ML20065N748

Rev 0 to UNT-005-014, Odcm

ML20065N748
Person / Time
Site:	Waterford
Issue date:	08/03/1990
From:	LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20065N588	List: ML20065N596 ML20065N748 ML20065N756 W3P90-1176, Application for Amend to License NPF-38,consisting of TS Change Request NPF-38-112 Re Generic Ltr 89-01 Implementation
References
UNT-005-014, UNT-5-14, NUDOCS 9012120274
Download: ML20065N748 (199)

Text

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I P_0RC/ Pert-ss 8L l

UNT-005-014 REVISION O EFFECTIVE DATE SAFETY-RELATED ADMINISTRATIVE PROCEDURE Offsite Dose Calculation Manual LP&L W-C RECORDS

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DO NOT USE (N ANY S/\FEi Y- EATED 15STWG, MAINTENANCE, OR OPERATIONAL ACTIVITY l

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yf2120274901207 p ADOCK 05000392 PDC UNT-001-002 Revision 12 .

Attachment 6.3 (1 of 2) 41

1 PORC ANB-PORE---S/6

-REVIEW AND APPROVAL SHEET REVIEW OF: UNT-005-014 - Offsite Dose PORC l10 I

Calculation Manual (Rev. 0) PORC - S/C O The PORC or PORC S/C has reviewed this item and determined that a Safety /

Commitment Review was performed, (if applicable) that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does not exist and that nuclear safety is/was not adversely affected.

R DAE M M ER SIO M M I NO 3BER-Ma'intenance Superintendent I g / bfl@b up r dent ((

Radiation Protection /

Superintendent" / [ .-

' ~

Operations Quality 6

/

Assurance Manager

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. Plant Engineering Sup'erintendent F/[

Assistant Plant- .

Manager PORC-S/C HEmber PORC-S/C Member

-PORC-S/C Member PORC-S/C Chairman 7

'PORC Chairman h,g / T[3/9p Meeting No.90-067 Item No. VIII-B Date: 8/2/90 This item is recommended for approval? E YES O NO

.This item requires SRC/NRC review prior to implementation? O YES E NO If yes, en:ure documentation supporting review is attached.

PLANT MANAGER-KUCLEAR APPROVAL Comments: f' f $/ h / /i ApprNed by M A,a v Mdk Date f[J((d

//

UNT-001-004

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/ Pla'nt sion 12 Mdnager-Nucp5ar Attachment 6.1 (1 of 1) 1 o

1

. 1 WCIRFORD 3 SES l PIMT OPERATING MANUAL Check Block Below NEW PROCEDURE REQUEST @PORCl[lPORC-S/C l PROCEDURE No.UNT-005-014 REV. NO. O PROCEDURE TTPE Mminint'ative TITLE Offsite Done Calculation Manual EFFECTIVE DATE [I/$ 88f[-e?(IF APPLICABII)

AUTHOR Dernadette R. Lee EXPIR CION DATE (IT APPLICABLE)

DESCRIPTION OF PROCEDURE Incorporate Radiological Effluent Tech Specs (RETS) and The Radiological Environmental Monitoring Program (REMP) into existing Offsite Doce Calculation Manual ( !!P-001-23 0 ) and make into an UNT procedure, s

REASON FOR PROCEDURE UcuRC Generic Letter, dated January 31, 1989, allowed far the RETS and RUMP to bo incorporato:3 isto the Offsite Doce Calculation Manual. Once this procodure in oporvved by the URC, these portions of the Tech Speen will be deleted.

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AUTHORIZED BY I d aea M k h [ DATE 4/2.7/fd ,

1 t Manager-Nuclear (POM) [ 7 SAFETT SCREENING / EVALUATION u k Signature, Author 9-23-96 Date -

TECHNICAL ~ ds IM/ - 7 ,2 5 - 1 D Date yitudture,TechnicalRev.mr GROUP HEAD iu.yu. b (.J .*T. / A /dM Y[U'[9 ,t

/'Signatde,GroupHead 'Date 1

Applicable Conditions (Temporary Procedures only):

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IDrr-001-003 Revision 12. Attachment 6.4 (1 of 1) 3G l

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 TABLE OF CONTENTS 1.0 PURPOSE ,

