.2m Wind and AT 42.7-12.2m Stability Joint Frequency Distributions (4/1/77 - 3/31/78) 4 l t l I I l i
?
1 I i I O IBM n--n- . - , _ -
ODCM Rev. 8 Page 108 NORTHERN STATES POWER COMPANY e PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS A ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 7 22 29 11 0 0 69 NNE 13 19 20 4 0 0 56 NE 11 35 16 1 0 0 63 ENE 11 33 20 0 0 0 64 E 14 37 24 0 0 0 75 ESE 4 45 49 7 2 0 107 l SE 4 10 22 13 1 0 50 SSE 1 7 19 12 2 0 41 2 23 45 27 0 0 97 S 22 39 14 0 0 76 SSW 1 SW 2 17 30 3 0 0 52 0 21 25 11 0 0 57 WSW W I 29 46 18 2 0 96 6 34 64 56 20 1 181 WNW 42 72 53 20 0 199 NW 12 43 49 20 2 0 125 NNW 11 0 0 0 0 0 VAR 0 0 ! TOTAL HOURS THIS CLASS 1408 HOURS OF CALM THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS 16.81 i IBM
ODCM
. . Rev. 8 Page 109 NORTHERN STATES POWER COMPAhT PRAIRIE ISLAND NUCLEAR GENERATING PLANT
((3)
, SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS B ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 0 3 5 1 0 0 9 NNE 1 2 1 1 0 0 5 NE O 2 0 0 0 0 2 ENE O 3 2 0 0 0 5 E 0 1 1 0 0 0 2 I
O SE 2 2 8 4 0 0 16 SSE O 3 4 3 0 0 10 S 1 0 7 9 0 0 17 SSW 0 1 7 0 0 0 8 SW 0 4 1 0 0 0 5 4 WSW 1 2 5 1 0 0 9 W 0 8 7 3 0 0 18 WNW 1 5 8 6 3 0 23 NW 2 4 11 10 1 0 28 NNW 1 5 3 1 0 1 11 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 191 HOURS OF CALM THIS CLASS 0 g PERCENT OF ALL DATA THIS CLASS 2.28 i IBM
ODCM Rev. 8 Page 110 NORTHERN STATES POWER COMPANY
' PRAIRIE ISLAND NUCLEAR GENERATING PLANT ~
SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS C ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 2 4 4 1 0 0 11 NNE 2 3 1 0 0 0 6 NE 1 5 1 0 0 0 7 ENE O 3 1 0 0 0 4 E 1 8 3 0 0 0 12 ESE O 7 11 2 0 0 20 SE O 2 5 6 0 0 13 SSE O 2 6 7 1 0 16 S 0 2 10 4 0 0 16 SSW 1 6 4 0 0 0 11 SW 2 2 3 2 0 0 9 , WSW 1 6 5 1 2 0 15 W 0 2 11 4 1 0 18 WNW 1 3 6 7 1 0 18 NW 2 7 11 16 6 1 43 NNW 3 5 7 3 3 0 21 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 240 HOURS OF CALM THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS 2.87 IBM
ODCM Rev. 8 Page 111 NORTHERN STATES POWER COMPANY
""^'"" ^"" ""*" '"'"^" "" "'**'
(D SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION' PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS D ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 9 24 11 8 0 0 52 NNE 6 22 9 0 0 0 37 NE 16 26 4 0 0 0 46 ENE 11 41 4 0 0 0 56 E 11 95 27 0 0 0 133 ESE 8 57 154 19 0 0 238 SE 10 30 90 38 5 0 173 SSE 8 40 59 51 10 0 168 S 1 51 72 17 4 0 145 SSW 5 29 30 12 0 0 76 SW 4 15 17 4 0 0 40 WSW 5 23 31 21 3 4 87 W 6 53 61 28 6 1 155 WNW 14 57 76 75 21 0 243 NW 14 44 72 110 41 0 281 NNW 16 22 41 25 13 0 117 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 2051 O HOURS OF CALM THIS CLASS PERCENT OF ALL DATA THIS CLASS 4 24.49 IBM
ODCM
