Text

Rev 10 to, Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual (Odcm)
	ML20246P131
Person / Time
Site:	Prairie Island
Issue date:	04/27/1989
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20246K241	List: ML20246K236; ML20246P061; ML20246P074; ML20246P098; ML20246P109; ML20246P113; ML20246P131; ML20246Q233;
References
	PROC-890427, NUDOCS 8909110050
	Download: ML20246P131 (127)
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H4 Rev. 10 Page 1 of 127

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1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) l DOCKET NO. 50-282 and 50-306 l

l NORTHERN STATES POWER COMPANY i

i i

MINNEAPOLIS, MINNESOTA l

I OPERATIONS COMMITTEE FINAL REVIEW DATE: h 2[- @h' REVIEWED BY:

b

~4h DATE:

T,2 7 - f 'f

)

DATE: M.2.2 - P 7 APPROVED BY:,/

r/

l IBM 8909110050 890828 PDR ADOCK 050002B2 i

R PDR l

Iy.

p H4 K

Rev.=10-Page 2-TABLE OF. CONTENTS Sectionc Title' Page Table of Contents..................................

2 l-i Li s t o f : F i gu r e s.................................... 3 L

' Li s t - o f Table s..................................... 4 -

Record of Revisions.................................5:

1 1=. 0 - ' I N T R O D U C T I O N................................................. 6 3

12'.0L ~ LIQUID EFFLUENTS...............r..............................6 2.1 iMonitor, Alarm Setpoint determination....................

6L

2.2 ; Liquid Effluend Concentre ico - Compliance

with 10 CFR 20..........

............................... 15

.2.3 : Liquid. Effluent' Doses - Compliance with

.10 CFR 50.............................................. 16-References.............................................

20 3.0 GASEOUS EFFLUENTS............................................

23 3.1 : Monitor Alarm Setpoint Determination...................

23 3.2--Gaseous Effluent Dose Rate - Compliance with

. 10 CFR 20..............

................................29

.3.3' Gaseous Effluent Doses - Compliance with 10 CFR 50.............................................. 33 References..............................................38 INFORMATION. ELATED TO 40 CFR 190 and 40 CFR 141............

59 R

4.0 5.0-RADIATION ENVIRONMENTAL MONITORING PROGRAM..................

61 APPENDIX A - Meteorological Dispersion Parameters........... 69 APPENDIX B - Joint Frequency Distribution Tables...........

108 y

APPEND 1X C - Dose Parameters for Radiciodines, Particulate and Tritium......................

116 IBM.

m- _ _ - - - - - - - - - _ - - - - _. - -

H4 Rev. 10 age 3 4'

LIST OF FIGURES t

Figure Page 5.1-1 Prairie Island. Nuclear Generating Plant Radiation Environmental Monitoring Program........

66 5.1-2 Site Boundary TLD Locations..........

........... 67 5.1-3 4-5 Mile Ring, Control, and Special Inte re s t TLD Loc a t ions............................ 6 8 I

l l

l.

IBM

H4 Rev. 10 7([

LIST OF TABLES

. Tables Page 2.1-1 Liquid Source Terms for PINGP.....................

14 2.3-1 A Values for the PINGP...........................

21 g

3.1-1 Monitor Alarm Setpoint Determination for PINGP.... 27 3.1-2 Gaseous Source Terms for PINGP....................

28 3.1-3 Dose Factors and Constants........................

29 3.2-1 P Values for the P1NGP...........................

32 g

3.3-1 Dose Factors for Noble Gases and Daughters........ 39 3.3-2 R Values for the PINGP - Ground, All Ages........

40 g

3.3-3 R Values for the PINGP - Vegetable, Adult........

41 g

3.3-4 R Values for the PINGP - Vegetable, Teen.........

42 g

3.3-5 R Values for the PINGP - Vegetable, Child........

43 g

3.3-6 R Values for the PINGP - Meat, Adult............. 44 g

3.3-7 R Values for the PINGP - Meat, Teen.............. 45' g

3.3-8 R

Values for the PINGP - Meat, Child.............

46 g

3.3-9 R Values for the PINGP - Cow Milk, Adult.........

47 g

3.3-10 R Values for the PINGP - Cow Milk, Teen..........

48 g

3.3-11 R Values for the PINGP - Cow Milk, Child.........

49 g

3.3-12 R; Values for the PINGP - Cow Milk, Infant........

50 3.3-13 R

Values for the PINGP - Goat Milk, Adult........

51 g

3.3-14 R Values for the PINGP - Goat Milk, Teen.........

52 g

3.3-15 R Values for the PINGP - Goat Milk, Child........

53 j

3.3-16 R. Values for the PINGP - Goat Milk, Infant.......

54 1

3.3-17 R Values for the PINGP - Inhalation, Adult.......

55 g

3.3-18 R

Values for the PINGP - Inhalation, Teen........

56 g

3.3-19 R

Values for the PINGP - Inhalation, Child.......

57 g

3.3-20 R. Values for the PINGP - Inhalation, Infant...... 58 1

5.1-1 PINGP - Radiation Environmental Monitoring Program Sampling Locations........................

62 IBM

H4 Rev. 10 Page 5 RECORD OF REVISIONS Revision No.

Date Reason for Revision Original June 7, 1979 1

April 15, 1980 Incorporation of NRC Staff comments and correction of miscellaneous errors 2

. August 6, 1982,

Incorporation of NRC Staff comments 3

February 21, 1983 Change in milk sampling location 4

November 14, 1983 Change in milk sampling location and change in cooling tower blowdown 5

March 27, 1984 Change Table 3.2-1 6

February 14, 1986 Change in location to collect cultivated crops (leafy green veg.) and removal of meat animals from the land use census.

7 July 31, 1986 Retype and format ODCM.

No change in content.

8 January 8, 1987 Addition of Discharge Canal Monitor Setpoint calculation.

9 June 29, 1987 Change inhilation dose factor to child and address change in land use survey.

10 April 27, 1989 Change in method for calculating liquid effluent monitor setpoints.

Fix of various typing errors.

Change in location of two REMP sampling locations.

Deletion of one REMP sampling location.

1BM

H4 Rev. 10 Page 6

1.0 INTRODUCTION

1 This Offsite Dose Calculation Manual (ODCM) provides the information and methodologies to be used by the Prairie Island Nuclear Generating Plant (PNGP) to assure compliance with certain portions of PNGP's Operating' Technical Specification.

These portions are those related to liquid and gaseous radiological effluents.

They are intended to show compliance with 10 CFR 20, 10 CFR 50.36A, 10 CFR 50, Appendix A (GDC 60 & 64) and Appendix 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 Specifica-tions for Nuclear Power Plants (NUREG-0133, October 1978),"

and other inputs from the Nuclear Regulatory Commission (USNRC).

Specific plant procedures for implementation of this manual are provided elsewhere.

These procedures will be utilized by the operating staff of the PNGP to assure compli-ance with the Technical Specifications.

Also included in this manual is information related to the Radiological Environmental Monitoring Program (REMP) in the form of Figures 5.1-1, 5.1-2, 5.1-3 and Table 5.1-1.

These figures and table designate specific sample types and locations currently used to satisfy the technical specification require-ments for the REMP.

They are subject to change based on the results of the periodic land use census.

Although the ODCM has been prepared as generically as possible in order to minimize the need for future revisions, some changes to the ODCM may be required in the future.

Any such changes will be properly reviewed and approved as required by the PNGP Technical Specifications.

2.0 LIQUID EFFLUENTS 2.1 Monitor Alarm Setpoint Determination This procedure determines the monitor alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released at the site boundary exceeds the concentrations specified in 10 CFR 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2 x 10-4 pCi/ml for dissolved or entrained noble gases.

Since re-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the liquid monitor setpoint determinations should be completed using the most recent available composite sample results.

IBM

H4 Rev. 10 Page 7 Monitor high alarm or isolation setpoints will be established in one of these ways:

a.

Monthly calculation of setpoints using the methodology of Sections 2.1.1 and 2.1.3.

b.

Calculation of alarm setpoint based on analysis prior to discharge using methodology of Section 2.1.2.

c.

Alarm setpoint determined using methodology of Sections 2.1.1 and 2.1.3 assuming all radionuclides have an MPC of lE-7 pCi/ml.

No recalculation of setpoints is necessary unless an increase in alarm setpoint is desired.

PWR GALE Code source terms (Table 2.1-1) may be used if there were no detectable isotopes in the previous month or in the analysis prior to release.

If the newly calculated aetpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value.

If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value.

2.1.1 Liquid Effluent Monitor Setpoints The following method applies when determining the isolation setpoints for the Waste Effluent Liquid Monitor (R-18), Steam Generator Elowdown 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.

2.1.1.1 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 the activity concentrations (ACi) of all non-gamma emitters iacluding H-3, Sr-89, Sr-90, Fe-55, and alpha activity.

)

IBM I

i

H4 Rev. 10 Page 8 c.

DetermineNGF (the total fraction-jl of the MPC in the liquid effluent)

-for all.non-gamma emitting nuclides.

ACi NGF = g MPCi (2.1-1) i where:

ACi-= Activity concentration of nuclide 'i' in the liquid

)

effluent (pCi/ml).

MPci = The liquid effluent radioactivity concentration limit for radionuclides 'i' (pCi/ml).from Table 2.1-1 or Reference 3.

d.

Determine Si (the fraction of the gamma emitting radioactivity in the liquid effluent comprised by radionuclides 'i') for each

-individual radionuclides in the liquid effluent.

Si =

Ai Ai (2.1-2)

}{

where:

Ai =

the radioactivity of gamma emitting radionuclides 'i' in the liquid effluent.

Determine WGF (the sum of fractional e.

activities weighted by the MPC) for the gamma emitting nuclides.in the liquid effluent.

WGF= Si MPCi (2.1-3) i 1 where: MPCi = The liquid effluent radioactivity concentration limit for radionuclides 'i' L (pci/ml) from Table 2.1-1 or Reference 3. l I l IBM

H4 4 Rev.-10 b I Page 9

2.1.1.2 Determine C -(the maximum acceptable total radio $ctivity concentration of gamma u

emitting.nuclides in the liquid effluent prior to dilution;(pCi/ml). x [- F' (2.1-4) ~~ C.= l- - NGF t WGF ( f F ~ F = Dilution water flow rate (gpm) P where: = 67,306 gpm from' cooling tower blowdown f'= The maximum attainable. discharge flow rate prior to dilution (gpm)1 l- = 60 gpm from the ADT tank pump (2). = 100 gpm from the CVCS tank pump (2) l' = 60 gpm from the SGBD tank pump (2) 2.1.l'.3 Determine C.R. (the calculated monitor L count rate above background attributed to the radionuclides (nepm)). 1 C.R. is'obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate that corresponds to-the " adjusted" total radioactivity concentration (C )'t 2.1.1.4 Determine HSP (the monitor high alarm-l setpoint above background (nepm)). HSP = T C.R. (2.1-5) l m T* = Fraction of the radioactivity from L the site that may be released via each release point to ensure that the site boundary dose rate limit is not exceeded due to simultaneous releases from several release points. = 0.90 for the Waste Effluent Liquid Monitor (R-18) = 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 1 (lR-19) = 0.05 for the Steam Generator Blowdown l Liquid Monitor - Unit 2 (2R-19) IBM i '"1'----- --.m_

H4 Rev. 10 Page 10 T values may be revised from the I v31ues given above. The summation of all the T values for active release poinEs shall not be greater than unity. 2.1.1.5 The monitor high alarm setpoint above background (ncpm), shall be set at or below the HSP value. 2.1.2-Setpoint Based on Analysis of Liquid Prior to Discharge (Optional) This method may be used in lieu of the method in Section 2.1.1 to determine the setpoints for the maximum acceptable discharge flow rate prior to 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 (1R-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19), during all operational conditions. 2.1.2.1 Determine f (the maximum acceptable discharge flow rate prior to dilution (gpm)). I f = 0.8 F Tm C (2.1-6) ~,, i MPC.1 i F = Dilution water flow rate (gpm) 67,300 gpm from cooling tower blowdown = C. = Concentration of radionuclides "i" in 1 the liquid effluent prior-to dilution (pCi/ml) from analysis of the liquid effluent to be released. MPC. = The liquid effluent radioactivity concentration limit for radionuclides 1 "i" (pCi/ml) from Table 2.1-1 or if not listed in Table 2.1-1 from Reference 3. T* = Fraction of the radioactivity from the site that may be released via each release point to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points. Refer to Section 2.1.1.4. IBM

i H4 I l Rev. 10 Page 11 l - ' ~ 2.1.2.2 Determine the monitor setpoint based on j the radionuclides mix of the liquid effluent. a. Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (nepm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radia' tion Monitor Calibration file. C.R. is the count rate point'that corresponds to the " adjusted" total radioactivity concentration (C )* t C = The total radioactivity concen-t tration of the radionuclides (minus tritium and other radionuclides that are only beta emitters) in the liquid discharge prior to dilution (pCi/ml) as determined using Equation 2.1-4. b. Determine HSP (the monitor high alarm setpoint above background (nepm)). HSP = C.R. (2.1-7) 0.8 0.8 : A correction factor to increase the monitor setpoint to prevent spurious alarms caused by deviations in the mixture of radionuclides that affects monitor response. The ronitor high alarm setpoint c. above background shall be set at or below this HSP value when this optional method is selected. The maximum discharge flow shall not exceed the value of f as determined in Section 2.1.2.1 when this optional method is selected. 2.1.3 Discharge Canal Monitor The following method determines the high alarm setpoint for the Discharge Canal Monitor (R-21) during all operational conditions. j IBM

w W 'H4 Rev. 10 h PageL12 '2.1.3.1 Determine the " mix" (radionuclides:and l l composition) of-theJ11guid effluent. a. Determine the liquid source terms that are representative'ofsthe ~ " mix" of all liquids released into-the discharge canal. Liquid source-terms are the total curies:of each isotope released ~during the previous month. -Table-2.1-1 source terms may be used if: there -have been no liquid releases. b. Determine.the activity concentrations ~ '(ACi) of all non-gamma emitters including H-3, Sr-89, Sr-90, Fe-55, and alpha activity, c. Determine NGF'(the total-fraction of the MPC in the liquid released to the discharge canal) for all.non-gamma emitting nuclides. The volume used to calculate the non-gamma emitting activity concentrations is the volume released via. cooling tower blowdown during a one month period at the minimum flow rate of 67,300 gpm. NGF. = ACi MPCi i Activity. concentration'of where: ACi = nuclide 'i' released to the discharge canal (pci/ml) The liquid effluent MPCi = radioactivity concentration l l limit for radionuclides 'i' (pCi/ml) from Table 2.1-1 or Reference 3. d. Determine Si (the fraction'of the gamma emitting radioactivity in the liquid released'to the discharge canal comprised by radionuclides 'i')-for each individual radionuclides released to the discharge canal. 1 i IBM i

H4-Rev. 10. Page 13 .,7 Si = ' Ai bi The radioactivity of gamma where: Ai emitting radionuclides 'i' . released to the discharge canal-. e. Determine WGF (the sum.of fractional' activities weighted by the MPC) for the gamma emitting nuclides released-to the discharge canal. WGF- = Si MPCi i The liquid effluent where: MPCi = radioactivity concentration limit for radionuclides 'i' (pCi/ml) from Table 2.1-1 or Reference 3. 2.1.3.2 Determine C (the maximum acceptable total radioactivity concentration of gamma emitting nuclides released to the discharge canal (pCi/ml)). Ct = l-NGF WGF 2.1.3.3 Determine C.R. -(the calculated monitor count rate above background attributed to the radionuclides (nepm)). l C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate that corresponds to the " adjusted" total radioactivity concentration (Ct). 2.1.3.4 The monitor high alarm setpoint above background (nepm) shall be set at or below the C.R. value. IBM l

k I H4 Rev. 10 Page 14 I TABLE 2.1-1 LIQUID SOURCE TERMS j WASTE-EFFLUENT SGBD RADIONUCLIDES MPC (pCi/ml) (A.)(Ci/Yr) (A.)(Ci/Yr) .Mo-99 4E-5 6.42E-3 1.415E-2 1-131 3E-7 3.061E-2 4.11E-2 Te-132-2E-5 2.11E-3 3.61E-3 1-132 8E-6 2.83E-3 1.88E-2 1-133 1E-6 2.365E 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 1.862E-2 Cs-137 2E-5 8.214E-2 2.69E-2 All Others 1E-7 0 2E-5 H-3 3E-3 1.89E2 1.41E2 Noble gases 2E-4 Total 1.894E2 .1.'412E2 IBM

