ML20062N083
| ML20062N083 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/13/1982 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20062N069 | List: |
| References | |
| PROC-820831, NUDOCS 8208200300 | |
| Download: ML20062N083 (135) | |
Text
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PRAIRIEISLAND NUCLEAR ;
GENERATING PLANT j Red Wing, Minnesota l
UNITS 1 AND 2 l l
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~=:::n OFFSITE DOSE CALCULATION MANUAL !
i NORTHERN STATES POWER COMPANY !
MINNE APOLIS. MINNESOTA
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t-PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION M ANUAL (ODCM) .
AUGUST, 1982 REV. 2 b
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Q DOCKET NO. 50-282 and 50-306 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA r
PREPARED . u4 7/28/82-DATE:
REVIEWED 8/h- - 4 DATE: A c2 8o2 OPERATIONS CO) E FIF L IEW-MEETING NO. [ 3 DATE: ["/ 7-8Q APPROVED BY:
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TABLE OF CONTENTS Section Title Page Table of Contents i List of Figures 11 List of Tables lii Record of Revisions v i
List of Effective Pages vi
1.0 INTRODUCTION
1-1 2.0 LIQUID EFFLUENTS 2-1 2.1 Monitor Alarm Setpoint Determination 2-1 ,
2.2 Liquid Effluent Concentration - Compliance 2-7 With 10 CFR 20 2.3 Liquid Effluent Doses - Compliance 2-9 -
With 10 CFR 50 References 2-13 ,
3.0 GASEOUS EFFLUENTS 3-1 3.1 Monitor Alarm Setpoint Determination 3-1 3.2 Gaseous Effluent Dose Rate - Compliance 3-7 With 10 CFR 20 3.3 Gaseous Effluent Doses - Compliance 3-12
, with 10 CFR 50 -
References 3-18 4.0 INFORMATION RELATED TO 40 CFR 190 4-1 AND 40 CFR 141 5.0 RADIATION ENVIRONMENTAL MONITORING 5-1 PROGRAM L
APPENDIX A - Meteorological Dispersion A-1 Parameters APPENDIX B - Joint Frequency Distribution B-1 Tables APPENDIX C - Dose Parameters for Radioiodines, C-1 Particulates and Tritium I
i Rev. 2 ,.
P
LIST OF FIGURES Figure Page 5.!-l Prairie Island Nuclear Generating 5-6 Plant Radiation Environmental Monitoring Program 5.1-2 Site Boundary TLD Locations 5-7 5.1-3 4-5 Mile Ring, Control, and Special 5-8 Interest TLD Locations O
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LIST OF TABLES Tables Page 2.1- 1 Liquid Source Terms For PNGP 2-6 2.3- 1 A; Values for the PNGP 2-14 3.1-1 Monitor Alarm Setpoint Determination For PNGP 3-4 3.1-2 Gaseous Source Terms For PNGP 3-5 3.1-3 Dose Factors and Constants 3-6 3.2-1 P; Values for the PNGP 3-11
- 3. 3- 1 Dose Factors for Noble Gases and Daughters 3-19 3.3-2 R; Values for the PNGP- Ground, All Ages 3-20 3.3-3 R; Values for the PNGP- Vegetable, Adult 3-21 3.3-4 R; Values for the PNGP- Vegetable, Teen 3-22 3.3-5 R; Values for the PNGP- Vegetable, Child 3-23 3.3-6 R; Values for the PNGP - Meat, Adult 3-24 3.3-7 R; Values for the PNGP- Meat, Teen 3-25 3.3-8 R; Values for the PNGP - Meat, Child 3-26 3.3-9 R; Values for the PNGP- Cow Milk, Adult 3-27 3.3-10 R; Values for the PNGP - Cow Milk, Teen 3-28 3.3-11 R; Values for the PNGP - Cow Milk, Child 3-29 3.3-12 R; Values for the PNGP - Cow Milk, Infant 3-30 3.3-13 R; Values for the PNGP- Goat Milk, Adult 3-31 3.3-14 R; Values for the PNGP- Goat Milk, Teen 3-32 3.3-15 R; Values for the PNGP- Goat Milk, Child 3-33 3.3-16 R; Values for the PNGP - Geat Milk, Infant 3-34 3.3-17 R; Values for the PNGP-Inhalation, Adult 3-35 3.3-18 R; Values for the PNGP - Inhalation, Teen 3-36 iii
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__ . -. . . . = - . - .- _- -- - . _ . . -
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LIST OF TABLES (Continued) i Tables Page i
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3.3-19 R; Values for the PNGP - Inhalation, Child 3-37
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4 3.3-20 R; Values for the PNGP - Inhalation, Infant 3-38 l
5.1-1 PNGP - Radiation Environmental Monitoring 5-3 ;
Program Sampling Locations !
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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 Aug 6, 1982 Incorporation of NRC Staff comments W
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'y Rev. 2
LIST OF EFFECTIVE PAGES Page No. Revision No. Page No. Revision No.
Cover 2 3-11 2 1 2 3-12 0 11 1 3-13 2 111 0 3-14 2 iv 0 3-15 2 y 2 3-16 2 vi 2 3-17 0 1-1 1 3-18 1 2-1 2 3-19 0 2-2 2 3-20 2 2-3 2 3-21 2 2-4 1 3-22 2 2-5 1 3-23 2 2-6 1 3-24 2 2-7 2 3-25 2 2-7a 2 3-26 2 2-8 2 3-27 2 2-9 0 3-26 2 2-10 2 3-29 2 2-11 2- 3-30 2 2-12 2 3-31 2 2-13 1 3-32 2 2-14 2 3-33 2 -
2-13 2 3-34 2 -
3-1 2 3-35 2 3-2 1 3-36 2 3-3 1 3-37 2 3-4 2 3-38 2 3-5 2. 4-1 1 3-6 1 4-2 0 3-7 1 4-3 0
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3 2 5-1 1 3-9 2 5-2 2 3-10 2 5-3 2 5-4 1 5-5. 1 5-6 2 5-7 2 5-8 1 A-1 thru 0 A-39 B-1 thru' O B-8 C-1 thru ?
C-14 vi -Rev.12.
1.0 INTRODUCTION
This Offsite Dose Calculation Manual (ODCM) provides the information and meth-odologies to be used by the Prairie Island Nuclear Generating Plant (PNGP) to assure compliance with certain portions of PNG P'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 1, 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 Specifications for Nuclear Power Plants (NUREG-0133, October 1978)," and other inputs from the Nuclear Regulatory Commission (USNRC). Specific plant pro-cedures for implementation of this manual are provided elsewhere. These pro-cedures will be utilized by the operating staff of the PNGP to assure compliance with the Technical Specifications.
Also included in this manual is information related to the Radiological Environ-mental 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 requirements 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 min-imize 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.
1-1 Rev.1
2.0 LIQUID EFFLUENTS 2.1 Monitor Alarm Setpoint Determination This procedure determines the monitor alarm setpoint that indi-cates if the concentration of radionuclides in the liquid. effluent released at the site boundary exceeds the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration ,
of 2 x 10-4 gCi/ml for dissolved or entrained noble gases.
Monitor high alam or isolation setpoints will be established in one of these ways:
- a. Monthly calculation of setpoints using the methodology of Section 2.1.1
- b. Calculation of alam setpoint based on analysis prior to discharge using methodology of Section 2.1.2
- c. Alam setpoint detemined using methodology of Section 2.1.1 assuming all radionuclides have an HPC of IE-7 uCi/ml. No recalculation of -
setpoints is necessary unless an increase in alam setpoint is desired.
PVR CALE Code source tems (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 set-Points for the Waste Effluent Liquid Monitor (R-18), Steam Genera-tor 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 constant at the maximum design flow rate.
2-1 Rev. 2
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. Determine Si (the fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i") for each individual radionuclide in the liquid effluent.
= Ai Si
}[Ai (2.1-1) i Ai = The radioactivity of radionuclide "i" in the liquid -
effluent 2.1.1.2 Determine Ct (the maximum acceptable total radioactivity concentration of all radionuclides in the liquid effluent prior to dilution (gCi/ml)). .
Ct*
f Si (2.1-2)
MPCi i
F = Dilution water flow rate (gpm)
= 4.52E5 gpm from cooling tower blowdown and water entering the discharge canal. from Sturgeon Lake (l) f = The maximum attainable discharge flow rate prior to dilution (gpm) 2-2 Rev. 2
= 60 gpm from the ADT tank pump (2)
= 100 gpm from the CVCS tank pump (2)
= 60 gpm from the SGBD tank pump (2)
MPCi = The liquid effluent radioactivity concentration limit for radionuclide "i" (pCi/ml) from Table 2.1-1 or if not listed in Tabla 2.1-1, obtained from Rererence 3.
2.1.1.3 Determine Cm (the maximum acceptable total radioactivity concentration o'f the radionuclides (minus tritium) in the liquid discharge prior to dilution (gCi/ml)).
Cm=Ct- (CtHS ) (2.1-3) -
SH = The fraction of the total radioactivity in_the liquid effluent contributed by tritium and other -
radionuclides that do not emit gamma or X-ray radiation. .
2.1.1.4 Determine C.R. (the calculated monitor count.rateiabovel background attributed to the radionuclides (nepm)).
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C.R. is obtained by using the' applicable Effluent. Monitor Effic-iency Curve located in the Radiation Monitor Calibration file.
C.R. is the count rate that corresponds to)the " adjusted" total radioactivity concentration (C m)-
(
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2-3 1 ,
Rev. 2
2.1.1.5 Determine BSP (the monitor high alarm setpoint above background (nepm)).
HSP = T mC.R. (2.1-4)
Tm = Fraction of the radioactivity from the site that may be released via each release point to ensure that '
L the site coundary 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) ~
Tm values may be revised from the values given above.
j The summation of all the Tm values 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 Discharce '
(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 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.
2-4 Rev. 1
2.1.2.1 Determine f (the maximum acceptable discharge flow rate prior to dilution (gpm)).
g , 0.8 F Tm Ci (2.1-5)
MPCi i
F = Dilution water flow rate (gpm)
= 4.52E5 gpm from cooling tower blowdown and water entering the discharge canal from Sturgeon Lake.(1)
Ci = Concentration of radionuclide "i" in the liquid effluent prior to dilution (#Ci/ml) from analysis of the liquid effluent to be released.
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MPCi = The liquid effluent radioactivity concentration limit for radionuclide "i" (gCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1 from Refer-ence 3.
Tm = 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 (ncpm)).
C.R. is obtained by using the applicable Effluent Moni-tor Efficiency Curve located in the Radiation Monitor 2-5 Rev. 1 s
o
Calibration file. C.R. is the count rate point that corresponds to the " adjusted" total radioactivity con-centration (C m)-
Cm = The total radioactivity concentration of the radio-nuclides (minus tritium and other radionuclides that are only beta emitters) in the liquid discharge prior to dilution (pCi/ml) as determined using Equation 2.1-3. (Ct and SH being determined by analysis of undiluted liquid effluents.)
- b. Determine HSP (the monitor high alarm setpoint above background (ncpm)).
HSP = C.R. (2.1-6) 0.8 0.8 = A correction factor to increase the monitor set-point to prevent spurious alarms caused by devia-tions 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 i optional method is selected. ,
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2-6 Rev. 1
TABLE 2.1-1 LIQUID SOURCE TERMS (2) WASTE EFFLUENT SGBD RADIONUCLIDE MPC (gCi/ml) (Ai)(Ci/Yr)
( A_) (Ci/Yr)
I-131 3E-7 3.061E-2 4.llE-2 Te-132 2E-5 2.12E-3 3.61E-3 1-132 8E-6 2.83E-3 1.88E-2 1-133 IE-6 2.365E-2 4. 856E-2 Cs-134 9E-6 1.464E-1 4.047E-2 1-135 4E-6 4.84E-3 1.792E-2 Cs-136 6E-5 5.743E-2 1.862E-2 Cs-137 2E-5 8.214E-2 2.69E-2 All Others IE-7 0 2E-5 11 - 3 - 3E-3 1.89E2 1.41E2 Noble gases 2E-4 - -
r Total 1.894E2 1.412E2 .
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2-7 Rev. 2
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 permissable concentrations (MPC) as de-fined in Appendix B, Table 11 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 blow-down. The alarm trip set points 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 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:
C3 R Conc; =
MDF (2.2-1) 2-7a Rev. 2
B where Conc; = concentration of radionuclide i at the site boundary, pCi/ml; C; = concentration of radionuclide i in the potential batch release, Ci/ml; R = release rate of the batch MDF = minimum dilution flow (=67,300 gpm) 4 The projected concentration at the site boundary is compared to the MPCs in Appendix B, Table II 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.
Conc'.
I m gc. s 0.9 <2.2-2>
1 1 MPC; = Maximum permissible concentration of radionuclide i from Appendix B, Table 11 of !O CFR 20, pCi/ml 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 tems shall not be greater than 1.0 of the 10 CFR 20 limit.
2-8 Rev. 2
l' 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 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.
t 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 separated by unit, steam generator blowdown and turbine building sump releases, contribute a very small portion 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 !
will be doubled.
]
2.3.1 Determination of Liquid Effluent Dilution 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:
R9 F *
(2.3-1) k X ADF k where Rk =
release rate of the batch or continuous releases during the period, k, gal; ADF k = actual dilution flow during the time period of release k, gal.
2-9
The value of X is th'e site specific factor for the mixing effect of the PNGP dis-charge structure. This value is 10 for PNCP while operating in the closed cycle cooling mode.(1)The product of X and ADFk is limited to 1000 cfs (4.5 x 105 gpm). Therefore, since blowdown flow in closed cycle is 150 cfs, the denominator of Equation 2.3-1 is always 4.5x105 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:
Dr 11 A *k C ik F k
= (2.3-2) ir ka where:
Dr = the dose commitment to the total body or any organ r , from the liquid effluents for the period of release, mrem; C ik = the average concentration of radionuclide, i, in undiluted liquid effluent for liquid release k, pCi/ml; A = the site related ingestion dose commitment factor ir to the total body or any organ r for each identified I
principal gamma and beta emitter, mrem /hr per pCi/ml; I
I F = the near field average dilution factor for C during 9 ik liquid effluent release k,
! t k
= the duration of release k, hours.
l 2-10 Rev. 2
The dose factor A r was calculated for an adult for each isotope using the fol-lowing equation:
A = 1.14x 10' 21BF; DF;, (2.3-3) ir where 6
1.14x105 = 10 pCi x 3 10 mj x 1 yr ,
pCi 1 8760 hr '
21 = adult fish consumption, Kg/yr; BF. =
bioaccumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109 Rev.l(5) pCi/Kg per pCi/1; DF =
dose conversion factor for radionuclide i for adults for ir .
a particular organ r from Table E-ll of Regulatory Guide 1.109 Rev.1,( } mrem /pCi.
A table of A ir values for an adult at the PNGP are presented in Table 2.3-1.
Mississippi River water is not used as a potable water supply within 300 miles downstream of the PNGP. Wells are used for irrigation downstream of the plant.'
2.3.3 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 for the combined releases of both reactor units. The following relationships should hold:
For the quarter, Dr < 3.0 mrem total body (2.3-4)
Dr < 10 mrem any organ (2.3-5) 2-11 Rev. 2
For the calencar year, .
Dr < 6.0 mrem total body (2.3-6)
D, < 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 sub-mitted to the USNRC identifying the cause and co rective action to be taken. If -
'f 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 the projected doses for the month exceed 2 percent of Equation 2.3-6 or 2.3-7, additional components of tile liquid radwaste treatment system will be used to process waste. The projected doses will be calculated using Equation 2.3-2.
The dilution factor, Fk, will be calculated by replacing the term ADF9in Equation 2.3-1 with the term MDF from Equation 2.2-1. The total source term utilized for the most recent dose calculation should be used for the projections unless information exists indicating that actual releases could di!fer significantly in the- ,
next month. In this case, the source term whould 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.
2 Rev. 2
- REFERENCES (1) " Prairie Island Final Environmental Statement," USAEC, May,1973, p. V-26.
(2) "NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis -
Supplernent No.1 - Docket No. 50-282 and 50-306," Table 2.1-1.
(3) "10CFR20," Appendix B, Table II, Column 2.
(4) "NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis -
Supplement No.1 - Docket 50-282 and 50-306," July 21,1976, Table 2.1-2.
(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 10CFR50, Appendix 1," Rev.1, 1977.
i 2-13 Rev.I
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TA3LE 2.3-1 A u VALUES FOR THE PRAIRIE ISLAND NdCLEAR OENERATING PLANT (MREM /HR ped gGI/ML)
NUCLIOE BndE LIVER T.dOOf THYRIod XIDNEY LUNG G I-LL I IH 3 0. 00 E-01 2. 26 E-01 2.26E-]! 2.26E-01 2.26E-01 2.26E-01 2.26E-Gi 6C 14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 Il!!A 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 1.27 E 00 7.6lE-01 2.dlE-01 1.69E 00 3.20E 02 254N 54 0.00E-01 4.38E 03 S.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 25M.1 56 0.00E-01 1.10E 02 1.95 E 01 0.00 E-01 1.40E 02 0.00E-01 3.5IE 03 25FE 55 6.58E 02 4.555 02 1.06E 02 0.00E-01 0.00E-01 2.545 02 2. 61 E 02 26FE 59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6 925 02 8.14E 03 27C0 58 0. 00 E-01 S.92E 01 2.00E 02 0.006-01 0.00E-01 u. 00 E-01 1. d l E 03 27CO 60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4. ale 03 28MI 63 3.IIE 04 2.16E 03 1.04E 03 0.00E-01 0. 00 E-01 0.00E-Ol' 4.50E 02 2SNI 65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 20C0 64 0.00E-01 J.97E 00 4.6dE 00 0.00E-01 2.51E 01 0.00E-01 S.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./3E 03 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01-35 8R 83 0. 00 E-01 0.00 E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.32E 01 35BH 84 0.00E-01 0.00E-01 5.24E 01 0.005-01 0.00E-01 0.00E-01 4.llE-04 35 BR 85 0.00E-01 0.00E-01 2.15 E 00 0. 00 E-01 0.00 E-01 0.00 E-01 1.01E-15 37dB d6 0.00E-01 1.OIE 05 '4./IE 04 0.00E-01 0.00E-01 0.00E-01 1.19E 04 37W3 dd 0.00E-01 2.90E 02 1.54E 02 0.00 E-01 0. 00.E-01 0. 00 E-01 4.00E-09 37R3 39 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-Il 38SR 89 2.21E 04 0.00E-01 6.35E 02 0.00E-01 0. 00E-01 0.00E-01 3.55E 03 38Sd 90 5.44E os 0.00E-01 l_34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 385R 91 4.07E 02 0.00 E-01 1.64E 01 0.00 E-01 0.00 E-O l 0.00E-01 1.94E 03 1SSR 92 1.54E 02 0.00E-01 6.6SE 00 0.00E-OI 0.00E-01 0.00E-01 3.06E 03 39Y 90 5. 76 E-01 0. 00 E-01 1.5 4 E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 39Y 91M 5.44E-03 0.005-01 2.llE-04 0.00E-01 0. 00E-01 0.00E-01 1.60E-02 39Y 91 S.44E 00 0.00E-01 2.25E-01 0.00E-01 0.00E-01 0. 00E-01 4.64E 03 39Y 92 3.06E-02 0.00E-01 1.4dE-03 0.00E-01 0.00E-01 0.00E-01 8.d6E 02 39Y 93 I.60E-01 0.00E-01 4. 43 E-03 0.00 E-01 0.00E-01 0.00E-01 5.09E 03 40ZH 95 2.40E-01 7.70E-02 5.21E-02 0.00E-01 1.21E-01 0.00E-01 2.44E 02 40ZR 97 1.33E-02 2.68E-03 1.22E-03 0.00E-01 4.04E-03 0.00E-01 8.30E 02 41NS 95 4.47E 32 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-Ol 1.51E 06 4240 99 0.00E-01 1.03E 02 1.16E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 43TC 194 a.87E-03 2.51E-02 3.19E-01 0.00E-01 3.dlE-01 1.23E-02 1.48E 01 43T0101 9.I2E-03 1.3iE-02 I.29E-01 0.00E-01 2.37 E-01 6.72E-03 3.95E-l4 14RU103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.60E 01 0.00E-01 5.17E 02 14Rul05 3.69E-01 0.00E-01 1.46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 44R0106 6.58E 01 0.00E-01 8. 33 E 00 0.00 E-01 1.27E 02 0. 00E-01 4.26E 03 47AGil04 d.8lE-GI S.15E-01 4.84E-01 0. 00E-01 1.60E 00 0.00E-01 3.33E 02
! 52TE125M 2.57E 03 9.30E 02 3. 44E 02 7.72E 02 1.04E 04 0. 00 E-01 1.02E 04 l 52TE127'A 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0. 00 E-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 l 52TE129M 1.10E 04 4.11E 03 L.74E 03 3.78E 03 4.60E 04 0.005-01 5.54E 04 l 52TE129 3.0IE 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 l 52TEl31M l.66E 03 d.10E 02 6.75E 02 1.28E 03 8.21 E 03 0.00E-01 8.04E 04 l 52TE131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 3.26E 01 0.00E-01 2.61E 00 52TE132 2. ale 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.38E 04 63I 130 2.7tE 01 a.0IE 01 3.16E 01 16.7dE 03 1.25E 02 0.00E-OI 6.39E 01 53I 131 1.49E 02 2.14E 02 1.225 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 l
2-14 Rev. 2
TABLE 2.3-1 (Co.1T.)
