ML20204G119

From kanterella
Jump to navigation Jump to search
Rev 1 to Procedure 26.1, Offsite Dose Calculation Manual
ML20204G119
Person / Time
Site: Maine Yankee
Issue date: 08/31/1988
From:
Maine Yankee
To:
Shared Package
ML20204G096 List:
References
26.1, NUDOCS 8810240056
Download: ML20204G119 (63)
v • d • e


Text

,

v.

'4 ffoc. No. H.1 Rev. No.

I Page 25 of 88 AIIACitiDG_.I NAINE YANKEE ATONIC POWER COMPANY OFF-5(TE DOSE CALCULATION MANUAL l

t t

t

[

b I

I l

i i

i L

i Yankee Atomic Electric Company Nuclear Services Civision 1671 Worcester Road

[

framingham. MA 01701 i

[

8010240056 880831 PDR ADOCK 05000309 L

R PDC

\\

9530L-DS l

L

Proco Noo 2601 Rev. No.

1 Page 76 of 88 ATTACHMENT I MINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MNUAL DISCLAIMER OF RESPONSIBILITY This document was prepared by Yankee Atomic Electric Company ("Yankee").

The use of information contained in this document by anyone other than Yankee, or the Organization for which the document was prepared under contract, is not authorized and, with reinset to any unauthorized ute, neither Yankee nor its officers, directors, agents, or* employees assume any obligation, responsibility, or liability or make any warranty or representation as to the accuracy or completeness of the material contained in this document.

l i

I L

is 9530L-05

Proc. No. 26.1 Rev. No.

1 Page 27 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL ABSTRACT The Maine Yankee Nuclear Power Station Off-Site Dose Calculation Manual i

(NY 00CM) contains the approved methods to estimate the doses and radionuclide concentrations occurring beyond the boundaries of the plant caused by normal plant operatloc. With initial approval by the U.S. Nuclear Regulatory Commission and the NYMPS Plant Management and approval of subsequent revisions by the Plant Management (as per the Technical Specifications), this 00CM is suitable to show compliance where referred to by the Plant Technical Specifications. Sufficient documentation of each method is provided to allev regeneration of the methods with few references to other material. Most of the methods are presented at two levels. The first. Method I, is a linear equation which provides an' upper bound and the second. Method II 15 an in-depth analysis which can provide more realistic estimates.

9 4

9530L-OS

Proc. 400. 24.1 r

Rev. No.

1 Page 28 of 88 l

t ATTACHMENT I i

MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL i

TABLE OF CONTENTS EASA O!SCLAINER OF RESPONSIBILITY.....................................

26 ABSTRACT.........................................................

27 I

LIST OF FIGURES..................................................

31 32 LIST OF TABLES...................................................

33 l

1.0 INTR 000CTION.....................................................

34 2.0 LIQUID EFFLUENT DOSE CALCULATIONS................................

i 2.1 Technical Specification 3.16.B.1. Dose to an Individua1............................................

34 2.1.1 Dose to the Total Body.................................

34 L

l 2.1.2 Dose to the Critical 0rgan.............................

36 k

3.0 GASEOUS EF F LUENT DOSE CALCULATIONS...............................

38 f

t 3.1 Technical Specification 3.17.A.1 Gaseous Effluent Dose Rate..........................................

38

[

3.1.1 Dose Rate to the total Body from Noble Gases.......................................

38 l

3.1.2 Dose Rata to the Skin 40 from Noble Gases.......................................

i 3.1.3 Dose Rate to the Critical Organ 41 from Radiciodines and Particulates.....................

1.2 Technical Specification 3.17.5.1 Gaseous

}

42 Effluent Dose from Noble Gases..............................

l 42 3.2.1 Gamma Air Dose.........................................

j 43 l

3.2.2 Beta Air Dose..........................................

l j

e v

I 9530L-05 1

e Proc. No. 26.1

~

Rev. No.

1 Page 29 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POMER CG4PANY OFF-SITE DCSE CALCULATION MANUAL IARLE OF CONTENTS ELat 3.3 Technical Specification 3.17.C.1. Gaseous Effluent Dose from Indine-151. Zodine-133. Tritium, and Radioactive Material in Particulate Fora................................

44 3.3.1 Dose to the Critical 0rgan.............................

45 4.0 ENVIRONMENTAL MONITORING.........................................

50 5.0 HONITOR SETP0!NTS................................................

60 5.1 T6chnical Specification 4.13.8 Liquid Effluent Monitor Setpoints...........................................

60 5.1.1 Allowable Concentrations of Radioactive Materials in Liquid Effluents....................................

60 3.1.2 Monitor Response for Liquid Effluents..................

62 5.2 Technical Specification 4.13.0. Gaseous Effluent Monitor Setpoints...........................................

63' 5.2.1 Allowable Concentrations of Radioactive Materials 64 2

in Gaseous Effluents...................................

5.2.2 Monitor Respcase for Gaseous Effluents.................

65 68 i

6.0 METEOROLOGY......................................................

L APPENDIX A BASIS FOR TNE DOSE CALCULATION METH005.................

72 l

72 A.1 Liquid Effluent Doses.......................................

t 75 A.2 Total Body Dose Rate from Noble Gases.......................

77 l

A.3 Skin Oose Rate from Noble Gases.............................

A.4 Critical Organ Dose Rate from Iodines and Particulates......

79 9530L-05 mm m.

m

Ptst. Mo. 26.1 Rev. No. 1 Page 30 of 88 f

i ATTACMMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL i

TABLE OF CONTENTS F.Hi 80 A.5 Gamma Air Dose..............................................

81 A.6 Beta Air Dose...............................................

82 A.7 Dose from Iodines and Particulates..........................

86 APPENDIX B Meteorology............................................

88 REFERENCES.......................................................

)

I 1

5 4

l P

P 1

i I

I I

L I

f I

i P

t i

l i

s 9530L-DS I

Proco Moo 26.1 Rev. No.

1 L

Page 31 of 88 ATTACHNENT I l

MAINE YANKEE ATOMIC PONER COMPANY OFF-SITE DOSE CALCULATION MANUAL LIST OF FIGURES L

Numbe,'

li,tig Eggt 4.1 Environmental Radiological Sampling Locations 54 Within 1 Kilometer of Maine Yankee 4.2 Environmental Radiological Sampling Locations 55 Within 12 Kilometers of Maine Yankee 4.3 Environmental Radiological Sampling Locations 56 Outside 12 Kilometers from Maine Yankee 4.4 Direct Radiation Monitoring Locations Within 57 1 Kilometer of Maine Yankee 4.5 Direct Radiation Monitoring Locations Within 58 e

12 Kilometers of Maine Yankee 4.6 Direct Radiation Monitoring Locations Outside 59 12 Kilometers from Maine Yankee 5.1 Maine Yankee Liquid Radwaste System 66 5.2 Maine Yankee Gaseous Radwaste System 67 l

?

i I

l l

i 1

9530L-05

Proc.-No. 26.1 Rev. No.

1 Page 32 of 88 T

ATTACHMENT I MAINE YANKEE ATOMIC PONER COMPANY OFF-SITE DOSE CALCULATION MANUAL l

LIST OF TABLES Number I111,g Eggt 2.)

Maine Yankee Dose Factors for Liquid Releases 37 3.1 Maine Yankee Dose Factors for Noble Gas Releases 47 3.2 Maine Yankee Dose Factors for Iodines, Tritium, and 48 l

Particulate Releases 3.3 Maine Yankee Dose Factors for Iodine. Tritium, and 49 I

Particulate Released Via the Auxiliary Boiler 4.1 Radiological Environmental Monitoring Stations 51 t

6.1 Maine Yankee Maximum Annual Average Atmospheric 69 Dilution Factors A-1 Usage Factors for Various Liquid Pathways at Maine Yankee 74 A-2 Usage Factors for Various Gaseous Pathways at Maine Yankee 84 A-3 Environmental Parameters for Gaseous Effluents at Maine 85 I

Yankee l

l I

i

[

i 9530L-05 t

Proc. No. 26.1 Rev. No.

1 Page 33 of 88 ATTACHMENT I HAINE YANKEE ATOMIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL

1.0 INTRODUCTION

The purpose of this manual is to provide methods to ensure compliance with the dose requirements of the Technical Specifications.

Fach method is based on a plant-specific application of the models presented in Regulatory Guide 1.109 (Reference 1).

Methods are included to calculate the doses to individuals from both gaseous and liquid releases from the plant. Under normal operations, experience has shown that the plant will be operated at a small fraction of the dose limits imposed by the Technical Specifications.

For this reason, the dose evaluations are presented at different levels of sophistication.

The first method being the most conservative, but simplest to use; the second method requiring a full analysis following the guidance presented in Regulatory Guide 1.109 (Referent.e 1).

The first method, Method I, is based on a critical organ, critical age group, and critical receptor location; as such, it provides a conservative estimate of the doses required by the Technical Specifications.

If the Technical Specifications are met by application of the first method, no further analysis will bo required.

If, however, it indicates that the Technical Specification limits may be ap;. roached or exceeded, a more realistic estimate may be obtained by application of the second method.

The second method, Method !!, will calculate the dose to seven organs of four age groups for potentially critical individuais.

It is based on measured releases for each nuclide, site-specific parameters, and measured meteorological parameters. Method !! is more accurate, but less conservative than hathod I, and will be used to assess doses for the Semiannual Radioactive Effluent Release Report.

Liquid effluent dose calculation methods are presented in Chapter 2.

Gaseous effluent dose calculatica methods in Chapter 3.

In both chapters relevant Technical Specifications are followed by the apprcpriate Nethod I dose equation >. When necessary. Method !! analyses may be performed by applying the site-specific parameters and etasured meteorological paraette. s to the appropriate dose equations specified in Regulatory Guide 1.109 (Reference 1).

The basis for each of the dose calculation methods is described in Appendix A.

9530L-DS

M oc. No. 26.1 Rev. No.

1 Page 34 of 88 i

ATTACHMENT I a.

MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL l

f 2.0 LIOUID EFFLUENT DOSE CALCULATIONS 2.)