H4-Rev. 10 Page 15 2.2 Compliance With 10 CFR 20 t In order to comply with 10 CFR 20, the concentrations of~ radionuclides in liquid effluents will not exceed the maximum permissible concentrations (MPC) as defined in Appendix.B, Table 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 wil'1 be calculated using these r'esults. 2.2.1 Continuous Releases Continuous liquid releases can occur from PNGP through steam generator blowdown. The alarm trip setpoints discussed in Section 2.1 will assure that releases from this pathway will not exceed the limits of 10 CFR 20. Other minor releases of a continuous nature have occurred at PNGP through the turbine building sump system. These releases were minor and are not expected to occur in the future. However, a continuous composite sampler will be maintained 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 cont.ent of each batch release will be determined prior to release. The concentration of the various radionuclides in the batch release prior to dilution, is divided by the minimum dilution flow to obtain the concentration at the site boundary. This calculation is shown in the following equation: C R f (2.2-1) Conc. = 1 @F where Conc. = concentration of radionuclides i at the 1 site boundary, pCi/ml; IB.P i

1 H4 Rev. 10 .Page 16-p 1-C- = concentration ~of' radionuclides-i in the i y ~ potential batch release, pCi/ml; R. = release rate'of the batch -MDF = minimum dilution flow (=67,300 gpm) 1The projected concentration'at the site' boundary' is compared to the MPCs in Appendix B, Table 11' of 10'CFR 20 which are given in Table 2.1-1. L 'Before a release may occur,' Equation 2.2-2 must be-met for all isotopes.' Conc i i MPC 0.9 (2.2-2) f Maximum permissible concentration MPC. = 1 of radionuclides i from. Appendix B, Table 11 of 10 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 i all source terms shall not be greater _than 1.0 of the 10 CFR 20 limit. 2.3 Liquid Effluent Doses - Compliance with 10 CFR 50 Doses resulting from liquid effluents will be calculated monthly.to show compliance with 10 CFR 50. A cumulative 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. L Since Fe-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the monthly liquid effluent dose calculations.and comparisons to quarterly and annual limits should be' completed using the most recent available composite sample results.- The quarterly and annual dose calculations shall be completed using the actual composite sample results. 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 se?arate 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 I will be doubled. ~1BM

w-H4 Rev. 10 -Pagef17' 2.3.1 Determination of Liquid Effluent Dilution-d l 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. U The dilution factor is determined by: 1 L R.k.

(2.3-1)

F = k-X ADFk l where release rate of the batch or R = k continuous releases during the-period, k, gal; actual dilution flow during the- .ADF = k time period'of release k, gal.- The value.of X is the site specific factor for. the mixing effect of the PNGP discharge structure. This value is 10 for PNGP while (1) operating in the closed cycle cooling mode. Us limited.to'1000 TheproductofXandADFThIre: fore, since blowdown cfs (4.5.x 10 gpm). flow in closed cycle is 150 cfs, the5 denominator of Equation 2.3-1 is always 4.5 x 10 in closed cycle. In once through or helper mode,1the 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 E following equation: where: DT = IIA t C F (2.3-2) g7 k ik y k1 where: the dose commitment to the total Dr = body or any organ I, from the liquid effluents for the period of release, mrem; IBM i

L ~ 'H4-Rev.'10:

Page_18L C'k1 the average concentration off

=' i iD.. radionuclides,;i,,in undiluted; liquid effluent for liquid release k, pCi/ml; A' I ' .the. site related ingestion dose = g . commitment factor-to the total-j body:or anyforgan T for each; identified: principal gamma-and

beta' emitter, mrem /hr per pCi/ml;.

the near : field: average dilution F= =- y effluentrelkks.duringzliquid factor for C e k, the duration of release k,-~ hours. [-[ k t '= The dose. factor A was'calculatedefor an adult-for each; isotope Aling the following equation: 5 1.14 x 10 - [21BF DF17] (2.3-3L A = g g7 where: 5 6 3 = 10 pCi x 10 ml x 1 yr

_~

1.14'x 10 pCi- . I 8760 hr = adult fish consumption, Kg/yr; -21 bioaccumulation factor for BF. = 1 radionuclides i'in fish'from Table A-1-of Regulatory Guide 1.109 Rev. 1-(5) pCi/Kg per.pCi/1; dose conversion factor for DF*. = T radionuclides i for adults for a particular organ t from Table E-11 of Regulatory Guide 1.109-Rev. 1, (5) mrem /pCi. A table of A values for an adult at the PNGP arepresente$ Tin 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. IBM

H4 Rev. 10 Page 19 2.3.3 Cumulation of Doses i 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, D 3.0 mrem total body (2.3-4) 7 D 10 mrem any organ (2.3-5) 7 For the calendar year, D 6.0 mrem total body. (2.3-6) z D 20 mrem any organ (2.3-7) 7 The quarterly limits given above represent one half ~ of the annual design objective. If these quarterly or annual limits are exceeded, a special report should be submitted to the USNRC identifying the cause and corrective action to be taken. If twice the quarterly or annual limits are exceeded, a special report shall be submitted showing compliance tcith 40 CFR 190. 2.3.4 Projection of Doses Anticipated doses resulting from the. release of liquid effluents will be projected monthly. If the projecte'l doses for the month exceed 2 percent of Equation 2.3-6 or 2.3-7, additional components of the liquid radwaste treatment system will be used to process waste. The projected doses will be calculated using Equation 2.3-2. The dilution factor, F will N,in be calculated by replacing the term ADF Equation 2.3-1withthetermMDFfromEkuation 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 differ significantly in the next month. In this case, the source term would be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month. IBM

H4 Rev. 10 Page 20 REFERENCES t 1. " Prairie Island Final Environmental Statement," USAEC, May, 1973, p. V-26. 2. "NSP - Prairie Island Nuclear Generating Plant, Appendix 1 Analysis - Supplement No. 1 - Docket No. 50-282 and 50-306," Table 2.1-1. t 3. "10 CFR 20," Appendix B, Table' II, Column 2. 4. "NSP - Prairie Island Nuclear Generating Plant, Appendix 1 Analysis - Supplement No. 1 - docket 50-282 and 50-306," July 21, 1976, Table 2.1-2. 5. U. S. Nuclear Regulatory Commission, " Regulatory Guide 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10 CFR 50, Appendix 1," Rev. 1, 1977. IBM

H4 Rev. 10 Page 21 T703LE 2.3-1 . A" VALUES TOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT f (MREM /HR PER pCI/ML) NUCLIDE BONE LIVER T. BODY' THYROID KIDNEY LUNG GI-LLI IH 3 0.00E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 '6C 14 3.13E 04-6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03-6.26E 03 11NA 24 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 24CR 51' 0.00E-01 0.00E-01 .1.27E 00 7.61E-01 2.81E-01 1.69E 00 3.20E 02 25MN 54 0.00E-01' 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 25MN 56 0.00E-01 la10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.51E 03 26FE 55 6.58E 02 4.55E 02 1.06E 02' O.00E-01 0.00E-01 2.54E 02 2.61E 02 26FE 59 '1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03. 27C0 58 0.00E-01 8.92E 01 2.00E 02 0.00E-01 0.00E-01 0.00E-01 'I.81E 03 27C0 60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81E 03 28NI 63 3.11E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 28NI 65 '1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 29CU 64 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51E 01 0.00E-01 8.50E 02 30ZN 65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 L 30ZN 69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 35BR 83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 35BR 84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E 4.11E-04' 35BR 85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 1.01E-15 37RB 86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 37RB 88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 37RB 89 0.00E-01 1.92E 02 1.35E 02 0.00E 01 0.00E-01 0.00E-01 1.12E-11 38SR 89 2.21E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 38SR 90 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 38SR 91 4.07E 02 0.00E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01 1.94E 03 38SR 92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 3.06E 03 39Y 90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 39Y 91M 5.44E-03 0.00E-01 2.11E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 39Y 91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 39Y 92 5.06E-02 0.00E-01 1.4BE-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 39Y 93 1.60E-01 0.00E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 40ZR 95 2.40E-01 7.70E-02 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 41NB 95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 42MO 99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 43TC 99M 8.87E-03 2.51E-02 3.19E-01 0.00E-01 3.81E-01 1.23E-02 1.48E 01 43TC101 9.12E-03 1.31E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95E-14 44RU103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.69E 01 0.00E-01 5.17E 02 44RU105 3.69E-01 0.00E-01 1.46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 .44RU106 6.58E 01 0.00E-01 8.33E 00 0.00E-01 1.27E 02 0.00E-01 4.26E 03 47AG110M 8.81E-01 8.15E-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 0.00E-01 1.02E 04 52TE127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 52TE127 1.05E 02 3.78E 01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03 52TE129M 1.10E 04 4.11E 03 1.76E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 52TE129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 52TE131M 1.66E 03 8.10E 02 6.75E S2 1.28E 03 8.21E 03 0.00E-01 8.04E 04 52TE131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.00E-01 2.67E 00 52TE132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.3BE 04 53I 130 2.71E 01 8.01E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01 53I 131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 IBM

H4 Rev. 10 Page 22 TABLE 2.3-1 (CONT.) A VALUES FOR TEE PRAIRIE ISLAND NUCLEAR GENERATING PLANT. (MREM /HR PER pCI/ML) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 53I 132 7.29E 00 1.95E 01 6.82E 00 6.82E 02 3.11E 01 -0.00E-01 3.66E 00 53I 133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01 53I 134 3.81E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01E-03 53I 135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 55CS134 .2.98E 05 '7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 55CS136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.38E 03 1.40E 04 .55CS137 3.82E 05 5.22E 05 3.42E 05' O.00E-01 1.77E 05 5.89E 04 1.01E 04 55CS138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 56BA139 9.29E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 56BA140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 56BA141 4.51E-01 3.41E-04 1.52E-02 0.00E-01 3.17E 1.93E-04 2.13E-10 56BA142 2.04E-01 2.10E-04 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.37E-19 57LA140 1.50E-01 7.54E-02' 'I.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 57LA142 7.66E-03 3.48E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 58CE141 2.24E-02 1.52E-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 58CE143 3.95E-03 2.92E 00 3.23E-04 0.00E-01 1.29E-03 0.00E-01 1.09E 02 58CE144 1.17E 00 '4.88E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 59PR143 5.51E-01 2.21E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41E 03 59PR144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04' O.00E-01 2.59E-10 60ND147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2.54E-01 0.00E-01 2.09E 03 74W 187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 93NP239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-0* 5.75E 02 l l l l l IBM

H4 Rev. 10 Page 23 3.0 GASEOUS EFFLUENTS 3.1 Monitor Alarm Setpoint Determination This procedure determines the monitor alarm setpoint that indicates if the dose rate at or beyond the sit 7 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: Monthly calculation of setpoint using the methodology a. 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. In lieu of (a) and (b) above, alarm setpoints may c. be established using the methodology of Section 3.1.1 using conservative assumptions (e.g., 100% Kr-89). No recalculation of setpoints is necessary unless an increase is desired. PWR GALE Code source terms (Table 3.1-2) may be used if there were no detectable isotopes in the previous month or in the analysis prior to purging. If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value. 3.1.1 Effluent Monitors The following method applies when determining the isolation or high alarm setpoint for the monitors listed in Table 3.1-1. 3.1.1.1 Determine the " mix" (noble gas radio-nuclides and composition) of the gaseous effluent. a. Determine the gaseous source terms that are representative of the gaseous effluent. Gaseous source terms are the total curies of each noble gas released during the previous month or a repre-sentative analysis of the gaseous effluent. Table 3.1-2 source terms may be used if the releases for the previous month were below the lower limits of detection (LLD). IBM

H4 Rev. 10 Page 24 b. Determine S. (the fraction of the total radioactivity.in the gaseous effluent comprised by ncble gas radionuclides "i") for each individual noble gas radionuclides in the gaseous effluent. S. = A 1 i - (3.1-1) 3Ag 1 The radioactivity of noble A. = gas radionuclides "i" in the 1 gaseous effluent from Table 3.1-2. 3.1.1.2 Determine Q the maximum acceptable total releahe(rate of all noble gas radionuclides in the gaseous effluent (pCi/sec)) based upon the whole body exposure limit. 500 (3.1-2) Q- = t (x/Q) } KSi1 1 The highest calculated annual (x/Q) = average relative concentration of effluents released via the plant vents for any area at or beyond the site boundary for all sectors (sec/m ) from the 3 "x/Q" column in Table 3.1-1. The total whole body dose factor due K. = to gamma emissions 'from noble gas 3 1 radionuclides "i" (mrem / year /pCi/m ) from Table 3.1-3. 3.1.1.3 Determine Q based upon the skin exposure t limit. 3000 (3.1-3) Q' = S (x/Q) { (Li + 1.1 M ) i i 1 The total skin dose factor L. + 1.1 M. = due to emissions from noble 1 1 gas radionuclides "i" (mrem / year /pCi/m ) from Table 3.1-3. 3 IBM

H4 Rev. 10 Page 25 3.1.1.4 Determine C (the maximum acceptable

i total radioactivity concentration of all noble gas radionuclides in the gaseous effluent (pci/cc))~.