2.0 . REFERENCES -

. 3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 5.1 Site Characteristics 5.2 Specifications and Sur.veillance Requirements 5.3 Liquid Effluents 5.4 Gaseous Effluents' 5.5 Total Dose 5.6 Instrumentation 5.7 Liquid and Gaseous Radwaste Processe's 5.8 Radiological Environmenial Monitoring Program Requirements 5.9 Technical Specification Cross-References 6.0 ATTACHMENTS 6.1 Site Boundary for Radioactive Gaseous and Liquid Effluents 6.2 Hi'storical Average Dispersion and Deposition P. ameters for Areas at or Beyond the Unrestricted Area Boundary 6.3 Site Related Liquid Ingestion Dose Commitment Factors (Ag ) for Individual Nuclides -

6.4 Dose Factors for. Exposure to a Semi-Infinite Cloud of Noble Gases 6.5 Inhalation Pathway Doses Due to Radionuclides Other Than Noble Gases, R g 6.6 Ground - Plane Deposition Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R g 6.7 Cow's Milk Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R g i

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, Administrative' Procedure - UNT-005-014

, . 0ffsite Dose-Calculat' ion Manual -

- Revision 0-21  !

6.8j Heat Pathway Dose Factors Due to Radionuclides Other Than Noble-Gases,Rg

.' 6 . 9 - Leaf-Vegetable Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, Rg.

.6.10 : Goat's Milk Pathway Dose Factors Due1to Radionuclides Other Than.

Noble Gases, Rg 6.1'1j. Liquid' Waste' Management System Effluent Sources and delease Pathways .

- and Points

' 6.12. - Gaseous Effluent Sources, "Jaseous Waste Management Systems Ef fluent Sources and Exhaust Relr.ase Points 6.13L Radiological Environmental Monitoring Program

.6.141-Sample Location Table t '6015 Sector and Zone Designators for Radiological Sampling and Monitoring:

t Points

6.16IREMPSamplingLoc$tionsWithin2MilesofWaterford3 16 17H REMP Sampling: Locations Within 10 Miles-of Waterford 3 ,

6.18 REMP Sampling; Locations Within 50 Miles of Waterford 3 '

16;19 ; Specifications Cross-Reference Table' 16.20 -Technical-Specification Cross-Reference Table m LIST OF EFFECTIVE PAGES Revision 0 o- - Title .

~ 1-196 Revision-0

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- Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual +

Revision 0 1.0 PURPOSE 1.1 The offsite Dose Calculation Manual (ODCM) is a supporting document of the Waterford 3 Technical Specifications. This document provides (1) The Radiological Effluent Specifications and Radiological Environ-mental Monitoring Program required by Technical Specification 6.8.3; (2) the general characteristics of the Waterford 3 site; (3) the detailed Radiological Environmental Monitoring Program (REMP); (4)

,the description of the Radiological Environmental Monitoring Inter-laboratory Comparison Program; (5) the liquid and gaseous radwaste block flow diagram; (6) the Radioactive Liquid and Gaseous Waste

. Sampling and Analysis Programs; (7) the general methodology to be

, used to calculate dose to individuals due to relec:es of radioactive gaseous and liquid effluents from the Waterford 3 site; (8) the

- general methodology to the used to calculate effluent monitor setpoints and allowable release rates to ensure compliance with the Radiological Effluent Controls, 10CFR20, and 10CFR50 c.riteria; (9) the methodology to be used to ensure representative sampling of liquids; and (.10) the methodology to be used to comply with 40CFR190 criteria.

1.2 The Offsite Dose Calculation Manual (ODCM) follows the general models suggested by NUREG 0133 and Regulatory Guide ,1,109. However, alternate calculation meth'ods from those presen'ted may be used provided the overall methodology is acceptable and consistent with regulation or provided the alternate methodology is conservative. In addition, the most up-to-date dose conversion factors and bioaccumulation factors may be substituted in lieu of Regulatory Guise 1.109 values.

1.3 Actual step-by-step dose calculation will be performed by in plant procedures which are consistent with the methodology presented in this document.

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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0

2.0 REFERENCES

2.1 Waterford 3 SES Technical Specifications, Chapter 16 of Waterford 3 FSAR.

2.1.1 Technical Specification 6.14.1 2.1.2 Technical Specification 6.14.2 2.2 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous, Effluents in Routine Releases for Gaseous-Effluents from Light-Water-Cooled Reactors, July 1977.