Technigal Snecification 3.16.B.1. Lieutd Effluent Deze to an Individual Technical Specification 3.16.8.1 limits the dose or dose connitment to a member of the public from radioactive materials in liquid effluents released I

from the site to Back River:

a.

during any calendar quarter to less than or equal to 1.5 mrem to the total body, and to less than or equal to 5 mrem to any organ; and b.

during any calendar year to less than or equal to 3 mrem to the total body, and to less than or equal to 10 ares to any organ.

L f

2.1.1.a Done to the Total Body (Methed I)

The total body dose in mrem for a 11guld release is:

(2-1) tb

  • K r' 0 0Flitb O

1 1

where:

Qt is the total activity released for radionuclide 1. in C1 (for strontiums use the most recent measurema.nt available); and DFlitb is the site specific total body liquid dose factor for radionuclide

1. in sres/C) (see Table 2-1).

i K

is equal to 935/F ; where Fd is the average (typically monthly l

d average) dilution flow of the Circulating Water System at the point r

3 of dischar,e frem the multiport diffuser (in ft /sec).

L i

i

{

l 9530L-OS

s M wc. M. 26.1 Rev. No.

1 Page 35 of 84 ATTACHMENT I MAINE YANKEE ATOMIC PONER COMPANY OFF-SITE DOSE CALCULATION MANUAL 2.1.1.b Data to the Total hadv (Mathed II)

Nethod !! consists of the models, input data and assumptions (bioaccumulation factors, shore-width factor, d.se conversion factors, and transport and buildup times) in Regulatory Guide 1.10g, Rev. 1 (Reference 1),

except where site-specific data or assumptions have been identified in the 00CH. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section A.1, are also applied to Method !! assessments, except that doses calculated to the whole body from radioactive ef"luents are evaluated for each of the four age groups to determine the maximum whole body dose of an age-dependent individual via all existinti exposure pathways.

Table A-1 lists i

the usage factors for Method !! calculations.

i e

i

[

v l

t l

l P

l l

l l

l l

sssct-os i

Proc. No. 26.1 Rev. No.

1 Page.36'of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE LOSE CALCULATION K\\NUAL 2.1.2.a Dose to the Critical Oraan (Method I)

The critical organ dose in mrem for a liquid release is:

I Oco - K E Qt DFlico i

where:

Qi is the total activity released for radionuclide 1, in C1 (for strontiums use the most racent measurement available); and 0FLico is the site specific critical organ liquid dose factor for radionuclide 1 ir. mrem /C1 (see Table 2.1).

K is equal to 935/F ; where Fd is the averagc (typically monthly d

average) dilution flow of the Circulating Water System at the point 3

of discharge from the multiport diffuser (in ft /sec).

2.1.2.b Dose to the Critical Oroan (Method II)

Method II consists of the models, input data and assumptions (bicaccumulation factors, shore-width factor, dose conversion factors, and transport and buildup times) in Regulatory Guide 1.109, Rev. 1 (Reference 1),

except where site-specific data or assumptions have been identified in the OOCH.

The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I acproach as described in the Bases Section A.1, are a*so applied to Method II assessments, except that doses calculated to critical organs from radioactive ei'fluents are evaluated for each of the four age groups to determine the maximum critical organ of an age-dependent individual via all existing exposure pathways.

Table A-1 lists the usage factors for Method II calculations.

9530L-DS

u

-Proc. No. 26.1 Rev. No.

1 Page 37 of 68 ATTACHMENT I MAINE YANKEE ATOMIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL Table 2.1 Maine Yankee Dose Factors for Liauid Releases Total Body Critical Organ Dose Factor Dose Factor mrem /C1 mrem /C1 Nuclide

__QELitb DFLjce H-3 2.96E-07 2.96E-07 Na-24 2.46E-05 2.83E-OS Cr-51 1.54E-05 1.45E-03 Mn-54 4.27E-03 2.55E-02 Mn-56 1.89E-06 4.09E-06 Fe-55 1.24E-02 7.53E-02

.Fe-59 8.58E-02 6.54E-01 Co-58 2.22E-03 1s35E-02 Co-60 4.79E-02 7.80E-02 Zn-65 2.68E-01 5.39E-01 Sr-89 2.13E-04 7.45E-03 Sr-90 3.16E-02 1.29E-01 Zr-95 5.15E-04 1.74E-02 Ho-99 2.95E-05 2.63E-04 Tc-99m 3.79E-05 6.22E-05 Sb-124 1.34E-03 9.36E-03 I-131 2.07E-04 9.86E-02 I-132 2.53E-06 3.24E-06 I-133 2.46E-05 1.13E-02 4

I-135 7.26E-06 4.31E-04 3.12E-02 Cs-134 2.79E-02 Cs-137 2.92E-02 3.41E-02 Ba-140 1.54E-04 3.41E-02 Co-141 2.81E-05 9.13E-03 H-187 6.28E-06 1.32E-03 S

6 6

e f

9530L-OS I

,__.-_______-_..,e.

-froc. No.' 26.1 Rev. No.

1 Page 38 of 88 ATTACHMENT I HAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.0 GASEOUS EFFLUENT DOSE. CALCULATIONS 3.1 Technical Soecification 3.17. A.1. Gaseous Effluent Oose Rate Technical Specification 3.17.A.1 timits the dose rate (when averaged over 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary:

a.

for noble gases:

less than or equal to 500 mrem /yr to the total body, and less than or equal to 3000 mrem /yr to the skin, and; b.

for Iodine-131, Iodine-133, tritium and radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem /yr to any organ.

3.1.1.a Dose Rate to the Total Body from Noble Gases (Method I)

The total body dose rate in mrem /yr from noble gases released via the plant stack is:

(3-1) 1.40 E di DF8t 6tb

=

where:

Di is the release rate of noble gas i released via the plant stach, in uCi/sec; and DF8t is the total body dose rate factor for noble gas 1, in mrem-m3/pCi-yr (see Table 3.1).

m 9530L-OS

?

Ptnc. No. 24.1 Rev. No.

1 Page 39 of 88 ATTACHMENT I

.=

MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.1.1.b Dose Rate to the Total Body from Noble Cases (Method II)

Method II consists of the model and input data (whole body dose factors) in Regulatory Guide 1.109, Rev. 1 (Reference 1), except where site-specific data or assumptions have been identified in the OOCH.

The general equation (8-8) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section A.2, is also applied to a Method II assessment. No credit for a shielding factor (Sp) associated with residential structures is assumed.

Concurrent meteorology with the release period may be ut1112ed for the gamma atmospheric dispersion factor identified in Appendix 8 for the release point frcm which recorded effluents have been discharged.

In sectors where the site boundary is adjacent to Back River, the total body dose rate will be evaluated on the nearest opposite shoreline where the potential exist for uncontrolled occupancy. On-site areas or areas with limited and controlled occupancy will be evaluated with those occupancy factors included.

The most restrictive location in any of the 16 sectors will be used in determining the dose rate.

l i

)

9530L-OS

Proc. No. 26.1 Rev. No.

1 Page 40 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.1.2.a Dose Rate to the Skin from Noble Cases (Method I)

The skin dose rate in arem/yr from noble gases released via the plant sthek is:

(3-2) 6 skin -

D1 0F'j where:

D1 is the release rate of noble gas i released via the plant stack, in uC1/sec; and DF't is the combined skin dose rate factor for noble gas 1, in aren-sec/pC1-yr (see Table 3.1).

3.1.2.b Dose Rate to the Skin from Noble Gases (Method II)

Hethod II consists of the model.and input data (skin dose factors) in Regulatory Guide 1.109, Rev.1 (Reference 1), except where site-soecific data or assumptions have been identified in the 00CM.

The general equation (B-9) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the 8ases Section A.3, is also applied to a Method II assessment. No credit for a shielding factor (S )

F associated with residential structures is assumed. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor and undepleted atmospheric dispersion factor identified in OOCH Appendix B for the release point from which recorded effluents have been discharged.

InsectorswherethesiteboundaryisadjacenttoBackRiver,the Skin Oose Rate will be evaluated on the nearest opposite shoreline where the potential exist for uncontrolled occupancy. On-site areas or areas with limited and controlled occupancy will be evaluated with those occupancy factors included. The most restrictive location in any of the 16 sectors will be used in determining the dose rate.

9530L-OS

e e Proc. No. 26.1 Rev. No.

1 Page 41 of 88 ATTACHMENT I MAINE YANKEE ATONIC POWER COMPANY OFF-SITE D0!E CALCULATION MANUAL 3.1.3.a Dose Rate to the Critical Oraan from Radiciodines and Particulates l (Method I)

The dose rate to the critical organ in mrem /yr from iodine-131, iodine-133, tritium and radioactive materials in particulate form with half-lives greater than 8 days released via the plant stack is:

b 23 h DFG (3-3) eo ggo 1

where:

Dj is the release rate of radionuclide i released via the plant stack, in uC1/sec: and DFGjeg is the ' site specific critical organ dose rate factor for radionuclide 1, in mrem-sec/uC1-yr (see Table 3.1).

3.1.3.b Dose Rate to the Critical Oraan from Radiciodines and Particulates (Method II)

Method II consists of the models, input data and assumptions in Appendix C of Regulatory Guide 1.109, Rev. 1 (Reference 1), except where site-specific data or assumptions have been identified in the OOCH (see Tables A-2 and A-3).

The critical organ dose rate will be determined based on the location (site boundary, nearest resident, or fa'm) of receptor pathways as identified in the most recent annual land use census, or by conservatively assuming the existence of all possible pathways (such as ground plane, inhalation, ingestion of stored and leafy vegetables, milk, and meat) at an off-site locatijn of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Appendix 8 for the release point from which recorded effluents have been discharged. The maximum critical organ dose rates will consider the four age groups independently, and take no credit for a shielding factor (S ) associated w.th residential structures.

Site F

boundary locations adjacent to the river will be evaluated on the nearest opposite shoreline.

Mud flats exposed at low tide will include an occupancy factor of 0.037 for evaluation of doses at those locations.

I i

9530L-DS

Prot.1to. ' 26.1 Rev. No.

1 Page 42 of 88 ATTACHMENT I MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.2 Technical Soecification 3.17.B.1. Gaseous Effluent Dose f rom Noble Gases Technical Specification 3.17.8.1 limits the air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary to the following:

a.

during any calendar quarter:

less than or equal to 5 mrad for gama radiation, and less than or equal to 10 mrad for beta radiation; and b.

during any calendar year:

less than or equal to 10 mrad for gama radiation, and less than or equal to 20 mrad for beta radiation.