Act VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT (MREM /HR PER p0I/ML) . . _ . _ . . . . .- . . _ _ _ _ . . _ .
NUCLIDE BONE LIVER T. BODY THYRIOD KIONEY LONG GI-LLI
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ = - - - - - - - - -
53I 132 7.29E 00 1.955 01 6.82E 00 6.82E 02 3.llE 01 0.00E-01 3.66E 00 531 133 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. 03 E 01 _ 3. 70E 00 ..l. 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 0.1 0.00E-01 4.70E 01 55CS134 2.98E 05 7.09E 05 5.79E 05 0. 00 E-01 2.29E 05 7.6lE 04 1.24E 04 55CS135 3.12E 04 1.23E 05 8.36E 04 0. 00E -01 6.85E 04 9.3BE 03 1.40E 04 55CS137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 55.05138 2.64E 02 5.22E 02 2.59E O2 0.00E-01 3.84E 02 3.79E 01 2.23E-03 563Al30 9.29E-Ol 6.62E-04 2.72E-O'2 0.00E-01 6.19E-04 .3.75E-04 1.65E 00 563A140 1.94E 02 2.44E-01 1.27E 01 0. 00E-01 8.30E-02 1.40E-01 4.00E 02 56BAl41 4. 51 E-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. 37 E-19 57LA140 1.50E-01 7.545-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 57LA142 7.66E-03 3.48E-03 8.63E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 5dCE141 2.24E-02 1.52E-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 58C2143 3.95E-03 2.92E 00 3.23E-04 0.00E-01 1.2dE-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 59PRl43 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-0! 2.5 4 E-01 0.00E-01 2.09E 03 744 187 2.96E 02 2.47E 02 S.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 93NP239 2.85E-02 2.80E-03 1.5 4 E-03 0.00E-01 8. 74 E-0 3 0.00E-01 5.75E 02 G
2-15 Rev. 2
3.0 GASEOUS EFFLUENTS l
3.1 Monitor Alarm Setpoint Determination This procedure determines the monitor alarm setpoint that indi-cates 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.
t
- 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. 1007. Kr-89).
No recalculation of setpoints is necessary unless an increase is desired.
PWR CAIZ Code source terms (Table 3.1-2) may be used if 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 i
to the new value.
l i 3.1.1 Effluent Monitors The following method applies when determining the isolation or
- high alarm setpoint for the monitors listed Table 3.1-1.
l l
i 3-1 Rev. 2
3.1.1.1 Determine the " mix" (noble gas radionuclides and compo-sition) of the gaseous effluent.
- a. Determine the gaseous source terms that are representa-tive of the gaseous effluent. Gaseous source terms are l the total curies of each noble gas released during the previous month or a representative analysis of the gas-eous effluent. Table 3.1-2 source terms may be used if the releases for the previous month were below the lower limits of detection (LLD).
- b. Determine Si (the fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionu-clide "i") for each individual noble gas radionuclide in the gaseous effluent.
Si = Ai
)[^i (3.1-1) i Ai = The radicactivity of noble gas radionuclide "i" in the gaseous effluent from Table 3.1-2.
3.1.1.2 Determine Qt (the maximum acceptable total release rate
! of all noble gas radionuclides in the gaseous effluent (gCi/sec))
l based upon the whole body exposure limit.
500 gD ,
(X/Q) }{ K Sii (3.1-2) i i
l t
(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/m )3 from the "X/Q" column in Table 3.1-1.
I l
i 3-2 Rev. 1
Ki = The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem /
year /pCi/m3 ) from Table 3.1-3.
3.1.1.3 Determine Qt based upon the skin exposure limit.
3000 Qt"
(%/Q) )[ (Li + 1.1 Mi ) Si (3.1-3) i Li + 1.1 Mi = The total skin dose factor due to emissions from noble gas radionuclide "i" (mrem /ycar/
pCi/m 3 ) from Table 3.1-3.
3.1.1.4 Determine Ct (the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the. gaseous efflu-ent (pCi/cc)).
.1 E-3 Ot Ct" F
( 3 .1- 4 )
NOTE: Use the lower of the Qt values obtained in Sec-tions 3.1.1.2 and 3.1.1.3.-
F = The maximum effluent flow rate at the point i 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.
l l
l , 3.1.1.5 Determine C.R. (the calculated monitor count rate above i-I background attributed to the noble gas radionuclides (nepm)).
C.R. is obtained by using the applicable Effluent'~ Monitor Effic-iency Curve located in the Radiation Monitor Calibration file.
3-3 Rev. 1 1
C.R. is the count rate point that corresponds to the total radio-activity concentration (Ct )- .
3.1.1.6 Determine HSP (the monitor high alarm setpoint above background (nepm)).
HSP = Tm C.R. (3.1-5)
Tm = Fraction of the total radioactivity from the site that may be released via each release point to en-sure 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 !
(ncpm) for the monitors should be set at or below the HSP values.
3.1.2 Air Eiector Monitors Radiation monitors 1R-15 and 2R-15 provide an indication of gross noble gas activity at the main condenser air ejector of Unit I and Unit 2, ,
respectively. These monitors are provided to 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 releases are monitored by the auxiliary building vent monitoring system.
s 3-4 Rev. 2 .
TABLE 3.1-1 MONITOR ALARM SETPOINT DETERMINATION FOR PNGP SOURCE SOURCE EF FI,UENT PELEASE RELEASE Or TERR!S (Al) 3 Ft.0V PATE If0NITOR FRACTION rolf!T RElIASE (TABLE 3.1-2) X/Q(sec/m )
IR-30 (F) (cfm) (Tn) and Aux. Ridg. Auz. Ridg. -
2 IR-37 Vent - Unit I _ Unit i Exhaunt Aux. Bldg. 3.38E-5 2.9E+4 0.2 Air Ejector Air Ejector 3.38E-5 Unit i 2.9E+4 2R-30 Aux. Rida. Aux. nidg. -
Vent - Unit 2 Unit 2 Frhaust Auw. nide. 3.30E-5 4.IEe4 3
2R-37 Cas Decay Tanks Xc-133 (1007.) 1.32E-4 4.lE+4 Air Ejector Air Ejector 3.3RE-3 y y Unit 2 h IR-12 Shield illdg. Cont. - Unita l&2 Shield Hldg. 1.320-4 3.20*4 0. 3 and Vent - Unit I rurge, Unit I (Note 2)
IR-22 Inservice rurge 21:-1 2 Shield Didg. Cont. - l'ntt 2 Shield fttdg. 1.32E-4 4.6E+3 0. 3 and Vent - Unit 2 Inservice rurge 2R-22 R-35 Radwaste Radwaste Bldg. Aux. Bldg. 3.38E-5 6.11:+ 3 0.1 Bldg. Vent Exhangt R-25 Spent Fuct Spent Fuel rool Aux. Ridg. 3.380-5 1.HE+4 U.1 and inol Air Exhaunt R-31 Air Vent fl0 TEST
- 1. Values listed for Tm are nominst values only. They may be adjusted an necennary to allow a rennonnble margin to the monitor setpoint. Duplicate values of Tm are assigned to both Shield Building vente etnce nnly one containnent will be purged at any one tine. The aantgned Tm values of all active relenee points shall nnt he greater than unity.
- 2. Ehen purging the Unit I containment via the inservice purge system, the monitor setpoints may be based on 4.6Et3 cfm for the duratinn of the release. .
pcf se n
i TABLE 3.1-2 CASEOUS SOURCE TERMS AUX. BLDG. SHIELD BLDC. AIR EJECTOR RADIONUCLIDE (A1 ) (Ci/Yr) (A ) (Ci/Yr) 1 (4) (Ci/Yr)
Kr-85m 3E0 -
2E0 l Kr-85 2E0 2.2E1 -
Kr-87 1E0 - _
Kr-88 SEO LEO 3go ;
Xe-131m 2E0 2.lEl IE0 Xe-133m SE0 2E1 3E0 $
Xe-133 3.7E2 2.7E3 2.3E2 !
Xe-135 8EO 6E0 SE0 Xe-138 IE0 - _
Total 3.97E2 2.77E3 2.44E2 I i
i
" " indicates that the release is less than 1 Ci/yr..
[
1 i
t P
l 3-6 Rev. 1;
IABLE 3.1-3 DOSE FACTORS AND CONSTANTS SKIN TOTAL WHOLE BODY DOSE FACTOR DOSE FACTOR RADIONUCLIDE 3
(Kg) (mrem /yr/pCi/m )
(Li + l lMi ) 3 (mrem /yr/uCi/m )
Kr-83m 7.56E-2 2.12El Kr-85m 1.17E3 2.81E3 Kr-85 1.61El 1.36E3 Kr-87 5.92E3 1.65E4 Kr-88 1.47E4 1.91E4 Kr-69 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4 Xe-131m 9.15El 6.48E2 Xe-133e 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 Ar-41 8.84E3 1 29E4 O
8 9
i 3-7 'Rev. 1
3.2 Gaseous Effluent Dose Rate - Compliance with 10 CFR 20 Dose rates resulting from the release of noble gases, and and radiciodines 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 Cases 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 set point determinations discussed in the previous section are based on the dose calculational method presented in NUREG-0133.(2) They represent a backward t 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 calc 61ations 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 Radiciodine, Radioactive Particulates, and Other Radionuclides The dose rate at the site boundary resulting from the release of radioiodines and t
particulates with half lives greater than 8 days is limited by 10 CFR 20 to 1500 I
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 re-leases. The calculations will be based on the results of sample analyses obtained pursuant to the PNGP Technical Specifications. To show compliance, Equation 3.2-1 will be evaluated.for I-131, tritium, and radioactive particulates with half-lives greater than eight days.
l y, Pg ( Y/Q ) < 1500 mrem /yr (3.2-1) i -
V.
3-8 Rev. 2 l
whzra P = infant critical organ dose parameter for radionuclide 3 ,
I i for the inhalation pathway, mrem /yr per pCi/m (Table 3.2-1);
(XQ)y =
annual average relative concentration for long-term release at the critical location, sec/m3 (Appendix A, Table A-4);
(D/Q), =
annual average relative deposition for long-term re-lease at the critical location,1/m2 (Appendix A, Table A-5);
Q;y =
the total release rate of radionuclide i from all vents from both units for the batch or week of interest, pCi/sec; Radiciodines, tritium, and radioactive particulates.will be released from up to six individual vents all within 300 feet of each other. For show- -
ing compliance with 10 CFR 20, calculations based on Equation 3.2-1 will be made once per week. The source terms (Qty) will be determined from the results of analysis of vent particulate filters and charcoal canisters and vent flow rate. These source terms include all gaseous releases
- from PNGP.
l 1
1 1
3-9 Rev. 2
l Significant short-term batch releases of long-lived radioactive particulates and tritium will result from containment purges. Calculations will be made for these releases separately to further assure compliance with 10 CFR Part 20 prior to release. These calculations will be used only to determine whether or not the purge release will be allowed to occur. Source terms will be determine 1 from the results of isotopic analyses of samples from containment prior to release. Equation 3.2.1 will be used in conjunction with the following relationship to demonstrate that the batch release does not exceed the dose rate limit:
BL = 1500 - (Dy - Dp) (3.2 2) where BL = limiting dose rate for the batch, mrem /yr; Dy = previous week's doses from all vent releases, mrem /yr; Dp = previous week's doses from all purge releases mrem /yr.
3.2.3 Critical Receptor Identification The atmospheric dispersion parameters given in Appendix A will be used to identify the critical receptor. Compliance with Part 20 will always be shown at the site -
boundary location with the highest X/Q. As discussed previously, weekly and batch dose calculations will be performed at this location. The critical site boundary l location, based upon long term ground level releases %/Q (Table A-3), is 0.36 miles
! in the WNW sector.
t 3-10 Rev. 2
k TABLE 3.2-1 Pg7 VALUES FOR AN INFANT FOR THE PNG?
l Isotope StI '
mrem /vr uCi/n3 ,
H-3 6.47(2)
P-32 2.03(6)
Cr-51 3.57(2)
Mn-54 2.53(4)
Fe-59 2.35(4) "
Co-53 1.11(4)
Rb-86 1.90(5)
Sr-89 3.97(5)
Sr-90 4.09(7) __
Y-91 7.00(4) -
I Zr-95 2.17(4)
No-95 1.30(4)
Ru-103 1.60(4)
Ru-106 1.60(5)
Ag-110m 3.30(4)
Te- 127m 3.80(4)
Te-129m 3.20(4) .
Cs-134 7.02(3) '
Cs-136 1.35(5)
Cs-137 6.12(5)'
Ba-140 5.59(4) :
Ce-141 2.15(4) -
Ce-144 1.50(5) 1-131 1.48(7) e 3-11 ' Rev. 2
3.3 Gaseous Effluents - Compliance with 1,0 CFR 50 Doses resulting from the release of noble gases, and radiciodines and particulates must be calculated to show compliance with Appendix I of 10 CFR 50. The cal-culations 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 ef-fluents 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 M; (X/Q)y Qjy + ( X/q)yqiy
< 10 mrad for any calendar quarter
< 20 mrad for any caltpndar year (3.3-1)
For beta radiation:
3.17 x 10'8 N; ( X/Q) yQ;y +
( X/q)yggy
< 20 mrad for any calendar quarter
< 40 mrad for any calendar year (3.3-2) 3-12
where:
M; = The air dose factor due to gamma emission for each identified noble gas radionuclide i, mrad /yr per gCi /m3 ;
(Table 3.3-1)
Ng =
the air dose factor due to beta emissions for each iden-tified noble gas radionuclide i, mrad /yr per pCi/m3; (Table 3.3-1)
( X/Q)y = the annual average relative concentration 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/m3 (Appendix A, Table A-7);
f q;y = 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; Qjy = 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 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 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 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.
3-13 ~Rev. 2
-,-%..r , - - - - - , - . , -, - ,- --,
3.3.1.2 Cumulation of Doses ,
i Doses calculated monthly will be summed for comparison with quarterly and annual ;
e limits. The monthly results will be added to the doses cumulated from the other j months in the quarter of interest and 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 be submitted.
t 3.3.2 Raidioidine. Particulates. and Other Radionuclides ;
3.3.2.1 Dose Ecuations The worse case dose to an individual from I-131, tritium, and radioactive 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 or year-
-8 3.17 x 10 7., T., R ijak I9v 1v + "v9 1v j i j
< 15 mrem (per quarter)
< 30 mrem (per calendar year)
(3.3-3) ;
where:
Q iy = release of radionuclide i for long-term vent releases from both units (greater than 500 hrs /yr), pCi; I
l q;y = release of radionuclide i for short term purge releases from l both units (equal to or less than 500 hrs /yr); pCi; i t
l 3-14 Rev. 2 ;
Wy = the dispersion paramct:r fer cstimsting the d2se to an Individual at the controlling location for long-term vent releases (greater than 500 hrs /yr);
W = the dispersion parameter for estimating the dose to y
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;p
= the dose factor for each identified radionuclide 1, 2
pathway j, age group a, and organ k, m mrem /yr per nCi/see or mrem /yr per pCi/m3 . !
The above equation will be applied to each combination of age group and organ.
Values of R ijak have been calculated using the methodology given 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 which will have one .
or more of the following: residence, vegetable garden,-most animal,and milk animal. The selection of the actual receptor is discussed La Section 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 values are in terms of %/Q(sec/m3) for the inhalation pathways and for tritium (Tables A-4 and A-5) and in terms of D/Q(1/m2) 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 repe.-t will be ,
submitted in accordance with the PNGP Technical Specifications. If twi{c theRe limits are exceeded, a special report showing compliance with 40 CFR 193 will be '
submitted. '
~
l l 1,
3-15 L [Rav. 2 , M
, , 7-c > .
___ _ _ _ . _. - _a _ _ - - - - - -
3.3.3 Projection of Doses 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-131, 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 equioment is required if not currently in use. '
3.3.4 Critical Receotor Identification e
The critical receptors for compliance with 10 CFR 50, Appendix I will be iden-tified. For the noble gas specification the critical location will be based on the beta and gamma air doses 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, Table A-3. This location will remain the same unless meteorological data is reevaluated or the site boundary changes.
The critical location for the I-131, tritium, and long-lived particulate pathway will be selected once each year. The selection vill follow the annual land use census perfomed within 5 miles of the PNGP. Each of the following locations will be evaluated as potential critcal 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 Equatm., t. a for all new identified receptors and those receptors whose characteristics have changed significantly. The calculation will include appropriate information about each
~
b
..i 8
i
,, ,, 3-16 Rev. 2
.e
receptor location. The dispersion parameters given in this manual should be employed. The total releases reported for the previous calendar year should be used as the source terms.
I 1
1 t
l 1 3-17 1
REFERENCES (1) "NSP - Prairie Island Nuclear Generating Plant, Appendix ! Analysis - Supplement No.1 - Docket No. 50-282 and 50-306", Table 2.1-4.
3-18 gey, 1
TABLE 3.3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- Total Body Gamma Air Beta Air Dose Factor Skin Dose factor Dose Factor Dose Factor K L M N Radionuclide (mrem /yrI per pC1/m3) (mrem /yr pdr pC1/m3 ) (mrad /yrI per pC1/m3 ) (mrad /hrperpCf/m) 3 Kr-83m 7. 56E- OL* * ---
1.93E+01 2.88E+02 Kr-85m 1.17EiO3 1.46E+03 1.23E*03 1.97 E+ 03 Kr-85 1.61EiOI 1.34E*03 1.72E401 1.95E+03 Kr-87 5.92E103 9.73E+03 6.17E403 1.03E+04 Kr-88 1.47Et04 2.37E+03 1.52Et04 2.93E+03 o Kr-89 1.6CEiO4 1.01E+04 1.73E+04 1.06E*04 f; Kr-90 1.56Et04 7.29Et03 1.63E+04 7.83E+03 Xe-131m 9.15E *01 4.76E+02 1.56E+02 1.11E+03 Xe-131n 2.51E402 9.94E+02 3.27E402 1.48E+03 Xe-133 2.94E402 3.06E+02 3.53E+02 1.05E*03 Xe-135m 3.12E t 03 7.11Et02 3.36E*03 7.39E+02 Xe-135 1.81E403 1.86E+03 1.92E+03 2.46E403 Xe-137 1.42Et03 1.22E+04 1.51E+03 1.27E+04 Xe-138 .8.83E403 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- The listed dose factors are for radionuclides that may be detected in gascous effluents. All others are 0.