- - Rev. 8 Page 112 NORTHERN STATES POWER COMPANY ,F PRAIRIE ISLAND NUCLEAR GENERATING PLAh7 SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS E ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 22 30 9 11 1 0 73 NNE 18 29 7 0 0 0 54 NE 22 26 7 1 0 0 56 ENE 19 30 5 1 0 0 55 E 25 96 10 0 0 0 131 ESE 28 144 140 27 0 0 349 O SE 24 107 125 41 2 0 299 SSE 21 67 74 23 0 0 185 S 11 56 73 29 1 0 170 SSW 3 26 29 40 1 0 99 SW 14 22 17 12 0 0 65 WSW 14 24 24 11 1 0 74 W 26 73 48 18 1 0 166 I 4 357 l
WNW 46 136 127 44 0 46 98 101 62 8 0 315 NW 43 53 48 10 3 0 157 NNW 0 0 0 0 0 0 VAR 0 TOTAL HOURS THIS CLASS 2612
/~
( HOURS OF CALM THIS CLASS 7 31.18 PERCENT OF ALL DATA THIS CLASS IBM
CDCM
. . Rev. 8 Page 113 NORTHERN STATES POWER COMPANY p PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS F ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 18 8 3 0 0 0 29 NNE 11 6 1 0 0 0 18 NE 11 5 2 0 0 0 18 ENE 13 7 0 0 0 0 20 E 29 33 2 0 0 0 64 ESE 39 61 9 1 0 0 110 SE 38 69 36 3 0 0 146 SSE 27 32 17 2 1 0 79 S 12 16 21 7 0 0 56 SSW 6 11 17 6 0 0 40 SW 5 3 9 4 0 0 21 WSW 8 8 8 0 0 0 24 W 25 39 12 2 0 0 78 WNW 56 63 12 0 0 0 131 NW 66 71 16 3 0 0 156 NNW 29 19 6 2 0 0 56 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 1053 O HOURS OF CALM THIS CLASS PERCENT OF ALL DATA THIS CLASS 12.57 7
IBM
. s ,
ODCM
- * . Rev. 2 Page 114
,, i NORTHERN STATES POWER COMPAhT PRAIRIE. ISLAND KUCLEAR GENERATING PLANT d SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 . .
STAB'ILITY CLASS G ELEVA% ION 40 FT DIRECTION 1 TO 3 4 TO'7 T . TO 4 ABOVE 24 TOTAL N 14 5 0 [0 0 0 19 NNE 13 2 1 0 0 0 16 NE 12 2 1 0 0 0 15 ENE 22 1 2 ;O O O 25 E 52 E 2 0 0 0 62 ESE 50 17 1 0 0 0 68 SE 37 23 8 1 0~ 0 69 SSE 18 i 8 7 2 0 0 , 35 11 4 4 0 0 0 19
S .
13 2 2 0 0 0 17 SSW 15 5 1 0 0 0 21 SW 10 1 0 0 0 12 WSW . I i i 0 0 61 W 41 19 l 0 75 50 0 0 0 0 125 WNW 80
- 66 3 - 0 0 0 149
- NW 47 19 5 0 0 0 7 '.
NNW ,. t 0 0 0 0 0 0 VAR 0 i TOTAL EOURS THIS CIMS 821
\ HOURS OF CALM THIS CLASS 37 PERCEN't 0F ALL DATA THIS CLASS 9.30
~
IBM 4
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ODCM Rev. 8 Page 115 A U APPENDIX C 4 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AND TRITIUM i This appendix contains the methodology which was used to ! calculate the dose parameters for radioiodines, particulates, and , tritium to show compliance with 10 CFR 20 and Appendix I of 10 CFR 50 for gaseous effluents. These dose parameters, P. and R g, were calculated using the methodology outlined in NURfG-0133 along with Regulatory Guide 1.109 Revision 1. The following sections provide the specific methodology which was utilized in calculating the P f and R g values for the various exposure pathways. C.1 Calculation of P. - 1 The parameter, P , contained in the radiciodine and L particulates porbion of Section 3.2, includes pathway-transport parameters of the ith radionuclide, the receptor's ,
,,/ usage of the pathway media and the dosimetry of the ^
j exposure. Pathway usage rates and the internal dosimetry are functions of the receptor's age: however, the youngest age group, the infant, will always receive the maximum. dose under the exposure conditions assumed. ,- C.l.1 Inhalation Pathway P = K'(BR) DFA g (C.1-1) ', i I where: P.1 = t dose inhalation parameter formrem pathway, radionuclide i for3;he