3.2.1.a Gama Air Dose (Hethod I)

The gama air dose in mrad from noble gases released via the plant stack is:

0[ir 0.044 Qt DFj (3-4) where:

I Q1 is the total activity of noble gas i released via the plant stack I

during the period of interest, in Ci; and 1

0Fj is the gama dose factor to air for noble gas'i, in mrad - m3/pCl-yr (see Table 3.1).

3.2.1.b Gama Air Dose (Method II)

Hethod II consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Revision 1 (Refarence 1), except where site-specific data or assumptions have been identified in the OOCH.

The general equations (B-4 and E-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section A.5 are also applied to Method II assessments. Concurrent meteorology with the release period may be utilized for the gama atmospheric dispersion factors (see Appendix B) for the release point from which recorded effluents have been discharged.

For sectors adjacent to the Back River, the nearest opposite shoreline with an assumed potential occupancy factor of 1007. will be used to evaluate doses. On-site areas with limited and controlled occupancy will be evaluated with those occupancy factors included.

9530L-05

-Proc. Mo. 26.1 Rev. No.

1 Page 43 of 88 ATTACHMENT I MAINE YANKEE ATOMIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.2.2.a Beta Air Dose (Method I)

The beta air dose in arad from noble gases released via the plant stack is:

If Qt OFT (3-5)

DQir 0.03 where:

Qi is the total activity of noble gas i released via the plant stack during the period of interest, in C1; and DF9 is the beta d se factor to air for noble gas 1 in mrad - m3/pC.-fr (see Table 3.2).

3.2.2.b Beta Air Oose (Method II)

Hethod II consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Revision 1 (Reference 1), except where site-specific data or assumptions have been identified in the OOCH.

The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section A.6, are also applied to Method II assessments.

Concurrent meteorology with the release period may be utilized for the atmospheric dispersion factors (see Appendix B) for the release point from which recorded effluents have been discharged.

For sectors adjacent to the Back River, the nearest opposite shoreline with an assumed potential occupancy factor of 100%

will be used to evaluate doses. On-site areas or areas with limited and controlled occupancy will be evaluated with those occupancy factors included.

I 9530L-OS

' Proc. Mo' 26.1 Rev. No.

1 Page 44 of 88

,, ATTACHMENT [

MAINE YANKEE ATONIC PONER COMPANY 0FF-SITE DOSE CALCULATION MANUAL 3.3 11thpical Snecification 3.17.C.1. Gaseous Effluent Dose from Iodine-131.

Iodine-133. Tritium. and Radioactive Material in Particulate Form Technical Specification 3.17.C.1.a and b limits the dose to a member of the pubile from iodine-131, todine-133, tritium and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary to the following:

1-'

than or eque.1 to 7.5 mrem to any a.

during any calendar quarter:

organ; and b.

during any calendar year:

ss than or equal te 15 mrem to any organ.

Technical Specification 3.17.C.1.c limits the dose to a member of the public from these same radionuclides to less th?n 0.1 percent of the limitt noted above, as a result of burning contaminated oil.

4 I

l I

I 9530L-OS

Proc.llo. 26.1 Rev. No.

1 Page 45 of 88 ATTACHMENT I MAINE YANKEE ATOMIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.3.1.4 Dose to the Critical Oraan (Method I)

The dose to the critical organ in area from todine-131, iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days released via the olant stack is:

Qt OFGjco (3-6)

Oco where:

01 is the. total activity of radionuclide i released via the plant stack during the period of interest, in C1; and DFGjco is the site specific critical organ dose factor for radionuclide i for a gaseous release from the plant stack, in mrem /Ci (see Table 3.2).

The dose to the critical organ in mrem from iodine-131, iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days releas':d to the atmosphe're from the auxiliary boiler due to the burning of contaminated waste oil is:

-hQ N

. OFH (3 4 aux D

ggo n

where:

Qgux is the total activity of radionuclide i released via the auxiliary boiler stack during the period of interest, in C1; and DFHjco is the site specific critical organ dose factor for radionuclice i for gaseous release from the auxiliary boiler, in mrem /C1 (see Table 3.3).

B 9530L-05

a Jroc. Mo, 26.1 Rev. No.

1 Page 46 of 88 ATTACHMENT I MAINE YANKEE ATOMIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL 3.3.1.b Dose to Critical Oraan (Method II)

Method II consists of the models, input data and assumptions in Appendix C of Regulatory Guide 1.109, Revision 1 (Reference 1), except where site-specific data or assumptions have been identified in the OOCH (see Tables A-2 and A-3).

The critical organ dose will be determined based on the location (site boundary, nearest resident, or farm) of receptor pathways, as identified in the most recent annual land use census, or by conservatively assuming the existence of all possible pathways (such as ground plane, inhalation, ingestion of stored and leafy vegetables, milk, and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Appendix B for the release point from which recorded effluents have been discharged. The maximum critical organ dose will consider the four age groups independently, and use a shielding factor (SF)ide Mud flats exposed at low t of 0.7 associated with residential structures.

in areas where the Back River is adjacent to the site boundary will include an occupancy factor of 0.037 for evaluation of doses at those locations. Only the inhalation and ground pla te exposure pathways are included in the assessment of doses on the mudflats (for 10CFR50, Appendix I, and 40CFR190 considerations).

9530L-05

Proc. No. 26.1 Rev. No.

1 Page 47 of 88 ATTACHMENT I MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL Table 3.1 Maine Yankee Dose Factors for Noble Gas Releases Gamma Total Body Combined Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Oose F ctor mrem-m3/pCi-yr mrem-sec/uci-yr mrad-m3pCJ-yr mrdd-m /DCl-yr

/

Nuclide DFBj OF'g 0Fj 0Fy Kr-83m 7.56E-08 3.01E-05 1.93E-05 2.88E-04 Kr-85m 1.17E-03 3.30E-03 1.23E-03 1.97E-03 Kr-85 1.61E-05 1.29E-03 1.72E-05 1.95E-03 Kr-87 5.92E-03 1.88E-02 6.17E-03 1.03E-02 Kr-88 1.47E-02 2.60E-02 1.52E-02 2.93E-03 Kr-89 1.66E-02 3.65E-02 1.73E-02 1.06E-02 Kr-90 1.56E-02 3.23E-02 1.63E-02 7.83E-03 Xe-131m 9.15E-05 6.94E-04 1.56E-04 1.11E-03 Xe-133m 2.15E-04 1.45E-03 3.27E-04 1.48E-03 Xe-133-2.94E-04 8.40E-04 3.53E-04 1.05E-03 Xe-135m 3.12E-03 5.91E-03 3.36E-03 7.39E-04 Xe-135 1.81E-03 4.75E-03 1.92E-03 2.46E-03 Xe-137 1.42E-03 1.39E-02 1.51E-03 1.27E-02 Xe-138 8.83E-03 1.83E-02 9.21E-03 4.75E-03 Ar-41 8.84E-03 1.71E-02 9.30E-03 3.28E-03

=

l i

9530L-05

Proc.. No. 26.1 Rev. No.

1 Page 48 of 68 ATTACHHENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL Jable 3.2 Maine Yankee Dose Factors for Iodine. Tritium.

and Particulate Releases Critical Organ Critical Organ Dose Factor Dose Rate Factor arem/Ci arem-sec/uCl-yr Nuclide DFG DFG'ggg gg, H-3 2.85E-04 8.99E-03 C-14 1.73E-01 5.46E+00 Cr-51 8.11E-03 2.81E-01 Hn-54 9.33E-01 3.69E+01 Fe-59 9.31E-01 3.08E+01 Co-58 4.81E-01 1.72E+01 Co-60 1.02E+01 4.54E+02 Zn-65 4.96E+00 1.60E+02 Sr-89 1.52E+01 4.79E+02 Sr-90 5.74E+02 1.81E+04 Sb-124 1.68E+00 5.62E+01 I-131 1.03E+02 3.25E+03 I-133 1.05E+00 3.31E+01 Cs-134 2.11E+01 7.03E+02 Cs-137 2.17E+01 7.41E+02 Ba-140 1.49E-01 4.83E+00 Ce-141 2.25E-01 7.19E+00 1.62E+02 Ce-144 5.13E+00 9530L-OS

I Proc..Mo. 26.1 Rev. No.

1 Page 49 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL.

Table 3.3 Maine Yankee Dose Factors for Iodine. Tritium.

and Particulate Released Via the Auxiliary Boiler

  • Critical Organ Dose Factor (mrem /C1)

Nuclide DFWjce H-3 3.24E-03 C-14 1.96E+00 Cr-51 2.15E-02 Hn-54 2.39E+00 Fe-59 2.42E+00 Co-58' 1.25E+00 Co-60 2.60E+01 Zn-65 1.27E+01 Sr-89 3.88E+01 Sr-90 1.49E+03 Sb-124 4.38E+00 I-131 2.65E+02 i

I-133 3.55E+00 Cs-134 5.41E+01 Cs-137 5.53E+01 Ba-140 6.63E-01 6.05E-01 Ce-141 Ce-144 1.33E+01 OFW co for use with the burning of contaminated waste oil.

i 0

9530L-OS

Prot. 100. 26.1 Rev. No.

1 Page 50 of 88 ATTACHMENT I MAINE YANKEE ATCHIC POWER CONPANY OFF-SITE DOSE CALCULATION MANUAL 4.0 ENVIRONMENTAL MONITORING The Radiological Environmental Monitoring Stations are listed in Table 4.1.

The locations of these stations with respect to the Maine Yankee facility are shown on the maps in Figures 4.1 through 4.6.

e f

e 1

l t

l 9530L-05 i

Prtn:.10. 25T1 Rev. No.

1 Page 51 of 88

&ITACHHENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL TABLE 4.1 Radiolooical Environmental Monitorina Stationsa Distance Direction From the From the Exposure Pathway Sample Location b and/or Samele and Desianated Code Plant (km)

Plant 1.