9 (3.1-4) C = 2.12 E-3 t t F NOTE: Use the lower of the Q values t obtained in Sections 3.1.1.2 and 3.1.1.3. -F = The maximum effluent flow rate at the point of release (cfm) from the " Effluent Flow Rate" column in Table 3.1-1. 2.12 E-3 = Unit conversion constant *o convert pCi/sec/cfm to pCi/cc. 3.1.1.5 Determine C.R. (the calculated monitor count rate above background attributed l to the noble gas radionuclides (nepm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. I C.R. is the count rate point that corresponds to the total radioactivity concentration (C )- t 3.1.1.6 Determine HSP (the monitor high alarm setpoint above background (nepm)). HSP = T, C.R. (3.1-5) T = Fraction of the total 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 from the " Release Fraction" column in Table 3.1-1. 3.1.1.7 The isolation or high alarm setpoints above background (nepm) for the monitors should be set at or below the HSP values. 3.1.2 Air 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 1 and Unit 2, respectively. These monitors are provided to IBM o

H4 Rev. 10 Page 26 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. l IBM

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o h i-. .H4 Rev. 10 Page 28 TABLE 5 1-2 GASEOUS SOURCE TERMS (y) l Lp AUX. BLDG SHIELD BLDG. AIR EJECTOR RADIONUCLIDES (A ) (Ci/Yr) (A ) (Ci/Yr) (A )-(Ci/Yr) g g g l 2EO Kr-85m 3E0 Kr-85 2EO 2.2El Kr-87 1EO Kr-88 5EO 1EO 3E0 Xe-131m 2EO 2.1El 1EO Xe-133m SEO 2E1 3E0 Xe-133 3.7E2 2.7E3 2.3E2 Xe-135 8EO 6EO SEO Xe-138 1EO Total 3.97E2 2.77E3 2.44E2 " " indicates that the release is less than 1 Ci/yr. I IBM

7 V -H4 Rev. 10' h Page 29 TABLE 3.1-3 b DOSE FACTORS'AND CONSTANTS SKIN

.i TOTAL WHOLE BODY DOSE FACTOR 1

(ham /yr/p I 3 m) RADIONUCLlDE -(K ) em yr Ci/m ) g .l Kr-83m 7.56E-2 2.12El I

Kr-85m-1~.17E3 2.81E3 l

'Kr-85 T.61El 1.36E3 Kr-87 L5.92E3 -1.65E4 1 Kr-88 1.47E4 1.91E4-Kr-89 1.66E4 2.91E4 Kr-90 1.56E4 2.52E4

Xe-133m 2.51E2

~ 6.48E2 i Xe-131m 9.15El 1.35E3 i Xe-133' 2.94E2 6.94E2 i Xe-135m 3.12E3 4.41E3 l Xe-135 1.81E3 3.97E3. 'Xe-137 1.42E3 1.39E4 l Xe-138 8.83E3 .1 43E4' i Ar 8.84E3 1.29E4 q 3.2 Gaseous Effluent Dose Rate - Compliance with 10'CFR 20 Dose rates resulting from the release of' noble gases, and-radiciodines and particulate 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. Since Sr-89 and.Sr-90 concentrations are determined from composite samples, the pre-release, weekly and monthly j airborne dose calculations and comparisons to quarterly and annual limits should be completed using the most j recent available composite sample results. The quarterly dose values and critical receptors reported semi-annually to the USNRC shall be calculated using the actual composite results. i I i -IBM

P H4 Rev. 10 Page 30 I< 3.2.1 Noble Gases The dose rate at the. site boundary resulting from n(>ble gas effluents is limited by 10 CFR 20 to 500 mrem /yr to the total body and 3000 mrem /yr to the skin. The setpoint determinations discussed in the previous section are based on the dose (2) calenlational method presented in NUREG-0133. They represent a backward solution to the limiting dose equations in NUREG-0133. Setting alarm set trip points in this manner will assure that the limits of 10 CFR 2'O are met for noble gas releases. Therefore, no routine dose calculations for noble gases will be needed to show compliance with this part. Routine calculations will be made for doses from noble gas releases to show compliance with 10 CFR 50, Appendix I as discussed in Section 3.3.1. 3.2.2 Radiciodine, Radioactive Particulate, and Other Radionuclides The dose rate at the site boundary resulting from the release of radioiodines and particulate with half lives greater than 8 days is limited by 10 CFR 20 to 1500 mrem /yr to any organ. Calculations showing compliance with this dose rate limit will be performed for batch releases prior to the release and weekly for all releases. The calculations will be based on the results of sample analyses i obtained pursuant to the PNGP Technical Specifications. To show compliance, Equations 3.2-1 will be evaluated for 1-131, tritium, and radioactive particulate with half-lives greater than eight days. I P (x/Q ) Q < 1500 mrem /yr (3.2-1) f, y 1y 1 I where P child critical organ dose parameter for i radionuclides i for the inhalation pathway, 3 (Table 3.2-1); mrem /yr per pCi/m annual average relative deposit. ion for (X/Q)y = long 3 term release at the critical location, sec/m (Appendix A, Table A-4); 1BM

H4 Rev. 10 Page 31 annual average relative deposition for {' (D/Q)y = C long-term release at the critical-(Appendix A, Table A-5); 2 location, 1/m the total release rate of radionuclides i 'Q = iv from all vents from both units for the-batch or week of interest, pCi/see; Radiciodines, tritium, and radioactive particulate will be released from up to six individual vents all within 300 feet of each other. For showing com-pliance with 10 CFR 20, calculations based on Equa-tion 3.2-1 uill be made once per week. The source terms (Q4y) 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. Significant short-term batch releases of long-lived radioactive particulate 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 determined 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: D) (3.2-2) BL = 1500 - (D y p where BL = limiting dose rate for the batch, mrem /yr; previous week's doses from all vent D = V releases, mrem /yr; previous week's doses from all purge D = p 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 l location. The critical site boundary location, i based upon long term ground level releases x/Q l (Table A-3), is 0.36 miles in the WNW sector. IBM

~ H4 Rev. 10 Page 32 TABLE 3.2-1 Values for Child p ll l mrem /yr l 3 isotope l P pCi/m gy l-1 I l-H-3 l 1.12 E 3 l 1.70 E 4 l l Cr-51 'l -l Mn-54 l 1.58 E 6 i 1 Fe-59 l 1.12 E 6 l l Co-58 l 1.11 E 6 l l Co-60 l 7.07 E 6 l l Zn l 9.95 E 5 l l Rb-86 l 1.98 E 5 l l l Sr-89 l 2.16 E 6 l l l Sr-90 l 1.01 E 8 l l Y-91 l 2.63 E 6-l l Zr-95 l 2.23 E 6 l l Nb-95 l 6.14 E 5 l l Ru-103 l 6.62'E 5 l l Ru-106 l 1.43 E 7 l l Ag-110m I 5.48 E 6 l l Te-127m l 1.48 E 6 l l Te-129m i 1.76 E 6 l l Cs-134 l 1.01 E 6 l 1 Cs-136 l 1.71 E 5 l l Cs-137 l 9.07 E 5 l l Ba-140 l 1.74 E 6 1 l Ce-141 l 5.44 E 5 l l Ce-144 l 1.20 E 7 l l I-131 l 1.62 E 7 l l 1 l 1 IBM

H4 Rev. 10 3.3 Gaseous Effluents - Compliance with 10 CFR 50 .I - Doses resulting from the release of noble gases, and radioiodines and particulate must be calculated to show compliance with Appendix 1 of 10 CFR 50. The calculations will-be performed monthly for.all gaseous effluents. The limits of 10 CFR 50 are on a per reactor unit basis. The gaseous radwaste treatment system and.the auxiliary building at PNGP is shared by both' reactor units making it impossible to separate the releases of the two units. The releases that can be separated by unit contribute a very small portion of the total gaseous releases from PNGP. Therefore, for compliance with 10 CFR 50 the releases from both units will be summed and'the limits of Appendix 1 will be doubled. Since Sr-89 and Sr-90 concentrations are determined from composite samples, the pre-release, weekly and monthly nirborne dose calculations and comparisons to quarterly and annual limits should be completed using the most recent available composite sample results. The quarterly dose values and critical receptors reported semi-annually to the USNRC shall be calculated using the actual composite results. 3.3.1 Noble Gas 3.3.1.1 Dose Equations The air dose at the critical receptor due to noble gases released in gaseous effluents is determined by Equations 3.3-1 and 3.3-2. The critical receptor will be identified as described in Section 3.3.4. For gamma radiation: 3.17 x 10-8 3 (Xfq) giv. ( jq)v iv q < 10 mrad"Ior any calendar quarter' < 20 mrad for any calendar year (3.3-1) For beta radiation: -8 3.17 x 10 N (x/Q)y Q + (x/9)ygiy i iy 1 < 20 mrad for any calendar quarter < 40 mrad for any calendar year (3.3-2) IBM

H4 Rev. 10 Page 34 where: p The air dose factor due to gamma emission M. = for each identified noble gas radionuclides 1 i, mrad /yr per pCi/m ; (Table 3.3-1) 8 the air dose factor due to beta emissions N. = 1 for each identified noble gas radionuclides i, mrad /yr per pCi/m ; (Table 3.3-1) 8 the annual average relative concentration (x/Q)V = for areas at or beyond the restricted area boundary for long-term vent releases 3 (greater than 500 hr/ year), sec/m (Appendix A, Table A-4); the relative concentration'for areas at or (x/q)v = beyond the restricted area boundary for short-term vent releases (equal to or less 3 than 500 hrs / year), sec/m (Appendix A, Table A-7); the total release of noble gas radionuclides = ggv i in gaseous effluents for short-term vent releases from bcth units (equal to or less than 500 hrs / year), pCi; the total release of noble gas radionuclides Q. = tv 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 hours per year short term releases and are given in Appendix A (Table A-7). Values of M and N were calculated using the methodology presented in NUREG-0133 and are given in Table 3.3-1 3.3.1.2 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits. The monthly results will be added to the doses cumulated from the other months in the quarter of interest in the year of interest and compared to IBM

n js . H4.. 4 Rev.110' l Page 35 e the limits given-in Equations-3.3-1 and-L 3.3-2. If these limitsLare exceeded, a special report will:be pubmitted 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. 3.3.2 Radioiodine, Particulate, and Other Radionuclides L L 3.3.2.1 Dose Equations l The worst case dose to an' individual from. E 1-131, tritium, and radioactive particulate 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-3.17 x 10-8 IIR W91v + "v iv 9 ijak V J1 < 15 mrem (per quarter) < 30 mrem (per calendar year) where: Qgv release of radionuclides i for long-term = vent releases from both units (greater than 500 hrs /yr), pCi; release of radionuclides i for short term = qiv purge releases from both units (equal to or less than 500 hrs /yr); pCi; the dispersion parameter for estimating W = the dose to an individual at the controlling v i location for long-term vent releases (greater than 500 hrs /yr); the dispersion parameter for estimating the w = V dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hrs /yr); -8 the inverse of the number of seconds in 3.17 x 10 = a year; R the dose factor for each identified ij ak = radionuclides i, pathway j, age group a, and organ k, m mrem /yr per pCi/see or mrem /yr 3 per pCi/m. IBM

H4 Rev. 10 Page 36 The above equation will be applied'to each combination of age group and organ. Values of have been calculated using the methodology R..hinNUREG-0133andaregiveninTables3.3-2 gl4$ 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 wi'l have one or more of the following: residence, vegetable garden and milk animal. The selection of the actual receptor is discussed in 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 x/Q(sec/m ) for the 8 L inhalation pathways and for tritium (Tables A-4 and A-5) and in terms of D/Q(1/m ) for all 2 i 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 l other months in the quarter of interest and in the year of interest and compared with the limits in Equation 3.3-3. If these limits are exceeded, a special report will be submitted in accordance with the PNGP Technical Specifications. If twice the limits. a exceeded, a special report showing compliance with 40 CFR 190 will be submitted. 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 I indicating that actual releases could differ significantly in the next month. In this case the source terms will be adjusted to reflect this information and the justification for the adjustment noted. If the projected release of noble gases for the month exceeds 2 percent of the calendar year limits of equation 3.3-1 or 3.3-2, additional waste gas treatment will be provided. If the projected release of I-132, tritium, and radioactive particulate with half-lives greater than 8 days exceeds 2 percent of the calendar year limit of equation 3.3-3, operation of the ventilation exhaust treatment equipment is required if not currently in use. IBM I

5) ~ H4' Rev. 10 Page 37-

j.,

3.3.4_. critical Receptor Identification The critical receptors for: compliance with 10_ CFR 50, Appendix'1 will be identified. -For the noble-gas specification.the critical location vill be based on the beta and gamma-air: doses unly.. This location.willE be the of fsite: 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 locationiforLthe I-131, tritium, and long-lived particulate. pathway.will'be selected once each year. The selection.will follow the annual land use census performed within 5 miles of the PNGP. Each of the following locations will be evaluated as potential; critical receptors prior to implementation of the Radioactive Effluent Technical Specifications:

1. Residence in each sector

2. Vegetable garden producing leafy green' vegetables-

3. All identified milk animal locations

t-Following the annual survey, doses-will be calculated using Equation 3.3-3 for all new identified receptors and'those: receptors whose characteristics have. changed'significantly. The calculation will. include appropriate information about each new location.

The' dispersion parameters given in this manual should be' employed. The total releases reported'for the previous calendar year should be used as the source terms'. IBM: l L

H4 Rev. 10 Page 38 i REFERENCES -(l) "NSP-Prairie Island. Nuclear Generating Plant Appendix 1 Analysis - Supplement No. 1 - Docket No. 50-282 and 50-306", Table 2.1-4. e IBM

l l

i

) 3 m / i C r p 2 3 3 4 3 4 3 3 3 3 2 3 4 3 3 o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 rt r + + + + + + + + + 4 + + + + t 0 i c e E E E E E E E E E E E E E E E Aa p 8 7 5 3 3 6 3 1 8 5 9 6 7 5 8 er 8 9 9 0 9 0 8 4 0 3 4 2 7 2 1 F.* a a Nr t e y 2 1 1 1 2 1 7 1 1 1 7 2 1 4 3 s es / r B o d e D a h r t m o ( l l A ) s 3 t m n / e i u C r p 1 3 1 3 4 4 G 2 2 2 3 3 3 3 3 l ro 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 f i t r 4 + + + 4 + 4 4 + + + 4 + 4 + f Ac e E E E E E E E E E E E E E E E e a p 3 3 2 7 2 3 3 6 7 3 6 2 1 1 0 s 9 2 7 5 7 6 5 2 5 3 9 5 2 3 09 aF.* 1 u 13 m Hr S me y 1 1 1 6 1 1 1 1 3 3 3 1 1 9 9 oe R a s / s .e E G o d a vg T D a g l r 4ea i RP G m n 1 1 U ( i AD de D t N c A e ) t S 3 e 1 E r m d S o / A t i 3 e G c C 3 a p 3 3 3 3 4 3 2 2 2 2 3 4 3 3 b E F 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E L r + + + + 4 + + + 4 + + + + + y L B e e - E E E E E E E E E E E E E E a B O s p 6 4 3 7 1 9 6 4 6 1 6 2 3 9 m 4 3 3 0 2 7 9 0 8 2 6 1 1 7 A N o.* t T DL r R y 1 1 9 2 1 7 4 9 3 7 1 1 4 2 a h O n / t F i m k e s S S r e R m d O ( i T l C c A u F n ) o E 3 i S m d O / a D i r C r p r yo dt r 2 3 1 3 4 4 4 1 2 2 3 3 3 3 3 o oc e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 f B a p - + + + + + + + + + 4 + + + + E E E E E E E E E E E E E E E e F 6 7 1 2 7 6 6 5 1 4 2 1 2 3 4 r K'r l a ae y 5 6 9 4 6 5 5 9 8 4 8 8 1 1 1 t s / oo m 7 1 1 5 1 1 1 9 2 2 3 1 1 8 8 s r2 TD e o_ r t 0 m c 1 ( a f x e 6 5 so d 7 d = e e t 2 d s 0 i i - E l l c 6 u m m m 1 3 3 5 5 7 8 e 5 n m m h o 3 5 5 7 8 9 0 3 3 3 3 3 3 3 1 8 8 8 8 8 8 9 1 1 1 1 1 1 1 4 T 7 i d a r r r r r r r c e e c e e e r R K K K K K K K X X X X X X X A l l IlI!l!