- 7.56E-02 = 7.56 x 10 2,
, - - , . . - - - + - - -
TAHLE 3.3-2 Il VALUES FOR TifE PRAIRIE ISLAllD NUCLEAll GEllEllATitlG PLAtlT*
PATil.1AY a GilOUtl0 fl0CLIDE T.00DY 01-THACT B0HE LIVER KIDt!EY TilVROID
_-______-s___---____+__________+-_-_--____s---_______q__________+__-_-_-___+______lG LUl SKiti
+____--_-__+
Hil 54 1 1.34E 09 I 1.34E 09 s 1.34E 09 I 1.34E 09 1.34E 09 1.34E 09
_----__-_p-____--___g_________-+-------__-s___---____q__________s_____ 1.34E 09 i 1.57E 09
__+_____--_-_y-____----_+
FE 59 1 2,75E 08 4 2,75E 08 a 2,75E 08 I 2.75E 08 I 2.75E 08 1 2.75E 08 1 2. 75E 08 1 3.23E 08 i
______---s_______-__+_-_---___-+__-______-+---____--_+__-_---___+_----__-__+___-__-___t___-___---+
CO 58 i 3.79E 08 I 3.79E 08 i 3.79E 08 i 3.79E 08 i 3.79E 08 i 3.79E 08 I 3.79E 08 8 4.44E 08 :
_--__--_-g_--____-__y______,__-g_-________+___--_---_s--________g_----_____+_---_=_
CO 60 +-______-__s a 2.15E 10 1 2,15E 10 t 2,15E 10 1 2.156 to i 2.ISE 10 1 2.15E 10 s 2.15E 10 s 2
_________,___--___-_,____-____-t-___--_-__,-____--___,_______-__,_________-,________-_q-__.52E10 ____--_,
SR 89 I 2.23E 04 I 2.23E 04 1 2.23E 04 i 2.23E 0 3 2,23E 04 8 2.23E 04 1 2.23E 04 s 2.58E 04
__--____-t______--__,--___--___,___--____-,_________4 -#_____-____q--_____-__+______-___+__--_-_--_+
I 131 1.72E 07 I 1,72E 07 1,72E 07 I 1.72E 07 I 1.72E 07 1.72E 07 8 1.72E 07 s 2.09E 07 1
--____-__t--_______-g_---_--_-_g_____--___,____-_--_-#__---____-#_________-#-________-,-_________,
CSl34 i 6.82E 09 i 6.82E 09 I 6.82E 09 3 6.82E 09 s 6.82E 09 i 6.82E 09 3 6.82E 09 7.96E 09
---____-t___-~_---_,________.-t_____-__-_+__-------t----------+----------+----------+-----
4 o
CSi37 i 1.03E 10 I l.03E 10 1.03E 10 i 1.03E 10 g 1.03E 10 i 1.03E 10 i 1.03E 10 1.20E 10 t
.________t----_---_-+__-_----__,___-______t--__-_-___+__________+___-______+---_--____,_________-+
all 2VALUES Ill UtilTS OF MllEH/YR PER pCI/M FOR lilllALATION AND TRITIUM, Al10 IN UtlITS OF M -MNEH/Yll PEli pCI/SEC FOR ALL OTifERS n
n
TABl.E 3.3-3 11 VALUES FOR Tile PR AlHIE ISLAtID fluCLEAR GEllERATING PLAtlT*
PATildAY = VEGET AGE GROUP EQUALS ADULT t10CLIDE T.00DY 01-TRACT 80ffE LIVER KIDNEY TilYRu LUNG SKIN
---______+____-_--_-+-_-------+-_---_---+_----_-__+-____---_+-_--_.tD __+--________+--__ -----+
11 3 s 2.28E 03 6 2.28E 03 g 0.00E-01 e 2.28E 03 I 2.28E 03 1 2.28E 03 2.28E 03 e 2.28E 03
_+____--_-_-+-_---_-___+----__-___s- -----_-_t-____----_+__- . _-__+_--______- ______--__,
MN S4 I 5,83E 07 I 9,36E 08 0.00E-01 1 3.0SE 08 I 9.09E 07 1 0.00E-01 0.00E-01 0.00E-01 s
+___---____t----------+-----__--_t----------4-------__-+----------+----------+----------+
FE S9 1.12E 08 I 9.75E 08 g 1.24E 08 g 2,93E Oa I 0.00E-01 s 0.00E-Ol' 3.17E 07 0.00E-01
+----------t----------+----------+----------*----------+----------+----------+----------+
CO 58 I 6.7lE 07 6,07E 0'8 I 0.00E-01 1 2.99E 07 1 0.00E-Ol I 0.00E-01 1 0.00E-01 0.00E-01
t----------t----------+----------t----------t----------+----------+----------+----------&
CO 60 I 3.67E 08 i 3,12E 09 I 0.00E-01 1 1.66E 08 3 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01
-_--___-_p----------+--____----+__--_____-+_--------_+------_ +___---___-+-----_____+__--_--___+
SH 09 2.87E 08 I 1,60E 09 I l.00E lo 1 0,00E-01 1 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :
__----_-_+ .
t_______---+----------t----------t----------t----------+ ---------+----------t w SR 90 1.64E il i 1.93E 10 t 6.70E 11 : 0.00E-01 1 0. 00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 4 ____--_-_e______----+____------+-----_____t-__-__---_+___-____--+_--_ -,___ -_-___+_-_---__-_,
- I 131 I 6,61E 07 8 3.04E 07 8.07E 07 I l.lSE 08 s 1.98E 08 3.78E 10 0.00E-01 0.00E-01
t----------t----------t----------t----------t----------t----------t----------+----------+
CSl34 I 8.83E 09 s 1,89E 08 4.54E 09 1.08E 10 s 3.49E 09 0.00E-01 1 1.idE 09 0.00E-01 :
______--_,--_---_-__+-----_____,-__----___,--__--____+_--_______+____-__---+-_-_______+--_--_-__-+
CSl31 : 5.94E 09 1.76E 08 s 6.63E 09 I 9.07E 09 3.08E 09 1 0.00E-01 : 1.02E 09 0.00E-01 :
_________+_-__-- .t___---_-__+-___----_-+-------_--+----_--__-+--________+____--____,-----____-+
3
- R2VALUES IN UllITS OF MREll/YR PER pCI/M FOR IHilALATinti AND TRITIUM, AND Ill UllITS OF M -MREM /YR PER pCl/SEC FOR ALL UTilERS m
o 4
TABLE 3.3-4 R VALUES FOR Tile PRAIRIE ISLAt10 fluCLEAR GEllERATillG PLAtlT*
PATilrlAY = VEGET AGE OROUP EQUALS TEEll fl0CLIDE T,00DY 01-TRACT ButlE LIVER KIDilEY TifYHOID LUtlG Skill
+- -----+---------+--------+----------+---------+---------+---------+---------+
11 3 I 2.6lE 03 s 2,61E 03 3 0.00E-01 1 2.6lE 03 a 2.6lE 03 I 2.6lE 03 1 2.6lE 03 s 2.61E 03 s t-----+--------+-------+-------+---------+--------+---------+----------+
Mtl 54 79E 07 ; 9.09E Ou I 0.00E-01 1 4.43E 08 s+ -1.32E
. ------ ,I 8.---...-.--t------------t------------t---------- 08 0.00E-01 s 0.00E-01 0.00E-01 i
+------------+-----------+------------+
FE 59 1,60E 08 i 9,78E 08 1.77E 08 I 4,14E 08 0.00E-01 s 0.00E-Ol's 1.30E 08 0.00E-01 s
+------t----------t-------------*-----------+-----------+------------+------------*----------+
C0 Sd I 9,79E 07 : S.8SE 08 3 0.00E-01 s 4.2SE 07 s 0.00E-01 0.00E-01 s 0.00E-01 0.00E-01 s
.---.t-------t------------t-------------t----- = - - - * - - - - - - - - - - - - - + - - - - - - - - - - - + - - - - - - - - - - - - - - + - - - - - - - - - - - - - - +
CO 60 l S.57E 08 I 3.22E 09 s 0.00E-01 I 2.47E 08 0.00E-01 0 0 0 E -0 1 0.00E-01 1 0.00E-01
-- t -- . . --- + - --- - + -- - -- + - --- ---- - + - -- - - q -----
_4- ----- --+------- - +
SR 89 I 4.36E 08 1 1,81E 09 1.52E 10 1 0,00E-01 s 0.00E-01 1 0,00E-01 : 0.00E-01 0.00E-01 s
-.---+---_--g--_+---------+---.-#------+------+-----+--------a Y SR 90 l 2.0SE ll 1 2,33E 10 i 8.32E ll I 0,00E-01 0.00E-01 s 0.00E-01 0.00E-Ol : 0.00E-01 y -------t----.-+------t-------------*----------*------------+----------t-------------+-----------+
1 131 i S.77E 07 I 2.13E 07. 7.68E 07 I l.07E 08 8 1.USE 08 I 3.I4E IO i 0.00E-01 0.00E-01 1
+----------+----------+----------+----------+---------+----------+----------+----------g CSl34 s 7,S4E 09 s 2.02E 08 s 6.90E 09 1,62E 10 s 5.16E 09 0.00E-01 1.97E 09 0.00 CSl37 t----------+----------+----------t----------+----------+----------+*---------+---=E-01 3 4.90E 09 s 2,00E 08
-+
1.06E 10 s 1.41 E 10 4.78E 09 s 0.00E-01 1.86E 09 0.00E-01
+----------+----------+----------+----------+------- +----------g----------+----------+
3
- R 2VALUES Ill Uti!TS OF MREM /YR PER pCI/M FOR IllilALATION AtlD TRITIUM, AtlD iti utilts OF M -MREWYR PEll pCI/SEC FOR ALL OTHERS w
o 4
l
TAllLE 3.3-5 ll VALUES Foli Tile PR AIRIE ISL AtlD tlUCLEAll GEllEll ATI tiG PL AtlT*
PATilWAY = VE0ET AGE OROUP EQUALS Cil!LD tl0CL 10E T.80DY OI-TRACT. DollE LIVER KlotlEY TilYllo t D LUtlG SK itt
+----------g----------+-__ _ _ _ _
g----------+------- +----------+----------+----------+
11 3
___----__,1 4.04E 03 1 4.04E 03 s 0.00E-01 1 4.04E 03 8 4.04E 03 s 4.04E 03 3 4.04E 03 3 4.04E 03 :
-_+
_-+-------_--+-----_--_-#----------#-----_-_-_+--__--____+-_----_---+_----
Mil 54 1.73E 08 i S.44E 08 I 0.00E-01 s 6.49E 08 1.82E 08 : 0.00E-01 0.00E-01 0.00E-01
--- _. -g------ -g----------+--------_+------____,--__ _---+----------+-_--------+---_------+
FE 59 3.17E 08 I 6.62E 08 1 3.93E 08 I 6.36E 08 I 0.00E-01 0.00E-01's 1.84E 08 1 0.00E-01 1
,------_--_t--------_-+-_------_-+----_-_-__,-_--_----_+____----__,-_--------,--_----_--+
C0 58 I 1.92E 08 3.66E 08 1 0.00E-01 : 6.27E 07 s 0.00E-01 s 0.00E-01 0.00E-0I 0.00E-01
a_---------g-_---_----+---- ---g----------+----------g----------r----__----+----------+
CO 60 1 1.IIE 09 s 2,08E 09 I 0,00E-01 s 3.76E 08 I 0.00E-01 0.00E-01 I 0.00E-01 0.00E-01 :
.---_--__-+_-----_---+-__--__---,_-----_---+---_-_-__-t--------_-+------_-__,---------_+--_-------+
SR 89 I I.03E 09 I 1.40E 09 I 3.62E 10 1 0.00E-01 1 0.00E-01 0.00E-01 0.00E-01 0.00E-01
.----_---g----------g----------+----------+----------+----------+----------s---------_s----------+
w 611 90
_--,I 3.49E 11 I 1.86E 10 1 1.38E 12 1 0.00E-01 1 0.00E-DI i 0.00E-01 s 0.00E-01 : 0.00E-01 I g ----------o------ -s----------+-_--------,----------,-----_----,----------,--_-------+ l w I 13I 8.16E 07 I l.28E 07 I l.43E 08 1.44E 08 I 2.36E 08 s 4. /SE 10 1 0.00E-01 0.00E-01
_-----_--g----------g----------,----------,----------r----------&----------*----------+---------*
CSl34 I S.40E 09 I l.38E~00 I 1.56E 10 1 2.56E 10 s 7.93E 09 : 0.00E-01 : 2.84E 09 0.00E-01
_----_---r----------+----_-----+---------t----------+----------+----------+----------+----------* 2.00E 09 0.00E-01 CSl31 8 3.52E 09 I 1.50E 08 s 2.49E 10 1 2.39E 10 7.78E 09 0.00E-01
_--------,----------t----------+----------+----------+----------+----------+----------+----------+
- ll 2VALUES Ill utilTS OF MllEM/YR PEll pCl/M FOR ltillALATinti Atl0 TRITIUM, AtlD iti Uti!TS OF M -HilEM/YR I Ell pel/SEC Fall ALL OTilElls l
l W
u o j 1
o .
i l
l 9
TABLE 3,3-6 11 VALUES FOR Tile PRAIRIE ISLAt1D fluCLEAR GEtiERATitlG PLATE
- PATildAY = MEAT AGE OROUP EQUALS ADULT tluCLIDE T.Il0DY OI-THACT 80f1E LIVER KloilEY TilYROID LUllo SK ill
__-------+--__------g-__------_t_---------+---_------+----------+-------_-_t-----__---+---_----_-+
11 3 3 3.27E 02 3 3.27E 02 0.00E-01 3 3,27E 02 8 3.27E 02 s 3.27E 02 3 3.27E 02 e 3.27E 02 8
t----------+----------+----------t----------+----------+----------+----------+----------+
l.lti 5 4 i 8.98E 05 1.44E 07 3 0.00E-01 s 4.7lE 06 s 1.40E 06 s 0.00E-01 1 0.00E-01 1 0.00E-01 s
--_------+------__--+----------+_--_-----_+-------__-+_---------+--------_-s----------+_---------+ ,
FE 59 1.12E 08 9.73E 08 s 1.242 08 s 2.92E 08 s 0.00E-01 0.00E-Ol's 8.16E 07 0.00E-01 '
_---+--__---:-+___--__-__+_---_--_--4____-_--__+------_-__4_---_--_-_,----_--_-_,_--_____--+
CO 58 I 1.95E 07 I 1.76E 08 *: 0,00E-01 I 8.68E 06 8 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01
t----------t----------+----------t----------+----------+----------+----------+---- ---+
CO 60 s 8.87E 07 I 7.SSE 08 3 0.00E-01 s 4.02E 07 1 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01
--_------g-_---_--__+-------_-_,_----_--_-+--_-------+-_-____---+----------+-----_---_+___-------+
SR 89 : 4.12E 06 s 2.30E 07 s 1.43E 08 I 0.00E-01 0.00E-01 : 0.00E-01 1 0. 00E-01 1 0.00E-01 s
+--_-_--_--+------__--+_---__--_-+--_-------+_---------+----------,--_------,----------+
w Sil 90 I l.76E 09 3 2.07E 08 s 7.17E 09 : 0.00E-01 0.00E-01 0.00E-01 1 0.00E-01 : 0.00E-01 4
__-,--____-_-_+-___---__-,_--_-_____#-_-------_+____------+_--____---+--___--__-+---_-__-__,
I 131 s 4.33E 06 1.99E 06 5.28E 06 3 7,5SE 06 s 1.29E 07 8 2.48E 09 0.00E-01 : 0.00E-01
-_---__--+--------_-t-----_--_-+-__--____,+----__--__+-_---_----+------_--_+---_---_-_+----______, y CSl34 s 6.68E 08 1 1.43E 07 1 3.43E 08 I 8.17E 08 s 2.64E 08 0.00E-01 i fl.78E 07 0.00E-01 s
_----s------__--+------_--_+---_----__+-------_--+------_-_-+____----_-+-__------+-----_---_+ '
CS131 s 4.33E 08 s 1.28E 07 4.83E 08 I 6.61E 08 s 2.24E 08 0.00E-01 7.46E 07 0.00E-01
,-_-__-----+__________+------___-+-__-----__+___--___--+_______---+-_--__---_+--.--_--__,
- R 2VALUES Itf WillTS OF MREM /YR PER pCI/M FOR !!illAL ATIOil Atl0 TRITIUM, AtlD Ill UtlITS OF I4 -MREluYR PER pCl/SEC FOR ALL OTilERS w
n 4
e
TABLE 3.3-1 R VAltlES FOR Tile PRAIRIE ISLAllD fluCLEAR OEllERATitlG PLAllT*
PATilriAY = MEAT AGE OROUP EQUAI.S TEEll tillCl. l DE T.IluDY GI-TRACT 00 tie LIVER KI DilEY TilYROID LUtlG ski rl
_________,_-________,_--_______t_____-____t-----_____+--_-______+______-___+__________+--_____-__e 11 3 I l.95E 02 i 1.95E 02 i 0.00E-01 1.95E 02 I 1.95E 02 a 1.95E 02 1.95E 02 s 1.9SE 02 :
__---____4-- _______a_____-____,__ -__ ___,----____ _#-__-_____+-_________+-________-;__________,
Mil S 4 I.7.I2E 05 7.3/E 06 i 0,00E-01 1 3.59E 06 I.0/E 06 1 0.00E-01 1 0.00E-01 1 0.00E-01
_______ -4_____ ____e__________e__________t _________+ -_____ _-t__________,______-__-,__ ___----+
FE S9 I 8.95E 01 i S.48E 08 i 9.93E 07 I 2,32E 08 8 0.00E-01 1 0.00E 7.3lE 07 0.00E-01
_________t__________,__________t__________,__________+__________,__________+-_________+__________,
C0 58 I l.54E 07 I 9,22E 07 I 0.00E-01 I 6.69E 06 1 0.00E-01 0.00E-01 0.00E-01 0.006-01 s
t----------t----------f----------t----------d----------F----------+----------+----------+
CO 60 7,03E 07 I 4,06E 08 i 0.00E-01. I 3.12E 07 I 0.00E-01 1 0.00E-01 1 0.00E-01 0.00E-Oi i
________ t--____---_+_--_______t---_______+__________+ __ -___ _+________ _+__________+-_________,
Sil 09 i 3.47E 06 1 1,44E 07 s 1.2iE 08 8 0.00E-01 a 0.00E-01 1 0.00E-01 0.00E-01 0.00E-01 :
__--_____t--________t-_________t_-__-_____t__________+______- _+___..-_____+__________+__________+
w SR 90 I l. lSE 09 l 1,30E 08 I 4.64E 09 t 0.00E-01 1 0.00E-01 0.00E-01 1 0.00E-01 : 0.00E-01 s y ---__-_t____-___+-_-___-___t____-____-t__---_____+---____-__+__---_____,..-_--_____s__________+
u i 131 1 3.30E 06 I l .22E 06 i 4.39E 06 1 6.14E 06 1 1.06E 07 1.79E 09 i 0.00E-01 0.00E-Ol :
---_____-+--________t__________t-_-_______+-_________t__________+__________+__________+__________,
CSl34 i 2.98E 08 1 7.99E 06 s 2.73E Oa i 6.42E 08 s 2.04E 08 0.00E-01 1 7.79E 07 s 0.00E-01
______-__t__________t-_-_______+__________#_____--___,__--______,__________+-________-,-______-__;
CSl31 I l.06E 08 i 7.59E 06 i 4. ole 03 i S.34E 08 8 1.82E 08 0.00E-01 7.06E 07 0.00E-01
_________t__--______+-______---+__________e__________#_______ +__________,__________+.--_______+
3
- R 2VALUES Itl UtiiTS OF MREM /YR PEll pCl/M FOR lilllALATicil Arld. TRITIUM, AllD Ill UlllTS OF M -NilEM/YR PER pCl/SEC FOR Al.L OTilERS
- o n
4
TABLE 3.3-d il VALuliS Full file Pila llllE ISLAt19 lidCLE All OEifEllATIrJo PL ArlT*
PATilrtAY = MEAT AGE Gil00P EQUALS ClllLu fluCLIDE T,00DY GI-Til AC T Hor 4E LIVEll K IDtlEY TiltitoID LUtio SK ill
t----------t----------t----------t----------t----------+----------*----------+----------+
11 3 8 2.36E 02 1 2.36E 02 s 0.00E-05 s 2.36E 02 1 2.36E 02 ; 2.36E 02 s 2.3aE 02 2.36E 02 s
--_-__---g-------_--p-_--------p----___---g----------+---------+--___-----+-----_,--+---_--_---+
Mil 5 4 s 1.0VE 06 3.4SE 06 1 0.00E-01 1 4. l l E 06 1. lS E 06 s 0.00E-01 0.00E-01 0.00E-01
-t----------t----------t----------+----------+----------t----------+----------+----------+
FE 59 I l.42E 08 I 2.9/E 00 I 1.76E Od i 2.8SE 00 1 0.00E-01 s 0.00E-01 8.26E 07 s 0.00E-01 3
,----__----g---_-__-_-t-------_-g-__-------+--------_-+------_---+_---------+-----_----,
C0 Sd i 2.39E 07 4.56E 07 i 0.00E-01 I l.02E 06 s 0.00E-Ol I 0.00E-01 1 0.00E-01 0.00E-01 :
--_------g-----__---g----------q-_--___--+---------_g--_-------g---__-----+----_-----+----------+
CO 60 i 1.09E 00 1 2.0SE 00 1 0.006-01 s 3.70E 07 I 0.00E-01 1 0.00E-01 0.00E-01 0.00E-01