2.3 USNRC Regulatory Guise 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.

2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October, 1977.

2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978.

2.6 Code of Federal Regulations: Title 10, Parts 20, 40, 50 and 100, 1987;. Title 40, Part 190.

2.7 HP-001-215, NRC and EPA Radiological Reporting Requirements 2.8 USNRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological- Effluents Technical Specifications in the Administra-l tive Controls Section of the Technical Specification and the Reloca-tion of Procedural Details for RETS to the Offsite Dose Calculation Manual or to the Process Control Program.

I 2.9 UNT-006-010, Event Notification and Reporting 4

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Adninistrative Procedure UNT-005-014 i Offsite Dose Calculation Manual Revision 0 3.0 DEFINITIONS 3.1 ACTION shall be that part.of a Specification which prescribes remedial measures required under designated conditions.

3.2 CHANNEL CALIBRATION shall be the adjustment, as necessary, of,the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel including' the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, and total channel steps such that the entire channel is calibrated.

3.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during~ operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

3.4 A CHANNEL FUNCTIONAL ' TEST shall be:

a. Analog channels.- the injection of a simulated signal into channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

c. Digital computer channels - the exercising of the digital

' computer hardware using diagnostic programs and the injection of simulated process data into the channel to -

verify OPERABILITY including alarm and/or trip function.

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-Offsite-Dose-Calculation Manual - Revision 0 6 '

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3.0 _ DEFINITIONS (cont'd). ,

i 3.5 The FREQUENCY NOTATION specified for the performance of Surveillance i Requirements shall correspond to the following intervals.

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o NOTATION FREQUENCY I

At least once.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i D- At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days. {

P: Completed. prior to each release.

Q. At least once per 92 days-SA At least once per 184 days.

, R At least o'nce,per 18 months.  !

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S/U Prior to each-reactor startup.

Not applicable.

N.A.

3.6 KEMBER(S) OF THE PUBLIC shal1 include all persons who are not

occupationally associated with the plant.- This category does not

. I include employees of the licensee, its. contractors,-or vendors. Also

' excluded from this category:are persons who enter the site' to service 1

equipment ~or make deliveries. -This category does include persons who' >

use portionslof the site for recreational, occupational, or other-

. purposes (not associated with the~ plant, e 0'

p' '3.7l-A' system,--subsystem, train, component, or device shall be OPERABLE or

/' have OPERABILITY when it is capable of performing its specified

.g function (s), and when all necessary attendant instrumentation,:

a controls, electrical power, required for the system, subsystem, train, component, or device to perform its function (s) are also 9y -

.capabli of performing their related support function (s),

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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 -

- 3.0 DEFINITIONS (cont'd)-

3.8 An OPERATIONAL MODE (i.e. MODE) shall-correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature as specified.-

REACTIVITY  % OF RATED AVERAGE COOLANT ~

-OPERATIONAL MODE CONDITION, K,ff THERMAL POWER

• TEMPERATURE _ ,

R

1. POWER OPERATION 1 0.99= > 5% . 1 350'F .

' 2.. STARTUP, 1 0.99- 55% 2 350'F.

. 3. HOT STANDBY d 0.99 0. > 350'F

- 4. HOT SHUTDOWN- < 0.99- 0 350*F) T,yg>200 FL 5.- COLD SHUTDOWN- < 0.99 0 5 200'F ,

6. ~ REFUELING ** 1 0.95 0 $ l140'F : ,

• Excluding; decay _ heat' ,

• • Fuel in the reactor vessel with'the vessel head closure bolts less than

. fully tensioned or with the head removed.

3.9: PURGE or PURGING sha'll: be the controlled process of discharging air.or gas from a confinement to. maintain temperature, pressure, humidity,_ concentration or other operating condition, in such a

-manner that-replacement air or-gas is required to purify the '

l confinement.

• 3.10 The SITE BOUNDARY shall be that line beyond:which-the land is neither.

owned, nor leased, nor otherwise controlled by the licensee, e i.

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'3.11 A SOURCE CHECK shall be the qualitative assessment of channel

. response when the channel sensor is exposed to a source of increased radioactivity.