I 7 3 4 K 5 2 4 5 5 0 9 2 S 1 3 4 2 2 2 7 1 R IlIIl1iI l l 1IIlII1Ii1I EP 9 8 8 0 4 7 9 0 R 0 0 0 1 0 0 0 1 Y / G E E E E E E E E M N 4 5 9 5 3 2 2 3 E T U 3 7 2 7 8 0 R 7 1 M N L A_ 1 2 3 2 2 1 6 1 L 2 M P I1IIllI1II1lI1II1IIIIll1 G FO N I 9 8 8 0 4 7 9 0 T D 0 0 0 1 0 0 0 1 ST A I 00 R O E E E E E E E E I 14 E R 4 5 9 5 3 2 2 3 N E I 3 7 2 7 8 0 U N Y 7 1 I .e 1 2 3 2 2 1 6 1 N G T vg I 4ea R D RP A IlI IlIIlIIl1Il lIIlIi11 N I I EL A C 9 8 8 0 4 7 9 0 U Y C 0 0 1 0 0 0 1 N E M N E E E E E E E E U D D 4 5 9 5 3 2 2 3 I N 3 7 2 7 8 0 T I 7 1 I A K L 1 2 3 2 2 1 6 1 RT S I IlIIlIIl 1iI1II1 lIi11 DN E A I R 9 8 8 0 4 7 9 0 I 0 0 0 1 0 0 0 1 N A R O R E E E E E E E E E I P V 4 5 9 5 3 2 2 3 T 7 8 0 A 7 7 1 2 3 I L l L E A i 1 2 3 2 2 1 6 1 I T I N R IlIIlII1IIlIIlIIlIIiIil1 I O R F 9 8 8 0 4 7 9 0 O S 0 0 0 1 0 0 0 1 F E E U N E E E E E E E E 3 L O 4 5 9 5 3 2 2 3 H 2 7 8 0 / A B 3 7 2 2 1 6 1 C 7 1 I V 1 2 3 p R IlIIlI I1 1I IlII1IIIIi11 RE 2 P 3 T 9 8 8 0 4 7 9 0 R C 0 0 0 1 0 0 0 1 Y 3 AR E E E E E E E E / E T 4 5 9 5 3 2 2 3 M E 8 0 L 7 7 1 2 7 3 R B I 1 2 3 2 2 1 6 1 MS A G R T FE IllI1IIlII11IlII1III' ll Oi l T SO Y 9 8 8 0 4 7 9 0 T L 0 0 0 1 I D 0 0 0 1 NL D O N B E E E E E E E E UA U 4 5 9 5 3 2 2 3 7 2 7 8 0 NR 1 O 3 7 I O R T 2 2 1 6 F 1 2 3 G 1 S = IllIl II11 l ]I11 ' l1i l l EC UE LS Y E A/ A D Wl i. 4 9 8 0 9 1 4 7 Vl 5 5 5 6 8 3 3 3 C i C, I 1 1 1 R p TA t N E O O R S S l' N M F C C S I C C t l

1 I 1 i M e.* e-. C C C C C C o o o C s e e a e o e a e 2 W W t.s2 Es2 54 ta2 W W W t.s3 co o o o o o o o o o M N. O. O. C. o. o. o. o. o. o. to N O C C C C C C C C D:l s.a M N

=

e.= a Ch m oc C C C C C C C C o o Ea e o e e a e N O ta3 tal W Ca2 523 ta2 Ca2 ta2 s.s3 W Z Z cc o N O o o o o N W D N. o. o. o. o. o. o. o. A N C cc C C C C C r* e N A ~ O C M 6i ,= C H C o O C C C C C C O in. 6 4. 6 t e s e e e s O -d c:: C 123 ta3 W ta2 W Ca3 ta2 ta3 ta2 W c o o o o cc o o

zt c.4 <

42 m cc o C. C. C. o. o. r=. C. o. D Z >= N. o. j W = O t-= N O C o O C C M C o Z ,g > 00 < c ce c:: O = g, a Z Ca2 AU M r= .= cc ch ch D >= C C C C C C C o o o a 3"e 2 ta2 e e e a Z W Ca2 f.c 123 ta2 Ed ta3 ta3 142 N C C CO ch o o o o o co ch CO N. o. o. o. o. o. o. ch. 4 o. f. 2 W N m C C C C C M M U2 e-. c 2 r.c a CC M cc cc N cc e.= cc C ch e-. O o o O C o o C C ZO Oc e i . ta2 W ta2 ta3 14 ts: W Cz3 ta2 ta3 s.O A cc in M ch o o 6n cc N f-N. O. C.s ch C. C. C. o. I ga g N M N N o O C% <= ia Z ,= g C W cc C N ch ch C D o C C C o C o o sd 54 s a e e R Z t.d W W W W ts2 8.0 t,c W W M A C o C 4 o o o o n 4 M 2 C. O. o. N. O. Q o. N. C. en. C C C C cc 4 U1 g W M L e M fa M c0 cc to ch th C N cc cc U C o C C C C C o C >= M 2:: f.d ta3 Ca3 1.0 ta2 W tal 143 ta3 ta3 tal E-. cc an rw N o M 4 ch EW cm. o. cc. 5 t% N. M. C. .2 a Czt 5::8 M

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n cc i

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I i ? l m w ~ w e e O C-O C C C C C C o i. (/ - M N W W W W W W W W W a-e e e e a e-a o o o o o o o o o M o. C. C. C. o. o. C. C. o. m N. O C C C C C C C C W m m m ~ n w m e m m C C o O C C C C C o A e e e i e O W W W W W W W W W W E i Z o o o o o o o N w l C Q n. C. C. o. C. o. e. m. W i r 4 i N O C O C C C e j N% 4 N C C 2m m e m m m e m o m m H Q C C C C C C o O C M a e e a e s a H CN C W W W W W W W W W W-O o o o o o a o o Z M4 g F C_ C. o. O. C. O. C. C. o, D W C H N C C C C C C M C C 2 .g yg <vm C =gs Z W JO M w ~ ~ ~ ~ ~ m m m P H C o C o C o O C C C 5" Z s e e e a W W W W W W W W W W Q C N o o o o o a m K m. C. O. o. O. C. m. N. H q g N O C C C C m 4 H -W m C 2 W -m M w w N m e o C W C C o C O O C C 2 \\ e e O m W W W W W W W W W W W m a m N o o N N H< 4 N. 4 O. C. C. w J W J = N 4 4 4 N O O H Z m g C 4 ~ ~ C N m O C M C C O C C O C A N W e a e e P Z W W W W N W W W W W m J O o o n o o N N m o E Q C. C. N. O. o. m. M. m. O. N C O O C 2 5 O; g W 4 M H m 2 m m m m C N 2 m U C C C C C C C o o

m W

W W W W W W W W W N o e m N m M N o Z W H W 4 e C. m. N. m. M. O. C. N x C N N N N EM C N m m m M H WW 2 C= W H W MC H > m N w N e m N m H C C o O C C C C C C -d 24 MC H4G W W W W W W W W W W O< W< m o e N m N 4 Om 2% m. -O N N. m. n. o. N CD Wgh >W' N 2 m m 4 N m N 4 W Z Wu na GW 3 4M HOW <x; 30-m 4 e m o 7 C 4 = 4 m m m m m M M U M W U6 <O04 Z W C l C 'I Z M l l U U se M M L < Z: = Z W U l v