t-------~~-t----------t----------t----------+----------t---------+----------+----------+
Sil 89 I 6.SSE 06 I 6.87E 06 s 2.29E 08 8 0.00E-Of 0.00E-01 s 0.00E-01 I 0.00E-01 0.00E-01 i u, -_------_t_------_--g-__--__---t.__-------g-_--------+------- +---______-+----_-----+----------,
4 o
Sit 90 I.52E 09 i 8.0dE 0/ s 6.00E 09 I 0.00E-01 0.00E-01 I 0.00E-01 0.00E-01 0.00E-01 i
g----__----g--__-----_g__--------g----------g----------g---------+--__--- -+----------+
1 131 s 4.6SE 06 s 1.29E 05 8.14E 06 s 0.19E 06 s 1.34E 07 8.2./IE 09 0.00E-01 : 0.00E-01
+----------,----------+-------_--g----------g----------g---------g----_--_;--------_;
CS134 s 1.67E 08 i 4.26E 06 s 4.81E 08 4 7.90E 00 s 2.4SE 08 0.00E-01 s 8.70E 07 1 0.00E-01
_,----------g------_--s------_---,_---------,---------+.---------+----------+--_-------,
CSl3/ s 1.04E 08 I 4.43E 06 I 1.39E 08 1.01E 08 i 2.30E 08 0.00E-01 e u.2VE 07 0.00E-01 1
+----------,------___-+---------_,_--_____-_+___-------,--------_-,_-__--_-__,-_---_----,
- !! 2VALUES lti Ulli fS OF MilEM/Yll l' Ell pCl/M 3 Foll lilll ALATInff AllD TillTIUM, AllD Ifl OfflTS OF M -MilEM/Yli PEll pel/SEC Full ALL orilElis m
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TABLE 3.3-12 Il VAI.UES Full Tile Pil AllllE ISLAtlD flUCLEAll GEllEllATitlG PLANT
- PATilNAY = COW MILK AGE GilouP EQUALS lilFAfff fluCLIDE T.fl0DY G I-Til ACT DollE LIVEll K IDilEY TilYliotD LUllG SK ill
-- ___ _,_________ e _-_-- _ _t___ _____ +__ -_____+- __--_-----+-_-______ + _____ ___+-_-_______,
11 3 I 2.40E 03 1 2,40E 03 3 0.00E-01 1 2.40E 03 1 2.40E 03 s 2.40E 03 1 2.40E 03 8 2.40E 03 i
___------g-______---g----__--__g-_--______+__________,____ ___
+__________4_________-+-________-+
litt 5 4 i 4.54E 06 I 7.36E 06 3 0.00E-01 3 2.00E 07 1 4.44E 06 0.00E-01 0.00E-01 0.00E-01 :
_--___,_____.t---------i----------+-----------t----------+---------i----------t---------*
FE 59 i 7.21E 07 s 8.74E 07 I 1,0SE 0a 1.83E 08 0.00E-01 0.00E-01 S.4tE 01 0.00E-01 :
_________t______--__+__________+-____-____+--________t------____+__________+_____---__+__________+
CO So i 2.00E 07 s 2.08E 01 0.00E-01 I 1.lSE 07 1 0.00E-08 I 0.00E-01 0.00E-01 0.00E-01 i
_ _ _ _ _ _ , _ _ _ _ _ _ _ -+___ ____+--- .__+_ ______-+______+_-_ ____+----___+_-___---_-+
CO 60 i I.IIE 00 I J.I2E 08 0.00E-01.I 4.71E 07 1 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 i
________ s __ _ _ _,-_________+ -- _ _ p__ -_____+__- ____ _ ,--__ ---+__ ______+__-___-__-+
Sil 89 : 1.70E 08 I 1,22E 08 5.94E 09 s 0.00E-01 1 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01
________-t_-____----,________--t___-_-_-_+__________+__________+_____--_-_+-______-__4__--______+
Sil 90 I.79E 10 s 0,75E 08 7.0IE 10 s 0.00E-01 1 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 y _________+__ --- _e______ . ,_________+__________,_ -_______4_________-+ _________+__________+
81 131 1 6.92E 00 5.62E 07 1.34E 09 8 1.Sr7E 09 5 1.04E 09 s 5.17E ll t 0.00E-01 s 0.00E-01
____ _ #________ t __ _____+_----__ _ +-______ . $_________ 4___-_____-+______ -_-4__________+
CSl34 1 3.59E 09 9.6SE 07 i 1.90E 10 1 3.SSE 10 1 9.14E 09 0.00E-01 1 3.~lSE 09 s 0.00E-01
-___t______ -__e _ - _ e___ -____+____.. --__, ____ __
t_- ---__+ _______. _,__ ____ ,
CSill i 2.37E 09 I l.04E 08 I 2.8SE 10 I 3.34E 10 1 8.96E 09 0.00E-01 1 3.63E 09 0.00E-01
___---___+-_____--__t_________-t__________+__________+__________+______-___+___-______+_________-4 3
All2VALUES Ill VillTS OF MilEM/YR PER pCI/M FOR lilllALATIOrt APID TRITIUM, AND fil UtlI~1S OF M -MilEWYR PEll PCl/SEC Full ALI. OTilERS ,
us 4
.TAllLE 3. 3-13 R VALUES Full Tile PilAIRIE ISLAtID fluCLEAll GEt1 Ell ATitlG PL AllT*
PATilWAY = GOATillLK AGE Gil00P EOUALS ADULT lluCLIDE T.110DY GI-TRACT BollE LIVER K lot 1EY TilYl201D LUtlG SK i ti
+----------;----------g----------+----------+----------+----------+----------+----------+
II 3 : 1.57E 03 I I,57E 03 s 0,00E-01 s 1.57E 03 1.57E 03 1.57E 03 : 1.57E 03 1.57E 03
s----------+----------+----------g----------+------- +----------+----------+----------+
I 9.89E 04 1 1.59E 06
i----------t--_-------,i Mil 5 4 0.00E-01 S.19E 05 1.54E 05 s 0.00E-01 1 0.00E-01 a 0.00E-01 :
-_--------,----------t---_------+----------t----------+----------+
FE 59 i 1.62E 05 I 1.41E 06 I 1.80E OS 4.23E 05 1 0,00E-01 0.00E-01 : 1.18E 05 s 0.00E-01
+----------t----------t----------+--_-------+----------+----------+---_--_---,----------+
CO Sd i 6.03E 05 I.S.46E 06 i 0.00E-01 1 2.69E OS I 0.00E-01 1 0.00E-01 s 0.00E-01 : 0.00E-01
+----------g----------g----------+----------+----------+----------+----------s----------s Co 60 s 2.32E 06 I l.98E 01 1 0.00E-01 : 1.0SE 06 I 0.00E-01 s 0.00E-01 '
0.00E-08 I 0.00E-01 :
t----------t----------t----------+----------t----------+ t----- -
=t----------+
Sil 89 4.13E 07 s 2,31 E 08 I 1.44E 09 : 0.00E-01 : 0.00E-01 1 0.00E-01 : 0.00E-01 I 0.00E-01
g----------t----------y----------g----------+----------s----------+----------+----------+
w Sil 90 1.39E 10 s 1.64E 09 i S.67E 10 s 0.00E-01 : 0,00E-01 : 0.00E-01 : 0.00E-01 I 0.00E-01 :
0---------t----------t-----
--+----------+----------+----------t----------+----------t----------+
I 131 a 1.43E 08 I 6.59E 07 I 1.74E 08 1 2.50E 08 1 4.2HE 08 I 8.10E 10 s 0.00E-01 0.00E-01 :
g----------+----------+----------+----------+----------+----------4----------+----------+
CSi34 I l.72E 10 3.69E 08 8 8.USE 09 1 2.llE 10 i 6.82E 09 I 0.00E-01 1 2.26E 09 0.00E-01 I
s----------+----------+----------+----------+----------s----------+-.--------+----------+
CSl31 1.10E 10 I 3.2SE 08 1.23E 10 s 1.68E 10 S.70E 09 : 0.00E-01 : I.89E 09 0.00E-01 s
,-_----- _,----------+-_--------+----------+_------_--+----------+----------+--------_-+
cil 2VALUES Ill UtilTS OF MREM /Yli PEll pCl/M FOR lilllALAT10fl AtID TRITIUM, AtiD lti utilfS OF M -MilEM/Yll PEll FCl/SEC FOR ALL OTilEllS
(*
4 t
, ,_y .. _ . , , . _ . , _ . . _ . _ . - - . _ _ -
.TAlH.E 3.3-14 11 val.UES FOR Tile PR AllllE ISLAllD tiUCLE AR OEllER ATlHG Pl. ANT
- PATil.1AY = GOATMILK A0E GHOUP EQUALS TEEN 110CLIDE T.110DY 01-TRACT 110tlE LIVER KIDHEY Til LUNO SKIN
__--_--_-s_---------g-----_-__-+------____+_____-____+_---______+-___YROID ______+-_______--+-________-+
11 3 s 2.04E 03 s 2.04E 03 s 0.00E-01 s 2.04E 03 a 2.04E 03 s 2.04E 03 s2
__--_--_-g--_--_----g______-_-_t-_-_-_--__+--______--s__-____---s_-____----+___.04E03 1 2.04E 03
_____--s___---_-__,
MN S4 s 1.71E 05 s 1.77E 06 0.00E-01 1 8.64E 05 a 2.50E 05 0.00E-01 0.00E-01 s 0.00E-01
--_____--,------_---,--_-_-__--,____--_-_-t_-__-__---g____--_-_-,___----__-+--_--_____e_-----_---,
FE 59 s 2.83E 05 1.74E 06 I 3.14E 05 I 7.34E 05 1 0.00E-01 : 0.00E-01 2.3lE OS : 0.00E-01
--______-t____-----_e--_------_+-----_--__,-----____-4_________-+_-_____---+_---------+-______-_-+
C0 58 1.04E 06 6.2SE 06 s 0.00E-01 4.53E 05 0.00E-01 : 0.00E-01 : 0.00E-Oi 0.00E-01
____--_--+_-_-__-__-+--___--___+---_----_-+_-___---__q_--_-___-_t___-----_-+--_--__---+___--__-__s CO 60 4.02E 06 s 2.32E 07 0.00E-01 1.78E 06 0.00E-01 0.00E-01 : 0.00E-01
__--__-__t____------+-----_-_--+-_______--,_______---+________--+ ---___--__+___--___--+___-_-___-, 0.00E-01 :
SR 89 : 7.59E 07 3.16E 08 s 2.6SE 09 : 0.00E-01 s 0.00E-01 s 0.00E-0 : 0.00E-01 0.00E-01
+_-____-_-_t-_--__-_--+-__----_--g_-_----___+-_-_--_--_,_________1 -+--_-----__e_-_--__---+
y SR 90 1.98E 10 1 2.2SE 09 8. ole 10 s 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 s 0.00E-01 s nu _______-_+________-_+----__--_-+__-__-_-__+--_____--_+-__--_-___+:
i 131
__________+-_____-_--,-___--____+
2.38E OB : 8.77E 07 s 3.17E 08 I 4.43E 08 I 7.63E 08 1.29E 11 0.00E-01 : 0.00E-01
--_----__+-______--_#--_-----__+-----_---_+_--__--_--t-_---_-_-_+-______-__-_-___-___-_-______-,
CS134 s 1.6HE 10 : 4.50E 08 1.54E 10 s 3.62E 10 s 1.lSE 10 s 0.00E-01 1 4.39E 09 0.00E-01 s
+----------t----------+----------t----------+----------t_----_----+-_-_---__-+----_-_---+
CSl37 P l.03E 10 4.21E 08 s 2.22E 10 a 2.96E 10
---_--___,----_---__,,-_-____--_+-_________+-__----_-_+---_-_____,_-_-1. ole 10 3 0.00E-01 8 3.91E 09 : 0.00E-01
___--+__-----___,-__- _
3
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u n
t
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TABI.E 3.3-16 Il VALUES Full Tile PilAi!!!E ISLAtlD fluCLEAR GEllER ATitlG PL AllT*
PATilWAY = GOATHILK AGE Gl100P EOUALS IllF Atir flUCLIDE T.00DY GI-TRACT ButlE LIVER K !OtlEY TilYl2010 LUtlG SKiti
-__-_----+_--___--_-,__-_______s-__--___--+-______-_-+_-_--__-_-+___--____-+_________-+-_--___-_-+
11 3 1 4.90E 03 1 4.90E 03 1 0.006-01 I 4.90E 03 1 4.90E 03 1 4.90E 03 I 4.90E 03 4.90E 03
_--____--,___-_-____+_--____-__+----_--___,-_..----
___--____S -t----------t----------t----------t Mil S4 i S.4SE 05 I 8.01E 05 1 0.00E-01 1 2.403 06 i S.33E 05 I 0.00E-01 1 0.00E-0; a 0.00E-01 i
________-e----__--__,__________t-_____---_,_________-,_________-,_-__--____,_-_-___--_,__-_---_-_ ,
FE 59 9. 3 t E 05 i 1.14E 06 I 1.36E 06 6 2.30E 06 1 0.00E-01 I 0.00E-01 I 1.03E 05 0.00E-01
-__-_-___s----__---_,__--______q--_-_-__--p--------__p--________t-_-_--__-_+_-__-__---,____---_-_+
C0 SS I 3.4SE 06 i 3.4SE 06 1 0.00E-01 1 1.38E 06 1 0.00E-01 s 0.00E-01 s 0.00E-01 1 0.00E-01 s
-__--_---t__________p-_-______-t--________,_-____-_-_+_-_-______+________--,-________-4-____-__--+
CO 60 I 1.34E 01 I l.35E 07 I 0.00E-01 i S.6SE 06 i 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01
--_-_---_s_____-_-__+_-_- =-+_-__-__-_-+_---_____-g_---___ -s_-------_-+__---_-_--+-_---____-s Sil 09 I 3.58E 08 s 2.57E 08 1 1.2SE 10 i 0,00E-01 0.00E-01 I 0.00E-01 0.00E-01 1 0.00E-01
_____----,-----__-__,__--__-__-t-__---_---t_-______-_e________--,--___-____+____----__e__-_____--,
y SR 90 I 3.75E 10 I l.04E 09 I l.47E il i 0.00E-01 1 0.00E-01 0.00E-01 s 0.00E-01 1 0.00E-01 I w-------__,----------+----------t----------+----------t----------+----------t----------e----------+
P I 131 i 8.3lE 08.I 6.74E 01 1.60E 09 I l.89E 09 s 2.2tE 09 6.2iE 11 : 0.COE-01 : 0.00E-01
-t_-__---___+-__ --___+--__--__-_+___-__--__+-----____-t__---_____4-___-_____e__--______,
CSl34 1.00E 10 1 2.89E 08 i S.71E 10 i 1.07E ll I 2.74E 10 1 0,00E-01 I 1.12E 10 s 0.00E-01 :
__--____->__----____,---___-___+-_-_ ___+-_---_____+-_-_-___--,__----____,--__-__---,_____---_-,
CSl31 1 1.10E 09 3 3.13E 08 i 8.SSE 10 s 1.00E 11 1 2.69E 10 s 0.00E-01 1.09E 10 s 0.00E-01 3
-_______-s___-_____-+___-______>____----__+_____-__--+__-___- +__-____-__,____-_--__,_-___--__-+
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4.0 INFORM ATION 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 I are exceeded, a special report is required. Therefore, if twice l the annual limits of Equations 2.3-6, 2.3-7, 3..' ', 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 real individual 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 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 re-sulting in doses that exceed the 40 CFR 190 Standard may have occured, then a variance from the Commission to permit such releases will be obtained. The Standard Technical Specifications 3.11.1.2, 3.!!.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 direct 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 milling 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 fue.1, and repro-cessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mir.ing operations, operations at waste disposal sites, transporta: ion of any radioactive material in wpport of-these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."
( 4-1 Rev.I l
The Special Report will contain:
- 1) A determination of which uranium fuel cycle facilities or operations, i
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 these other fuel cycle facilities within 5 miles of FNGP need be considered. No such facilities exist or are planned at present.
- 2) A determination of the maximum exposed member of the public as given for determining compliance with 10 CFR 50, Appendix I.
- 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 I in this ODCM. Where additional information on pathways and nuclides is needed, the best available inforrnation 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 resultird from liquid effluents from the PNGP will be summed with the organ doses resulting from releases of noble gases, radiciodines ,
and particulates. These doses will be based upon releases from the PNGP during l 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 max-l imum exposed individual contributed from other operations of the uranium fuel cycle.
The direct dose componer.2 will be determined by either calculation or actual measurement. The N-16 component of direct radiation may be calculated using SKYSHINE. A Comouter Procedure for Evaluating Effects of Structure Design on l
N-16 Gamma-Ray Dose Rates, Radiation Research Associates, Inc. Report RRA-T)209, November 1972. (Available in the NSP-NSS Library). The calculation or actual measurement will be documented in this Special Report.
1 i
4-2
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 and ,
an analysis of possible impacts through the drinking water pathway. l i
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5.0 RADIATION ENVIRONMENTAL MONITORING PROGR AM 5.1 Samolinc 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 Interlaboratory Comoarison Procram 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 controllaboratory as well'as with other laboratories 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.
e o,
5-1 Rev.1
s TABLE 5.1-1 .
PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM 1
~
SAMPLING LOCATIONS Type of ,
Samole Code ' Collection Site Location River Water c P-S : Upstream of Plant 0.6 rm @ 60 /ENE River Water P-6 Lock & Dam #3 1.6 rni @ 129 /SE Drinking Water P-Il City of Red Wing c 7.1 mi @ 135 /SE Well Water P-25 Kinneman Farm 11. I mi (c 331 /NNW Well Water P-6 Lock &; Dam l'3' I.6 mi @ 129 /SE Well Water P-8 K'inndy. Store 2.0'ml/ @ 280 /W Well Water P-9 Plant V) ell #2 c 0.3 mi @. 306 /NW Sediment-River P-S Upstream of Plant # '
0.6 mi @ 60 /ENE -
Sediment-River P-6 Lock & Dam #3
' J 1.6 mi @ '129 /$E Sediment-Shoreline P-12 Recreatien Area 3.4 ini @.116 /ESE Periphyton or P-3 C Opstream of. Plant Macroinvertebrates P-6 Lock & -Dani #3 0.6 mi @ 60 fENE -
c 1.6 mi @ 129 /SE ,
Fish P-S Upstream of iP!cnt-
'l0.6 mi @ 60 /sNE- 1-Fish P-6 Lock & Dam #3 'l.6 ' mi @ 129 /SE x, P-25 c Milk Kinnemar: Fa'rm 11.1 mi @ 331 /NNW ' b Milk P-14 Gustafson Farm O 2.2 'mi @ '168 /SSEl '
Milk - '
P-16 A Dosdahl Farm n '2.5 mi @ 39 /NE Milk
.~
P-17 Place Farm 3.5 mi @ 25 /NNE i< ,
Milk P-IS Birk Farm '
3.5 mi @ 181 /S m p
.. +'
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- 5-2 * -Rev. 2
.o
l TABLE 5.1-1 (continued) i
' PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS
. Type of .