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UNT-005-014 Offsite Dose Calculation Manual Revision 0 I

3.0 DEFINITIONS (cont'd) 3.12 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreation purposes.

4 3.13 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates-from the gaseous exhaust stream prior to the release to the environment,. such a system is not considered to have any effect on noble gas effluerits.

-Engineered Safety Feature (ESF)( atmospheric cleanup systems are not considered to'be VENTILATION EXHAUST TREATMENT SYSTEM' components.

3.14 VENTING shall be the controlled process of discharging air or gas

, from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

3.15 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting coolant system -

offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

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Administrative Procedure UNT-005-014 Offsite' Dose, Calculation Manual -

. Revision 0 4.01 RESPONSIBILITIES *

- 4.1 Nuclear Plant Operations Manager has lead responsibility for insuring implementation of the Radiological Effluent Specifications and '

Radiological Environmetal Monitoring Program.as required by Technical Specification 6.8.3 and as set forth in this procedur'e.

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4.2 The Radiation Protection Superintendent is responsible for ensuring

, Radiological 5ffluent Specifications and the Radiological Effluent Monitoring Program are performed as required according to procedures <

and methodologies established by the document, lie is also responsible for insuring the Land Use Census and Semi-Annual Effluent Release Report are performed.and~ issued as' required. . .

4.3 Nuclear'Operat. ions Support and Assessment - Manager is responsible '

for-the issuance and submittal of the Annual Environmental Report as required by this document. He is also responsible for the negotiation and mainenance of vendor contracts to supply Sample Analyses and Reports as required by.the. Radiological Environmental Monitoring Program, s ,

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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.0 PROCEDURE 5.1 SITE CHARACTERISTICS Waterford 3 SES is located on the west (right descending) bank of the Mississippi River.at River Mile 129.6 between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the north-western section of St. Charles Parish, Louisiana, near the towns of

.Killona and Taft.

The geographic coordinates for the Waterford 3 reactor are Latitude 29' 59' 42" North, and Longitude 90 28' 16" West. Based on the UTM (Universal Transverse Mercator) Zone 15, the UTM coordinates are Northing 3,320,743 meters and Easting 743,962 meters.

The Mississippi River is the closest prominent natural feature to Waterford 3, while other important nature features include Lac des Allemands, about 5.5 miles southwest of the site, and Lake Pontchar-train, about 7 miles northeast of the site. The land slopes gently from its high points near the Mississippi (10-15 ft. above mean sea level) to extensive wetlands located 1.5 to 2.5 miles inland from the river.

Most of the man-made features are located on the narrow strip of dry land between the Mississippi River and the wetlands. Near the Waterford 3 site are several large industrial facilities, including Waterford I and 2 (0.4 miles northwest of the site), Little Gypsy -

Steam Electric Station (0.8 miles northeast of the site, across the .

river from Waterford 3), Agrico, a fertilizer manufacturer (0.6 miles east-southeast), Occidental Chemical Company (0.8 miles east-southeast), and Union Carbide, a chemical manufacturer (1.2 miles east-southeast). Louisiana Power & Light Company (LP&L) owns and operates the above-mentioned steam electric stations. I 10 b.

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'Administrativa Procedure UNT-005-014 Offsite Dose Calculation Manual . Revision 0 i

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. 1 S.1, SITE CHARACTERISTICS (cont'd) '

Attachment 6.1 provides a map of the UNRESTRICTED AREA and SITE BOUNDARY for radioactive effluents. LP&L will have full control of all activities conducted within the exclusion area boundary of the Waterford 3 site. All of the property within the' designated exclusion area is owned by LP&L with the exception of the bottom i lands below mean low water of the Mississippi River.

LP&L owns, in title, all surface rights within the exclusion area ,

3 boundary of the plant. There is presently no intention to allow. f exploration for subsurface minerals from points on the surface of

, the exclusion area.

The Mississippi River, Louisiana Highway 18, the Missouri. Pacific.

Railroad right-of-way, and the west.(right descending) bank levee of:  ;

the Mississippi River constitute traversals of the site exclusion 1 area as allowed by 10CFR100.3-(a). Refer to the Waterford 3-Emergency-Plan Implementing Document for the arrangesents which have been made to giveLLP&L authority and control over these traversals.