[.. l M C O O O O C C C O C e a e e e e a e s i[ Z W W W W W W W W W W' 4 O O O O o o o o o M C. . C. C. C. C. O. O. C. O. O. w 4 'O O O O O C C O O EW M m m m g C C O C C O C C o o e e e a e e N O W W W W W W W W W W E M 4 C 4 o o o o o 4 o W w X O. O. O. O. C. g p C. C. W 4 C C O C C C N N e N% 4 k C C Z e C M F C Q C C C C C C O C. M a e e a e a e e H CM M C W W W W W W W W W W M4 W m 4 o o o o o o m o o ZD Z g o. o. o. C. C. o. o. N. o. O. W 4 C C C C-o C 4 C C Z .g C E pg < cc M c =ga Z W A U M m m A H C O C C C C C C C C Z W e e e e s E Z W W W W W W W W W W D C C 4 N C O O o O M M N H W C. C. C. C. C. M. C. Z g A 4 C O C C C N N N M M c Z W M e e N m 2 C C C O C J o O C C Z i e C i M W W W W W W W W W W W m N o o a m H< W M. J Q 4 M. N. N, C. C. 4 p W = 4 M C C N N <= H Z M O 4 m C N C C C M C C C C C O W W W s e s D 2 W W W W W W W W W W n 4 C C C M o C N m M m Z M. 4 O. 4 Q C. O. m. C. O. C C M C Q M N UL M g W A D M P M 2 2 2 m m C N m m U C C O o C C C C C M W W W W W W W W W W N W H 4 4 N m O C W C E W w N. M. m. o. 4 O. 4 J e z c C 4 W M N EM= H C WW 4 C= ~ ~ ~-----

~~~~-----

H = MC U > M m e m 7 N m o C C C O O O O C O C -W 24 HWC m W W W W W W W W W W =< W< 4 M N N M m C N ZZ O. N. m. C. 4 4 A. CD -o WCF M t F6 >W 4 M M WU nm l OW D l 4Z WCW <x=1 30-1 M 4 m O C 4 >= 2 49 A A c W M M M U 3 L W W Ut <'J O: 2 W O C M M i U U 48 A < Z! = l E W U U M M =

- - __= - 'i i I: ---~~------~~~~~-----~~---____ N o O O O o C O o o O a e e e e e a e g 2 W W W W W W W W W W N o -o o o-o o o o o M N. C. o. o. o. o. C. o. o. o. m 'M C C o O C o C o C ll 1 W 1 ~~~~~~-~~~- ---~~-~~-~~-- N .N N N g o o o C o o o C o C 8 I e e e s C W W W W W W W W W W E

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o o o o o o e c W P, N. O. C. o. o. o. o. N. 4 g M C C o C O o o e W e N X b W C o Z-N m H C C C o o o C O o o o m a e e e e a e p CC M C W W W W W W W W W W MC N N o o o o o o e o o Z b_ N. o. o. C. o. o. C. 4 o. o. D ZW O b M o O C C C C N o C 2 ,y pg COC c =gA Z W W U N ~ N m m o o C o o. C. o. r G c o C a W i Z W W W W W W W W W W D C o N o o o o o o m 4 4 N. o. o. C. o. o. N. N. H Z y X M O C C o C N N %E M c Z W N m C N o o o o C o o o o o Z ( s n o M g W W W W W W W W W W H s N N m N o o m N o. o. o. 4 J N N. m. W W = M N C C N m b 2 g o W C m o W O C o C o o o o o C W W W e s O 2 W W W W W W W W W W M M C o o 4 o o m N 2 m m E c o. o. N. o. o. 4 N. M. N N n m 4 O C o C o L M ~~----- g W l e M. F N N 2 M M N N N U C C o o o O C o o o M W W W W W W W W W W N W H N M c o N m M m EW N. m. M. C. m. 4 N. N N. A 0 g = C M m N N N EM% b b kW Jp C-5 C ec N 4 e N r-w m H c O o o o o o o o o o -4 2d WC JC W W W W W W W W W W G< H< N m N m N N m m m M Z% N. m. m. m. N. M. <O -C Weg EW M m ~ W M WO (t A RW D >OW &D <MC 30-M 4 m m o m O 4 = 4 m W m m m M m M U % 1 HWU <CO Z W C C M i n m U i U 48 4 < Z. = = 6 U U Z i i .-__.--_-_3

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Z 4 m C H m C C C C C C C C C O m 2 e e e e e e e e H CO C W W W W W W W W W W m O C C C C C M C C g Mc ..W m. C. C. C. C. C. C. C. O. P c = ,g H O C C C C C N O C Z >M M <UC C =x2 g z U C M m o o C C C C C C C C C C W e e e e e r A Z W W W W W W W W W W C Z c m N C C C C C c N y A. C. C. C. C. C. C. C. C. W H g c M M C C C C C F C W Z M N N N 2 O C Z C C C C C C C C e e o A W W W W W 4 W W W W W ~ H m e m N C O 4 4 D. C. C. M. C. C. 4 m. N. W W W = W ~ m m N O C H = --~~--- ~____-- ~~~---__ CW 2 m N m o e C C C W C C C C C C C 4 C W s e e e 4 Z W W W W W A W W W W m C C C O C M o O m m C m C. C. C. C. C. 4 4 N. U C C 4 C C M g W A e M b M N N e m m N m M U C C C C C C C C C C M W W W W W W W W W W N W H m 4 m N m m M e N E m. C. 4 m. N. N. N. O. C. W J e g c EZ m m M 2 4 C H C kw J ~

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l. l - i 1 i m C C C C C C C C C C e B 4 e e e e e a ,j 2 W W W W W W W W W. W O C o -o o o C. O C o 1 x 4 C. C. C. o. O. C. C. C. o. m l N O O C C C C C C C W n N m m E C C C C C C C C C C H e a e e e s C W W W W W W W W W W E O O o o C o o e m W D 4 C. 4 C. C. o. o. C. 5 p N O C C C C C n n e i A N

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?. .i 7 r m e l, O C C C C C C C C C e i e i e i e l( ~ 1 W W W W W W W W W W 5 C C o C o o o o o M e C. O. O. O. C. C. C. C. C. m 2 C' O C C C C C C C W 4 m m m m C C C C C C C C C C s a e a e N c. C W W W W W W W W W W r Z N O m o C o o o m W D m. C. O. C. C. C. C. N. e. W W C C C C C C N s N A C C N Z C H e e C Q C C C C C C C C O M M a e a e e e e s b OH W C W W W W W W W W W W MO Z-N C C o o o o e o .O Z W d. C. C. - O. C. C. C. C. O. P g = ,g H C C C C C C m C C Z >M m 40C C =gg W Z W U e e m p m m 2 c C C o C O C C C C W s e a s s y C Z W W W W W W W W W W s Z C N 4 o o o o o e N O t. D. C. C. C. C. o. N. m. N. W g M O C C C C 4 D %H C W Z A A m m o C M Z C C C C C C C C e e C 1 M 6 W W W W W W W W W W ? N m n m e o o C m H C. C. C. e. D. N. W ~_ W G H D 4 N C O N. N Z = -~~-~~~----------~~~~~~~~~~--- CW X m n C w C C O C W W C C C C C C 3 W s e e a W Z W W W W W W W W W W M o o o O o C 4 N 4 e n C c C. C. m. C. C. 4 C. N. m. N. N O C c m u m C C g M W 6 s M H M N M m N m M O C C O O O o C C C C

n W

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m m m m e w w m C C o O C C C C C C e 4 e e s e e a Z W W W W W W W W W W ~ m o o o o o O C o o W N. O. C. C. C. C. C. C. o. o. m m O C C C C C C C C y m m m m ~ w w m m m x C C C C C C C C C C s e e e e s C W W W W W W W W W W E m O 4 o o o o o N W gJ N. C. N. O. O. o. O. C.

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=

m C C C C W C C C C C C C 6 D W s e s e 4 Z W W W W W W W W W W M o o o m o o c m m c 2 c C. C. N. O. o. e. n. m. M. C C N C C C N m W U g m W L 4m M M c c c N 2 m N m e O C C o C C C C C C C m W W W W W W W W W W X W H m m m 4 m 4 N w W N. o. N. C. m. e. m. w N. W e x C c m n =Z C m 4 N H C 4 kW C=

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= H U MC W m e e c c 2 C C C H 4 C C C C C C C C C -4 ZW - q =C E-W W W W N W W W W W D< H< m 4 w N N N m m m N N c C 4 m N A 2% <3 -C + COH CW m m m N m m 4 N 6 Z WU 11 A - - - ~ ~ ~*- - - ~ ~ - - - -*- - = ) OW >CW l az <x3 l 4 N 3C. m o e e C m C = 4 c c m C C m m m M U r W uzl I W C C l = i 2 W

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~~

c 4 2 Q -p M .= C C C C C C C C

=

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2:

p:. o o C o o o o C C Ch. C. C. C. C. C. C. N. O. C. D laJ .a g =

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H4 L Rev. 10 4.0L INFORMATION RELATED TO 40 CFR 190 and 40 CFR 141 ( The PNGP Technical Specifications indicate that if twice the l per unitRlimits of 10.CFR 50, Appendix 1 are exceeded, a l special report is-required. Therefore, if twice the annual l limits of Equations 2.3-6, 2.3-7, 3.3-1, 3.3-2 or 3.3-3 are-l exceeded,Lthe 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 n 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 i effluent pathways and direct radiation) are less than the standards in 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations. If L analysis indicates that releases resulting in doses that j exceed the 40 CFR 190 Standard may have occurred, then a variance from the Commission to permit such releases will be l obtained. The Standard Technical Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3 consider doses to a real individual L and apply.to each reactor but do not include any o*her l portion. of the uraniuru fuel cycle or direct shine com the i I

reactor, i

The " Uranium fuel cycle" is defined in 40 CFR Part 190.02(b) I as: " Uranium fuel cycle means thes operations of milling of a uranium ore, chemical conversion of uranium, isotopic l enrichment of uranium, fabrication of uranium fuel, L generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical pover for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle." TheShecialReportwillcontain: .1) A determination of which uranium fuel cycle facilities or operations, in addition to the nuclear power reactor units at the site, contribute to the annual dose to the maximum exposed member of the public. Only those other fuel. cycle facilities within 5 miles of PNGP need be considered. No such facilities exist or are planned at present. IBM

!!4 Rev. 10 Page 60

2).

.A determination of the maximum exposed member of the public as given for determining compliance with 10 CFR ,( 50, Appendix 1. 3) A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents using the methodologies described for compliance with 10 CFR 50, Appendix 1 in this ODCM. Where additional information on pathways and nuclides is needed, the best available information will be used and documented. 4) A determination of the dose resulting from direct radiation from the plant'and storage facilities. The various organ doses resulting from liquid effluents from the-PNGP will be summed with the organ doses resulting from releases of noble gases, radioiodines and particulate. These doses will be based upon releases from the PNGP during the past 3 quarters and from the quarter in which twice the specification was exceeded. The doses from the PNGP will be summed with the doses to the maximum exposed individual contributed from other operations of the uranium fuel cycle. l. The direct donc components will be determined by either calculation or actual measurement. The N-16 ccmponent of direct radiation may be calculated using SKYSHINE. A Computer Procedure Evaluazing Ef fects of Structare Design on N-16 .{ Gamni^-Way Dose Rates. Radiation RTGarch Associates, 3 c. ~ Report RRA-T7209, November 1972. (Availabic in the NSP-NSS Library). The calculation or actual measurement will be documented in this Special Report. l. If the ouarterly 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 l IBM

l f H4 Rev. 10 Page 61 5.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling I 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. An annual land use survey will be conducted to determine whether corn #' elds are irrigated with water taken from the Mississipp; Kiver between the plant and a point 5 miles downstream. If corn fields are being irrigated with Mississippi River water, appropriate samples will be collected and analyzed per Technical Specifications, Table 4.10-1. 5.2 .Interlaboratory Comparison Pro, gram Analyses shall be performed on radioactive samples supplied by the EPA crosscheck progr&m. This program involves the analyses of samples provided by a control laboratory and comparison of results with those of the control laboratory 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. IBM

. j. Z - H4 t .Rev. 10 Page 62 TABLE 5.1-1 y" PRAIRIE ISLAND NUCLEAR GENERATING PLANT. RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPL1NG LOCATIONS, -Type of Collection'S!te Location Sample. Code C River Water P-5 Upstream'of Plant 0.6 mi-@ 60*/ENE River Water P-6 Lock,& Dam #3. 1.6 mi @ 129*/SE Drinking Water P-11 City of Red Wing 7.1 mi @ 135 /SE Well Water TP-25c Kinneman Farm 11.1 mi @.331 /NNW .,Well Water P-6 Lock & Dam #3 1.6 mi @ 129 /SE -Well Water P-8 Community Center 1.0 mi @.321 /WNW Well Water .P-9 Plant-Well #2 0.3 mi 0 306 /NW C ! Sediment-River F-S Upstream of Plant 0.6 mi @ 60 /ENE P-6 Lcck & Dam #3 1.6 mi @ 129 /SE~ Sediment-River 4 . Sediment-Shoreline. P-12 Recreation area 3.4 mi @ 116a/ESE. e PeriphytonDor P-S Upstream of Plant 0.6 mi @ GO*/ENE ...G mi @.129*/fE i (b Macroinvertebratos P-6 Lock & Dam #3 ' Fish: P-5' Upstream of Plant 0.6 mi @ 60"/ENE-6 mi.@ 129*/SE-Fish' P-6 Lock & Dam #2 C MilkL P-25 Kinneman Farm 11.1 mi @ 331"/NNW' . Milk P-14 Gustafson Farm 2.2 mi @ 1686/SSE. j Milk P-16 Jchnson Fann 2.6 mi @ 60 /ENE' Milk P-17 Place Farm 3.5 mi @ 25*/NNE Milk P-18 Christensen Farm 3.7 mi @ 88*/E 1 l 1 i l l l IBM-

3. m t.. [.3

H47

'Rev. 10 E Page 63 L l f. TABLE 5.1-1_(Continued) y b, ' PRAIRIE. ISLAND NUCLEAR GENERATING PLANT-L RADIATION ENVIRONMENTAL MONITORING PROGRAM L SAMPLING LOCATIONS Type'of. Sample Code Collection Site' Location Cultivated Crops c (Leafy Green-Veg) P-25 Kinneman Farm 11.1 mi @'331 /NNW P-24 .Suter Residence 0.6 mi'@ 158*/SSE c ' Particulate,and. P-l Air Station P-1 '16.5.mi-@ 348 /NNW Radiciodine-(air) ~ . Particulate and' P Air Station P-2 0.5 mi-@ 294 /WNW r;L, LRadiciodine:(air) Particulate and P-3 Air Station'P-3 0.8 mi-@ 313 /NW Radiciodine'(air) 13 4 .Pasticulates and'. P-4 Air Station'P-4 0.4 mi @'359 /N Radiciodine~(air) Particulate and. P-6 Air Station P-6

1,6 mi-:@ 129*/SE Radiciodine (air.)

Direct Radiation - (TLD ) - POlA Property.Line 0.4 mi @ 359 /N Direct Radiation (TLD) PO2A' Property Line 0.3 mi @ 19*/NNE Direct. Radiation (TLD) P03A' Property Line 0.5 mi @ 183'/S Direct Radiat.on i (TLD) PO4A Property Line 0.4 mi @ 204/SSW - Direct Radiation "(TLD)' POSA Property Line 0.4 mi @ 225*/SW ' IBM-

n. 4 H4~ Rev. 10- -Page 64 -TABLE. 5.-l-r ' (Continued) PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM: SAMPLING LOCATIONS-Type'of. Collection Site-Location Sample ~ Code

Direct Radiation.

. P06A' . Property Line 0.4 mi @'249*/WSW - (T13 ). Direct Radiation (TLD) P07A-Property Line '0.4 mi @ 268 /WL Direct Radiation (TLD) P08A- . Property:Line 0.4 mi 0.291 /WNW Direct' Radiation' (TLD) .P09A Property Line' O.7 mi @ 317*/NW 1 Direct. Radiation Property Line. OL,5 mi 0 333*/NNV

(TLD)"

F 10A' Direct Radiation L(TLD) 'PolB ~ Tom Killian Res. 4.7 mi-@ 335*/N' .. g -Direct' Radiation ( (TLD). P02S Roy Kinneman Farm-4.8 mi @ 17*/NNE. Direct Radiatiori (TLD). P03B Vayne' Anderson Farm 4.9 mi' @ 46*/NE Direct Radiation (TLD) PO4B Nelson Drive (Road). <4.2 mi 9 61 /ENE -Direct' Radiation-(TLD)- 'P05B County Rd E &' Coulee 4.1 mi @ 97 /E I i Direct Radiation (TLD) P06B William Houschildt Res. 4.4 mi @ ll2*/ESE Direct Radiation (TLD) P07B Red Wing Public Works 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*/S Direct Radiation (TLD) P10B Cannondale Farm 4.9 mi @ 200*/SSW IBM-