Samole Code Collection Site Location Culti rated Crops (Leafy Green Veg) c P-25 Kinneman Farm 11.1 mi @ 331 /NNT P-24 H Larson Resicence c
1.6 mi @ 257*/WNT (Corn) P-25 Kinneman Farm 11.1 mi @ 331 /NNW P-24 Gustafson Farm 2.2 mi @ 16S /SSE C
Particulates and P-1 Air Station P-1 Radiciodine (air) 16.5 mi @ 34S /NNW Particulates and P-2 Air Station P-2 0.5 mt @ 294 /WMJ Radiciodine (air)
Particulates and P-3 Air Station P-3 0.8 mi @ 3130/mi Radiciodine (air)
Particualtes and P4 Air Station P-4 0.4 mi @ 3590/N Radiciodine (air) '
Particulates and P-6 Air Station P-6 1.6 ~mi @ 1290/SE Radioicdine (air)
Direct Radiation (TLD) P01A Property Line I 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' O.4. mi @ 225 /SW i 5-3 'Rev. 2
TABLE 5.1-1 (continued)
PRAIRIE ISLAND NUCLEAR GENERATING PL ANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of .
Samole 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 /WNT 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) P01B 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 Direct Radiation (TLD) P05B County Rd E & Coulee 4.1 mi @ 97 /E Direct Radiation (TLD) P06B William Houschildt Res. 4.4 mi @ 112 /ESE -
Direct Radiation (TLD) P07B Red Wing Service Center 4.7 mi @ 140 /SE Direct Radiation (TLD) P08B David Wnuk Res. 4.1 mi @ 165 /SSE Direct Radiation (TLD) P09B Hwy 19 South 4.2 mi @ 187 /5 Direct Radiation (TLD) P10B Cannondale Farm 4.9 mi @ 200 /SSW Direct Radiation (TLD) PilB Wallace Weberg Farm 4.5 mi @ 221 /SW s 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 @ 306 /NW l Direct Radiation (TLD) PISB Holst Farms
~
4.2 mi @ 347 /NNW i Direct Radiation (TLD) POIS Federal Lock & Dam 3 1.6 mi @ 129 /SE Direct Radiation (TLD) P025 Charles Suter Res. 0.5 mi @ 155 /SSE Direct Radiation (TLD) P03S Carl Gustafson Farm 2.2 mi @ 168 /SSE Direct Radiation (TLD) PO45 Richard Burt Res. 2.0 mi @ 22S /SW Direct Radiation (TLD) POSS Kenney Store 2.0 mi @ _270 /W l
l 5-4 Rev. 1 l
i 1
j TABLE 5.1-1 (continued) I i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT i RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of .
Samole Code Collection Site Location Direct Radiation (TLD) P065 Earl Flynn Farm 2.5 mi @ 299 /WNW Direct Radiation (TLD) POIC Robert Kinneraan Farm 11.1 mi @ 331 /NNW "c" denotes control location ~. All other locations are indicators.
The letters af ter 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 i
"S" denotes special interest locations.
5-5 Rev. I
FIG U R E 5.1-1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRO N M ENTA L MONITORING PROGRAM uosrs I f - _. -e N. .
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1 Appendix A - Meteorological Analyses t
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 f.ong 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 -)(/q
. Table A-8 Short Term - Ground Level - Standard Distances - D/q t
e E'
1-i
(
A-1 l
f APPENDIX - A r
Summary of Dispersion Calculational Procedures Undepleted, undecayed dispersion parameters were computed using the computer program XOQDOQ (Sagendorf and Goll,1977). Specifically, sector averageX/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 XOQDCQ.
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. ComputedX/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 B1 were used as input to XOQDOQ. '
Data were collected and 6T stability classes were defined in conformance j with NRC Regulatory Guide 1.23. Disp'ersion calculations for the plant I
complex were based on AT 42.7-12.2m and 12.2 meter wind data (joint data recovery of 96 percent).
A-2
f r
References .
- 1. Sagendorf, J.F. and Goll, J.T. , XOODOO Procram for the Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG-0324, !
U. S. Nuclear Regulatory Commission, September 1977. [
[
i-1 ;
si 4
6 s
t i >
t l
A-3 t
-, - - - , , . - . . , , , - - - - , - -- . m._, --- -
TABLE A-1 Prairie Island Release Conditions Shield Buildings Auxiliary Building Turbine Building Type Release Ground Level Ground Level Ground Level (Long Term and Short Term) (Long Term) (Long Term)
Release Point Height (m) 56.4 24.4 33.6, 12.2 Adjacent Building Height 62.2 62.2* 62.2A Relative Location to Adjacent to Adjace Lt to Adjacent to p Adjacent Structures Auxiliary Building Shield Buildings Auxiliary Building
,L Exit Velocity (m/sec) N.A. N.A. N.A.
Internal Stack Diameter (m) N.A. N.A. N . A.
Building Cross-Sectiona1 -
Area (m2) 2,170 2,170** 2,170**
Purge l'requency***(times /
yr.) 20 N.A. N.A.
Purge Duration ***(hours /
release) 5 N.A. N.A.
Ileight of Shield Buildings
- Shield Building cross-sectional area
- Applied to short-term calculations only
, _ _ . , .,w -
e TABLE A-2 Distances (Miles) To Controlling Unrestricted Area Boundary Locations As Measured from Edce of Plant Complex Sector Distance
. N 0.28 .
f NNE 0.26 i
NE 0.84*
1 ENE 0.62*
E 0.59*
i.
ESE 0.61*
S .0.43 SSW 0.40 ,
SVV 0.40 :
WSW. 0.37 i W 0.36 WNW 0.36 .
NW 0.43 a
NNW 0.48
- Over-water distances
'l a
e A-5
TABLE A-3 Prairie Island Dispersion Parameters for Long Term Ground Level Releases >500 Ifrs/Yr or >150 Ifrs/QTR for Unrestricted Area Boundary Locations (identified in Table A-2)
Unrestricted Area Doundary Sector y/Q (sec/m ) D/Q (1/m )
HNL N 1.82E-05 1.52ta05 h.55FM 8755Fwo8' L
HE 1,85Eao6 7.74E=09 kNE 3.dSE=06 1.84E=08 E 1.0SE=05 4.23Fa08 ESE 1,86E=05 7.30F=08 St 1,67E=05 6.80F=06 SSE 1,95E-05 6.81F=08 S 8.12E*06 3.19Ea08 SSW 7.08E=06 2.5SF=08 SW 7,66Ea06 2.77Fa08
> WSW 1,13E-05 3.S3F=38 i W 2,66E=05 WHH 3,38E-05 (7.63E=04 jd2f = 0 Q I tid 2.13E=0s 02E=08) 3 NHW l.1lE*05 PWB Period of Record: 4/1/77 - 3/31/78
, _ _ , , _ --.. - - - - + -
- TABLE A-4 Prairie Island Dispersion Parameters ( X/Q),sec/m .
For Long Term Ground I.evel Releases >S00 lirs/Yr or > lSO IIrs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 ri l$20E=04 6,44E-05 1,'66t=05 1,02E=05 7.04E=06 5,29E-06 4,13E*06 i4NE 8:53E*05 2,44t=05 1,18E-05 7,20E=06 4,93E=06 5,67E-06 2,63E-06 tit d.18E=05 2 35E=05 1.14E*05 6,87f 76 4.69E=06 3.49E=06 2,69E-06 f tit 7,88E=05 2.26E=05 1,100 05 6,7 0 Es - 4 e62E=06 3:46E=06 2.09E=06 E 2.40E-04 6.89E=05 3.34E*05 2,02E=05 1,38E=05 1,02E=05 7.88E=06 tSE 4,52E=04 1,30E=04 6,28E-05 3,80E.05 2.59E=05 1.92E-05 1348E-05 SE 4,85E.04 1,39E.04 6: 14Ea05 4,07E=05 2,17Ea05 2,04Ee05 1.56E*05-p SSE 2,59E=04 7,44E=05 3.60f=05 2,17E=05 1:48E-05 1,10E-05 8,44E=06
- 3 1,08E=04 3.09E-05 1,49E=05 9.06E=06 6: 20E-06 4.62E=06 3.58E*06
" ' 5 S .4 6,60E=05 2,46E=05 1.19E*05 7.19E*06 4e9tE-06 3,66E=06 2,83E=06 Sn 9,19Eac5 d,62E=05 1326t=05 7.72E=06 5,31E-06 3,98E-06 3.09E-06 HSH 1,17E = 0 4 3,35E*05 1.61Ea05 9,80E=06 6,70E=06 4,97E=06 3.81E=06 h 2,60E=04 7,56E 05 3,66E 05 2,22E=05 1.5tE=05 1,12E-05 8,6tE=06
.i tJ w 3,42E*04 9,80E=05 4,75E=05 2,88E-05 Is 98E=05 1.47E=05 1.14E=05 IM 2,91f-04 8.35E=05 4,05E-05 le 68E=05 1.25E-05 9.67E=06 2.46E=05 14t84 1.76t=04 5.04E=05 2.45E.05 1,50E.Os 1.03E-05 7.70E=06 5.99E=06 Period of Record: 4/1/77 - 3/31/78
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4 TABLE A-4 (Cont.)
Prairie Island Dispersion Parameters ( Y/Q),sec/m ,
For Long Term Ground Level Releases >500 lirs/Yr or > 150 lirs/Qtr For Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 u 1,57Ea07 6.S9t=07 S.79E=07 S.13E=07 4.59t=07 4.14E=07 3.76L=u?
urJE S,07E=07 4,41E=07 3,87E=07 3,43E-07 3,07E=07 2,17E=07 2,52t=07 Ng 4.17E=07 4,15E=07 3,64E=07 3,23E-07~ 2.89E=07 2,61E-07 2,38E=07 thL 4.86L=07 4:23E*07 3,71E*07 3.29t=07 2,94E=07 2.65E=07 2,41Le07 E 1,41E=06 1.23E=06 1.0AE=06 9,SSE=07 8.S6t=07 7,15E=07 7.05E=07
! ESE 2.b4E=06 2,30E=06 2.02L=06 1,79E=06 1,olt-06 1.46E-06 2,79E=06 2,43E*06 1,32t=06 SE 2,14E=06 1,9 0 E a'3 6 1,70E=06 1 S4Ea06 1,40L=06 2 SSE 1,50L=06 1.31E=06 1.15E-06 1,02E-06 9,12E-07 8,25L-07 7,51L-07 1 5 6.49E=07 S.6SE=07 4,97Ea07 4.41t-07 3.95E=07 3.56E-07 3. d a t. ~ 0 7 Ssn S.10t=07 4,44La07 3.90E=07 3,46E=07 3,10E-07 2.60E-07 2.S4E-07 SW S.59t=07 4 t07E"07 4,27E-07 3,79t=07 3.39E-07 3,06t = 0 7 2"78t-07 hSH 6.H2E-07 S,93E=07 5,2tg=u7 4,6th=07 4,15E-07 3,74E=07 3,40E-ul H 1,SSEa06 1,43E-06 1,17E=n6 1,04E=06 9.29te07 8.40t=07 WHW 2,07E-06 1,80Ea06 7.64t-07 1,$9E-06 1,4tE=06 1,26E=06 1.14t-06 1.03E-06 dd 1,76E=06 1.S4E=06 1,3SE-06 1,20E=06 1.08L-06 9./2L-07 uten 1.10t=06 9.59E-a7 8.8TE-07 4,43t=07 7.47E 07 6,09E-07 0.04F-07 S.49t-07 l
Period of Record: 4/1/77 - 3/31/78
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Prairie Island Dispersion Parameters ( X/Q),sec/m , .
For Long Term Ground Level Releases >500 lirs/Yr or > 150 ifrs/Qtr for Standard Distances (As Measured from Edge of Plant Complex) >
Miles Sector 3.6 3.7 3.8 3.9 4.0 4,1 4.2 N
1,3SE=07 1,28E=07 1,22E=07 hHE 9,18t=08 1 16E=07 1,11t=07 1.07E=07 1302E=07 8,74E=08 8.34E=08 7,97C=08 DE 8.75E=08 o g34E=08 a 7,62E=08 7,30E=08 7,00E=08 EHL 7,96E=09 7,61E=08 7,28E=08 6,98E=08 B,66E=08 8.24E=06 7,86E=08 7,50E=06 6.70E=08 E 2,60E=07 2,48E=07 2,37E=07 7,17E=0p 6,86E=08 6.S8E=08 E SI- 4,9tE=07 2,26E=07 2,17E=07 2,08t=07 1,99t=07 St 4,68E=07 4,47E=07 4,27E=07 5,22t=07 g,97E=07 4,09E=07 3.92E=of 3,76E-07 4,75E=07 4,54E=07 4,3SE=07 ySSE 2.78E=07 2,6SE=07 2,S3E=07 4:17E=07 4,00E=07
- 3 1.18E=07 2.42E=07 2.32E=07 2.22E=07 2,13E-07 "SSN 1,12E=07 1,07E=07 1,02E=07 9,79E=08 9,3SE=08
, 9,29E=00 8,8SE=08 8,44E=08 8,07t=08 8,99E=0a Sw g,00g=o7 9,S4E=08 7,72E=0g I.39E=08 7,09E-08 HSH 9310E=08 8.69E=08 8,3tE=06 7.95E=08 1a26E*07 1,19E=07 1 14E=07 7,62E=08 H 2,8 3E = 0 7 1.09E-07 1,04E=07 9 s98E=08 9,57E=08 NHN 2,70E=07 2,, S 8 E = 0 7 2,47E=07 2.46E,07 3,78E=07 3,60E=07 2,36E=07 2,17E=07 HH 3,24E=07 3 44E=07 3,28E.07 3. ole =07 3,09E=07 2,95E=07 3.14E=07 2.89E=07 HH* 1,99E=07 2,82E=07 2,70E=07 2. 58 Ep 0 7 2,48E=07 1.89E=07 1.80E=n? 1.72E=07 1, HSE =07 3.58E"07 1.51E=07 Period of Record: 4/1/77 - 3/31/78
TABLE A-4 (Cont.) ,
Prairio Island Dispersion Parameters ( X/Q),sec/m ,
For Long Term Ground I.evel lleleases >500 Ilts/Yr or > l50 ifrs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 4.3 4.4 4.5 4.6 4.7 4.8 .4.9 n 9.79E-08 9,4tE=08 9.04E=08 8,7tE*08 B,39E-08 8,09E 08 7.81E*08 ot4E 6,72Ea08 .6,46E-08 6,22E=08 S,99E,08 S.77E=08 5,57E=08 S.38E-08 f.E 6,43E=08 6,18t=08 S 95E=08 S,74Ea08 5,STE-08 S,34E*08 S.16t-08 t ilt. 6,31E=08 6.06E=08 5,83E=08 S,62E-08 5,4tE*08 5.22E-08 5,04E=08 t 1,91E=07 1,84E=07 1,77t=07 1.71E=07 lab 5E=07 1,S9E=07 1sS4Ee07
- f. S E 3,62E*07 3,48E=07 3,55E-07 3,23E*07 J ellEa07 3,0lE*07 2,91E-07 SE 3,8St=07 3,70E=07 3,S6E=07 3,44E-07 3.3fE-07 3,20Ee07 3.09E-07
- > SSE 2.0St-07 1g97E=07 1,90E-07 1.81E=07 1,76E-07 1,10E=07 1,65E=07 1 S 8.61E-08 8,30Ea08 7,98E=08 7.69E=08 7,4tE-08 7,1SE-08 6.9tteua sSw b,81E=08 b,SSE=08 6,30E=08 6,07E-08 5.85F-08 S,65E 08 5,46E=08 Ss 7.32E=08 7,03E=08 6.76E*08 6,SlE-08 6.28f=08 6,06Ee08 5.BSE-08 WSH 9.19t=08 8.84E=08 8,SIE=08 8,20E=08 7,91t=08 7,64Ea08 7,58E=08 w 2,09E=07 2,0lE=07 1,9 3 t.- 0 7 1,86E 07 1,80Ea07 1,73E=07 1,6 8 E.= 0 7 uttu 2,77E*07 2,66E 07 2.56E-07 2.47E-07 2,58E=07 2,30E-07 2 g22E-07 Hw 2,38F-07 2,29E=07 2,20E=07 2,12E=07 2,05t=07 1,97E-07 1,91E-07 HNu .l.4SE*07 1.39E=07 1,34E=07 1,29t-07 1.24E-07 1.20E*07 1.16E=07 Period of Record: 4/1/77 - 3/31/78 1
..w--- . - , . - - , - ,--
w
TABl.E A-4 (Cont.)
Prairie Island Dispersion Parameters ( X/Q).sec/m ,
for I.ong Term Ground I.evel f(eleases >500 llrs/Yr or >150 IIrs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 5.0 s
t4 7,Sqg,og NNE 5,20E*08 88E 4,99E*08 LNL 4.87t=08 E 1,49E 07 ESE 2.81L=07 S t.' 2.99E-07 p SSE 1,59E*07 s
S 6,68Fn08
% SSW S.27Ea08 SH S 65E*08 hSH 7,14E*p8 W 1,62Lw07 WNW 2.18sE
- 0 7 NW 1,84F*07 i:Hn 1.12b-07 Period of Record: 4/1/77 - 3/31/78
, , , - - , - . - , - ,, , - , - - - - - - , w - -
TAllLF A-5 Prairie Island Dispersion Parameters (D/Q),1/m .
For Long Term Ground Level Heleases >S00 IIrs/Yr or >l50 Ilts/Qtr for Standard Distances (As Measured from F4lge of Plant Complex)
Miles Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 N 5.38F=07 2.0!F=07 1.09E=07 6.97F=08 4.87E*06 3.62E=08 2.8tt-no tent 1.39E=67 1.27Fa07 6.87E=08 3.07F=08 2.28F=08 1.77F=08 HL 4.19E=08 2.21E=07 8.28F=08 4.49F=08 2.8'/F 08 2.0lE=08 1.49F.08 1.16F=08 E N t- 2.88E=07 1.08F=07 S.8SF=08 3.73Fwoo 2.61F=08 f.94Ea08 1.5tF=08 L 6.lSE=07 2.30Ea07 1.2SE=07 7.97E=08 5.57F=08 4.14Fn08 3.22F=o8 FSE 1.12E=n6 4.19F=07 2.27Fe07 SE l.45E-07 1.02F=07 7.54 Fan 8 5.86F=08 1.22F=06 4.5SE=07 2.47F=07 1."S 8 F = 0 7 1.10F=07 8.19E.08 6.36F-08
> SSE 5.8tF=07 2.17F=07 1.lBE=07 7.53Fa08 5.27F=08 3.91Fano 3.04Eaco
,8 3 S 2.72E=07 1.02F=07 S.53F=08 3.53 Fan 8 2.47F=08 l.83F-08 1.42Fano ci SSn 2.n0F=07 7.47E=08 4.06Fano 1.81F"08 1.34F no 2.59E=40 1.04F=ne SH 2.I6F=07 8.06E=08 4.38F=08 2.79E=08 .1.95F=08 1.4SF=08 1.13F-08 HSH 2.19F=07 8.93F=08 4.85F=08 2.16t=08 l.61Fano 1.2SE-08 3.09F-08 H S.00F=n1 1.87F=n7 1.01F=07 6.47F=0a 4.53Feno 3.T6E.06 2.61F 08 nHH 9.50F=01 5.SSE=07 1.93Fa07 1.23F=07 8.60F=08 6.39F=n8 4.96F=o8 HH 7.9SF=07 2.97F=07 1.61F.07 7.20Fanb S.3SFand talhi 1.03E 07 4.1SFan8 S.54F=n1 2.07E-07 1.12Fe01 7.17F=08 5.02Eand 1.72 Fen 8 2.89FanB Period of Record: 4/1/77 - 3/31/78 e
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TAllLI: A-5 (Cont.)
Prairie Island Dispersion Parameters (D/Q),1/m .