AIRBORNE AP/CF-11 Montsweag Brook 2.7 NH (Radiotodine and AP/CF-13 Bailey Farm (ESL) 0.6 NE Particulate)

AP/CF-14 Mason Steam Station 4.8 NNE AP/CF-16 Westport Firehouse 1.8 S

AP-CF-29 Oresden Substation 19.8 N

2.

DIRECT RADIATION TL-1 Old Ferry Rd.

1.0 N

TL-2 Old Ferry Rd.

0.8 NNE TL-3 Bailey House (ESL) 0.6 NE TL-4 Westport Island, Rt. 144 1.2 ENE TL-5 HY Information Center 0.2 E

TL-6 Rt. 144 and Greenleaf Rd.

0.9 E

TL-7 Westport Island, Rt. 144 0.8 ESE TL-8 HY Screenhouse 0.2 SE TL-9 Hestport Island, Rt. 144 0.9 SE TL-10 8 alley Point 0.4 SSE TL-11 Mason Station 4.8 NNE TL-12 Hestport Firehouse 1.8 S

TL-13 Foxbird Island 0.4 SSH TL-14 Eaton Farm 0.8 SH TL-15 Eaton Farm 0.8 HSH TL-16 Eaton Farm 0.7 H

TL-17 Eaton Farm Rd.

0.6 HNH TL-18 Eaton Farm Rd.

0.8 NH TL-19 Eaton Farm Rd.

0.9 NNH TL-20 Bradford Rd., Wiscasset 6.5 N

TL-21 Federal St., Wiscasset 7.2 NNE I

9530L-OS 1

.b Proc. ko. 26.1 Rev. No.

1 Page 52 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL TABLE 4.1 (Continued)

Radioloaical Environmental Honitorina Stattertia Distance Direction From the From the Exposure Pathway Sample Location b and/or Samole-and Desianated Code Elant (km)

-__ Plant TL-22 Cochran Rd., Edgecemb 8.3 NE TL-23 Hiddle Rd., Edgecomb 7.0 ENE TL-24 River Rd., Edgecomb 7.8 E

TL-25 River Rd. and Rt. 27 7.5 ESE TL-26 Rt. 27 and 7.8 SE Boothbay RR Museum TL-27 Barters Island 7.0 SSE TL-28 Hestport Island, Rt. 144 and East Shore Rd.

7.7 S

TL-29 Harrison's Trailer 6.3 SSH TL-30 Leeman Farm, Hoolwich 7.6 SH TL-31. Barley Neck Rd., Hoolwich 6.7 HSH TL-32 Baker Farm Hoolwich 7.2 H

TL-33 Rt. 127, Hoolwich 7.3 HNH TL-34 Rt. 127. Hoolwich 7.9 NH TL-35 Rt. 127, Dresden 9.1 NNW l

TL-36 Boothbay Harbor Fire Sta.

11.4 SSE TL-37 Bath Fire Sta.

10.4 HSH TL-38 Dresden Substation 19.8 N

3.

HATERBORNE a.

Surface HE-12 Plant Oucfa11C 0.3 SH (Estuary)

(Composite Sample)

HE-20 Kennebec River 9.8 Sh (Grab Sample)

'd b.

Grourdwater HG-13 Bailey Farm (ESL) 0.6 HG-24 Horse Hell 9.8 A

c.

Sediment from SE-18 Foxbird Island 0.7 9

Shoreline SE-16 Old Outfall Area 9530L-OS

Proc..h. 26.1 Rev. No.

1 Page 53 of 88 TABLE 4 1 (Continued) 2 Radioloaical Envircnmental Monitorina Stationsa Distance Direction From the from the Exposure Pathway Sample Location b

__jnd/or Samole and Desianated Code Plant (km)

Plant 4.

INGESTION a.

Milk TM-16 Baker Farm 7.2 H

TM-17 Leeman Farm 7.9 SH TM-25 Hanson Farm 16.0 W

b.

Fish and FH/HU/CA/HA-11 Long Ledge Area 1.1 S

Invertebratesd MU/CA/HA/24 Sheepscot River 11.2 S

c2 Food Crop TV-IX Indicator Vegetation (to be determined)

TV-1X Indicator (to be determined)

TV-2X to be determined Footnotes:

a Sample locations are shown on Figures 4.1 to 4.6.

b Station-1X's are indicator stations and Station 2-X's are control stations.

c A dilution factor of 10 shall be applied to any radioactivity detected in a sample at this station.

d The station code letters will vary with the sample media collected.

The sampling of all four media types is not required during each sampling period.

Food crop sampling is not required while milk sampling is being done.

e 9530L-05

a Proc. No. 26.1 Rev. ho.

1 Page 54 of 88 ATTACHMENT 1 MAINE YANKEE ATONI.C P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL FIQlRE 4.1_

Environmental Radioloaical Samolina locations Mithin 1 Kilometer of Maine Yartig

./**

,/./

//

' / l,.

  • N 5./*s

\\<

,\\

)

i N.

s i

  • N, N.

Ng.'

g 1

g stit toWWSAA,

.i

=

t l

(

y i

/

9 jsF g

,/

../

./

),:

w* t s l

l ;** *...

k asser.it 1

e...

\\.

l

.I y

,et,,, nn nun o:

e

....d.,f.

4 V: i l,

e

,3

/

Duf Nef IstAht

/

{*

l l

w.i ulttr W.

l l

  • /

l e

l ma.ll

.I I

ca.i.

, II*l8

[

i t

g 144

  • II gg 9 t f.*illt.

N k

i

"88 8 1.:

(*,-

t r..g s t}

'?

  • M l

l ll 9530L-OS

t

~

Proc. N9. 26.1 Rev. No.

1 Page 55 of 88 ATTACHMENT I MAINE YANKEE ATONIC PONER COMPANY OFF-SITE DOSE CALCULATION MANUAL FIQJRE 4.2 Environmental Radioloaical Samolina Locations M1 thin 12 Kilometers of Maine Yankee

/

s sa usettai

/

l

.,im,.

N

. 4. 1 usoura w :=sissa..,

y;q.v..

0 n'"" ""

ny,j '

'8 y

.e..n

[g

. cxuw ;,

). u.y[.

m.in$

(

'l.

/

....%-.m.

i y (y

c b;

n.,,.

.1 f

[

t 1

=

f.

~

e.

l

==

q g jj j Q g or..,.....

Q' f, y.

o 7,-

9530L-OS

w f

fr% No. 26.1 Rev. No.

1 Page 56 of 88 ATTACHMENT I MAINE YANKEE ATONIC P0HER COMPA'lY OFF-SITE DOSE CALCULATION MANUAL FIGURE 4.3 Environmaqtal Radioloaical Samolina locations Outside 12 Kileneters From Maine Yankee I

f,

.... ~, -

q 1

2... $

t

=

AN 47*19

$(I C%AFM I8 II a(4Aift 1

Y,.

- ix nA

,c V

.iioiin,. /

.i 8

. s j "f

..iirx.

~,<a

[,fLP h.,

~ ~

z

,A.

'f

$0$ fulA f.'

- =

0 H

aftauftf fCl49 f

l 27 i.

l 4 li gre )(.m d

9530L-OS l

Proc. flo. 26.1 Rev. No.

1 Page 57 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL FIQJRE 4.4 Direct Radiation Monitorino locations Within 1 Kilqmeter of Maine Yanket I

D.

  • ll g

,it H

/ I

~.

Y I

f

!s" /

p l

N.s.

N s

t.

\\

s,n mesu

.I

+e

,I

(

l y

n.,

../

,..e C...-

w..

n.,

g

/

n.,, 4..

n.,
y :..:

, n.n e..

.... e,

/

,i

.m..

n.,., -

1

n.,

c

.g i

n... gp, p., n.. w :

.amnun "s' "

..I.

1,.,,, :'.

n.,,7

,a, n.

e n.,

.v t '.i

.i e n.,

y:

,i p

y'J

.f I

II J

  1. f&

yg I

9530L-05

~Pr:c. No. 26.1 i

Rev. No.

1 Page 58 of 88 ATTACHMENT I HAINE YANKEE AT0 HIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL FIGURE 4.5 Direct Radiation Monitorino locations Within 12 Kilometers of Maine Yankee yV- \\"/~-

I.

,, -n...

j I

  • r

' r, ~py.

O n.n

/

n " sud,,.

N..., Rn.n t ft.,

..)

r.

y. n -

7

/ $(f MaacMuf gv p;stg 4,,

\\

q n.n

$p

..h' k

j t

A.

P...

eun, wa

..g.....

'w

^

t

.r;, r

. w.em ;

g p,..

n.,e g'1-l i

.i ps n.n,g..

n.n.

", p y y y"(s ' - e j . g n.n. f n"* ~ 4 l =- 7 1 5 , n.,, n..,jj l na

)n.
  • .i

/,/ R; ip,, \\.f V n.n g . j +( ! Q $ ~ ~ g.,,. ~ ]f ,,n-p,,, lf,& 9530L.DS

~ g froc. No. 26.1 Rev. No. 1 Page 59 of 88 ^ &I,bip4 MENTI MAINE YANKEE ATOMIC POMER COMPANY OFF-SITE DOSE CALCULATION MANUAL I i FI@RE 4.6 Direct Radiation Monitorina Locations Qutside 12 Kilometers From Maine Yankee 's, 88 4*r u.ui.. i . aincu s 1 1 4 l +e I \\ .N U g n.u l i n x'N eso.e\\e 's. P ' '.. ~. 7). / s, ..ons. e 'l f . %s mY. ,,l l m woner := nw 4.s 's A.,-- -~- -' j'h.im,,,.- i 3 y ,,..,. N-,, -) ...m l N 8 \\,,f,;M 's;4 ..w s'

L p46 l

i e. 1 a/. i x*~ + , = %u l i t .[' l N M q i ^ }p'(l,7. u g....... e j g + / \\ s i g' af net f( fag i 4 ..\\ l y j \\ i N i n. l l I 9530L-05