/yr per pCi/m r
K' = a constant of unit conversion: 6
= 10 pCi/pci; BR = tgebreathingrateoftheinfant m /yr; age group,
() DFA g = the maximum organ inhalation dose factor for the infant age group for radionuclide i, mrem /pCi. IBM
1 ODCM Rev. 8 ' Page 116 l N The age group considered is the igfant group.' The infant's
/
d breathing rate is taken as 1400 m fyr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the infant, DFA are presented in Table E-10 ofRegulatoryGuide1.109ik,unitsofmrem/pCi. The total body is considered as an organ in the selection of DFA. . The incorporation of breathing rate of an infant and tfie unit conversion factor results in the following: 9 Pg = 1.4 x 10 DFA g (C.1-2) I C.2 Calculation of R. The radiciodine and particulate Technical Specification is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are consiOtred based on their existence at the various locations. R. values have been calculated for the adult, teen, child,dnd infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is l Q V presented below. C.2.1 Inhalation Pathway R = K'(BR), (DFAf ), (C.2-1) f where: R.l = dose factor for each identified I radionuclide i of the organ of interest, mrem /yr per pCi/m3; K' = a constant of unit conversion: ( 6
= 10 pCi/pCi; (BR), = breathing ratg of the receptor of age group a,m fyr:
(DFAg )a
- organ inhalation dose factor for l radionuclide i for the receptor of age group a, mrem /pCi.
( I for the various age groups are The breathing tabulated rates below, (BR), in Table E-5 of the Regulatory as given
/G d Guide 1.109 Revision 1.
IBM l .. - . - - - -
ODCM Rev. 8 Page 117 Age Group (a) Breathing Rate (m /yr) v(~'] 1400 Infant Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA. for the various age groups are given in Tables E-7 throdg)8 E-10 of Regulatory Guide 1.109 Revision 1. C.2.2 Ground Plane Pathway
-A t R.i = I iK'K"(SF)DFG.1 (1-e i )/A i (C.2-2) g where:
R. = dose factor for the ground plane pathway l a for each identified radionuclide i for the organ of interest, mrem /yr per pCi/sec per m ~; K' = a constant of unit conversion;
= 10 pCi/pci; K" = a constant of unit conversion;
= 8760 hr/ year; A.1 = the radiological decay constant for
~
radionuclide i, sec *; t = the exposure time, sec;
=
8 sec (15 years); 4.73 x 10 DFG 1 = the ground plane dose conversion fact 9r for radionuclide i; mrem /hr per pCi/m"; SF = the shielding factor (dimensionless); I. 1
= factor to account for fractional deposition of radionuclide i.
For radionuclides other than iodine, the factor I is equal to one. For radiciodines, thevalueof1. bay
/~ vary. However, a value of 1.0 was used in calchlating (m]/ the R values in Table 3.3-2.
IBM
ODCM Rev. 8 Page 118 ('T A shielding factor of 0.7 is suggested in Table E-15
\v/ of Regulatory Guide 1.109 Revision 1. A tabulation of DFG. values is presented in Table E-6 of Regulaf.ory Guide 1.109 Revision 1.