Por Long Term Ground I.evel Releases >S00 Ilrs/Yr or >l50 Ifrs/Qtr For Standard Distances (As Measured from rdge of Plant Complex)
Miles Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1
- 4.27F=09. 3.65Fa09 3,14F.09 2.73F 09 2.40F=09 2.12E-09 1,89F.09 gent. 2.69E,09 2.30Fa09 1,98E,09 f.72Fe09 1.51F 09 1.33Fa09 1.19Ea09 tit 1.76F,09 1.50E=09 1.29F=09 1.13F=09 9.87F-10 8.72Fa10
- f. t F. 2.29E=09 1.95E=09 7. 7 6 ti- 10 1.68F=09 1.4bFa09 1.28F-09 1.14Fa09 1. 01 E e n 'd F 4.88F=09 4.17F*09 3.59E=09 3.13E-09 2.74Fa09 2.42F=09
> t.s! 8.90F=09 7.59F=09 2.lbF=09 cl 6.54F=09 S 69E=09 4.99F=09 4.41Fa09 5.93Fe09 St 9.66Ee09 8.2'2F 09 7,33F.09 6.18F=09 S.43F=09 4. 79F =09
" SSt 4.hlF.09 3.94E.09 4.27Fa09 3.39F-09 2.95F.09 2.59F=09 2.29F=09 2.04F=09 3 2.16F=09 1.85Fa09 1.59Ea09 1.38F,09 1.21E*09 1.07E*09 SSu 1.59F 09 f 35E=09 1,37F.09 9.55F-10 1.02Fe09 8.91Fal0 7.87F-10 7.00Fal0 S r, 1.7tE=09 1.46Fe09 1.26F*09 1.10F=09 9.61F-10 n s r. l.90Fw39 1.62Fa09 8.49E.10 7.56F-10 l.40F-09 1.21Ea09 1.06F 09 9.41F=10 6.37Fal0 e, 3.97F 09 3.39E=09 2.92Fa09 2.54F-09 2.23F-09 1.97F-09 niin 7.54F=09 6.44F=09 5,55p 09 1.75E-09 4.83F'09 4.23F 09 3.74F.09 3.33F 09 fi rs 6,31Fe09 5.39F=09 4.64F*09 4.04F-09 3.54F=09 3.13F=09 nw o 4.40E=09 3.75F-09 2.79F.09 3.23F=09 2.81F=09 2.47E-09 2.lbF=09 f 94F,09 i
l Period of itecord: 4/1/77 - 3/31/78
- n - - - - ,,,.v--v-4 , - - , . , . n ., , -- , . . . , . , - - - _
TABI.I: A-5 (Cont.)
Prairie Island Dispersion Parameters (D/Q),1/m ,
l'or I.ong Term Ground I.evel Releases > S00 lirs/Yr or >l50 lirs/Qtr for Standard Distances (As Measured from Fxige of Plant Complex)
Miles Sector 2.2 2.3 2.4 2.5 2.6 2.7 _2 . 8 il f 69F=09 1.52F=09 1.17F.09 1.25Fe09 1.14Fe09 1.04F=09 9.56F-10 Iltat - 1,0er.09 9.56F=10 8.65F=10 7.86tato 7.17F 10 taf 6.57Fa10 6. 0 3F -10 6.95F=to 6.25F=10 S 65F=10 5.13F=10 4.69Fa10 4.29F=10 3.94Felo Li3t 9.04F=10 8.14Falu 7.3bfa10 6.6bfet0 6.10F-10 S.59E=10 5.13Fa10 l- 1.93F=09 f.74F=09 1.57F=09 1.43F*09 1.30F=09 1.19F .0 9 1.10E-09 ESE 3.Sifa09 3.16F.09 2.86Ea09 2.6ur.09 2.37F-09 2.17F=09 2.00F=09 y: :iS E bL 3.82Fa09 3.44F=09 3.llF=09 2.82F=09 2.5bf-09 2.36F.09 2.l'/F-09 I,aar.09 1.64F 09 1.48F.09 1.35F-09 1.23F-09 1.13F-09 1.04E.09 5 S 8.55F-10 7.69F=10 6.95F.10 6.32Falo 5.7/F-lU 5.2BF 10 4.85F-10 b S.I 6.21F=10 S.10F.10 4.63Fa10 Sl8 S 64Fal0 4. 2 3F - 10 1.8/l.10 3.5br-lo 6.7bf=10 6.09Felo 5.50Fal0 5.00F=10 4.5bf=10 4. l llE- 10 3.84F-10 ri S ti' 7.49F=10 6.10F=10 5.54F=10 6.74Fal0 5.0bF-10 4.63Falo 4.26E-10 W l.57Fa09 1.4tF=09 1.28Fa09 1.lbE-09 1.0bf=09 9.68Fal0 H.90Fa10 HilH 2,96fpO9 2,68fy09 2.42Fw09 2.20F.09 IlH 2.0lFa09 1.t*4F.09 1.69F-09 2,49Fa09 2,pqf.g9 2,0jFgG9 l.fl4F=09 j,68f=09 j,5q{.g9 1, q 2[ .,0 9 Illiel 1.74Fa09 .l.56F=09 f.41F=09 1.2HF=09 1.17F*09 1.07F-09 9. fl 6F - l o Period of Record: 4/1/77 - 3/31/78 4 . _ . . . . . . . _ . . . , _ . _ , . - .. . , . -, , . _ m.., , ., ., _. _..r-._. _. _-
TABLE A-5 (Cont.)
Prairie Island Dispersion Parameters (D/Q),1/m ,
For Long Term Ground Level Releases >500 IIrs/Yr or >l50 lirs/Qtr For Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5 h 8.84F=l0 8.17F=10 7.58F=10 7.05F-10 6.57F=10 6.14F=10 5.75F=10 nhL 5.56t=10 5.lbF=10 4.77E=10 4.44F = 10 4.14F=10 5.87E=10 3.62F=10 UL 3.64E=10 3.36t=10 3.12E=10 2.90F=10 2.70F=10 2.S3E=to 2.37E*la Ehl 4.73E=10 4.38F=10 4.06Fe10 1.78F=10 1.52F=10 1.29F=10 3.08F-10 E 1.01F=09 9.34F=10 8.67F=10 8.06F=10 7, sil F= 10 7.02E=10 6.S/F=10 ESt 1.84E=09 1.70Fa09
- 4/F=09 1.58F=09 1.31F=09 1.28F=09 1.?0F=09 y SE 2.00E=09 1.8bF=09 1.71F=09 1.59F=09 f.49F=09 1.39Fe09 1.10E=09 g SSL 9.55F=10 8.83E=LO 8.19F=10 7.6tF=10 7.10E=10 6.63F=10 6.21F=10 S
4.47E=10 4.14F=10 3.84F=10 3.51F=10 3.33E=10 3.llE=10 2.9tF=10 SSd 3.2aF=10 3.04F=10 2.82F-10 2.62E=10 2.44E 10 2.28F=10 2.14F=10 SH 3.54E-10 3.27E=10 3.04F=10 2.82F=10 2.63F=10 2.46F=10 2.30F=10 WSH 3.92F=10 3.63F=10 W
- 3. 3 7E = l 0 3.I3F=10 2.92F=10 2.73F=10 2.SSE=10 8.20F=10 7.59F=10 7.04F=10 6.54F=10 6.10F=10 S.70F=10 S.34F=10 Hub 1.56F=09 1.44F=09 1.34E=09 1.24F=09 1.16F=09 1.08F=09 1.0lE=09 Hn 1.31F=09 HHb 1.2tE=09 1.12F=69 1.04F=09 9.71F=10 9.07F=10 8.49F=10 9.09Falo 8.4tF=10 7.80E=10 7.25F-10 6.76F=10 6.32F=10 5.92E=10 Period of Record: 4/1/77 - 3/31/78
-- ,n- ,, . -g n ,- ---e m , ,-- y , , .,, ----s -_ - n- - - - , - - - - = , . . - - - , , - -, w - -_ ws-_, - . - - _ _ - __ -- - - - v
i TABLE A-5 (Cont.)
Prairie Island Dispersion Parameters (D/Q),1/m ,
For Long Term Ground Level Releases >500 ifrs/Yr or >l50 lirs/Qtr for Standard Distances (As Measured from Dige of Plant Complex) ,
Miles
- .cctor 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4 'i.40E=10 S 0/E=10 4.78E=10 4.51F=10 4.2bE-10 4.03F=10 3.82F=10 H"E 3.40F=10 3.19E=10 1.01E=10 2.84E=10 2.66F=10 2.54F=10 2.41F=10 HL 2.22F=to 2.09E=10 1.97F=10 1.86F=10 1.75F=10 1.66E=10 1.57F=10
- t* E 2.89F=10 2.72E=10 2.56E=10 2.42E=10 2.2er=10 2.lbF=10 2.05E=10 Lf 6.17E=10' 5.80E=10 5.46F=10 9.16F=10 4.87F=10 4.6tF=10 4.17F=10 i SI 1.12F=09 1.06F=09 9.95E=10 9.39F=10 8.87F 10 n.40F=10 7.96E.10 st 1.22F=09 1.lSF=0V 1.08E=09 1.02E=09 9.64E=10 9,12F=10 8.6SE=10
- =SSL 5.83F=10 5.48F=10 5.lbF=10 4.07E=to 4.60E=10 4.16F=10 4.13F=10 4 S 2.73E=10 2.S7E=10 2.42E=10 2.2BF=10 2.lbF=to 2. n e: E = 10 1.94F=10 o SSH 2.00E=10 1.88f=10 1.7BE=10 1.61F=10 t.58F=to 1.50F=10 t.42F=10 Sw 2.lbF=10 2.03F=10 1.92F=10 1.81F=10 1.7tF=10 1.62E=10 1.53F=to HSd 2.40E=10 2.25F=10 2.12F=to 2.00Eolo 1.89E=10 1.79E=10 1.70F=10 H S.0lF=10 4.7tF=10 4.44E=10 4.19F=10 3.9tF-10 3.75F=10 3.55F=10 h"d 9. 'i 3 E = 10 8.96F=10 8.44E=to 7.96F=10 7.52E 10 7.12F=10 6.7SF=10 HH 7.97Fel0 7.SOF=to 7.06F=10 6.6eF=10 6.29F=to S*96F=10 S.6SF=10 hhd 5.55F=10 5.22F=10' 4.92E=10 4.64F=to 4.38F=to 4.15E=10 3.93F=10 t
.-Period of Recordi 4/1/77 - 3/31/78 e
e I
I l ?
i ,. -
TABLC A-5 (Cont.) ~
Prairie Island Dispersion Parameters (D/Q),1/m ,
for Long Term Ground Level iteleases >500 Ilrs/Yr or >l50 lirs/Qtr for Standard Distances (As Measuied from rdge of Plant Complex) 4 Miles Sector 4.3 4.4 4.5 43 4.7 4.8 4.9 le 3.63E 10 3.45g=10 3.2BE=10 3.13E=10 2.99F=10 2.HStal0 2.73F=10
- tirit 2.29tato 2.17E=10 2.01E=to 1. 9 'IF = 10 1.8bF-10 1.80F=10 1.72F-10 til 1.49E=10 1.42E=10 1.3bE=10 1.29F=10 1.23F*10 1.17F-10 1.12F-10 thL 1.94Eu 10 - 1.8SE=10 1.76F=10 1.68F-10 1.60F 10 1.53F=10 1.46E-10
_ t. 4.lbr=10 3.94F=10 3.75E=10 3.58E=10 3.41F=10 3.26F=10 3.12F = t o
. t S E- 7.5t>F=10 7.1SF=10 6.84Fal0 6.52E=10 6.22E=10 5.94F-10 5.66F=10
.p .St 8.21F=10 7.80F=10 7.43E=10 7.08E=10 6.75E=10 6.n5F=10 6.17F.10 f3 bSt 3.92Fal0 3.73F=10 3.55Fal0 3.38E*10 3.23F=10 5.nuf=10 2.94F=10
~ b 1.84Ea10 1.7SF=10 1.66Fato 1.58F=10 1.5tF=10 1. t 4F=10 1.36E=10 SSH 1.35F=10 1.2nF=10 1.22F=10 1.16F=10 1.llE=10 1.n6E=10 1.01F-10 Sn .l.4SF=10 1.30F=10 1.32E=10 1.25F=10 1.20F-10 1.14E=10 1.09E=10 USd 1.6iF=10 1.53F=10 1.4ot-lo 1.39Fel0 1.33F=10 1.2/E=10 1.21F=10 W 3.3/F=10 3.20F=10 3.05E=10 2.91F-10 2.71F=10 2.6SF=10 2.53F=10 hean 6. si l F = 10 6.09F=10 5.80Ea10 5.52F=10 5.27E=10 5.03F 10 4. 81 F - 10 f 8 ri 5.36E=10 5.10F 10 4.8SE=10 4.62F=10 4.4lF-10 4.21F-10 4.03F-10 li'8 v8 3.75F 10 3.5SE=10 3.38E=10 5.22E=10 5.0/F=10 2.93F-10 2.80F=10 Period of Record: 4/1/77 - 3/31/78
S TABLE A-5 (Cont.)
Prairie Island Dispersion Parameters (D/Q),1/m ,
For Long Term Ground I.evel Releases >500 lirs/Yr or >l50 llrs/Qtr For Standard Distances (As PAcasured from Edge of Plant Complex)
Miles
. Sector 5.0 4
et 2.61F-10 id:#E I.64F=10 i'l 1.07F 10 ENE 1.40E=10 L 2.96f=10 ESL 5,43c a 10 ,
> S t.32F=10 h
N SSH g.69F=11 Sh 3,ogr.10 ASH 1.16F-10 W 2.42t.10 HilH -
dl.61F=10 fld 1.85Fal0 estih -
2.httF-10 I
Period of Record: 4/1/77 - 3/31/78 S
, _ , , - - , - - - - ,,---,y --y-- , , - ,,-, - m -, ,, , , , ,,-
TABLE A-6 Prairie Island Dispersion Parameters i'or Short Term Ground Level Relea::es $ 500 lirs/Yr or $150 IIrs/Qtr l'or Unrestricted Area Boundary Locations (Identified in Table A-2)
Unrestricted Area Doundary Sector y/g (sec/m ) D/q (1/m )
h 7. 09 E-05 4.o0E-07 hNE 7.32E-05 4.I1E-07 NE 1.60E-05 6 . 7 7 E-O d ENE 1 97E-05 1.11E-07 E 4.92E-05 1.99E-07 ES E L.40E-05 2.52E-07 SE 5.98E-05 2.43E-07 SSE E.79E-05 3.0 8 E-0 7 Y S 5.18 E- 05 2.04E-o7 U SSh 5.26E-05 1.u9E-07 SW 5.25E-05 1.9 0 E-0 7 WSw 7. 83 E-05 2.44E-07 h 1.32E-04 3.78E-07 WNW 3.10E-04 4.o1E-07 Nb 7.67E-05 3.25E-07 NNb 4.19E-05 2.34E-07 Period of Record: 4/1/77 - 3/31/78
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TAbl.E A-7 (Cont.)
Prairie Island Dispersion Parameters ( X /q), sec/m .
For Short Term Ground 1.evel Releases s500 firs /Yr or 5150 lirs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1 06E-05 7./3E-Oo c.76E-06 5.51E-06 N 1 57E-05 1 26E-05 E . 9 7E- 06 5.27E-06
- 1. 3 5 E- 05 1.11 E- 0 5 S.26E-06 7.87E-06 6. 81 E- 06 5.96E-06 idN E 1 74E-05 1 44E-05 1 21E-05 1 02E-05 8 57E-06 7 50E-06 6.63E-06 NE 5.97E-Oc t.27E-06 1.39E-05 1.14E-05 5.46E-06 6.04E-06 6. 8 3 E- 0 6 kNE 1.18E-05 3 11E-05 2 51E-05 2 11E-05 1 80E-05 1 53 E-05 1 33E-05 E 1.71E-05 4.35E-0$ 3.5dE-05 2.98E-05 2.54E-05 2.19E-05 1.91E-05 ESE 2.03E-05 1. 61 E- 0 5 4 6 5E-05 3 75E-05 3 18E-05 2 71E-05 2 32E-05 SE 1.51E-05 1.35E-OS 2.67E-05 2.41 E-05 2.05E-05 1.72E-05 Y SSE 3.53E-05 1 01E-05 E.836-06 7.81E-06 El 5 2 05E-05 1 66E-05 1 38E-05 1. lie-05 7.9 3 E- 06 7.02E-Oc 1.89E-0$ 1.5 4 E-05 1.29E-Ob 1.10 E- 05 5.0 5 E-On SSh 9 19E-06 d.0$E-06 7.21E-Ob SW 1 95E-05 1 54E-05 1 30E-05 1 12E-05 5. 41E- 06 WSW 2. 51 E- 05 2.0$E-05 1.72E-05 1.47E-05 1.21E-05 1.0tE-05 2 70E-05 2 30E-05 1 89E-05 1.65E-05 1.46E-05 W 4 01E-05 3 2 4 E-0 5 1.48E-05 1.31E-05 WNb 3.44E-05 2.75E-05 2.31E-05 1.56E-05 1.6HE-05 1 60E- 05 1. 4 0 E- 0 5 1. 2 4 E- 0 5 NW 3 15E-05 2. 5 7 E- 0 5 2 17E-05 1 85E-05 e.82E-06 1.86E-05 1.54E-05 1.31E-05 1.12E-05 5.85E-06 NNh 2.28E-05 Period of Record: 4/1/77 - 3/31/78
TA111.F. A-7(Cont.)
Prairie Island Dispersion Parameters ( X /q), sec/m .
For Short Term Ground Level Releases 5500 Ilts/Yr or 5150 lirs/Qtr For Standard Distances (As Measured from f219e of Plant Complex)
Miles 6ector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 N 5.27E-06 4.74E-06 4.30E-06 3.51E-06 3.59L-06 3.32E-06 3.07E-06 hhE 4.70E-06 4.22E-06 3.82E-06 3.47E-06 3.18E-06 2.97E-06 2.75E-Oo NE 5.89E-06 5.30E-06 4.80E-06 4.37E-06 4.01E-06 3.69E-06 3.42E-06 ENE 4.61E-06 4.21E-06 3.80E-06 3.45E-06 3. ALE-06 2. 91E- 0 6 2.10E-06 E 1.06E-05 5.52E-06 8.66E-06 1.90E-06 1.25E-06 6.74E-06 6.25E-06 ESE 1.52E-05 1.38E-05 1.25E-05 1.13E-05 1.04E-05 5.72E-06 5.03E-06 SE 1. 6 2 E- 05 1. 46 E- 05 1.33E-05 1. 2 ] E- 0 5 1.11 E- 05 1. 0 3 E- 05 5. 59 E- 06 Y SSE 1.20E-05 1.09E-05 S.d4E-06 8.96E-06 b.23E-06 7. sue-06 7.04E-06 M S L.97E-06 4.2TE-06 5.68E-06 5.18E-06 4.75E-06 4.36E-06 4.04t-06 SSW 6. 2 8 E-Oo 5. 66 E- 06 5.14 E- 06 4.69E-06 4.310-06 3.92t-06 3. 6 4 L- 06 Sh 6.43E-06 5.78E-06 5.24E-06 4.77E-06 4.37E-06 3.90E-06 3.62E-06 WSW E . 41 E- 0 6 1.5hE-OL 6.81E-06 L.27E-06 5.11E-06 5.11E-06 4.80E-06 h 1.30E-05 1 1TE-05 1.06E-05 S.62E-06 6.83E-06 E.33E-06 7.73E-06 hhh 1.17E-05 1.05E-05 5.65E-06 E.80E-06 E.08E-06 1.42E-06 c.89E-Ou NW 3 .11 E-0 5 1.00E-05 5.09E-06 E.30E-06 1.63E-06 1.13E-06 6.62E-Oc NNb 1.u9E-06 7.11E-06 6.47E-06 5.89E-06 5.41E-06 5.01E-06 4.64E-06 Period of Record: 4/1/77 - 3/31/78
, - - - -- - - - m- - , - , - , .y ..- - .. -,
TAnil A-7 (Cont.)
Prairie Island Dispersion Parameters ( X /q), sec /m .