, Proc.. No 26.1 Rev. No. 1 Page 60 of 88 LTIACHMEN7 ? MAINE YANKEE ATONIC POWER COMPANY ' 0FF-SITE DOSE CALCULATION MANUAL 5.0 MONITOR SETPOINTS 5.1 Technical Snecification 4.13.B. Licuid Effluent Monitor Seteolnts Technical Specification 4.13.8 requires that the discharge of liquid radioactive effluents be continuously monitored with the alarm / trip setpoint of the monitor set to ensure that the requirements of Technical Specification 3.16.A are met. Technical Specification 3.16.A.1 requires that the concentration of radioactive material in liquid effluents released (rom the site to Back River be limited to the concentrations specified in 10 CFR Part 20, Appendix 8 Table II, Column 2, for radionuclides other than noble gases and 2E-04 microcuries/ml total activity concentration for all dissolved or entrained noble gases. This section of OOCH descrioes the methodology that may be used to determine the setpoints of the liquid effluent monitors. Liquid effluent flow paths and release points, as well as the locations and identification numbers of the liquid effluent radiation monitors, are shown in Figure 4.1. The methodology for determining alarm / trip setpoints is divided into The first consists of calculating an allowable concentration for two parts. the radionuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings l on the monitors. i i l 1 ( 9530L-05

a Proc. No. 26.1 Rev. No. 1 Page 61 of 88 ATTACHMEMl l MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 5.1.1 Allowable Concentrations of Radioactive Materials in Lieuid Effluents Technical Specification 3.16.A.1 requires that the concentration of radioactive material in liquid effluents released from the site to Back River be limited to the concentrations specified in 10 CFR Part 20, Appendix 8 Table II, Column 2 for radionuclides other than noble gases and 2E-04 microcuries/mi total activity concentration for all dissolved or entrained noble gases. To ensure compliance with Technical Specification 3.16.A.1, the fol'nwing method may be used for each release of liquid effluent. Prior to ( each release a grab sample will be analyzed to determine the activity concentration of each radionuclide. The MPC-fraction, Rj, for each liquid effluent release point will be calculated by the relationship defined by Note 1 of 10 CFR Part 20, Appendix B: (5-1) R l j" H where: Rj is the HPC-fraction for the release point j, dimensionless. is the diluted activity concentration of radionuclide 1. in uCi/ml Ci and is equal to undiluted concentration of radionucliue i times fj/F. F* the total dilution flow in gpm. r is the maximum permissible concrentration of radionuclide i as HPCI i specified in 10 CFR Part 20, Appendix B, Table II, Column 2, in uC1/ml. The MPC-fractions for the various release points are then summed to yield the total HPC-fraction, R: (5-2) Rj R = The total MPC-fraction, R, at the discharge to the Back River must be less than or equal to one. (5-3) R=11 9530L-OS

g - -9 toc. No. 26,1 Rev. No. 1 Page 62 of 88 ATTACHMENT I MAINE YANKEE ATCNIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 5.1.2 Monitor Resnonse for Liouid Effluents The response of each liquid effluent monitor is established by combining the appropriate concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency. The radiation monitor ala'rm/ trip setpoint for a test tank release is set such that the sum of the MPC ratios of the diluted nuclides is less than or equal to 0.6 at the discharge to the Back River. The setpoints is determined in the following manner: 1. The CPM of each undiluted nuclide is determined from the response If a nuclide other than 58Co, 60Co 1311, 133!, 134Cs, and graphs. 137Cs or unidentified nuclides contributes more than 10% of the total activity use, the cunservative 1311 response curve to determine the CPM. (Unidentified nuclide activity is determined by subtrccting identified activity from gross gamma activity.) 2. Set the alarm setpoint at background plus the calculated CMP from Step 1. If the discharge HPC ratio is calculated to be less than 0.6, you 3. can increase the alarm setpoint CHP by a factor of 0.6/ actual ratio. The HPC ratio for a test tank discharge may be increased to less 4. than 1 if it is determined that no other radioactivity is being released to the Back River. 4 9530L-05

~ froc. No. 26.1 Rev. No. 1 Page 63 of 88 L ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 5.2 Technical snecification 4.13.0. Gaseous Effluent Monitor Setnoints Technical Specification 4.13.0 requires that radioactive gaseous effluents he continuously monitored with the alarm / trip setpoints of the monitors set to ensure that the requirements of Technical Specification 3.17.A are met. Technical Specification 3.17.A ensures that the dose rate at any time at the site area boundt.ry and beyond from gaseous affluents will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associat6d with the concentrations of 10 CFR Part 20, Appendix 8. Table II, These, limits provide reasonable assurance that radioactive material Column 1. discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, to annual average concentrations exceeding the limits specified in 10 CFR Part 20. Appendix 8. Table II, Column 1. 'This section of the OOCH describes the methodology that may be used to determine the setpoints of the gaseous effluent monitors. Gaseous effluent flow paths and release points, as well as the locations and identification numbers of the gaseous effluent radiation detectors, are shown in Figure 5.2. 1 The methodology for determining alarm / trip setpoints is divided into two parts. The first consists of calculating an allowable concentration for the radionuclide mixture to be released. The second consists of determining monitor response to this mixture in order to estabitsh the physical settings on the monitors. l j i l i 0530L-03

Proc.180. 26.1 Rev. No. 1 Page 64 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POMER CONPANY OFF-SITt, DOSE CALCULATION MANUAL 5.2.1 Allowable Concentrations of Radioactive Materials in Gateous Effluents The MPC-fraction, Ri, for each gaseous effluent release point is calculated by the relationship defined by Note 1 of 10 DFR 20 Appendix 8: C (5-5) R) - CX/Q) FE gp I where: Rj is the MPC-fraction for the release point j, jimensionless; is the most conservative sector site boundary or off-site long- [X/Q) term average dilution factor (see Table 6.1) (9.03E-06 sec/m3); F

  1. s the release flow rate (in m3 sec);

/ is the concentration of radionuclide i, in uC1/ce; C1 is the maximum permissible concentration of radionuclide i as i MPC1 specified in 10 CFR 20, Appendix 8. Table II, Column 1, in uC1/cc. The MPC-fractions for the various release points are then summed to yield the total MPC-fraction, R: (5-6) f R - E Rj 3 The total MPC-fraction, R, at the most conservative site boundary or off-site location must be less than or equal to one. (5-7) R 1 1. F l 9530L-05 . -. - ~ _ _ _ _.

JProc. No. 26.1 Rev. No. 1 Page 65 of 88 ATTACHMENT I MA NE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 5.2.2 Monitor Resnonsa for Gateous Effluents Normal radioactivity releases consist mainly of well-decayed fission gases. Therefore, monitor response calibrations are performed using fission gas typical of normal releases (mainly xenon-103). The total concentration of radioactive materials in gaseous effluents, in uC1/cc, at the monitor is calculated. The calibration curve or' constant, in cpm /(uC1/cc) is applied to determine the expected cpm for the mix of radionuclides. The setting of the monitor is established at some factor, b. greator than one but less than 1/R (see Equation 5-6). i f d w 9530L-OS t

rr ' Proc. No. 26.1 Rev. No. 1 Page 66 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POMER COMPANY 0FF-SITE DOSE CALCULATION MANUAL FIQJRE 5.1 Maine Yantag Liauid Radwaste System 9 Prie.ry 17118 - v s t mit. su s.r,. f.4 g "reet" Dr*'" '. serea Meat. 3.r.a y'd'" ~ [,$r Prie.ry 0.siner.Ilt.P ~? 7

  1. [

Deg.stft.rg ,,,t., i \\/ Sa/it Domin.P. lit.r .M f. S.11difttiti A Pria.ry $yt.t.m. j I'St ~ A.r.t.. Dr int l A.r.t.4 mit. fea.: i y e.,.q q Dr la

1...

g Flit r / ,,.. A & Is.).ti a W., e... ai re.0 Jk eilt 3 pga-c.ae.., m i.i,i.... p w. iai..tl.a m nit.r1 -slag, e j t.41 t. t . tit.e . r.acti..i e n 1., ,iis., I4 2601. 2602. 2603 }F 5d"' et m i t wt., n.st etie.. .,I. t insti.a

s.,ic.. tate m t.actiea)

.mt j r s r.ic...t.e f

1. s..i,it _

6 ....iucts.. u..ie out. e f1..at trutreat av'e. r 9530L-05

Proc. bio.-26.1 Rev. No. 1 Page 67 of 88 i-ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL FIGURE 5.2 Maine Yankee Gaseous Radwaste System s'.. 6 . as, a.46.ii ieu as.. e esi .e - is,,, i i..i. m.4tus, me 4:we e 't=laua" .e p.,.e ii w anse. 4 em 46 p.ege to.Lete.. es.39483. De.3.Nf?.e 8. Let p,6,. a.a ni ta ry 6 6146 4 49.tetese steest 84eet 4 ats ne.ase t

m. tee. alet. reenlee

'-'" et.a se.eese seee totM4 ee... n o.ees q t J.-. .= s.elettee m tsee. alare 4 to.Let tee an.3946 ree s tee, "- " " "

  • Tee 7 C Gie.