H4 Rev. 10' TABLE 5.1-1 (Continued) PRAIRIE ISLAND NUCLEAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Code Collection Site Location Direct Radiation (TLD) P11B Wallace Weberg Farm 4.5 mi @ 221*/SW Direct Radiation (TLD) P12B Roy Gergen Farm 4.5 mi @ 247*/WSW Direct-Radiation (TLD) P13B Thomas O'Rourke Farm 4.4 mi @ 270*/W Diract Radiation (TLD) P14B David Anderson Farm 4.9 mi @ 306 /NW Direct Radiation -(TLD) P15B Holst Farms 4.2 mi @ 347 /NNW Direct Radiation (TLD) P01S Federal Leck & Dam 93 1.5 mi @ 129 /SE Direct Radiation (TLD) PC2S Charles Suter Res. 0.5 mi @ 155 /SSE Direct Radiation (TLD) P03S Carl Gustafr.on Farm 2.2 n,i @ 168*/SSE L Direct Radiation (TLD) P04S Richard Burt Res. 2.0 mi @ 228a/SW Direct Radiation (TLD) PO5S Kinney Store 2.0 mi @ 270*/W Direct Radiation (TLD) P06S Earl Flynn Farm 2.5 mi @ 299 /WNW Direct Radiation (TLD) P01C Robert Kinneman Farm 11.1 mi 0 331 /NNW

"c" denotes control location.

All other locations are indicators. The letters after numbered TLD's are as follows: "A" denotes locations in the general area of the site boundary. "B" denotes locations about 4 to 5 miles distance from the plant. "S" denotes special interest locations. IBM L i _._._..______________J

H4 L. -Rev. 10 Page 66 t -[} FIG U R E 5.1-1 r - AIR! E !! LAND NUCLEAR GENEF.ATlHG FLANT y RAO!a'" ON. ENVIRO N M EN"'A L MONITORIN G PROGRAM. me"XE fn 5NES \\ I P M.r.5 CO'[T g -L- [ g e l il _ _i 1 %~. I V =)+f-r/ W. 7 (

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H4 Rev. 10 Page 69 APPENDIX A -. METEOROLOGICAL ANALYSES Table A-1 Release Conditions Tabic A-2 Unrestricted Area Boundaries Table A-3 Long Term - Ground Level - Unrestricted Area Boundary - X/Q and D/Q. Table A-4 Long Term - Ground Level - Standard Distances - X/Q Table A-5 Long Term - Ground Level - Standard Distances - D/Q Table A-6 Short Term - Ground Level - Unrestricted Area Boundary - X/q and D/q Table A-7 Short Term - Ground Level - Standard Distances - X/q' Table A-8 Short Term - Ground Level - Standard Distances - D/q 4 1. 1 IBM

H4 Rev. 10 Page 70 APPENDlX - A Summary of Dispersion Calculational Procedures Undepleted, undecayed dispersion parameters were computed using the computer program XOQD0Q (Sagendorf and Goll, 1977). Specifically, sector average x/Q and D/Q values were obtained for a sector width of 22.5 degrees. Building wake corrections were used to adjust calculations for ground-level releases. Standard open terrain recirculation correction factors were also applied as available as default values in XOQD0Q. 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 XOQD0Q is presented in Table A-1 and controlling unrestricted boundary distances are defined in Table A-2. Computed x/Q and D/Q values for unrestricted area boundary locations (relative to release points) and for standard distances (to five miles from the source in 0.1 mile increments) are presented in Tables A-3 through A-8. Onsite meteorological data for the period April 1, 1977 through March 31, 1978 (as presented in Appendix B) were used as input to XOQD00 Data were collected and AT stability classes were defined ir.conformance witn NRC Regulatory Guide 1.23. Dispersion calculations for the plant complex were based on aT 42.7-12.2m and 12,2 meter wind data (joint data recovery of 96 percent). l i IBM 1 I

H4 Rev. 10 Page 71 REFERENCES 1. Sagendorf, J.F. and Goll, J.T., XOQDOQ Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG-0324, U.S. Nuclear Regulatory Commission, September 1977. O I 1 IBM i \\.

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H4 Rev. 10 TABLE A-2 ~(' Distances (Miles) To Controlling Unrestricted Area Boundary Locations As Measured from Edge of Plant Complex Sector Distance 1 N 0.28 NNE 0.26 NE 0.84* ENE 0.62*' E 0.59* ESE 0.61* SE 0.67 SSE 0.43 S 0.43 SSW 0.40 SV 0.40 WSW 0.37 i W 0.36 WNW 0.36 NW 0.43 NNW 0.43

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E E E E E E E E E E E E E E E E 4 0 0 6 5 4 7 5 5 4 3 0 3 8 1 5 8 8 9 5 6 6 0 2 7 5 9 5 9 7 4 0 2 1 8 5 5 5 1 3 3 1 7 5 6 7 1 2 2 1 6 7 7 7 6 6 6 6 7 7 7 7 6 6 6 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 E E E E E E E E E E E E E E E E R 1 4 5 6 6 3 2 2 6 8 9 6 5 0 3 1 0 T) 0 9 5 6 9 6 8 0 8 9 6 3 8 4 5 1 Qx / e 1 6 6 6 1 3 3 2 8 6 7 9 2 2 2 1 sl r p m i ,l o 0E 06 m5 17 / 1 t c n 6 7 7 7 6 6 6 6 6 7 7 6 6 6 6 6 e> a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .e s l vg rP 2 E E E E E E E E E E E E E E E E , o 4 3 6 8 1 3 8 7 6 6 7 2 1 9 8 9 4ea 2 3 8 9 3 3 5 4 0 3 . 5 3 8 7 1 1 RP ) f 1 1 1 Qro 1 8 7 7 2 4 4 2 1 8 9 1 2 3 2 1 / Y X/ e ( sg ird sl E r ) e0 m t 0 o t e5 r 6 6 7 7 6 6 6 6 6 6 6 6 6 6 6 6 n m f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o a> E E E E E E E E E E E E E E E E C r d 1 1 2 0 2 2 8 8 1 9 2 2 7 7 3 0 8 ( a s e s 5 0 6 7 8 2 5 0 2 0 3 0 5 1 1 1 P er e 1 4 s u l na s i 1 1 9 9 2 5 5 3 1 1 1 1 3 4 3 2 A oea M il e E s eH L rR B e s 1 pl A T s e( i v 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 D es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L e 0 E E E E E E E E E E E E E E E E d c 7 7 0 1 2 8 6 6 1 7 9 1 3 4 5 1 nd n 8 2 2 2 5 5 9 7 6 2 3 7 8 3 1 7 a na 1 l ut i 1 1 1 3 6 6 3 1 1 1 1 3 5 4 2 sos I ri GD e i md rr r i ea a T d. 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 r i P ga 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 nt 9 oS E E E E E E E E E E E E E E E E L 0 9 2 /, 5 1 4 2 2 6 3 8 9 1 8 6 6 9 5 5 4 6 7 1 6 5 5 5 4 9 3 0 r 3 r o of 2 1 1 1 4 8 3 4 2 1 1 2 4 6 5 3 f 6 6 6 6 6 5 5 6 6 6 6 6 6 6 6 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 E E E E E E E E E E E E E E E E 0 8 7 6 7 2 3 9 5 4 7 8 3 7 7 0 0 7 1 3 7 4 . 9 5 . 4 6 0 0 0 1 1 1 1 6 2 2 2 2 6 8 7 4 3 2 2 2 6 1 1 o N E E E E E E E S V W W W W W W r t N N N S S S S S S N N N c N E E S S W U N e S

1 E E E E E E E E E E E E E E E E 6 2 8 1 5 2 0 1 4 4 8 0 4 3 3 9 . 5 3 4 0 3 4 5 2 5 7 4 6 0 8 4 2 7 3 2 2 2 7 1 1 7 3 2 2 3 7 1 8 5 7 7 7 7 7 6 6 7 7 7 7 7' 7 6 7 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E E E E E E E E E E E E E E E E R 2 4 7 1 5 5 6 4 5 6 0 6 4 0 4 2 4 T) 7 6 6 7 4 5 2 5 8 0 7 4 0 1 7 1 Qx /e 4 2 2 2 7 1 1 8 3 2 3 3 8 1 9 6 sl i p r m ,l o 3 0C 0/ m5 17 / 1 t c n 7 7 7 7 7 6 6 7 7 7 7 7 7 6 6 7 e> a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .e s l E E E E E E E E E E E E E E E E vg rP 9 ea ,o 9 7 9 4 6 1 0 2 5 0 9 3 9 6 8 9 41 RP ) f 1 5 0 8 9 5 6 . 9 . 3 2 2 0 6 7 1 1 1 1 Qro /Y 4 3 2 2 8 1 1 9 3 3 3 4 9 1 1 6 X/e ( s g t d r I E sl ) e0 m t 0 o t e5 r 7 7 7 7 7 6 6 6 7 7 7 7 6 6 6 7 n m f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o a> C r d 8 E E E E E E E E E E E E E E E E 3 3 3 9 5 9 0 2 1 6 9 1 4 1 0 7 ( a s e s 4 2 2 5 7 9 0 4 4 6, 0 4 2 4 7 P er e 1 1 4 s u l 5 3 3 3 9 1 1 1 4 3 3 4 1 1 1 7 na s i A oea M il e E s eH L rR B e s A pl A T s e( iv 7 7 7 7 6 6 6 6 7 7 7 7 6 6 6 7 D es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L e E E E E E E E E E E E E E E E E 7 d c 9 7 4 1 8 2 4 5 7 0 7 1 7 9 5 3 nd n 9 9 2 2 5 3 4 1 7 8 6 . 0 0 7 1 1 a na 1 l ut s os 5 3 3 3 1 2 2 1 4 3 4 5 1 1 1 8 I riGD et md r r r ea i aTd r n 7 i 7 7 6 6 6 6 7 7 7 7 6 6 6 7 P ga 0 O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 nt 6

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5 E E E E E E E E E E E E E E E E 5 2 7 8 7 0 0 1 1 4 0 5 4 1 9 2 . 6 3 0 5 2 3 2 9 . 3 5 3 0 4 9 1 3 7 5 3 2 3 6 1 1 6 2 2 2 2 5 1 8 5 + 0 0 0 0 0 9 9 0 0 0 0 0 0 9 0 0 1 1 1 1 1 0 0 1 1 1 1 1 1 0 1 1 4 E E E E E E E E E E E E E E E E R 3 4 7 3 9 2 8 9 3 1 8 6 3 0 8 7 2 8 5 2 0 2 6 2 4 7 7 0 0 3 3 1 T) 1 Qx /e 6 3 2 3 7 1 1 6 3 2 2 2 5 1 9 6 sl r p I m I o 0C 07 5 18 m1 t / n 0 0 0 0 0 9 9 0 0 0 0 0 0 9 0 0 1 > a 1 1 1 1 1 0 0 1 1 1 1 1 1 0 1 1 .e l vg ,rP 3 E E E E E E E E E E E E E E E E 4 ea ) o 7 4 0 2 1 7 9 0 3 4 3 2 0 6 1 6 5 5 3 4 3 4 6 9 7 1 1 1 7 RP Q f 3 5 1 7 1 1 /ro DY 6 4 2 7 7 1 1 7 3 2 2 2 6 1 9 6 (/ es g lrd s rl E e ) t 0 m e0 o t m5 r 0 0 0 0 0 9 9 0 0 0 0 0 0 9 9 0 0 0 1 1 1 1 1 1 0 0 1 n a f 1 1 1 1 1 o r> C a d 2 E E E E E E E E E E E E E E E E 5 4 0 8 6 7 9 1 7 2 2 3 4 4 4 5 ( P s e s 1 2 2 er e 3 0 . 9 7 0 4 5 6 5 6 8 5 . 0 4 5 ns u l oa s i 7 4 2 3 8 1 1 7 3 2 2 3 6 1 1 7 A i ea M sl e E rem L eR B p s A sl A T ie( Dv 0 0 0 0 0 9 9 0 0 0 0 0 0 9 9 0 es 1 1 1 1 1 0 0 1 1 1 1 1 1 0 0 1 dL e n c 1 E E E E E E E E E E E E E E E E t 9 4 2 4 7 4 4 2 0 ad n 8 7 2 6 7 8 l na 3 5 7 . 0 6 5 8 8 0 . 0 3 8 1 7 1 3 1 sut I os 7 4 3 4 8 1 1 8 3 2 3 3 7 1 1 7 ri eGD i rmd i r r a ea rTd P n 0 0 0 0 0 9 9 0 0 0 0 0 0 9 9 0 1 1 1 1 1 0 0 1 1 1 1 1 1 0 0 1 ga 0 nt E E E E E E E E E E E E E E E E oS L 3 7 5 6 8 4 0 5 3 4 4 7 3 9 4 1 1 . 3 3 3 . 8 8 . 0 2 6 5 4 2 4 7 1 r 1 1 r o of 8 5 3 4 9 1 1 8 4 3 3 3 7 1 1 8 f 0 0 0 0 9 9 9 0 0 0 0 0 0 9 9 0 1 1 1 1 1 1 0 0 1 1 1 1 1 0 0 0 9 E E E E E E E E E E E E E E E E 1 4 0 5 7 8 4 2 0 6 1 9 2 4 6 4 3 . 6 0 0 5 4 2 5 9 2 5 3 0 7 8 8 5 8 5 3 4 1 1 2 9 4 3 3 3 8 1 1 9 r o N E E E E E E E S W W W W W W V t N N N S S S S S S N N N c N E E S S W W N e S ll'

E E E E E E E E E E E E E E E E 2 1 7 5 7 6 5 3 4 2 3 0 5 5 5 3 2 8 4 5 0 3 9 6 9 4 5 7 5 7 6 9 1 4 3 2 1 2 4 7 8 4 1 1 1 1 3 6 5 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 E E E E E E E E E E E E E E E E 3 4 6 6 1 0 2 6 4 0 2 9 5 2 6 5 R T) 4 0 5 6 6 4 3 0 5 6 7 9 1 1 7 1 1 Qx /e 4 2 1 2 4 8 9 4 2 1 1 1 3 7 5 4 sl r p H mo 0C 08 5 18 m1 t / n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 > a 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 .e l E E E E E E E E E E E E E E E E ' vg ,rP 0 6 8 5 8 7 7 4 0 6 8 1 9 6 2 9 8 4 ea ) o / ro . 6 7 2 8 8 6 6 5 8 9 5 2 3 1 7 RP Q f 4 2 1 1 DY 4 2 1 2 4 8 9 4 2 1 1 1 3 7 6 4 ( /es g s rd rliE e ) t 0 m e0 o t m5 r 0 0 0 0 0 0 9 0 0 0 0 0 0 0 0 0 n a f 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 o r> E E E E E E E E E E E E E E E E C a d 9 1 4 6 2 6 9 2 7 8 7 1 0 9 6 6 4 ( P s e s er e 3 5 8 8 4 3 0 8 . 6 8 0 9 6 6 1 2 1 5 ns u l oas i 4 2 1 2 5 9 1 4 2 1 1 2 4 7 6 4 A i ca H sI e E r eM L eR B p s A sl A T i e( D v 0 0 0 0 0 0 9 0 0 0 0 0 0 0 0 0 es 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 dL e n c 8 E E E E E E E E E E E E E E E E ad n 8 1 7 6 6 5 8 6 2 8 2 2 4 4 6 2 0 9 5 9 0 4 9 4 4 0 9 4 1 7 1 l na 3 7 s ut I os 4 3 1 2 5 9 1 5 2 1 1 2 4 8 7 4 ri eGD i r md i r r a ea rTd P n 0 0 0 0 0 9 9 0 0 0 0 0 0 0 0 0 1 1 1 1 1 0 0 1 1 1 1 1 1 1 1 1 ga nt 7 oS E E E E E E E E E E E E E E E E L 3 7 9 9 2 0 6 5 8 7 8 3 5 1 6 0 2 9 5 2 1 7 1 2 7 0 0 8 0 4 5 8 0 r r o of 5 3 2 2 5 1 1 5 2 1 2 2 4 8 7 5 f 0 0 0 0 0 9 9 0 0 0 0 0 0 0 0 0 1 1 1 1 1 0 0 1 1 1 1 1 1 1 1 1 6 E E E E E E E E E E E E E E E E 3 0 0 2 9 7 2 2 3 3 0 6 0 1 3 7 5 2 8 0 . 4 0 5 9 5 7 1 4 4 2 8 1 1 5 3 2 2 6 1 1 5 2 2 2 2 5 9 7 5 r o N E E E E E E E S W W W W W W W t N N N S S S S S S N N N r N E E S S W W N c S

9 3 2 2 6 2 8 7 4 8 1 9 1 3 1 3 0 7 4 6 9 3 0 0 2 5 8 0 8 7 1 1 1 4 2 1 1 1 3 5 6 2 1 1 1 1 2 4 4 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 8 E E E E E E E E E E E E E E E E R 5 0 7 3 6 4 5 8 4 6 4 7 5 3 1 3 T) 4 8 8 5 2 9 4 0 4 0 2 6 0 2 9 1 1 Qx /e 2 1 1 1 3 5 6 3 1 1 1 1 2 5 4 2 sl r p im l o 0C 09 5 18 m1 t / n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 > a 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 .e l vg ,rP 7 E E E E E E E E E E E E E E E E 4ea ) o 9 8 3 0 1 2 5 3 1 1 0 3 7 7 1 7 RP Q f 4 9 8 2 6 4 2 . 2 5 2 3 . 2 4 0 7 1 7 1 1 / r o DY 2 1 1 1 3 6 6 3 1 1 1 1 2 5 4 3 (/ esg s rd riE e l ) t 0 m e0 o t m5 r 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 n a f 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 o r> C a d 6 E E E E E E E E E E E E E E E E 3 7 9 8 8 2 8 8 8 6 5 9 1 2 2 2 ( P s e s 9 2 6 5 5 0 . 5 2 3 9 5 6 2 3 1 er e 4 1 5 ns u l oa s i 3 1 1 1 3 6 7 3 1 1 1 1 2 5 4 3 A i ea M sl e E r eH L eR B p s A sl A T i e( D v 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 es 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 dL e 5 E E E E E E E E E E E E E E E E n c 8 7 5 6 5 4 5 5 6 2 2 6 5 0 5 8 ad n 2 0 3 . 8 4 5 6 2 3 4 0 8 3 7 7 8 l na 4 s ut I o s 3 2 1 1 3 6 7 3 1 1 1 1 3 5 4 3 ri cGD ir md i r r a ea rTd P n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 ga nt 4 E E E E E E E E E E E E E E E E

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0 3 5 3 9 6 9 9 . 0 8 2 0 6 2 1 1 1 1 7 1 1 1 1 1 2 2 1 1 1 9 1 1 2 2 1 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E E E E E E E E E E E E E E E E r 2 0 3 3 5 1 5 1 0 1 0 8 0 5 4 0 1 7 4 2 2 9 2 3 0 3 9 4 3 8 1 1 1 t) Qx 1 1 1 1 2 2 3 2 1 1 1 1 1 2 2 1 / e sl 1rp m 1 o 2 0C 00 2 5 11 m1 t / n 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 1 $a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 - e c l E E E E E E E E E E E E E E E E vg ,rP 9 7 6 7 8 2 3 5 4 6 4 4 9 2 2 2 9 4ea ) o 8 5 3 3 3 2 5 3 4 2 2 4 7 5 9 1 RP q f 1 1 1 / r o 1 1 1 1 2 3 3 2 1 1 1 1 2 2 2 1 DY (/ e s g s Ird rI E e ) t 0 m e0 o t m5 r 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 n a f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o r5 E E E E E E E E E E E E E E E E C a d 8 8 4 2 4 8 0 5 0 3 8 8 5 6 2 0 2 ( P se s 0 7 5 5 5 6 9 6 6 3 3 6 3 0 8 2 er e 1 8 ns u l 2 1 1 1 2 3 3 2 1 1 1 1 2 3 2 2 oas i i ea M A sl e E r eM L eR B p s A sl A T i e( D v 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 dL e E E E E E E E E E E E E E E E E 7 n c 3 5 0 2 9 3 1 1 2 4 4 4 4 8 2 B ad n 4 3 9 7 8 0 4 9 8 5 5 8 6 3 1 7 l na 1 s ut I os 2 1 1 1 2 4 4 2 1 1 1 1 2 3 3 2 ri eGD i rmd i r r a ea rTd P n 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 t a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 rt E E E E E E E E E E E E E E E E oS h 1 2 0 2 4 4 3 6 7 5 3 4 7 7 6 1 8 6 2 9 9 5 9 2 0 0 9 5 7 2 7 7 7 S r .o rf 2 2 1 1 3 4 4 3 2 1 1 2 2 3 3 2 o f 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 E E E E E E E E E E E E E E E E 1 8 9 7 0 6 2 1 0 2 5 7 4 7 6 7 5 1 2 1 7 3 1 9 4 . 6 6 3 9 9 3 . 2 9 2 3 4 3 3 2 2 2 2 3 5 5 3 2 1 1 r o N E E E E E E E S W W W W W W W t N N N S S S S S S N N N c N E E S S W W N e S l