Por Short Term Ground 1.evel Releases 5500 lirs/Yr ori150 lirs/Qtr for Standard Distances (As Measured from I:dge of Plant Complex)
Miles Sector 2.2 2.3 2.4 2.5 2.6 2.7 2.8 N 2.87t-06 2.67E-06 2.50E-06 2.32E-06 2.27E-06 1.94E-06 1.84E-06 2.24E-06 2.09E-06 2.03E-06 1.76E-06 1.66E-06 hhE 2.56E-06 2.39E-06 2.24E-06 2.11E-06 NE 3.19E-06 2.98E-06 2.79E-06 2.63E-06 2.57E-06 2.19E-06 2.05E-06 1.97E-06 1.74E-06 1.64E-06 LNE 2. 51E- 0 6 2.34E-06 E 5.82E-06 5.44E-06 5.10E-06 4.89E-06 4.75E-06 4.14E-06 3.92E-06 ESE t.41E-06 7.87E-06 7.38E-06 7.16E-06 7.09E-06 6.11E-06 5.78E-06 7.82E-06 7.70E-06 7.60E-06 6.62E-06 6. 2 6E -06
> SE E.93E-06 8.35E-06 4.73E-06 4.47E-06 h SSE 6.56E-06 6.14E-06 5.76E-06 5.55E-06 5.36E-06
" S 3.76E-06 3.51E-06 3.29E-06 3.18E-06 3.06E-06 2.73E-06 2.59E-06 2.96E-06 2.89E-06 2.75E-06 2.42E-06 2.28E-06 SSm 3.39E-06 3.16E-06 2.44E-06 2.30E-06 Sm 3.37E-06 3 15E-06 2.95E-06 2.84E-06 2.70E-06 WSW 4.41E-06 4.18E-06 3.92E-06 3.85E-06 3.67E-06 3.28E-06 3.10E-06 h 7.21E-06 6.74E-06 6.32E-06 6.45E-06 6.03E-06 5.30E-06 5.02E-06 kNm 6.42E-06 6.00E-06 5.65E-06 5.32E-06 5.23E-06 4.5 5 E-06 4.30E-06 hw 6.16E-06 5.76E-06 5.40E-C6 5.16E-06 5.03E-06 4. 3 7E-06 4.13E-06 NNh 4.31E-06 4.02E-06 3.76E-06 3.57E-06 3.46E-06 3.00E-06 2.83E-06 Period of Record: 4/1/77 - 3/31/78
9 TABI.E A-7 (Cont.)
Prairie Island Dispersion Parameters ( X/q), sec/m ,
For Short Term Ground I.evel Releases 5500 llrs/Yr ors 150 IIrs/Qtr l'or Standard Di. stances (As Measured from Edge of Plant Complex)
Miles Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5-H 1.74E-06 1.66E-06 1.5HE-06 1.50E-06 1. 4 3E-06 1. 3 7E-06 1.31E-06 f1NE 1.57E-06 1.50E-C6 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 1.6SE-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 3.11E-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. 9 3E- 06 5.63E-06 5. 3 6E-06 5.11E-06 4.87E-06 4.66E-06 4.46E-06
}' 55E 4.24E-06 3.97E-06 3.78E-06 3.60E-06 3.44E-06 3.29E-06 3.15E-06 N
- 5 2.45E-06 2.25E-06 2.14E-06 2.04E-06 1.94E-06 1.85E-06 1. 7 7E-0 6 SSW 2.16E-06 1.96E-06 1.87E-06 1.7dE-06 1.70E-06 1.63E-06 1.56E-06 SW 2.18E-06 2.03E-06 1.93E-06 1.84E-06 1.75E-06 1.67E-06 1.60E-06 WSW 2.94E-06 2.10E-06 2.57E-06 2.45E-06 2.34E-06 2.24E-06 2 14E-06 W 4.76E-06 4.34E-06 4.13E-06 3.95E-06 3.77E-06 3.61E-06 3.47E-06 WNW 4.07E-06 3.86E-06 3.67E-06 3.50E-06 3.34E-06 3.20E-06 3.06E-06 i4W 3.92E-06 1.69E-06 3.51E-06 3.35E-06 3.20E-06 3.06E-06 2.94E-06 NNW 2.68E-06 2.53E-06 2.40E-06 2.28E-06 2.18 E-06 2.08E-06 1 99E-06 Period of Record: 4/1/77 - 3/31/78
TABLE A-7 (Cont.)
Prairie Island Dispersion Parameters ( X /q), sec4n ,
l'or Short Term Ground I.evel Heleases $ 500 IIrs/Yr or $ 150 lirs/Qtr l'or Standard Distances (As Measured from l'dge of Plant Complex)
Miles Sector 3.6 3.7 3.8 3.9 4.0 4.1 4.2 t4 1.25E-06 1.20E-06 1.15E-06 1.10E-On 1.06E-06 1.02E-06 s.eet-of titJ E 1.14E-06 1.09E-06 1.05E-06 1.01E-06 9.73E-07 9.37E-07 9.o 4 c- o y tJE 1.45E-06 1.39E-06 1.34E-06 1.29E-06 1.24E-06 1.20E-06 1.InE-06 ENE 1.11E-06 1.07E-06 1.02E-06 9.83E-07 9.46E-C7 9.11E-0T E. 79t-01 E 2.67E-06 2.5FE-06 2.47E-06 2.38E-06 2.29E-06 2.21E-06 2.g3E-os ESE 3.94E-06 3.78E-06 3.64E-06 3.50E-06 3.38E-06 3.26E-06 3.15t-as
> SE 4.27E-06 4.10E-06 3.94E-06 3.79E-06 3.65E-06 3.52E-06 3. 39 E- 06 b SSE 3.02E-06 2.90E-06 2.79E-06 2.68E-06 2.59E-06 2.50E-06 2.41E-06 S 1.70E-06 1. 6 3E-06 1. 5 7E- 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. 20 E- 06 SW 1.53E-06 1.47E-06 1.41E-06 1.36E-06 1.29E-06 1.2SE-06 1.20E-06 WSW 2.06E-06 1.98E-06 1.90E-06 1.83E-06 1.76E-06 1.10t-06 1.64t-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 2.330-06 NW 2.82E-06 2.71E-06 2.60E-06 2.50E-Ob 2.41E-06 2.32t-on 2.24t-06 tc4W 1 91E-06 1.83E-06 1 76E-06 1.69E-06 1.63E-06 1.57E-06 1.b2E-06 Period of Record: 4/1/77 - 3/31/78
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TABLI: A-7 (Cont.)
Prairie Island Dispersion Parameters ( X/q), sec/m ,
for Short Term Ground Level Releases 1500 lirs/Yr ori150 lirs/Qtr For Standard Distances (As FAcasured from Lige of Plant Complex)
Miles Sector 5.0 -
N 1.67E-07 NNE t . 996- 0 7 NE 8.97E-07 ENE e.76E-07 E 1.67E-06 ESE 2.4SE-06
> SE 2. 6 2 t- 06
& SSE 1.89E-06
- S 1.0SE-06 SSW 5. 3 9 E- 0 7 ;
SW 9.35E-07 '
WSW 1.27E-06 W 2.11 t- G o WNW 1.81E-06 NW 1.74E-06 NNW 1.17E-06 Period of Record: 4/1/77 - 3/31/78 G
TABLE A-8 Prairie Island Dispersion Parameters (D/q),1/m .
For Short Term Ground Level Releases $500 lirs/Yr or 5150 lirs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 0.1 0.2 0.3 0.4 0.5 0.6 0.7 N 1.68E-06 6.63 E-0 7 4.32 E-0 7 3.00 E-0 7 2.18 E-0 7 1.69 E-0 7 1.290-07 NNE' 1.13E-06 5. 4 3 E-0 7 3.46E-07 2.40E-07 1.72E-07 1.36E-07 1.030-07 NE 1 19 E-06 4.68 E-0 7 3.05 E-0 7 2.060-07 1. 4 5 E-0 7 1.14E-07 9.10 E- 0 8 ENE 1.20E-06 4.86E-07 3.17E-07 2.23E-07 1.58E-07 f.23E-07 9.49 E-0 8 (
E 2.08E-06 8.09E-07 5. 21 E-0 7 3.46E-07 2.49E-07 1.96E-07 1.54E-07 ESE 2.90E-06 1.14 E-0 6 7.17 E-0 7 4. 85 E- 0 7 3.4 5 E-0 7 2. 69 E-0 7 2.110-07
> SE 3.20E-06 1.26E-06 7.54E-07 5.08E-07 3.71E-07 2.94 E-0 7 2.31E-07 d SSE 2.09E-06 8.24E-07 5.16 E-0 7 3.41E-07 2.40E-07 1.92E-07 1.55E-01 i S 1.27E-06 5.18E-07 3.24 E-0 7 2.23E-07 1.58t-07 1.23 E-0 7 1.00E-07 l S$h 1.06E-06 4.33E-07 2.82E-07 1.92E-07 1.33E-07 1.05E-07 8.51E-Od SW 1.0 5 E-0 6 4.42 E-0 7 2.uSE-07 1.91E-07 1.31E-07 1.04E-07 8.55E-08 kSW 1.24E-06 5.19E-07 3.24E-07 2.14E-07 1.48E-07 1.19E-07 9.94E-Od W 1.90E-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 c.10L-07 4.14 L-0 7 2.99E-07 2.31 E-0 7 1. u 1 E-0 7 NW 2.30E-06 8.91E-07 5.49E-07 3.72E-07 2.73E-07 2.12L-07 1.65E-ul huh 1.79E-06 7.01E-07 4 . 4 6 E- 0 7 3.01E-07 2.21L-07 1.72E-07 1.34E-07 Period of Record: 4/1/77 - 3/31/78 ,
TAllLE A-8 (Cont.)
Prairie Island Dispersion Parameters (D/q),1/m ,
For Short Term Ground Level Releases 1500 lirs/Yr or {l50 Ilts/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 0.8 0. 9_ l.0 1.1 1.2 1.3 1.4 N 1.05 E-0 7 8.2SE-08 6. 73 E-0 8 5.55E-08 4.66E-08 3.99E-08 3.41E-Od hhE 8.35E-u8 6. 76 E-0 8 5.48E-08 4.55E-08 3.85E-08 3.29E-08 2.85E-OS NE 7.39E-08 5.99E-08 4.95E-08 4. 0 H E- 0 8 3. 3 5 E- 0 8 2. 8 7 E- 0 8 2.49E-08 ENE 7.67E-08 6.15E-08 4.97E-08 4.13 E-0 8 3.42E-08 2.93E-08 2.530-08 E 1.25E-07 9.96E-08 8.17E-08 6 79E-08 5.63E-08 4.32E-Od 4.18E-08 ESE 1.71E-07 1.38E-07 1.12E-07 9.32E-08 7.8 7 E- 0 8 6.71E-Ge 5. 86 E- 0 8 p SE 1.88E-07 1.50E-ul 1.23 E-0 7 1.02 E-0 7 8.55E-08 7.34E-Od 6.3sE-08 1.26E-07 1. 01 E-0 7 8.26E-08 6.86E-08 5.63E-06 4. 8 3 E- C t: 4.22E-6,a
& SSE 3.0 7 E-0 8 u S 8.06E-08 6.40E-08 5.16 E-0 8 4. 29 E- 0 8 3.60E-08 2.66E-Os SSk 6.87E-08 5.49E-08 4.50E-08 3.73E-08 3.00E-08 2.57E-08 2.23E-08 Sh 7.00E-08 5.41E-08 4.47E-08 3.73E-08 3.00E-08 2.57E-08 2.25E-06 WSh u.11E-08 6.49 E-08 5.32E-08 4.44E-Ou 3.59E-08 3.0 8 E-0 8 2.67t-08 h 1.21E-OF 9.57E-08 7. DOE-08 6.46E-08 5.22E-08 4.46E-08 3.86E-08 kNW 1.47E-07 1.15E-07 9.45L-08 7.80E-08 c . 54 E- 0 8 5.61E-08 4. doe-06 NW 1.J4E-07 1.07E-u7 8.78E-08 7. 30 E-0 8 6.13E-08 5.23E-08 4.>3E-08 NHk 1.08E-07 8.62E-08 6.56E-08 5.34E-08 4.82E-08 4.12E-0a 3.60E-08 Period of Record: 4/1/77 - 3/31/78
TABLE A-8 (Cont.)
Prairie Island Dispersion Parameters (D/q),1/m ,
For Short Term Ground Level Releases $500 Ilrs/Yr or $150 lirs/Qtr l
Por Standard Distances (As Measured from Illge of Plant Complex)
Miles.
t Sector 1.5 1.6 1.7 1.8 1.9 2.0 2.1 N 2. 9 8 E-0 8 2.62E-08 2.33E-08 2.08E-08 1. 8 7 t- 0 8 1.10E-Ou 1.54E-08 hhE 2.49E-08 2.20E-08 1.95E-08 1.74E-08 1.56 E-0 8 1.43E-08 1.30E-08 NE 2.17E-08 1.92E-08 1.70E-08 1.52E-08 1.37E-08 1.23E-08 1.12E-08 ENE 2.20E-08 1.94E-08 1.72E-08 1 54E-08 1.38E-08 1.25E-Og 1.13E-08 E 3.66E-08 3.24L-08 2.89E-08 2.58E-08 2.32E-08 2.11E-08 1.91E-08 ESE 5.12E-08 4.53E-08 4.0 3 E- 0 8 3. 60 E- 0 8 3.23E-08 2.9 5 E- 0 8 2. 6 8 E-0 8
> SE S.61E-08 4.96E-08 4.41E-08 3.95E-08 3.55E-08 3.21 E-0 8 2.92E-08
& SSE 3. 7 0 E- 0 8 3.27E-08 2.91E-08 2.60E-08 2.34E-08 2.10E-08 1.91E-08
^ S 2.32E-08 2.0 5 E-0 8 1.82E-08 1.63 E-0 8 1.46E-08 1.31E-Og 1.19 E-0 8 Shh 1.95E-08 1.73E-08 1.54E-08 1.38E-Od 1.24 E-08 1.10E-08 1.00E-08 Sh 1.97E-08 1.74E-08 1.54E-08 1.38E-08 1.24E-08 1.08E-08 9.86E-09 WSW 2.34E-08 2.07E-08 1.d4E-08 1.650-08 1.49E-Od 1.30E-08 1.18E-08 h 3.37E-08 2.97E-08 2.64E-08 2.36E-Ou 2.12E-08 1.95E-08 1.77E-08 kNw 4.26E-08 3. 76 E- 0 0 3.3 8 E- 0 8 3.02E-08 2.72E-08 2. 44 E- 0 8 2.22E-08 hW 3.97E-08 3.21E-08 3.12E-08 2.80E-08 2.52E-08 2.30E-Ou 2.09E-08 NHh 3.15E-08 2.78E-08 2.4bE-08 2.22E-Oh 1.990-08 1.b1E-08 1.64E-08 4
Period of Record: 4/1/77 - 3/31/78
~ - -,_ _ - . . , , - _ _ - , .:.-,,.. - - . - - - _ . . - . , . . _ . ,
TABLE A-8 (Cont.)
Prairie Island Dispersion Parameters (D/q),1/m ,
for Short Term Ground Level Releases 5500 IIrs/Yr or 5150 lirs/Qtr for Standard Distances (As Measured from rd9e of Plant Complex) 1 Miles Sector 2.2 2.3 2.4 2.5 2.6 2.7 2.8 N 1.41L-08 1.29E-08 1.19E-08 1.09E-08 1.05E-08 8.80E-09 u.23E-09 hhE 1.18E-Od 1.08E-08 9.96E-09 9.12E-09 8.70E-09 7.42E-09 6.90E-09 taE 1.02E-08 9.34E-09 8. sue-09 7.92E-09 7.61E-09 6.51E-09 6.05E-09 Ent 1.03E-08 9.45E-09 8.69E-09 7.99E-09 7. sue-09 6.56E-09 6.10E-09 E 1.74E-08 1.60E-08 1.47E-08 1.3dE-08 1.32E-08 1.13E-Od 1.05E-06 ESE 2.44E-08 2.24E-Ou 2.0$E-08 1.96E-08 1.90E-0d 1.61E-08 1. 50E-03 SE 2.o6L-08 2.43E-08 2.24E-08 2.loE-Od 2.09E-08 1.19E-08 1.06E-do y SSE 1.14E-08 1.60E-08 1.47E-08 1.39E-08 1.32E-08 1.14E-08 1.06E-08 5 1. 09 E-0 8 9.97E-09 9.17E-09 8.70E-09 8.23E-09 1.22E-09 6.73E-09
& 5.96E-09 ui SSk 9.14 E-09 U.37E-09 7.70E-09 7.37E-09 6.91E-09 3.54E-09 Sh 9.00E-09 8.25E-09 7.60E-09 7.18E-09 6. 72 E-0 9 5.98E-09 5.56E-09 WSW !.08E-08 9.89E-09 9.09E-09 8.77E-09 u.21E-09 7.20E-09 6.o9E-09 h 1.62E-08 1.48E-08 1.36E-08 1.3bE-08 1.25E-08 1.duE-08 1.00E-03 kNb 2.02E-Ou 1.86E-Ou 1.71E-08 1.59E-03 1.53E-03 1.31E-Od 1.226-08 NW 1.90E-08 1.74E-Od 1.60E-08 1.51E-Od 1.44E-Od 1.23E-08 1.14E-08 Nhk 1.50E-Od 1.37E-Ou 1.26E-Ou 1.17E-0d 1.12E-08 9.53E-09 8.uoE-09 t
l Period of Record: 4/1/77 - 3/31/78 l
l l
7-% - -- -,,. v-
TABI.T A-8 (Cont. )
Prairie Island Dispersion Parameters (D/q),1/m ,
Por Short Term Ground Level Releases iS00 lirs/Yr or 5150 lirs/Qtr For Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 2.9 3.0 3.1 3.2 3.3 3.4 3.5 N l.68E-09 7.22E-09 6.76E-09 6.35E-09 5.97E-09 5.03E-09 5.31E-09
. tJN E o.44E-09 6.04E-09 5.coE-09 5.32E-09 5.00E-09 4.72E-09 4.4oE-09 NE 5.64E-09 5.27E-09 4.94E-09 4.64E-09 4.36E-09 4.11E-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 7.32E-09 7.09E-09 c.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 9.11E-09 8.52E-09 8.00E-09 7.52E-09 7.08E-09 6.69E-09 p
8 5 6.27E-09 5.67E-09 b.31E-09 4.98E-09 4.6dE-09 4.41E-09 4.loE-09
$ SSW 5.16E-09 4.61E-09 4.32E-09 4.0bE-09 3.82E-09 3.61E-09 3.41 E- 09 SW b.18E-09 4. 74 E-09 4.45E-09 4.17E-09 3.93E-09 3.70E-09 3.50E-09 kSW 6.24E-09 5.04E-09 5.28E-09 4.96E-09 4.o7E-09 4.40E-09 4.loE-09 W 9.36E-09 8.39E-09 7.87E-09 7.40E-09 6.97E-09 6.58E-09 6.22E-09 WNW 1.13E-08 1.06E-08 9.92E-09 9.31E-09 8.76E-09 8.27E-09 7.81t-09 NW 1.0lE-08 9.88E-09 9.26E-09 8.10E-09 8.19E-09 7.72E-09 7.31E-09 tdNW 8.26E-09 7.6cE-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
TAlli.E A-8 (Gnt.)
l'rairie Island Dispersion l'arameters (D/q),1/m .