I_ .r. ii -.-* g., l, - rt s.4:easi ) I 'l s.eie l i i......,,,..e e.ee,, ce i 3 l se s e., e te.= l A '" arise.nese eve #stsee i .. t.ua # 31:ee (. Ch.etae I i n 4 4 s# 1 t i i i i 9530L.05 l l

a -Proc. Wo. 26.1 Rev. No. 1 Page 68 of 88 ATTACHMENT I = MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE cal.CULATION MANUAL L 6.0 METEOROLOGY 1 The atmospheric dilution factors in the dose calculation methods assume an individual whose behavior leads to a dose higher than expected for anyone else. Since long term (5-year) average meteorology is expected to be representative of the area, the location of the critical receptor can be predicted by scanning all the reasonable off-site locations to find the location with the most limiting dilution factors. Important off-site locations are: site boundaries and nearest residences in each of the sixteen meteorological sectors, as well as all allk farm locations within five alles of the plant. Exposure pathways assumed to exist at site boundary locations are direct exposure from radioactive materials in the air, direct exposure from radioactive materials deposited on the ground, and exposure from Inhalation of radioactive materials. In addition to the pathways present at site boundary locations, exposure pathways present at each residence are assumed to include ingestion of radionuclides in home grown vegetables. Farm locations include all exposure pathways found at residences plus ingestion of radionuclides in meat and allk. Meteorological data for the year 1981 through 1985 were analyzed for the values of the maximum average dilution factors at the important receptor locations described above. Yankee Atomic Electric Company's (YAEC) AEOLUS i computer code (Reference 2) calculated all atmospheric dilution factors. Appendix 8 briefly describes the Y/.EC AEOLUS computer code model. Table 6.1 lists the maximum average dilution factors for all important receptor locations for re, leases via the plant stack. Each dose and dose rate calculation method incorporates the maximum applicable off-site average dilution factors listed in Table 6.1. The maximum potential dose to a member of the public due to plant stack releases in any i year will be conservatively estimated by the dose calculated for a full-time resident living on a hypothetical allk fara 570 to 700 meters from the plant in the southeast sector. ( i o e 4 9530L-OS

Proc. No. 26.1 Rev. No. 1 Page 69 of 88 ATTACHMENI_1 MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL TABLE 6.1 Maine Yankee Maximum 5-Year Averaae Atmosnherie Dilution Factort(1) Direction From Distance From X/Q Undepleted X/Q Depleted D/Q (X/Q]I ,,_ tec/m ) __{jac/m ) (m-2) (3,ef,3.y 3 3 ( the Plant the Plant (m) Site Soundaries N 1219 6.64E-07 6.33E-07 4.20E-09 7.24E-07 NNE 2209* 3.88E-07 3.73E-07 1.10E-09 3.34E-07 NE 1280* 1.76E-07 1.66E-07 1.16E-09 3.24E-07 ENE 914* 1.76E-07 1.63E-07 1.50E-09 4.20E-07 E 731* 3.29E-07 3.06E-07 3.77E-09. 6.46E-07 ESE 670* 7.25E-07 6.74E-07 1.04E-08 9.85E-07 SE 670* 9.46E-07 8.80E-07 1.25E-08 1.34E-06 SSE 823* 5.67E-07 5.24E-07 6.19E-09 1.04E-06 S 1310* 3.22E-07 2.97E-07 2.99E-09 5.46E-07 SSH 2986* 1.97E-07 1.88E-07 5.96E-10 2.35E-07 NNE 1368** 6.14E-07 5.93E-07 2.49E-09 5.72E-07 NE 370** 5.35E-07 5.10E-07 4.75E-09 9.33E-07 ENE 306

  • 6.72E-07 6.43E-07 6.04E-09 1.10E-06 E

209** 2.14E-06 2.06E-06 ' 2.23E-08 2.14E-06 ESE 209** 4.46E-06 4.30E-06 5.97E-08 3.48E-06 SE 274** 3.65E-06 3.50E-06 4.75E-08 3.48E-06 SSE 209** 4.37E-06 4.21E-06 4.43E-08 3.97E-06 S 129'* 9.03E-06 8.79L-06 7.27E-08 5.08E-06 SSH 129** 4.96E-06 4.83E-06 3.53E-08 4.02E-06 SH 914 1.91E-07 1.81E-07 1.68E-09 4.44E-07 HSH 762 1.55E-07 1.47E-07 1.48E-09 3.81E-07 W 670 1.64E-07 1.60E-07 1.79E-09 3.80E-07 HNW 670 1.52E-07 1.43E-07 1.68E-09 3.28E 07 NW 762 3.90E-07 3.73E-07 3.04E-09 6.88E-07 NNH 1036 4.80E-07 4.46E-07 4.49E-09 6.97E-07 (1) 1981 through 1985 for release via the plant stack. i

  • 0pposite shore of Back River where site boundary coincides with the water boundary of the river.
    • Near shoreline where site boundary coincides with water boundary of river.

Occupancy factors for worm diggers apply. l l 9530L-OS

. Proc..No..26,1 Rev. No. 1 Page 70 of 88 ATTACHMENT I MAINE YANKEE ATONIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL TABLE 6.1 Haine Yankee Harimum 5-Year Averton Atmoneherie Dilution Factor 1(l) Direction From Distance From X/Q Undepleted X/Q Oepleted 0/0 (X/Q)' 3 3 3 the Plant ihtflant (m) (sec/m ) (sec/m )_ d (see/m ) ~ Hud Flats (Horm Diggers)"* E 250 1.55E-06 1.49E-06 1.72E-08 1.76E-06 S 450 1.07E-06 1.01E-06 1.21E-08

1. 56 E-06 SSN 700 3.34E-07 3.11E-07 3.52E-09 6.87E-07 SH 400-3.71E-07 3.53E-07 3.53E-09 7.88E-07 HSH 300 3.43E-07 3.29E-07 3.55E-09 6.74E-07 N

250 4 83E-07 4.64E-07 5.42E-09 7.24E-07 HNH 250 5.35E-07 5.14E-07 5.64E-09 7.10E-07 NNH 250 2.86E-06 2.74E-06 3.02E-08 2.64E-06 Nearest Residences N 1300 6.38E-07 6.07E-07 3.84E-09 6.79E-07 NME 2300 3.71E-07 3.57E-07 1.03E-09 3.19E-07 NE 1300 2.14E-07 2.04E-07 1.23E-09 3.57E-07 ENE 900 1.77E-07 1.65E-07 1.53E-09 4.26E-07 E 900 3.75E-07 3.54E-07 3.20E-09 6.79E-07 ESE 1400 5.27E-07 4.97E-07 3.85E-09 6.97E-07 SE 700 9.09E-07 8.43E-07 1.19E-08 1.40E-06 SSE 900 5.71E-07 5.30E-07 5.74E-09 1.06E-06 l S 1700 5.08E-07 '4.84E-07 2.54E-09 6.45E-07 l SSH 3000 1.96E-07 1.87E-07 5.91E-10 2.34E-07 SH 1400 2.07E-07 1.99E-07 1.15E-09 3.36E-07 HSH 1000 1.49E-07 1.43E-07 1.13E-09 2.98E-07 H 2600 1.35E-07 1.30E-07 3.78E-10 1.28E-07 HNH 800 2.13E-07 2.04E-07 1.75E-09 3.53E-07 NH 2000 2.83E-07 2.74E-07 8.61E-10 2.78E-07 NNH 1100 5.39E-07 5.06E-07 4.46E 7.14E-07 (1) 1981 through 1985 for release via the plant stack.

  • "Dilution factors must be corrected for occupancy factors of wnrm diggers on the mud flats at low tide equal to 325 hours per year (0.037).

Reference:

Maine Yankee Environmental Report. 9530L-OS

Croc. No. 26.1 Rev. N6. 1 Page 71 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL TABLE 6.1 Maine Yankee Maximum 5-Year Averaae Atmoseherie Dilution Factors (l) Direction From 01 stance From X/Q Undepleted X/Q Depleted 0/0 [X/Q)' 3 3 3 the Plant the Plant (m) (sec/m ) (sec/m ) LE'_1 (sec/m ) Milk Farms Within Five Miles N 2700 3.36E-07 3.19E-07 1.20E-09 3.10E-07 ESE 7100 2.12E-07 1.95E-07 4.41E-10 1.55E-07 SH 7900 1.03E-07 9.46E-08 1.65E-10 7.62E-08 H 7200 6.16E-08 5.24E-08 1.21E-10 4.59E-08 (1) 1981 through 1985 for release via the plant stack, w I I l 9530L-OS l

Y .Pr4c. No. 26,1 Rev. No. 1 Page 72 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MMUAL APPENDIX A antin for the Data C81eulation Methods A.) Liauid Effluent Dates Method I is used to demonstrate compliance with Technical pecification 3.16.8 which 11mits the dose commitment to a member of the public from radioactive materials in liquid effluents. Liquid pathways contributirg to individual doses at the Maine Yankee Nuclear Power Station are: ingestion of fish and shellfish, and direct The potable water pathway and the irrigated exposure from shoreline deposits. foods pathway are not considered since the receiving water is not suitable for dither drinking or irrigatioh. Method I is derived from Equations A-3 and A-7 of Regulatory Guide 1.109 (Reference 1). Equation A-3 calculates radiation doses from aquatic foods. Equation A-7 from shoreline deposits. The uss of the methodology of Equations A-3 and A-7 for a 1 curie release of each radionuclide in liquid effluents yielded the dose impact to the critical organ. Table 2.1 lists the resulting site specific total body and critical organ dose conversion factors giving the number of all11res per l curie released for each radionuclide. Since the dose factors of Table 2.1 represent a variety of critical organs, Method I conservatively calculates a critical organ dose consisting of the maximum critical organ for each radionuclide of any of the four age groups, and combines them into a e,omposite individual independent of age, l Except for the site specific values 1.ateo below, the parameter values l l recommended in Regulatory Guide 1.109 (Reference 1) were used to derive the liquid dose factors for Method I. Table A-1 lists the usage factors for l Itquid pathways utilized in the dose analysis. t 9530L-05

. Proc. No. 26.1 Rev. No. 1 Page 73 of 88 ATTACHMENT I MAINE YANKEE ATONIC PONER COMPANY OFF-SITE DOSE CALCULATION MANUAL APPENDIX A Liquid effluents discharge from the plant via a submerged multi-port diffuser which extends approximately 1000 feet into the tidal estuary and has a design circulating water flow of 420,000 gpm (935 ft3/sec). For the aquatic foods pathway, the dilution for the mixing effect of the diffuser is 10 to 1 (Reference 5). This dilution applies to the* edge of the initial mixing zone where the effluent has undergone prompt dilution only. For shoreline deposits, the nearest point where tidal flats could be occupied on a recurring basis is in Bailey Cove which borders the site on the south and west. The estimated average dilution for Bailey Cove with respect to the discharge is approximately 25 to 1 (Reference 5). ~ Shoreline activities in the vicinity of the site include a commercial worm digging industry along the tidal flats of Montsweag Bay. In the area of the plant (Bailey Cove), a commercial worn digger could occupy the mud flats for as long as 325 hours per year. This occupancy time is applied to both adults and teenagers in the dose calculations. For Method I, the period of time for which sediment is exposed to the contaminated water is fifteen years. This time period represents the -approximate mid> point of plant operating lifetime, and thus allows for the calculation of a plant lifetime average concentration of radioactivity in sediment. No credit is takers for the decay of activity in transit from the discharge point to the sediment in Bailey Cove. 9530L-OS

a Proc. No. 26.1 Rev. No. 1 Page 74 of 88 AII6CHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL APPENDIX A TABLE A-1 Usaae Factors for Various Liould Pathways at Maine Yankee (From Reference 1. Table E-5*, except as noted. Zero where no pathway exists.) LEAFY POTABLE AGE VEG. VEG. MILK MEAT FISH INVERT. WATER SHORELINE (KG/YR) (KG/YR) (LITER /YR) (KG/YR) (KG/iR) (KG/YR) (LITER /YR) (HR/YR) Adult 0.C0 0.00 0.00 0.00 21.00 5.00 0.00 334.00** Teen 0.00 0.00 0.00 0.00 16.00 3.80 0.00 67.00 Child 0.00 0.00 0.00 0.00 6.90 1,70 0.00 14.00 Infant 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 i i

  • Regulatory Guide 1.109, i
    • Regional shoreline use associated with mudflats - Maine Ytanee Atomic Power Station Environmental Report.