C.2.3 Grass-Cow or Goat-Milk Pathway
-A t IV(1-e i*b )- +
R ,7 g,Q FUapFm(DFL )a e f ff #(1~* I ) + b i i ps YA PE i PA 1 -
- -A U E
(1-f f )
#(1-* i e) + B fy (1-e - 1 b) , -Afh t- '( * ~ )
Ps _ Y,AE PA i 1 - - where: R. = dose factor for the cow milk or goat milk 1 M pathway, for each identified radionuclide i for the organ _gf interest, mrem /yr per pCi/sec per m ; J K' = a constant of unit conversion; 6
= 10 pCi/pCi; "w)
N_/ Qp
= the cow's or goat's feed consumption rate, kg/ day (wet weight);
U ap
= the receptor's milk consumption rate for age group a, liters /yr; Y
p
= the agricultural productivi3y by unit area of pasture feed grass, kg/m ;
Y = the agricultural pro 4uctivity by unit area s of stored feed, kg/m';
= the stable element transfer coefficients, F* pCi/ liter per pCi/ day; l r = fraction of deposited activity retained on l
cow's feed grass; (DFLg ), = the organ ingestion dose factor for radionuclide i for the receptor in age group l a, mrem /pCi; i l O IBM
. ODCM Rev. 8 Page 119
() A A E f
=
Ai+ AwI the radiological decyy constant for radionuclide i, sec ;
= the decay constant for removal of activity A"
on lyaf and plant surfaces by weathering, sec ;
= 5.73 x 10~7 sec ~1 (corresponding to a 14 day half-life);
cf = the transport time from feed to cow or goat to milk, to receptor, sec; t = the transport time from harvest, to cow or h goat, to consumption, sec; t b
= Period of time that sediment is exposed to 4 gaseous effluents sec; B = concentration factor for uptake of iv radionuclide i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil);
O(_j P = effectiye surface density for soil, (dry soil)/m ; f = fraction of the year that the cow or goat P is on pasture; f = fraction of the cow feed that is pasture s grass while the cow is on pasture; t e
- Period of pasture grass and crop exposure during the growing season, sec; I. = factor to account for fractional deposition 1
of radionuclide i. For radionuclides other than iodine, the factor I. is equal to one. For radioiodines, the value of I. day vary. However, a value of 1.0 was used in calculating the R values Tables 3.3-9 through 3.3-16. Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of f was considered unity in
/T lieu of site-specific info bation. The value of f P
(_) was 0.667 based upon an 8-month grazing period. IBM
ODCM Rev. 8 Page 120 Table C-1 contains the appropriate parameter values and (
/
their source in Regulatory Guide 1.109 Revision 1. The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R is based on X/Q: f R = K'K"'F,QpQpU ,p(DFL1 ), 0.75(0.5/H) (C.2-4) T where: R = dose factor for the cow or goat milk pathway T a fortritiumfortgeorganofinterest, mrem /yr per pCi/m ; K"' = a constant of unit conversion; 3
= 10 gm/kg; 3
H = absolute humidity of the atmosphere, gm/m ; 0.75 = the fraction of total feed that is water; 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. and other parameters gnd values are given above. A value of H of 8 grams / meter , was used in lieu of site-specific information. C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, I therefore: i
-A t 31v(1~* - i*b)-
-Al t, R = I K'Q UapFm(DFLi )a e ff r (1-e i *) +
ig i F ps YAp PA
~ -
-A t l r(1-e Eg e) B iy (1-e 1*b)~e 4t ih (C.2-5)
(1-fps f ) + YA 3 g PA g
.- I where:
R1 = dose factor for the meat ingestion pathway for radionuclide i for anv mrem /yr per pCi/sec per m 2;rgan of interest, B L 1 l IBM
ODCM Rev. 8 Page 121 the stable element transfer coefficients, ()
\_ '
F f
=
pCi/Kg per pCi/ day; U = the receptor's meat consumption rate for age ap group a, kg/yr; t = the transport time from slaughter to s consumption, sec; t = the transport time from harvest to animal h consumption, sec; e t* = period of pasture grass and crop exposure during the growing season, sec; I. = factor to account for fractional deposition 1 of radionuclide i. For radionuclides other than iodine, the factor I. is equal to one. For radiciodines, the value of I. may vahy. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3.3-8. All other terms remain the same as defined in Equation C.2-3. Table C-2 contains the values which were used in calculating R g for the meat pathway. The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R j is based on X/Q. RT = K'K"'F fF Q U,p(DFL1 ), 0.75(0.5/H) (C.2-6) B where: y B
= dose factor for the meat ingestion pathway for tritium for agy organ of interest, mrem /yr per pCi/m All other terms are defined in Equation C.2-4 and C.2-5, above.
C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
)
IBM
ODCM Rev. 8 Page 122 q -A t (V
~
* ~
~E Uf e
-A t ib #II-* I e) + BIV(1-e i b)-
R ly
=
I,K'(DFL
. 1)a aL YA y E PA f
1 - E
-A t
-A t B S
ih r(1-e E f e) , fy(1-e 1 b) ~ (C.2-7) Uf, ag YA yE PA f
- 1 -
where: R.l = dose factor for vegetable pathway for v radionuclide i for the organ of injerest, mrem /yr per pCi/sec per m ; K' = a constant of unit conversion: 6
= 10 pCi/pCi; b = the consumption rate of fresh leafy U
vegetation by the receptor in age group a, kg/yr; U, = the consumption rate of stored vegetation by the receptor in age group a, kg/yr; f = the fraction of the annual intake of t fresh leafy vegetation grown locally; f = the fraction of the annual intake of a stored vegetation grown locally; tg = the average time between harvest of leafy vegetation and its consumption, sec; t = the average time between harvest of h stored vegetation and its consumption, sec; Yy = the vegetation areal density, kg/m2;
= period of leafy vegetable exposure t* during growing season, sec; I. = factor to account for fractional deposition of radionuclide i.