I'or Short Term Ground Level Heleases 5500 lirs/Yr or $150 lirs/Qtr l'or Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 3.6 3.7 3.8 3.9 4.0 4.1 4.2 N 5.01h-09 4.75E-09 4.50E-09 4.20E-09 4.0?E-09 3.duE-09 3. lot-09 NNE 4.22E-09 4.00E-09 3.79E-09 3.60E-09 3.42E-09 3.26E-09 3.ItE-09 NE 3.68E-09 3.49E-09 3.31E-09 3.15E-09 3.00E-09 2.d5E-09 2.12L-09 ENE 3.l1E-09 3.51E-09 3.33E-09 3.11E-09 3.01E-09 2.8TE-09 2.14E-09 E 6.33E-09 6.00E-09 5.69E-09 5.41E-09 5.15E-09 4.91E-09 +.out-09 ESE 9.02E-09 8.54E-09 8.10E-09 7.70E-09 7.32E-09 6.90E-09 6. o 6 t- 0 9
> SE 9.99E-09 _9.4aE-09 8.96E-09 8.51E-09 8.09E-09 7.70E-09 7.33t-u9 L SSE 6.33E-09 5.99E-09 5.6BE-09 5.40E-09 5.14E-09 4.90E-09 4.67E-09 9 5 3.94E-09 3.73E-09 3.54E-09 3.36E-09 3.20E-09 3.05L-09 2 . 91 E- 0 9 SSW 3.23E-09 3.06E-09 2.91E-09 2.77E-09 2.64E-09 2.51E-09 2.400-09 SW 3.31E-09 3.14E-09 2.98E-09 2.u3E-09 2.66E-09 2. 5 3 t- 0 9 2.42L-09 WSW 3.94E-09 3.73E-09 3.54E-09 3.3FE-09 3.21E-09 3.o o t-0 9 2.92L-09 W 5.u9E-09 5.59E-09 5.31E-09 5.05E-09 4.81E-09 4.590-u9 4.380 o9 WNW 7.39E-09 7.00E-09 6.64E-09 6.31E-09 6.00E-09 5.720-09 5. 4 5 L- 09 NW 6.93E-09 o. sue-09 6.23E-09 5.92E-09 5.63E-09 5.36t-09 5.1gt-o9 NNW 5.33E-09 5.05E-09 4.79E-09 4.5cE-09 4.34E-09 4.13E-09 3.94L-09 Period of Record: 4/1/77 - 3/31/78
TABLE A-8 (Cont.)
Pralrlo Island Dispersion Parameters (D/q),1/m , ,
for Short Term Ground Level Releases 5500 lirs/Yr or $150 lirs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 4.3 4.4 4.5 4.6 4.7 4.8 4.9 N 3. S 5 E-09 3. 4 0 E- 09 3.26L-09 3.1zt-09 2.99 E-0 9 2 . d l E- 0 9 2. 7 6 t- 0 5 NNE 2.9FE-09 2.84E-09 2.11E-09 2 00E-09 2.490-09 2.39E-09 2.30E-09 NE 2.60E-09 2. 4 8 E- 09 2.37E-09 2.27E-09 2.18E-09 2.09E-09 2.01E-G9 ENE 2.61E-09 2.49E-09 2.39t-09 2.29E-09 2.190-09 2.100-09 2.02L-09 E 4.4dE-09 4.28E-09 4.10E-09 3.93E-09 3.77E-09 3.62E-09 3.47E-09 ESE 6.35k-09 6.076-09 5. 81 t- 09 b.57t-09 5.34t-09 5.136-09 4.92E-09 SE b .99 E-0 9 6.6 8 E-09 6.38L-09 0.12E-09 5.860-09 5.62E-09 5.38L-09
> SSE 4.48E-09 4.2bE-09 4.10E-09 3.93E-09 3.7dE-09 3.63E-09 3.48E-09 1 5 2.78E-09 2.65E-09 2.54E-09 2.4 3 E- 09 2.34t-09 2.z4 E-09 2.1SL-09
- SSW 2.30E-09 2.20E-09 2.11t-09 2.02E-09 1.940-09 1.66E-09 1.19E-u9 SW 2.31E-09 2.21E-09 2.12E-09 2. 03 E- 09 1.95E-09 1.870-09 1.80E-09 WSW 2.J9L-09 2.67E-09 2.55E-09 2.450-09 2.33t-09 2.24E-09 2.150-09 W 4.19E-09 4.01E-09 3.d4E-09 3.69E-09 3.54E-09 3.40E-09 3.z?E-09 WNW 5. 20 E-0 9 4.98 E-09 4. 76 E- 09 4.57t-09 4. .s 0 t- 0 9 4.210-09 4 . 0 4 L- 0 9 NW 4.88E-09 4.66E-09 4.44 E-09 4.25L-09 4.0 0 E-09 3.92L-09 3.?lt-09 NNW 3.76E-09 3.60E-09 3.43E-09 3.29E-09 3.16E-09 3. 03 E- 09 2.91E-09 Period of Record: 4/1/77 - 3/31/78
TABLE A-8 (Cont.)
Prairie Island Dispersion Parameters (D/q), I'm ,
For Short Term Ground Level Releases 5500 lirs/Yr or $150 lirs/Qtr for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 5.0 N 2.oSL-09 NNE 2.21E-09 NE 1.93E-09 l ENE 1.94t-09 E 3.34E-09 ESE 4.73E-09
> SE b.17E-09
& SSE 3.35E-O's
'8 S 2.07E-09 SSW 1.73E-09 SW 1.7sE-09 WSW 2.07E-69 W 3.15E-09 WNW 3.89E-09 NW 3.63E-09 NNW 2. DOE-03 i
Period of Record: 4/1/77 - 3/31/78
APPENDIX - B Prairie Island 12.2m Wind and AT 42 . 7-12 . 2 m Stability Joint Frequency Distributions (4/1/77 - 3/31/78) 9 B-1
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PAGE 170 -- -- -
NO2THERN STATES POWER Cor1P ANY - PR ISLAND NUCLEAR GENERATING PLANT SI 11ETEOROLOGY - FREQUENCY DISTRIEUTION TACLES L TE_.. _ . . - - - . _ . . . ... . .. . . ... . __. _ . .-
HOURS AT EACH WIND SPEED AND DIRECTION PEQlOD: 4/ t/77 THROUGH 3/31/78 STASILITY CLASS B ELEVATION 40 FT
- - . ~ . - - - -W I NO. SEE E D 4 M AH l AT__4 4 . FJ. - . L E VE L. ~. - - - - . -_ . . - . _ - - - . - - - . . . - .
DIRECTION I TO 3 4 TO 7 4 TO 10 13 TO IS 19 TO 04 ABOVE 24 TOTAL N 0 3 S I O O 9 7 _ _ ~ N N E - ~ - . . - I - - .-- * ~1...-~.-.&._. S ....0.,..-. .S --..__.---- - -.---. . - - - . . . . .
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NW. : 4 11 10 1 0 es NNW I S 3 1 0 1 11 VAR 0 0 0 0 0 0 0 TCTAL HOURS THIS CLASS , 191 H;U;S OF CALM THIS CLASE ..
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PAGE 100 .
N33THERN CTATES PCWE2 C7MPANY - P2 ICLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND GPEED AND DIRECTION l
PERIOD: 4/ 1/77 THROUGH 3/31/78 3TABILITY CLASS D ELEVATION 40 rT
.. ......_ _.. . MIND _SEEED At1RMn.AT.,AA..ET.. LEVEL . .. -- .. -. . _- _ . . _ _ . . . . . . . . . . . . . . . . . . _
DIRECTION 1 TO 3 4 TO 7 a TO 10 13 TO IS 19 TO 04 ABOVE 04 TOTAL N 9 04 11 8 0 0 50 NNE. . 4__ ' ' '
9..... 0 .0 O_. 37.
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0 46 ENE 13 41 4 0 0 0 56 E 11 95 27 0 0 0 133
.-..ESE. _...A. 5Z.. .... 151 . . . 1 9 . . . .. O. . O _ __ . 0 3 8 . . .. . . . . . .. . . _ . ._.
SE 10 '30 90 38 5 0 '73 '
SSE 5 40 59 51 10 0 I68
'S 1 51 TO 17 4 0 145 SSU 5.. . 09_ ._. 30. .10 . . 0 .0 .. 76. .. - - - . . .
SW 4 85 17 4 0 0 40 WS4 E 23 34 01 3 4 07 4 4 54 el OS. 6 1 155
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~NH 14 44 70 110 41 0 .081
-W NNW 14 00 41 05 13 0 117 b VAR 0 0 0 0 0 0 c 0 TCTAL HOURS THIS CLASS 2051 HIURS OF CAL.N THIS CLASS 4 PECCEMT.0F. ALL DATA.THIR. CLASS _ ... _.- 24.49 . . . . . . . . _ . . . . . . _ . . . .
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APPENDIX C DOSE PAR AMETERS FOR R ADIO!ODINES,' PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radiciodines, particulates, and tritium to show compliance with 10 CFR 20 and Appendix ! of 10 CFR 50 for gaseous effluents. These dose parameters, P and g
R , were calculated using the methodology outlined in NUREG-0133 along with Regulatory Guide 1.109 Revision 1. The following sections provide the specific methodology which was utilized in calculating the P g and R; values for the various exposure pathways.
C.I Calculation of P.
1 The parameter, P;, contained in the radiciodine and particulates portion 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 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.I.1 _ Inhalation Pathway Pj =
K'(BR) DFA i (c.1-1) where:
Pj =
dose parameter for radionuclide i for the inhalation pathway, mrem /yr per Ci/m3; C-1 Rev. 2
a Ill AW K' = a constant of unit conversion:
= 106 pCi/pCi; ER = the breathing rate of the infant age group, m3 fy,;
DFA; = the maximum organ inhalation dose factor for the infant age group for radionuclide i, mrem /pCi.
The age group considered is the infant group. The infant's breathing rate is taken as 3
1400 m /yr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the infant, DFA ,3are presented in Table E-10 of Regulatory Guide 1.109 in units of mrem /pCl. The total body is considered as an organ in the selection of DFA;.
The incorporation of breathing rate of an infant and the unit conversion factor results in the following:
9 P.
ig
= 1.4x10 DFA. (c.1-2) i C.2 Calculation of R.
1 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 considered based on their existence at the varicus locations. R; values have been calculated for the adult, teen, child, and infant age groups for the ground C-2 aev. 2
plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below.
C.2.1 Inhalation Pathway
=
R; K'(BR)a (DFA;)a (C.2-1) where:
R;I
= dose factor for each identified radionuclide i of the organ of interest, mrem /yr per pCi/m ;
K' = a constant of unit conversion;
= 106 pCi/pCi; (BR)a = breathing rate of the receptor of age group a, m /yr:
(DFA;)a = rgan inhalation dose factor for radionuclide i for the receptor of age group a, mrem /pCi.
The breathing rates (BR)a f r the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109 Revision 1. -
Age Grouo (a) Breathine Rate (m3 /yr)
Infant 1400 Child 3700 Teen 8000 Adult 8000 inhalation dose factors (DFA;)a f r the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.
C-3 Rev. 2
=. , . . -
c.2.2 Ground Plane Pathway R; =
I; K'K"(SF)DFG; (1-e I )/y (c.2-2) where:
R. = dose factor for the ground plane pathway for each identified
'G radionuclide i for the organ of interest, mrem /yr per pCi/sec per m -2; K' = a constant of unit conversion;
= 106 pCi/pCi; K" = a constant of unit conversion;
= 8760 hr/ year; A = the radiological decay constant for radionuclide i, sec-I ;
t = the exposure time, sec; 8
= 4.73x10 sec (15 years);
DFG; = the ground plane dose conversion factor for radionuclide i; mrem /hr per pCi/m2; SF = the shielding factor (dimensionless);
I I I; = factor to account for fractional deposition of radionuclide i.
l l For radionuclides other than iodine, the factor I; is equal to one. For radiciodines, the value of I; may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3 2.
y C-4 Rev. 2 I
A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109 Revision I. A tabulation of DFG; values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1.
s C.2.3 Grass-Cow or Goat-Milk Pathway
-A -A t
~Alf t -
-(1-e r E;te) . B;y (1-e i b) -
R; = I; K' QF Uap Fm (DFL;)a
- II
- ps Y Pg _
-A t
- B;y (1-e b -A;th '
I ) - r(1-eY A i *)
(I-I ps, +
PA; (C.2-3) s E. _ ,
I where:
R; = dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, mrem /yr per pCi/sec per m-2 ;
e K' = a constant of unit conversion;
= 106 pCi/gCi; Qp = the cow's or goat's feed consumption rate, kg/ day (wet weight);
U = the receptor's milk consumption rate for age group a, liters /yr; 3p Y = the agricultural productivity by unit area of pasture feed grass,
. P ,
kg/m';
2 Y = the agricultural productivity by unit area of stored feed, kg/m ;
s F = the stable element transfer coefficients, pCi/ liter per pCi/ day; m ,
r = fraction of deposited activity retained on cow's feed grass; (DFL;)a = the organ ingestion dose factor for radionuclide i for the receptor in age group a, mrem /pCi; C-5 Rev. 2
- *,r e-
A A E.
i+ wI 1
- A; = the radiological decay constant for radionuclide i, sec-I ;
A, = the decay constant for removal of activity on leaf and plant ,
surf aces by weathering, sec-I; !
I
= 5.73x10-7 sec -I (corresponding to a 14 day half-life);
t = the transport time from feed to cow or goat to milk, to receptor, f
sec; t = the transport time from harvest, to cow or geat, to consumption, h
sec; t = Period of time that sediment is exposed to gaseous effluents sec; b
B;y = concentration factor for uptake of radionuclide i from the soil by ,
the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry _
soil);
2 P = effective surface density for soll, Kg (dry soil)/m ;
fp = fraction of the year that the cow or goat is on pasture; ,
f = fraction of the cow feed that is pasture grass.while the cow is on s
pasture; t,
= period of pasture grass and crop exposure during the ' growing season, sec; -
I; = factor to account for fractional depositiers of radionuclide i.
C-6 Rev. 2 l- , , ._
For radionuclides other than iodine, the factor I; is equal to one. For radiciodines, the value of I; may 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 swas considered unity in lieu of site-specific information. The value of f was 0.667 based upon an S-month grazing period.
p 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 :
R =
K'K'"F m9 UF ap(DFL;)a 0.75(0.5/H) (C.2-4)
Tg where:
R = dose factor for the cow or goat milk pathway for tritium for the T
M 3 organ of interest, mrem /yr per gCi/m ;
K"' = a constant of unit conversion;
= 103 gm/kg; I !
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..
3 and other parameters and values are given above. A value of H of 8 grams / meter , was used in lieu of site-specific information.
9 C-7 , Rev. 2
C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:
-A
-A;t s
~
r ft-e E;te) . B;y (1-e i*b) -
II R;M = 1; K' Qp Uap Fm (DR;)a *
- ps - YpA P A*. ~
E.
-A t B II-, ib)- t (C.2-5) f } .(1-eY A i *)
r iv (1-fps
- P A. -
s E. 1 I
where: -
= dose factor for the meat ingestion pathway for radionuclide i for R;0 any organ of interest, mremlyr per C1/sec per m-2; l
Fg = the stable element transfer coefficients, pCi/Kg per pCi/ day; U ap = the receptor's meat consumption rate for age group a, kg/yr; t
s
= the transport time from slaughter to consumption, sec; t
h
= the transport time from harvest to animal consumptien, sec; t, = period of pasture grass and crop exposure during the growing season, sec; I; = factor to account for fractional deposition of radionuclide i.
1 For radionuclides other than iodine, the factor I; is equal to one. For radiciodines, the value of 1; may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3.3-8.
4 C-8 Rev. 2
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; for the meat pathway The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R; is based on X/Q.
R T
=
K'K"'Ffp Q U,p(DFL;)a 0.75(0.5/H) (C.2-6)
B where:
R T
= dose factor for the meat ingestion pathway for tritium for any B
organ of interest, mrem /yr per pCi/m3 .
All other terms are defined in Equation C.2-4 and C. '-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:
~A i b) ,
U f g e -AI t' - '(I~*f gEI *e)
BI " (1-e
+
R;V = I; K'(DFL;)a g v E. 4 1
-A i B;y (1-e"A *b) . - i
~ Ai *h r(1-e E;te)
U ,Sfg e y A
+
p y, (C.2-7) <
v E; .1 .
where:
E R.
8
= dose factor for vegetable pathway for radionuclide i for the organ V
of interest, mrem /yr per pCi/sec per m-2; K' = a constant of unit conversion; '
= 106 pCi/pCi; C-9 Rev. 2
~
U', = the consumption rate of fresh leafy vegetation by the receptor in age group a, kg/yr; U ab = the consumption rate of stored vegetation by the receptor in age group a, kg/yr; fg = the fraction of the annual intake of fresh leafy vegetation grown locally; f = the fraction of the annual intake of stored vegetation grown g
locally; t
g = the average time between harvest of leaty vegetation and its consumption, sec; t
h
= the average time between harvest of stored vegetation and its consumption, sec; 2
Yy = the vegetation areal density, kg/m ,
t,
= period of leafy vegetable exposure during growing season, sec; I; = factor to account for fractional deposition of radionuclide i. ,
For radionuclides other than iodine, the factor I; is equal to one. Fcr radioiodines, the value of I; may vary. However, a value of 1.0 was used in All other factors were defined above.
Table c-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.
C-10 -Rev. 2
In lieu of site-specific data default values for f and fg,1.0 and 0.76, respectively, were used in the calculation of R;. These values were obtained from Table Regulatory Guide 1.109 Revision 1.
The concentration of tritium in vegetation is based on the airborne conce rather than the deposition. Therefore, the R;~ is based on X/Q:
R = K 'K "'
T V -
UfL+Uf8* (DFL;)a 0.73(0.5/H) (C.2-8) where:
R =
T V dose factor for the vegetable pathway for tritium for any orga
, interest, mrem /yr per gCi/m3.
All other terms remain the same as those in Equouons C.2-4 and C.2-7.
(
1 i
t Rev.'2
TABLE c-1 Parameters For Cow and Goat Milk Pathways Parameter Value Reference (Rec. Guide 1.109 Rev. l' QF (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 Yp (kg/m ) 0.7 Table E-15 f
f (seconds) 1.73 x 10'. (2 days) Table E-15 f r 1.0 (radiciodines) Table E-15 0.2 (particulates) Table E-15 (DFL;)a (mrem /PCI) Each radionuclide Tables E-11 tc E-14 Fm (PCi/ day per pCi/ liter) Each stable element Table E-1 (cow)
Table E-2 (goat) t b (seconds) 4.73 x 108 (15 yr) T.'.ble E-15
~
2 Ys (kg/m ) 2.0 Table E-15 2
Yp (kg/ra ) 0.7 Table E-15 t
h (seconds) 7.78 x 100 (90 days) Table E-15 .
U ap (liters /yr) 330 infant Table E-5 330 child
- Table E-3 400 teen Table E-5 310 adult Table E-3 t, (seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 10 (stored feed)
B;y (pCi/Kg (wet weight) Each stable element Table E-1 per pCi/Kg (dry soil))
P (Kg (dry soil /m2 ) . 240 Table E-15 C-12 Fev. 2
TABLE c-2 Parameters For The Meat Pathway Parameter Value Reference (Rec. Guide 1.109 Rev.1) r 1.0 (radiciodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/Kg per pCi/ day) Each stable element Table E-1 U ap (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL;)a (mrem /PCI) Each radionuclide Tables E-II te E-14 2 Table E-15 Yp 0.7 (kg/m )
2 Table E-15 Ys (kg/m ) 2.0 t
4.73 x 108 (l5 yr) Table E-15 b (seconds) t 1.73 x 106 (20 days) Table E-15 s (sec nds) t 7.78 x 100 (90 days) Table E-15 h (seconds) t,(seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 106 (stored feed)
Qp (kg/ day) 50 Table E-3 B;y (pCi/Kg (wet weight) Each stable element Table E-1 per pCi/Kg (dry soil))
2 Table ' E-15 P (Kg (dry soil)/m ) 240 c-13 Rev.-2
TABLE c-3 Parameters for the Vegetable Pathway Parameter Value Reference (Ree. Guide 1.109 Rev.1 r (dimensionless) 1.0 (radiciodines) Table E-1 0.2 (particulates) Table E-1 (DFL;)a (mrem /Ci) Each radionuclide Tables E-Il to E-14 U (kg/yr) - Infant 0 Table E-5
- Child 26 Table E-5
- Teen 42 Table E-5
- Adult 64 Table E-3 Uf (kg/yr) - Infant 0 Table E-3 -
- Child 520 Table E-5
- Teen 630 Table E-5
- Adult 520 Table E-5 t
L (seconds) 8.6 x 10 (1 day) Table E-15 -
t 5.18 x 106 (60 days) Table E-15 h (seconds)
Y y (kg/m ) 2.0 ' Table E-15 t,(seconds) 3.18 x 10 (60. days) Table E-15 t
.b (seconds) 4.73 x 10 8 (15 yr) Table E-15 P(Kg(dry soil)/m2) 240 Table E-15 B;,,(pCi/Kg(wet weight) Each stable element Table E-1 per pCi/kg (dry soil))
C-14 Rev. 2