9530L-DS ~

-froc.-No. 26.1 Rev. No. 1 Page 75 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY 0FF-SITE DOSE CALCULATION MANUAL ( APPENDIX A I A.2 Total Body Dose Rate from Noble Cases Method I can be used to demonstrate compliance with Technical Specification 3.17.A.I.a. which limits total body dose rate from noble gases released to the atmosphere. Method I applies the methods of Equation B-8 in Regulatory Guide 1.109 (Reference 1) as follows: SF 3.17E+04 (X/03 p Qt OF8g (A-1) Dtb = i where: is the annual total body dose, in arem/yr; Otb is the attenuation factor that accounts for the dose reduction due SF to shielding provided by residential structures, but for all dose i rate calculations is assumed to be equal to 1 (dimensionless); 3.17E,04 is the number of pC1 per Ci divided by the number of seconds per year; (X/Q)I is the effective long term average gamma dilution factor, in sec/m3; Qt is the annual release rate of radionuclide i, in C1/yr; and is the total body gama dose factor for radionuclide i, in 0FBt arem-m3/pCi-yr. Section6yieldedamaximumeffectiveaveragegammadilutionfactor,(X/Q) The analysis of Haine Yankee five-year average =eteorology presente. of !.40E-06 sec/m3 The maximum gama dilution factor was identified for an 9S30L-OS

-Proc. Mo. 26.1 Rev. No. 1 Page 76 of 88 ATTACHMENT I MAINE YANKEE ATOMIC P0HER COMPANY OFF-SITE DOSE CALCULATION MANUAL i APPENDIX A off-site point located 700 metirs southeast of the plant. This location is along the opposite shoreline of Back River from the plant in a sector where the site boundary is adjacent to the river. The maximum gamma dilution factor for the site ooundary along the river's near shoreline has been determined to be a pre restrictive value (south sector at 129 meters, X/Q = 6.08E-6 sec/m3). However, the definition of site boundary in the Technical Specifications allows for the use of occupancy factors in assessing doses, and the expanded definition of unrestricted area in NUREG-0133 also does not require dose evaluations over water. For those portions of the adjacent shoreline to the site boundary where mudflats are exposed during low tide, an occupancy factor for worn diggers (0.037) is applied to the average gamma dilution factor at thoss locations. As a result, the opposite shoreline atmospheric gamma dilution factor becomes limiting due to its assumed "ull time occupancy since physical constraints (areas over water) do r.ot exist, and I there is no control on occupancy available. It should be noted that 3 controlling the maximum dose rate to 500 mrem per year at a location on the opposite shoreline from the plant still ensures that the dose rate on the exposed mudflats during low tide will not exceed a value which would give rise I to two arem in one hour (10CFR20.105(b)(1)] even assuming continuous occupancy during the hour. Incorporating the above into Equation A-1 and converting from annual releasetomaximuminstantaneousreleaserate,(multipleDinCl/yrby31.54 Cl-sec/uCl-yr which gives in uC1/sec) yields the method to calculate total f body dose rate from noble gases: (A-2) ( 6tb = 1.40 1 41 0FBj i i i r i 9530L-05

Proc. No. 26.1 Rev No. 1 Page 77 of 88 ATTACHMENT I MAINE YANKEE ATOMIC PONER COMPANY OFF-SITE DOSE CALCULATION i%NUAL P APPENDIX A A.3 skin Date Rate from Noble Cates Method I is used to demonstrate compliance with Technical Specification 3.17.A.1.a. which limits skin dose rate from noble gases released to the' atmosphere, for the peak noble gas release rate. Method I applies the methods of equation 11 in Regulatory Guide 1.109 (Reference 1) as follows: 3.17E+04 (X/Q)Y I: Qt DF ( Dskin " l Il SF t i + 3.17E+04 X/Q ]C Qt 0FSt (A-3) 1 where: Oskin is the annual skin dose rate, in eres/yr; 1.11 is the average ratio of tissue to air energy absorption coefficient; is the attenuation factor that ac:ounts for the dose reduction SF due to shielding provided by residential structures, but for all dose rate calculations is assumed to be equal to 1 (dimensionless); 3.17E+04 is the number of pC1 per C1 divided by the number of seconds per year; (X/Q)i is thg effective long ters average gamma.dllution factor in sec/mJ; Qt is the annual release rate of ra'dionuclide 1, in C1/yr; DFt is the gamma air dose factor for a uniform semi-infinite cloud of radionuclide 1 in mrad-m3 pci-yr; / X/Q is the long term average undepleted dilution factor in sec/m3; and w i 9530L-05

Proc. No. 26.1 Rev. No. 1 Page 78 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY

  • OFF-SITE DOSE CALCULATION MANUAL APPENDIX A 0FSj is the beta skin dose factor for a semi-infinite cloud of radionuclide 1, which includes the gttenuation by the outer "dead" layer of the skin, in aren-F /pC1-yr (taken from Reference 1. Table B-1).

The ximum effective fivt year average gamma dilution factor [X/Q), is 1.40E-06 sec/m3 (see Table 6.1), and the maximum five year average undepleted dilution factor, X/Q. is 9.46E-07 sec/m3 (see Table 6.1). Incorporating these constants into Equation A-3 and converting from annual release to maximum instantaneous release rate (multiple Q in C1/yr by 31.C4 Ci-secluci-yr which yields 6 in uC1/sec) yields: 6 skin - 1.56 13 Dj OF' + 0.946 12 D1 0FSt (A-4) t i 1 T 1 Qt (1.56 0Ft + 0.946 0FS ]. t i 1 A combined skin dose factor, OFj, may be defined: 1 0F ). = 1.56 0Ft + 0.946 0FS. t Incorporatingthecombinedskindosefactor.OFj,into Equation A-4 yields the method to calculate skin dose rate from noble gases: 6 skin-13 41 0Fj. 1 t t 9530L-OS i

Proc. No. 26.1 Rev. No. 1 Page 79 of 88 ~ ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL APPENDIX A A.4 Critical Oraan Dose Rate from Iodines and Particulates Method I is used to demonstrate compliance with Technical Specification 3.17.C. which limits the dose rate from todine-131, iodine-133, tritium and radioactive materlaIs in particulate form with half-lives greater than 8 days. The method to calculate the critical organ dose rate from radioactive iodines and particulates is derived from OOCH Equation 3-6 which limits the dose to the critical organ from radioactive iodines and particulates. Deo. E Qj OFGjeo (A-5) 1 where: Oco is the dose to the critical organ from iodine-131, iodine 133, ' tritium and radioactive materials in particulate form with half-lives greater than 8 days, in arem; Q1 is the total activity of radionucliae i released via the plant stack during the period of interest, in C1; and DFGjeo is the site specific critical organ dose factor for radionuclide i for a gaseous release, in arem/C1 (see Table 3.2). Applying the conversion factor 31.54 (Ci-sec/uCi-yr), to convert , Cl)toDj(uC1/sec)andchangingtheshieldingfactor(S)from0.7 F Qi,(1.0 for exposure from a, contaminated ground plan yields a new critical to organ dose rate factor DFG co(see Table 3.2) and a dose rate equation in the same form as Equation n-5 above: (A-6) 6 E D OFG'tco co 1 1 9530L-DS

r ~ Proc. Moi 26.1 Rev. No. I Page 80 of 88 I i ATTACHMENT I MAINE YANKEE ATOMIC PONER COMPANY [ 0FF-SITE DOSE CALCULATION MANUAL I APPENDIX A i A.S h-- Air Date Method I is used to demonstrate compliance with Technical Spccification 3.17.8, which limits the gasma,atr dose due to noble gases released in gaseous effluents via the plant stack to areas at and beyond the site boundary. Method I is derived from the methods of Equations 5-4 and 8-5 in Regulatory Guide 1.109 (Reference 1) which gives: finite,atr = 3.17E+04 (X/Q)' E Qt DFj (A-7) D I where: 1 D inite, air is the gamma air dose, in arad due to a finite aloud release; f 3.17E+04 is the number of pCi per C1 divided by the number of second per year; (X/Q)I is thg effective long-term average gamma dilution factor in sec/m- (see Appendix B for use of effective gamma atmospheric dilution factors); during the period of interest, gas i released via the plant stac is the total activity of noble Q1 in C1; and is the gasma dose factor to air for noble gas 1, in DFt arad-m3/pCi-yr (taken from Refsrence 1). Incorporating the maximum effective long-term average gama. dilution factor of 1.40E-06 sec/m3 (see Table 6.1) ytelds: 1 Y (3-4) Dair = 0.044 E Og DFt i 9530L-05

w . Proc. No. 26.1 Rev. No. 1 Page 81 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL 1 APPENDIX A A.6 Bata Air Dose I Method I is used to demonstrate compilance with Technical Specification 3.17.8, which limits the beta air dose due to noble gases relea.ed in gaseous effluents via the plant stack to areas at and beyond the site boundary. Method I is derived from the methods of Equations B-4 c.nd D-5 in Regulatory Guide 1.109 (Reference 1) which gives. 1 D{1r = 3.17E+04 X/Q E Qt OF{ (A-8) l 1 wheita 0l1r is the beta air dose, in arad; j 3.17E+04 is the number of pC1 per Ci divided by the number of seconds per year; X/Q is the long-term (5-year) average undepleted dilution factor, in sec/m3; l Og is the total activity of noble as i released via the plant stack during the period of interest, n Ci; and l DFS is the beta dose factor to air for noble gas 1, in arad-m3 pCi-yr. l / Incorporating the maximum long-term average undepleted dilution factor of 9.46E-07 sec/m3 (see Table 6.1) yields: 091r = 0.03 E Qt OF9 (3-5) i 1 I l 4 9530L-DS 0