1 l l IBM
ODCM Rev. 8 Page 123
? For radionuclides other than iodine, the factor I is equal to one. For radioiodines, the value of I kay vary. However, a value of 1.0 was used in calcblating the R values in cables 3.3-9 through 3.3-12.
All other factors were defined above. Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1. In lieu of site-specific data default values for ft and f , 1.0 and 0.76, respectively were used in the eftlculation of R These values were obtained from TableE-15ofReku.latory Guide 1.109 Revision 1. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R g is based on X/Q: [
"Ty - K'K"' U[fy + U[fg (DFLf ) , 0.75 (0.5/H) (C.2-8) where:
R = dose factor for the vegetable pathway for T tritium fp any organ of interest, mrem /yr per pCi/m All other terms remain the same as those in Equations C.2-4 and C.2-7. O IBM
ODCM Rev. 6 Page 124 TABLE C-1 Parameters For Cow and Goat Milk Pathways Parameter Value Reference (Reg. Guide 1.109 Rev. 1 Qp (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 2 Yp (kg/m ) 0.7 Table E-15 t 1.73 x 105 (2 days) Table E-15 f (seconds) i r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFLg ), (mrem /pCi) Each radionuclide Tables E-11 to E-14 F" (pCi/ day per pCi/ liter) Each stable element Table E-1 (cow) Table E-2 (goat) t 4.73 x 108 (15 yr) Table E-15 b (seconds) Y, (kg/m ) 2.0 Table E-15 Y p (kg/m ) 0.7 Table E-15 t 7.78 x 100 (90 days) Table E-15 h (seconds) U ap (liters /yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 t 2.59x10f(pasture) Table E-15
* (seconds) 5.18 x 10 (stored feed) l B
gy (pCi/Kg (wet weight) Each stable element Table E-1
,. per pCi/Kg (dry soil)) . P (Kg (dry soil /m 2) 240 Table E-15 IBM
ODCM
' - - Rev. 8 Page 125 fg TABLE C-2 V Parameters For The Meat Pathway Parameter Value Reference (Reg. Guide 1.109 Rev. I r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/ day) Each stable element Table E-1 U ap 0 infant Table E-5 (Kg/yr) 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFLg ), (mrem /pCi) Each radionuclide Tables E-11 to E-14 Y 0.7 Table E-15 p (kg/m )
2 Table E-15 Y, (kg/m ) 2.0 t 4.73 x 108 (15 yr) Table E-15 b (seconds) t, (seconds) 1.73 x 106 (20 days) Table E-15 t 7.78 x 100 (90 days) Table E-15 h (seconds) i t,(seconds) 2.59 x 100 (pasture) Table E-15 5.18 x 10 (stored feed) Qf (kg/ day) 50 Table E-3
- B (pCi/Kg (wet weight) Each stable element Table E-1 fy per pCi/Kg (dry soil))
P (Kg (dry soil)/m ) 240 Table E-15 O IBM
x-
., ODCM Rev. 8 Page 126 TABLE C-3 Parameters For The Vegetable Pathway Parameter Value Reference (Reg. Guide 1.109 Rev. I r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFLg ), (mrem /Ci) Each radionuclide Tables E-11 to E-14 UL*
(kg/yr) - Infant 0 Table E-5
- Child 26 Table E-5
- Teen 42 Table E-5
- Adult 64 Table E-5 Uf(kg/yr) - Infant 0 Table E-5
- Child 520 Table E-5
- Teen 630 Table E-5
- Adult 520 Table E-5 tg (seconds) 8.6 x 100 (1 day) Table E-15 t 5.18 x 100 (60 days) Table E-15 h (seconds) 2 Yy (kg/m ) 2.0 Table E-15 t,(seconds) 5.18 x 106 (60 days) Table E-15 t 4.73 x 108 (15 yr) Table E-15 b (seconds)
P(Kg(dry soil)/m2) 240 Table E-15 B y(pCi/Kg(wet weight) Each stable element Table E-1 er pCi/kg (dry soil)) O IBM}}