8 3 0 5 0 5 0 ~6 6 3 4 6 9 0 2 4 6 2' 2 9 0 0 5 6 0 7 5 5 6 0 2 8 1 1 8 6 6 6 1 1 1 1 6 5 5 6 1 1 1 8 9 9 9 9 8 8 8 8 9 9 9 9 8 8 8 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7 E E E E E E E E E E E E E E E E r 2 0 2 1 6 3 1 9 4 2 6 8 0 8 1 3 3 8 5 5 6 7 2 9 9 2 0 3 2 5 4 1 1 t) Qx 8 7 6 6 1 1 1 1 7 5 5 7 1 1 1 9 /e sl r p H m o 3 0C 00 2 5 11 m1 t 9 9 8 8 8 8 / n 8 9 9 9 8 8 8 8 9 9 1 1a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 '. e l vg ,rP 6 E E E E E E E E E E E E E E E E 5 0 1 8 2 0 9 2 3 1 2 1 5 3 4 2 4ea ) o RP q f 2 0 7 6 5 3 9 0 3 2 9 2 2 5 4 7 1 1 1 / ro 8 7 7 1 1 2 1 8 6 6 8 1 1 1 1 DY 1 (/ e . s g srd r1 E 1 e - ) t 0 'm e0 o r 8 9 9 9 8 8 8 8 9 9 9 9 8 8 8 8 m 5.f t 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 n a o r1 E E E E E E E E E E E E E E E E C a d 5 9 2 2 9 8 6 6 9 0 7 8 7 6 9 1 7 ( P s e s er e 2 0 9 9 3 9 3 7 3 7 3 5 5 1 1 1 1 8 ns u l oas i 1 9 7 7 1 1 2 1 8 7 7 8 1 1 1 1 ~. A i ea M sl e E r eM L eR B p s A sl A T ie( Dv 8 9 9 9 8 8 8 8 9 9 9 9 8 8 8 8 es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 dL e E E E E E E E E E E E E E E E E 4 n .c 9 6 8 9 7 5 4 7 7 0 0 9 6 1 0 6 ad n 0 2 4 7 6 0 3 7 6 2 9 5 6 4 1 l na 2 1 i sut I os 1 9 8 8 l 2 2 1 9 7 7 9 1 1 1 1 ri eGD irmd i rr a ea rTd P n 8 8 9 9 8 8 8 8 9 9 9 9 8 8 8 8 t a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 rt E E E E E E E E E E E E E E E E o S. h 2 9 8 4 5 0 4 3 0 7 7 5 9 8 6 4 7 2 0 3 4 6 2 4 6 9 3 2 8 4 8 7 3 S r . o rf 1 1 9 9 1 2 2 1 9 8 8 9 1 1 1 1 o f 8 8 8 8 8 8 8 8 8 9 9 8 8 8 8 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 E E E E E E E E E E E E E E E E 1 8 2 3 4 4 6 4 9 4 0 8 2 2 0 0 2 4 0 0 7 4 6 7 0 . 0 0 6 0 9 5 1 1 1 1 1 1 1 2 2 1 1 9 9 1 1 2 1 1 o N E E E E E E E S W W W W W W W r t N N N S S S S S S N N N c N E E S S W W N e S

1 6 9 2 9 3 6 9 6 1 0 6 2 1 1 3 3 3 4 8 9 6 5 0 6 4 5 2 8 3 6 1 1 5 4 3 3 6 9 1 6 4 3 3 4 6 7 7 5 9 9 9 9 9 8 8 9 9 9 9 9 9 9 9 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 E E E E E E E E E E E E E E E E r 3 3 2 1 6 9 1 2 8 1 1 0 0 8 7 2 7 0 0 0 4 6 7 4 5 2 7 9 1 6 '1 1 7 t) Qx /e 5 4 4 4 7 1 1 7 4 3 3 4 6 8 7 5 sl t p l m I o 4 0C 00 2 5 11 m1 t / n 9 9 9 9 9 8 8 9 9 9 9 9 9 9 9 9 1 $a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .e - l vg ,rP 3 E E E E E E E E E E E E E E E E 7 0 6 1 2 7 9 2 8 2 3 7 7 6 9 3 4 ea ) o 3 9 0 3 4 5 0 5 6 8 9 6 9 1 7 1 RP q f 3 { } / ro DY 5 5 4 4 7 1 1 7 4 3 3 4 6 8 8 6 (/ es g srd rliE e ) t 0 m e0 o t m5 r 9 9 9 9 9 8 8 9 9 9 9 9 9 9 9 9 n a f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o ri C a d 2 E E E E E E E E E E E E E E E E 5 2 4 9 0 4 7 0 8 6 7 6 0 1 0 3 ( P s e s er e 3 3 3 6 6 0 . 2 0 9 0 9 4 3 7 7 1 1 8 ns u l oa s i 6 5 4 4 8 1 1 8 4 4 4 4 7 9 8 6 i A i ea t sl c f E r ei L eR B p s A sl A T i e( D v 9 9 9 9 9 8 8 9 9 9 9 9 9 9 9 9 es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 dL e n c 1 E E E E E E E E E E E E E E E E ad n 6 6 4 0 2 1 5 2 1 2 5 8 7 2 6 7 sut . 6 9 0 5 2 3 5 3 3 4 2 8 9 2 1 l na 3 7 I os 6 5 4 5 8 1 1 8 5 4 4 5 7 9 9 7 ri eGD i r md i r r aea rTd P n 9 9 9 9 9 8 8 9 9 9 9 9 9 8 9 9 t a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 rt E E E E E E E E E E E E E E E E oS h 3 2 4 7 3 0 0 4 1 7 1 4 4 9 6 8 6 2 0 2 3 3 4 6 6 . 6 3 0 8 6 1 1 7 S r o rf 7 6 5 5 9 1 1 9 5 4 4 5 8 1 9 7 o f 9 9 9 9 9 8 8 9 9 9 9 9 9 8 8 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9 E E E E E E E E E E E E E E E E 2 8 4 4 9 8 9 5 8 7 6 8 4 6 3 7 6 3 . 0 2 1 7 3 2 1 1 2 6 4 6 6 5 8 7 6 5 5 9 1 1 9 6 5 5 6 9 '

R r

o N E E E E E E E S W W W W W W W t N N N S S S S S S N N N c N E E S S W W N e S

2 E E E E E E E E E E E E E E E E 0 1 2 4 8 6 3 7 1 0 2 2 8 5 1 4 7 7 6 6 3 6 9 4 4 9 3 4 9 1 4 7 1 3 3 2 2 4 6 7 4 2 2 2 2 4 5 5 3 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 E E E E E E E E E E E E E E E E r 4 8 6 5 7 1 8 0 0 5 1 3 6 9 2 6 3 8 2 8 8 9 9 . 9 0 5 5 0 5 7 3 7 1 t) Qx /e 3 3 2 2 4 6 7 4 3 2 2 3 4 5 5 4 sl r p I m I o 5 0C 00 2 5 11 m1 t / n 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 5a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 .e l vg ,rP 0 E E E E E E E E E E E E E E E E 7 2 0 1 5 2 9 4 0 4 6 1 1 0 3 4 4ea ) o RP q f 4 0 4 0 0 3 0 2 6 6 2 8 0 6 3 1 1 1 1 / ro DY 4 3 3 3 5 7 8 5 3 2 2 3 4 6 5 4 ( /er> g s t d riE l e ) t 0 m e0 o t m5 r 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 n a f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o r5 E E E E E E E E E E E E E E E E C a d 9 8 0 5 7 1 0 1 0 6 7 3 7 5 1 2 8 ( P s e s 2 6 . 4 5 4 3 7 8 3 0 3 9 5 1 1 7 er e 3 8 ns u l oa s i 4 3 3 3 5 7 8 5 3 2 2 3 5 6 5 4 1 A i ea 1 sl e E r ei t L eR B p s A sl A T i e( D v 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 dL e 8 E E E E E E E E E E E E E E E E n c 0 9 1 3 9 0 6 8 4 1 8 4 1 4 3 9 ad n 5 3 3 6 9 6 5 9 9 5 3 6 2 7 l n a 3 7 1 sut I os 4 3 3 3 5 8 8 5 3 2 2 3 5 6 6 4 ri eGD i r md i r r a ea rTd P n 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 t a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 rt 7 oS E E E E E E E E E E E E E E E E h 3 5 0 9 1 0 4 6 9 3 6 4 3 9 0 6 5 7 0 4 5 0 5 4 9 . 0 7 5 0 5 0 7 1 S ro rf 4 4 3 3 6 8 9 5 3 3 3 3 5 7 6 5 o f 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 E E E E E E E E E E E E E E E E 1 2 8 1 3 2 9 3 4 3 1 4 9 9 3 3 3 2 7 8 0 . 6 3 0 9 3 9 2 3 9 . 3 9 3 5 4 3 3 6 9 9 6 3 3 3 3 5 7 6 5 r o N E E E E E E E S W W W W W W W t N N N S S S S S S N N N c N E E S S W W N e S 1

9 E E E E E E E E E E E E E E E E 6 0 1 2 7 2 8 8 5 9 0 5 7 4 7 1 3 0 0 4 9 4 7 8 2 0 7 9 3 1 1 4 7 2 2 2 2 3 4 5 3 2 1 1 2 3 4 3 2 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 E E E E E E E E E E E E E E E E r 4 7 9 9 0 2 3 2 3 4 6 7 4 0 1 2 3 8 3 0 6 6 6 2 8 8 2 4 2 9 0 1 1 t) Qx /e 2 2 2 2 3 5 5 3 2 1 1 2 3 4 3 3 sl r p i m l o 6 0C 00 2 5 11 m1 t / n 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 1 ia 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .e l vg ,rP 7 E E E E E E E E E E E E E E E E 9 9 8 9 7 4 6 8 4 4 5 3 4 8 8 6 4ea ) o RP q f 4 9 4 7 . 8 7 3 9 9 5 3 0 1 1 3 3 1 1 1 / r o DY 2 2 2 2 3 5 5 3 2 1 1 2 3 4 4 3 (/ e . s g s rd rliE e ) t 0 m e0 o t m5 r 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 n a f 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o r5 E E E E E E E E E E E E E E E E 6 C a d 2 0 7 9 3 7 2 3 3 2 3 5 9 7 5 9 ( P s e s 8 ns u l . 6 2 2 9 5 9 4 0 0 4 6 5 . 2 2 er e 4 1 1 3 2 2 2 3 5 6 3 2 2 2 2 3 4 4 3 oa s i A i ea M sl e E r eH L eR B p a A sl A T e( i D v 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 es 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 dL e 5 E E E E E E E E E E E E E E E E n c 6 1 7 9 0 1 8 0 4 1 2 5 4 6 4 3 ad n l n a 4 2 . 3 3 8 3 5 5 8 7 4 4 7 1 1 1 1 sut I os 3 2 2 2 4 5 6 4 2 2 2 2 3 4 4 3 ri eGD i r md i r r a ea rTd P n 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 t a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 rt 4 oS E E E E E E E E E E E E E E E E h 4 0 4 8 9 8 7 8 8 5 0 1 7 1 8 6 0 0 6 2 6 2 . 6 0 9 6 6 2 2 4 8 4 4 S ro rf 3 2 2 2 4 6 6 4 2 2 2 2 4 4 4 3 o f 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 E E E E E E E E E E E E E E E E 4 5 7 0 1 8 5 9 8 8 0 1 9 9 0 8 6 7 2 8 5 9 6 6 4 3 9 7 . 3 4 3 7 1 3 2 2 2 4 6 6 4 2 2 2 2 4 5 4 3 r o N E E E E E E E S W W W W W W W t N N N S S S S S S N N N c N E E S S W W N e S

RT) Qx /e sl t p l m I o 7 0C 00 2 5 11 m1 t / n 1 5a .e l vg l ,rP 4ea ) o RP q f 1 1 / ro DY (/ es g s rd rliE e ) t0 m 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 e0 o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t m5 r 0 E E E E E E E E E E E E E E E E n a f 5 1 3 4 4 3 7 5 7 3 3 7 5 9 3 0 o r5 C a d 5 6 2 9 9 3 7 . 0 7 7 0 8 6 8 1 3 1 ( P s e s er e 2 2 1 1 3 4 5 3 2 1 1 2 3 3 3 2 8 ns u l oa s i i ea M A sl e E r eH L eR B p s A slA i e( r T D v o es t dL e c n c e N E E E E E E E S W W W W W W W ad n S N N N S S S S S S N N N l na N E E S S W W N sut I os .ri eGD i rmd i rr a ea rTd P n t a rt oS hS ro rf o f

H4 Rev. 10 Page 108 .( APPENDIX - B Prairie Island 12.2m Wind and AT Stability 42.7-12.2m Joint Frequency Distributions (4/1/77 - 3/31/78) i I l IBM L i.__.____

yh. Rev. 10.: JPage 109. NORTHERNgSTATES POWER COMPANY 1 lf PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY FREQUENCY DISTRIBUTION TABLES . HOURS AT EACH WIND SPEED AND DIRECTION PERIOD':. 4/1/77 THROUGH 3/31/78-STABILITY CLASS A-i' ELEVATION.40'FT-WIND SPEED-(MPH) AT 40 FT LEVEL t. . DIRECTION- -1 TO 3 ~4 TO 7~ 8 TO 12' 13 TO 18' 19 TO 24. .ABOVE 24 ' TOTAL l. N 7 22 29 11 0 0 69 .NNE' 13 19 20 4 0 0 56: NE II 35 16 1 0 0 63 ENE' 11 33 20 0 0 0 64 E~ 14- -37 24 0 0 0 75 .ESE: - 4 45 49 7 2 0 107 .SE -4 10 22 13 1 0-50 SSE. 1 7 19 12 2 0 41 S-2 23 45 27 0 0 -97 SSW-1 22 39 -14 0 0 76-SW 2 17 30 3 0 0 52 l WSW 0 21 25 II O O 57 W~ 1 29 46 18 2 0 96 WNW 6 34 64 56 20 1 181 .NW-12 42 72 53 20 0 199 NNW 11 43 49 20 2 0 125 VAR ~ 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 1408 HOURS OF CALM THIS CLASS 0 -PERCENT OF ALL DATA THIS CLASS 16.81 . IBM

H4 Rev. 10 Page 110 . NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS B-ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12' 13 TO 18 19 TO 24' ABOVE 24 TOTAL N O 3 5 1 0 'O 9 NNE 1 2 1 1 0 0 5 NE O 2 0 0 0 0 2 ENE O 3 2 0 0 0 5 E O 1 1 0 0 0 2 ESE 1 5 10 6 1 0 23 SE 2 2 8 4 0 0 16 SSE O 3 4 3 0 0 10 S 1 0 7 9 0 0 17 SSW 0 1 7 0 0 0 8 SW 0 4 1 0 0 0 5 WSW 1 2 5 1 0 0 9 V 0 8 7 3 0 0 18 WhN 1 5 8 6 3 0 23 hN 2 4 11 10 1 0 28 NNV 1 5 3 1 0 1 11 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 191 HOURS OF CAI.'i THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS 2.28 IBM I _ _ _ ___ _ __-__D

H4 Rev. 10 Page 111 -NORTHERN. STATES PokIR COMPAhT l PRAIRIE ISLAND NUCLEAR GEhTRATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES =: HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 TID?OUGH 3/31/78 STABILITY CLASS C ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 2 4 4 1 0 0 11 NNE 2 3 1 0

0 0

6 hT 1 5 1 0 0 0 7 EhT 0 3 1 0 0 0 4 E 1 8 3 0 0 0 12 ESE O 7 Il 2 0 0 20 s SE O 2 5 6 0 0 13 SSE O 2 6 7 1 0 16 S 0 2 10 4 0 0 16 SSW 1 6 4 0 0 0 11 SW 2 2 3 2 0 0 9 l WSW I 6 5 1 2 0 15 W 0 2 II 4 1 0 IB WhN 1 3 6 7 1 0 18 l hv 2 7 il 16 6 1 43 NNW 3 5 7 3 3 0 21 VAR 0 0 0 0 0 0 0 l TOTAL HOURS THIS CLASS 240 HOURS OF CALM THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS 2.87 IBM I a

H4 Rev. 10 Page 112 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT I SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH. WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS D ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1-TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL J l N 9 24 11 8 0 0 52 NNE 6 22 9 0 0 0 37 hI 16 26 4 0 0 0 46 ENE 11 41 4 0 0 0 56 E 11 95 27 0 0 0 133 ESE 8 57 154 19 0 0 238 SE 10 30 90 38 5 0 173 SSE 8 40 59 51 10 0 168 S 1 51 72 17 4 0 145 SSW 5 29 30 12 0 0 76 SW 4 15 17 4 0 0 40 WEf 5 23 31 21 3 4 87 W 6 53 61 28 6 1 155 W/ 14 57 76 75 21 0 243 NW 14 44 72 110 41 0 281 NNW 16 22 41 25 13 0 117 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 2051 HOURS OF CALM THIS CLASS 4 PERCENT OF ALL DATA THIS CLASS 24.49 IBM

H4 Rev. 10 Page 113 NORTHERN STATES POWER COMPANY L -- PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PEEIOD: 4/1/77 THROUGH 3/31/78 'S'rABILITY CLASS E ELEVATION 40 FT WIND SPE,ED (MPH) AT 40 FT LEVEL ^ DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOG 24 TOTAL N 22 30 9 11 1 0 73 NNE 18 29 7 0 0 0 54 NE 22 26 7 1 0 0 56 ENE 19 30 5 1 0 0 55 E 25 96 10 0 0 0 131 ESE 28 144 140 27 0 0 349 ,i SE 24 107 125 41 2 0 299 SSE 21 67 74 23 0 0 185 S 11 56 73 29 1 0 170 SSW 3 26 29 40 1 0 99 i SW 14 22 17 12 0 0 65 WSW 14 24 24 11 1 0 74 l W 26 73 -48 18 1 0 166 WNW 46 136 127 44 4 0 357 NW 46 98 101 62 8 0 315 NNW 43 53 48 10 3 0 157 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 2612 HOURS OF CALM THIS CLASS 7 PERCENT OF ALL DATA THIS CLASS 31.18 IBM

A W H4 Rev. 10. l' Page 114 NORTHERN STATES-POWER COMPANY b PRAIRIE ISLAND NUCLEAR GENERATING PLANT' SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES-HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78- -STABILITY CLASS F ELEVATION 40 Ft' WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3' 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N .18 8 3 0 0 0 29 NNE '11 6 1 0 0 0

18 NE 11 5

'2 0 0, 0-I8' ENE. 13-7 0 0 0 0 20 E 29 33 2 0 0 0 64 ESE 39 61 9 1 0 0 110 j. SE 38. 69. 36 3 0 0-146 SSE 27 32 17 2 1 0 79 S 12 16 21 7 0 0 56 SSW 6 11 17 6 0 0 40 SW 5 3 9 4 0 0 .21 WSV 8 8 8 0 0 0 24 W 25 39 12 2 0 0 78 WNW 56 63 12 0 0 0 131 -NW 66 71 16 3 0 0 156 NNW 29 19 6 2 0 0 56-VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 1053 HOURS OF CALM THIS CLASS 7 ' PERCENT OF ALL DATA THIS CLASS 12.57 IBM