- - -.. - ~, - - - - - _ - Jrec.. No.. 24.1 [ Rev. No. 1 i Page S2 of 88 j l ATTACMENT I l f MAINE YANKEE ATOMIC P0MER COMPANY 0FF-SITE DOSE CALCULATION MANUAL [ I APPENDIX A A.7 Done from fadinan and Particulaten l f Method I ta used to demonstrate compliance with Technical Specification 3.17.C which limits the dose commitment to a member of tne l f public from iodine-131, iodine-133, tritium and radioactive materials in particulate form with half-itves. greater than eight days in gaseous effluents i released via the plant stack or auxiliary botter stack to areas at and beyond [ the site boundary. For site boundaries adjacent to Back River, the off-site l i atmospheric dispersion parameters were determined (see Table 4.1) for l j locations on the opposite shore where there is a potential for exposure pathway's to exist on a continuous basis. The maximum of all off-site i atmospheric dispersion parameters in any direction was selected in the j determinatisti~of potential doses from iodines and particulates. t The dose commitments to an individual from iodine-131, iodine-133, l i tritium and radioactive materials.in particulate form with half-lives greater i than night dt.ys released to the atmospners via the plant stack are calculated i using the methods of Equations C-2, C-4, and C-13 in Regulatory Guide 1.109 (Reference 1). Gaseous pathways assumed to contribute to individual doses at ground surface, inhalation of radionuclides in air, and ingestion of f external irradiation from radionuclides deposited on the ) Maine Yankee are: atmospherically released radionuclides in focd. 1 f The use of the methodology of Equations C-2, C-4, and C-13 for a one curie release of each radionuclide in gaseous effluents yielded the dose [ impact to the critical organ. Table 3.2 lists the resulting site specific critical organ dose factors for plant stack releases giving the number of f Sunce the dose. factors of millires per curie released for each radionuclide. I' Table 3.2 represent a variety of critical organs, Method I"conservatively l ~ calculates 'a ' critical organ dose consisting of a combination of critical j l Siellarly, Table 3.3 list the site specific ( organs of different age groups. j dose factors for releases via the auxiliary boiler resulting from the burning j of contaminated waste oil. i i i i-l l t j l 9530L-DS l

~' '~ ~ ^ i Proc. No. 26.1 Rev. No. 1 Page 83 of 88 ATTACHMENT I MAINE YANKEE ATOMIC PONER COMPANY l OFF-SITE DOSE CALCULATION MANUAL APPENDIX A Parameter values used to derive the critical organ dose factors for todines and particulates are listed on Tables A-2 and A-3. l Milk and meat animals are assumed to be on pasture 50 percent of the time, consuming 100 percent of their feed from pasture during that period. This assumption is conservative since most dairy operations use supplemental feeding of animals when on pasture or actually restrict animals to full time silage feeding throughout the year. l i l l r L F l t 5 l l 9530L-OS

t froc..No. 26.1 Rev. No. 1 Page 84 of 88 4 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALOJLATION MANUAL APPENDIX A TABLE A-2 Usman Factors for Various Cateous Pathways at Maine Yankee (From Reference 1. Table E-5*) i r AGE LEAFY GROUP VEG. VEG. MILK MEAT INHALATION (KG/YR) tKG/YR) (1/YR) (KG/YR) (HJ/YR) ( Adult 520.00 64.00 310.00 110.00 8,000.00 l Teen 630.00 42.00 400.00 65.00 8,000.00 Child 520.00 26.00 330.00 41.00 3,700.00 Infant 0.00 0.00 330.00 0.00 1,400.00 I

  • Regulatory Guide 1.109.

i [ 1 I f i l f 9530L-05 . _ _. _ _ _ _ _ _ _. _,. _ _ _ _ _ _ _ _ _l

o. Proc. No. 26.1 Rev. No. 1 Fage 85 of SS ATTACHMENT I l MAINE YANKEE ATOMIC PONER COMPANY 0FF-SITE DOSE CALCULATION MANUAL I APPENDIX.A TABLE A-3 Effluents at Maine Yankee (nvir==tal Parameters far Catenut (Dettved from Reference I)* Vaastahtet few Milk Caat Mt' k Weat i Vae1mh1e 11ag31 La&f2 (Altur.t 11AIta f.A112f.1 h1AI14 Paiture iLltte t j YV Agricultural (kg/m2) 2. 2. 0.75 2.. 0.75 2. 0.75 2 Productivity P Soll surface Density (kgl.2)

240, 240, 240.

240. 240. 240.

240, 24C!

f Transport flee to User (hrt) 48. 48. 44, 48. 400. 48C, it $411 Esposure flee (l) (hrs) 131400. 131400. 131400. 131400. 131400. 131400. 131400. 13140C j TF Crop tiposure fing (hrs) 1440. 1440. 720. 1440. 720. 1440. 720. 144C ! L I te Plume Holdup Af ter Harvest (hrs) 1440. 24. O. 2160. C. 2160. O. 216,Cl 50. 50. 6. 6. 50. SC QF Animals Daily Feed (kg/ day) 0.50 0.50 0.50 i FP Fraction of Year on Pasture (2) 1. I* I* F5 Fraction Pasture m en on Pasture (3) TG Fraction of Stored 0.76 ( Veg. Crown in C4rden l 1.0 [ FI, Fraction of Leary veg. Crown in Garden f FI Frattton Elemental todine '0.5 0 Abs:19te (gale 3) Hueldtty. 5.6(4) i l

  • Regulatory Guide 1.109
1). For Method !! dose / dose rate analyses of identified radioactivity releases of less than one year the soll

[ etMskre time for that relette any be set at 1760 hours (1 year) for all pathways.

2) For Method !! dose / dose rate analyses performed for releases occurring during the first or fourth calendar

{ guerters, the fraction of time antails are assumed to be on pasture is zero (nongrowing season). For the second and third calender guerters, the fraction of time on pasture (FP) will be set at 1.0. FP may also be adjusted for spectf tc faru locations if this taformation is se identified and reported as part of the j land use C;,nsus. for Method !! analyses, the fraction of pasture feed while on pasture may be set to less than 1.0 for j ,) specific fare locations if this taformation is to identified and reported as part of the tard use census.

4) for all Method !! analyses, an absolute hvetitty value cual to 5.6 (gs/m3) shall be used to reflect I

conditions in the northeast (References Netith Physics Joonal. Vol. 39 (August), 1980; Page 318 300, i Pergamon Press). 9530L-OS L

c e s. Proc. No. 26,1 Rev. No. 1 Page 86 of 88 ATTACHMENT I MAINE YANKEE ATOMIC POWER COMPANY OFF-SITE DOSE CALCULATION MANUAL APPENDIX B Mateoroloav Long term (annual and five-year) average dilution factors based on on-site meteorological data were computed for routine primary vent stack releases by the Yankee Atomic Electric Company's (YAEC) AEOLUS (Reference 2) computer code. AEOLUS is based In part, on the straight-line airflow model as discussed in Regulatory Guide 1.111 (Reference 3). The following AEOLUS features were used in the assessment of dilution factors for the Maine Yankee site: hourly meteorological data input (wind direction, wind speed, and vertical temperature difference) straight-line air flow model with Gaussian diffusion. part-time ground level and part-time elevated releases (split-H model). multi-energy sector-averaged finite cloud dilution factors for gama dose calculations. terrain height correction features, 1 plume rise (momentum), depletion in transit, dry deposition rates (based on Regulatory Guide 1.111). l The following sector-average dilution and deposition factors were produced: non-depleted dilution factors for evaluating ground level i concentrations of noble gases, tritium, carbon 14 and non-elemental i todines. l l 1 i ? I [ i i 9530L-OS l

' Proc. No. 26.1 Rev. No. 1 Page 87 of 88 ATTACHMENT I MAINE YANKEE ATOMIC PONER COMPANY OFF-SITE DOSE CALCULATION MANUAL l l APPENDIX B I i depleted dilution factor for estimating ground level concentrations of elemental radiolodines and other part culates. effective gama dilution factors for evaluating gamma dose rates t from a sector-averaged finite cloud (multiple-energy undepleted [ source), and i deposition factors for computing dry deposition of elemental l radiolodines and other particulates. t i Gama dose rates are calculated throughout tne 00CM using the finite cloud model presented in "Meteorology and Atomic Energy - 1968" (Reference 4. Section 7-5.2.5. That model is implemented through the definition of an effective gamma atmospheric dispersion factor. CX/Q1 [ (Reference 2. Section 6), and the replacement of X/Q in infinite cloud dose i

  • quations by the (X/Q ).

l l i i u f l i l r f i 9530L-05 l i

-._.-.2.--.-:.__...,-r..#..-___ ~ Proc. No. 26,1 Rev. No. 1 Page 88 of 88 -4TTACHMENT I MAINE YANKEE ATOMIC P0MER COMPANY 0FF-SITE DOSE CALCULATION MANUAL ALLLLIELS Regulatory Guide 1.109, "Calculati M of Annual Doses to Man From 1. Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", U.S. Nuclear Regulatory Cosmiission, Revision 1, October 1977. Hamawi, J.M., "AEOLUS - A Computer Code for Determining Hourly and 1 2. Long-Ters Atmospheric Dispersion of Power-Plant Effluents and for Computing Statistical Distributions of Dose Intensity from Accidental Releases", Yankee Atomic Electric Company Technical Report, YAEC-1120, January, 1977. Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport i 3. i and Dispersion of Gaseous Effluents in Routine Releases from Light Mater Cooled Reactors". U.S. Nuclear Regulatory Comission, ".rch 1976. [ 4. Slade, D. H., "Meteefology and Atomic Energy - 1968," USAEC, July 1968. 1 "Supplemental Information for the Purposes of Evaluation of 10CFR50, 5* Appendix I", Maine Yankee Atomic Power Company, including Amendments 1 and 2, October 1976. l 1 t i i l i t l l 9530L-DS}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20204G119&oldid=4067339"