M4 Rev. 10 Page 115 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT I, SITE MEHOROLOGY - FPIQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS G ELEVATION 40 FT WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 14 5 0 0 0 0 19 NNE 13 2 1 0 0 0 16 hT 12 2 1 0 0 0 15 Eh1 - 22 1 2 0 0 0 25 E 52 8 2 0 0 0 62 ESE 50 17 1 0 0 0 68 SE 37 23 8 1 0 0 69 SSE 18 8 7 2 0 0 35 S 11 4 4 0 0 0 19 SSW 13 2 2 0 0 0 17 SW 15 5 1 0 0 0 21 WSW 10 1 1 0 0 0 12 W 41 19 1 0 0 0 61 Whv 75 50 0 0 0 0 125 NV 80 66 3 0 0 0 149 Nhv 47 19 5 0 0 0 71 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 821 HOURS OF CALM THIS CLASS 37 PERCENT OF ALL DATA THIS CLASS 9.80 IBM i

H4 Rev. 10 Page 116 f-APPENDIX C DOSE PARAMETERS FOR RADIOlODINES, PARTICULATE AND TRlTlUM This appendix contains the methodology which was used to calculate the dose parameters for.radiciodines, particulate, and tritium to show compliance with 10 CFR 20 and Appendix 1 of 10 CFR 50 for gaseous effluents. These dose parameters, P. and R, were i calculated using the methodology outlined in NURlG-0133 along with Regulatory Guide 1.109 Revision 1. The following sections provide the specific methodology which was utilized in calculating the P and R values for the various exposure g g pathways. C.1 Calculation of P. The parameter, P contained in the radiciodine and particulatesporbionofSection3.2,includespathway transport parameters of the ith radionuclides, 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.l.1 Inhalation Pathuay K'(BR) DFA. (C.1-1) P. = 1 1 I where: dose parameter for radionuclides i for the P. = 3 inhalation pathway, mrem /yr per pCi/m ; 1 1 K' = a constant of unit conversion: 6 = 10 pCi/pci; 1 tgebreathingrateoftheinfant age group, BR = m fyr; the maximum organ inhalation dose factor DFA. = for the infant age group for radionuclides i, 1 mrem /pci. IBM

l-H6-l: Rev. 10' E Page 117 L The. age group 1 considered is the igfant' group. The infant!s < breathing rate is taken as 1400 m /yr from. Table E-5 of-Regulatory Guide.l.109 Revision 1. The' inhalation' dose- -factors forJthe infant, DFA are presented in Table E-10 ofRegulatoryGuide'l.109ik, units-ofmrem/pCi. The total ' body istconsidered as an organ-in the selection of.DFA. The incorporation of breathing rate of an ' infant and tke-c_ unit conversion factor results in the following: 9 1.4 x 10 DFA (C.1-2) 'P = g 1 I C.2 Calculation of'R.. The'radioiodine 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 various locations. 'R. val s-' have been calculated for the adult, teen, child, And-in_ ant age groups for the ground plane, cow. milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these. values.is presented below. C.2.1 Inhalation Pathway K'(BR),.(DFA ), (C.2-1) R = 1 g I where: dose factor for each identified R. =- 1 radionuclides i of the organ of interest, 1 3 mrem /yr per pCi/m ; a constant of unit conversion: K' = 6 = 10 pCi/pci; breathing ratg of. the receptor of (BR), = age group a,m fyr: org&n inhalation dose factor for (DFA ),. = f radionuclides i for the receptor of age group a, mrem /pCi. for the various age groups are The breathing rates (BR), in Table E-5 of the Regulatory tabulated below, as given Guide 1.109 Revision 1. IBM 1

H4 Rev. 10 Page 118 3 i Age Group (a) Breathing Rate-(m /yr) Infant 1400 child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA for the various age groups are given in Tables E-7 throbg)d E-10 of Regulatory Guide 1.109 Revision 1. C.2.2 Ground Plane Pathway I K'K"(SF)DFG (1-e ) D., (C.2-2) R = g g where: dose factor for the ground plane pathway R. = l for each identified radionuclides i for a the organ of ipterest, mrem /yr per pCi/sec per m a constant of unit conversion; K' = 6 10 pCi/pci; = a constant of unit conversion; K" = 8760 hr/ year; = the radiological decgy constant for A. = 1 radionuclides i, sec the exposure time, see; t = 8 i~ 4.73 x 10 see (15 years); the ground plane dose conversion factgr DFG = g for radionuclides i; mrem /hr per pCi/m ; I the shielding factor (dimensionless); SF = factor to account for fractional 1. = deposition of radionuclides i. 1 For radionuclides other than iodine, the factor I is For radiciodines, the value of I ay equal to one. However,avalueof1.0wasusedincaledlating vary. the R values in Table 3.3-2. l IBM i

H4 rI Rev. 10 Page 119-A shielding. factor of O'.7 is suggested in. Table.E,. - L.; of Regulatory Guide 1.109~ Revision 1.- A tabulation b of DFG. values.is presented in Table E-6 of Regulatory Guide 1.109 Revision 1. C.2.3 Grass-Cow or Goat-Milk Pathway- ~A t . _A t I"( f b} '+

(I~*

I ) + R - F ap m(DFL )a F e ff b = I K'Q U i ps YA PA i pE. .i s g -A E ~ ~ ~ r(1-e i e) '+ B (1-e 1 b) 4t (g_f f ) gy fh (C.2-3) Ps YA gE PA i 1 where: dose ~ factor for the cow' milk or goat milk R =- gn pathway, for each identified radionuclides i for the organ gf interest, mrem /yr per pCi/sec per m a constant of unit conversion;

K'

= 6 = 10 pCi/pci; the cow's or goat's feed consumption rate, .Q = F kg/ day (wet weight); the receptor's milk consumption rate for age U = ap group a, liters /yr; the agricultural productivi3y by unit area .Y = p of pasture feed grass, kg/m ; theagriculturalproguctivitybyunitarea Y = s of stored feed, kg/m ; the stable element transfer coefficients, F* = pCi/ liter per pCi/ day; fraction of deposited activity retained on r = cow's feed grass; the organ ingestion dose factor for (DFL ), e f radionuclides i for the receptor in age group a, mrem /pCi; i 1BM

H4 Rev. 10 Page 120 A Ai+A I E w the radiological decgy. constant for i A. = 1 radionuclides i, sec A" the decay constant for removal of activity = on lyaf and plant surfaces by weathering, sec 5.73 x 10~7 -1 (corresponding to a see = l 14 day half-life); the transport time from feed to cow or goat t = f to milk, to receptor, see; the transport time from harvest, to cow or t = h goat,.to consumption, sec; period of time that ced W nt is e,xposed to t = b gaseous effluents sec; concentration. factor for uptake of B = iv radionuclides i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil); effectiye surface density for soil, (dry i-P = soil)/m ; fraction of the year that the cow or goat f = p is on pasture; fraction of the cow feed that is pasture f = grass while the cow is on pasture; s t* period of pasture grass and crop exposure = during the growing season, sec; 1. = factor to account for fractional deposition 1 of radionuclides i. For radionuclides other than iodine, the factor I, is equal to one. For radiciodines, the value of 1 6ay vary.However,avalueof1.0wasusedincalcukating the R values Tables 3.3-9 through 3.3-16. Milk cattle and goats are considered to be fed from two potential scurces, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of f was considered unity in lieu of site-specific information. The value of fp was 0.667 based upon an 8 ~ month grazing period. IBM

H4 - y Rev.. 10 Page 121-I Table C-1 contains the appropriate parameter. values and .their source in Regulatory Guide.l.109 Revision 1. D The concentration of tritium in milk is-based on the airborne concentration rather.than the deposition. Therefore, the-R is based on'X/Q: g K ' K" ' F,Q U,p (DFL ), 0.75_(0.5/H). (C.2-4) R = p y T M where: dose factor.for the' cow or goat milk pathway R7: = H fortritiumfortge.organofinterest,. mrem /yr per pCi/m ; l.

a. constant of unit conversion;

,K"' = = '103'gm/kg; 3 absolute humidity of the atmosphere, gm/m ; l H =- ,the fraction of total feed that isLwater; l 0.75 = the. ratio of the specific activity of.'the-0.5 = feed grass water to the atmospheric water. and other parameters 3nd values are given above. 5 value p .of'H of 8 grams / meter, was used in-lieu of site-specific information. C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore: -A f ~ 1*s r(1-e 1 *) +Bgy(1-e f 3h _A e ~ + F ap,M ), e f f, yx F I g p PE i i 1 - _x t iv( } ~ e i (C.2-5)~ r(1-e i ) + (1-f f ) ps Y,AE i I .where: dose factor for the meat ingestion pathway R = f for radionuclides i for any2;rgan of interest, 3 .{ mrem /yr per pCi/sec per m l l IBM 1 l l J

m7 i' H4 Rev.-10 Page 122- -. - ~ the stable element transfer coefficients,

F

=. ~ f pCi/Kg per.pCi/ day; .the receptor's meat consumption rate for age f U = ap-i_ group a, kg/yr; the transport time'from slaughter to-t = g consumption, sec; g 1' .the. transport time.from' harvest to animal t = h consumption, sec; r < t* period of pasture grass and crop exposure = during the. growing season, sec; .1 = factor to account for fractional deposition 1 of radionuclides i. For. radionuclides other than iodine, the factor 1. is equal For radioiodines, the'value of I. may vafy. -to one. However,.a value of 1.0 was used in calculating the R-values in Tables 3.3-6 through.3.3-8. All other terms remain the same as defined in Equation C.2-3. Table C-2 contains the values which were used { int calculating R for the meat pathway. g The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R is based on X/Q. g K'K"'F Q U,p(DFL ), 0.75(0.5/H) (C.2-6) Eh = fF g where: dose factor for the meat ingestion pathway R = T for tritium for agy organ of interest, a mrem /yr per pCi/m I All other terms are defined in Equation C.2-4 and C.2-5, l 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 betwee.1 harvest and consumption, therefore: IBM 4

~ LRev. 10-p Page 123 ~A t J -A t IV( i b} iL

I1~"

i ) + Uf e + b = ' K'(DFL ), R g 7vE. 1. i ~~ ~ -x t I ) iv( ~ i b} ~ -A t -) g - (1-* (C.2-7) SUN* + ag- .Y A E i l' .J. where: dose factor.'for vegetable' pathway for R. = ly' radionuclides i for the organ of-injerest, mrem /yr per.pCi/sec. per m a a constant of unit conversion:. K' '= 6 10 :pCi/pCi; = 1 L the consumption rate of fresh leafy U, = vegetation by the receptor'in. age l, groupfa, kg/yr; Uf the~ consumption rateof stored = vegetation by the receptor in age group a, kg/yr;- the fraction of-the annual intake of f = b fresh leafy vegetation grown locally; the fraction of the annual. intake of f = 8 stored vegetation grown locally; the average tirae between harvest of t = g leafy vegetation and its consumption,. sec; the average time between harvest of t = h stored vegetation and its consumption, sec; the vegetation areal density, kg/m ;. Y = y t, period of leafy vegetable exposure = during growing season, sec; I. = factor to account for fractional deposition of radionuclides i. 1 IBM

H4 Rev. 10 Page 124 For radionuclides other than iodine, the factor 1. is For radioiodines, the value of I day equal to one. However, a value of 1.0 was used in calculating vary. the R values in cab.les 3.3-9 through 3.3-12. All other factors were defined above. Table C-3 presents the appropriate parambter values and their source in Regulatory Guide 1.109 Revision 1. In lieu of site-specific data default values for fg and f, 1.0 and 0.76, respectively were used in the ellculation of R Thes'e values were obtained from TableE-15ofReku.latory. Guide 1.109 Revision 1. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R is based on X/Q: 1 R y t U,f (DFL ), 0.75(0.5/H) (C.2-8) T =.K'K"' Uf + f ~ where: dose factor for the vegetable pathway for R = T tritium fgr any organ of interest, mrem /yr y per pCi/m All other terms remain the same as those in Equations C.2-4 and C.2-7. l l 1BM .d

H4 Rev. 10 l: Page 125 1'(- TABLE C-1 Parameters For Cow and Goat Milk Pathways ~ Parameter Value-Reference (Reg. Guide 1.109 Rev. 1 Qp (kg/ day) 50 (cow) Table E-3 6 (goat) Table'E-3 2 Yp (kg/m ) 0.7 Table E-15 g (seconds) 1.73 x 105 (2 days) Table E-15 f-. t r 1.0 (radioiodines)' Table E-15 0.2 (particulate) Table E-15 (DFL ),'(mrem /pCi) Each radionuclides' Tables E-11 to E-14 g F* (pCi/ day per pCi/ liter) Each stable element Table E-1 (cow) Table E-2 (goat) b (seconds) 4.73 x 100 (15 yr) Table E t Y, (kg/m ) 2.0 Table E-15 2 0.7 Table E-15 p (kg/m ) Y g (seconds) 7.78 x 106 (90 days) Table E-15 t 330 infant Table E-5 ap (liters /yr) U 330 child Table E-5 400 teen Table E-5 310 adult Table E-5

(seconds) 2.59 x 106 (Pasture)

Tab'le E-15 t 5.18 x 10 (stored feed) Each stable element Table E-1 [Er(pCi/Kg(wetweight) 'B. pCi/Kg (dry soil)) ? (Kg (dry soil /m ) 240 Table E-15 IBM

g W n H4' Rev. 10 H Page 126- [ TABLE C-2 Parameters For The Meat Pathway ' Parameter Value Reference (Reg. Guide 1.109 Rev. 1-f r_ 1.0.(radioiodines)

Table E-15 0.2,(particulate)

Table E - F -(pCi/Kg per pCi/ day); Each stable. element Table E f 0 infant Table E-5 ap.(Kg/yr) F - U 41 child Table E-5 65-teen Table E-5 110 adult Table E-5 (DEL ), (mrem /pci) Each radionuclides Tables E-11 to E-14 g 2 Y- (kg/m ) 0.7 Table E-15 P 2 ),. Y, (kg/m ) 2.0 Table E-15 b (see nds) 4.73 x 108 (15 yr) Table E t-t, (seconds) 1.73 x 106 (20 days) Table E-15 (seconds) 7.78 x 106 (90 days)- Table E-15

(seconds) 2.59 x 106 (Pasture)

Table E-15 t 5.18 x 10 '(stored feed) 50 Table E-3 QF (kg/ day) - B (pCi/Kg (vet weight) Each stable element Table E-1 gy per pCi/Kg (dry soil)) 2 P (Kg'(dry soil)/m ) 240 Table E-15 - IBM I

<j- .M Rev.-10 Page 127 ,fu,, t TABLE C-3' Paramete'rs For-The. Vegetable Pathway - Parameter. Value. Reference (Reg. Guide 1.109 Rev. 1- -'r (dimensionless) 1.0 (radiciodines) ' Table E - .0.2 (particulate) Table E-1 s ' (DFL ), (mrem /Ci). Each radionuclides Tables E-11 to E-14' g U* (kg/yr) ' - Infant 0 Table 5-5 ~ .- Child 26' Table E - Teen 42 Tabl'e E - Adult 64 Table'E-5 U" (kg/yr)-' -~ Infant' '0 Table E / - Child .520 Table E-5 / - Teen 630 Table E-5 ) - Adult 520 Table E-5 h': .t{(seconds)_ 8.6 x 10 (1 day) Table E-15 t{(seconds) 5.18 x 106 (60 days) Table E-15 I 2 Y (kg/m ) 2.0 Table E-15 ^ y g(seconds) 5.18 x 106 (60 days) Table E-15 t y (seconds) 4.73 x 108 (15 yr) Table E-15 t 2 P(Kg(dry.s' oil)/m ) 240 Table E-15 Bh(pCi/Kg(wetweight)' Each stable element Table E-1 per pCi/kg (dry soil)) 1BM . _ _ _ _ _ - - _ _ _ _ -}}

ML20246P131

Text

1.0 INTRODUCTION

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