(Note that Louisiana Highway 3127 does traverse the SITE BOUNDARY-but not the exclusion. area. ;However, LP&L does have the authorit'y to control this traversal in accordance with'the Waterford 3 E..

Emergency Plan Implementing Document.)-

i o et In addition to Waterford 3, there are two fossil-fueled units, Waterford SES Units 1 and 2, which are owned by LP&L and which are ,

within the site exclusion area. The plant staff for these two units consists of about 60 people. Since this includes workers assigned to shifts, it is a conservative estimate of the maximum number of fossil plant personnel that would be within the exclusion area at ,

any given time. Evacuation procedures for Waterford SES Units 1 and 2 are described in the Waterford 3 Emergency Plant Implementing .

Document.

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Administrative Procedure UNT-005 014-Offsite Dose , Calculation Manual Revision 0 5.1 SITE CHARACTERISTICS (cont'd)

A' portion of the land within the SITE BOUNDARY is utilized for agricultural activities. Farmers presently work the land but can be expected to actually be in the field less than 10 percent of the time.

Fishing in the Mississippi River from the batture is a rare practice in the Waterford area. An estimated maximum of 2 people may be

.. expected to_be engaged in this activity for a period less than-10 percent of the time within the exclusion area.

~

Texaco maintains a gas valve station east-southeast of the Waterford 3 SES island structure just within the radius of the exclusion

.' area. This valve station is automated and, requires only periodic.

monthly' maintenance involving, typically, two persons. r scuation procedures for'these maintenance' workers are described _a the Waterford 3 Emergency Plan Implementing, Document.

The Waterford property is shown in Figure 5.1-3 of-the-STS and Lincludes 3,561.3 acres. The plant area'is about 48 acres and is  ;

. defined as including the' fenced area immediately adjacent.to

Waterford 3. The site area is shown in Figure 5.1-3 of the STS-

- along with-principal station structures and nearby features. The site includes.only station structures.and does not include any

+ residential, recreational, or other industrial structures.. There is> ,

a visitor center and adjacent recreational area approximately 1.0 mile SSW of the plant.

The SITE BOUNDARIES for establishing effluent release limits along with radioactive effluent release points.are given in Attachment.

6.1. The ' nearest distances to the boundary line are- shown in .

Attachment.6.2 of this procedure. The release point elevations for gaseous effluents are provided in Attachment 6.1. I i

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~~ Administrative Procedure ~ ,

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'Offsite. Dose Calculation Manual

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. Revision 0 5.1 SITE CHARACTERISTICS (cont'd)

The restricted area, defined for the purpose of controlling ingress j into'-and egress from the site, coincide with the plant area which is [

i enclosed by the plant perimeter fence,  !

For the purpose of establishing effluent release limits in accordance with 10CFR20 and Appendix I to 10CFR50, the concept of the restricted I

area,_as, defined above for the purpose of ingress and egress control, is not applicable. The effluent release limits are established in order to ensure that: (1) the concentrations of the radionuclides in j gaseous effluents discharged from the~ plant stack and exhaust systems do not result in' exceeding the limits outside the site boundary set  ;

' forth in Table II, Column 1 of Appendix B to 10CFR20; (2) the concen- l tration of radionuclid: in liquid effluent at the unrestricted area boundary does not exu w '.he limits set forth in Table II, Column 2

. of Appendix B to 10CTR2" and (3) the cumulative liquid and gaseous radionuclide releases _ do not result in exposures to l'ndividuals outside the UNRESTRICTED AREA or SITE BOUNDARY in excess of the-limits' set'forth in Appendix I to.10CFR50.

'1980 population-by annular sectors within 5 miles or Waterford 3,can be found in the Environmental Report. Population was estimated for 1977 and projected for 1980. The methodology for estimating and projecting population-is described . in detail ,in section 6.1.4.2 of -

thc' Environmental Report. 'The closest town-to'Waterford 3 is-Killona, 0.9 miles west-northwest. Other towns near the plant include Norco 2.5 miles east; Hahnville, 3.7. miles east-southeast; and Laplace, 4.7-miles north. There are aleo smaller sett3ements-and homes'along both banks-of the river, the marest such place to Waterford 3 being Montz, 1.0 mile northeast.

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Adqinistrctiva Procsdure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.2.1 Compliance with the SPECIFICATIONS contained in the succeeding sections is required during the OPERATIONAL MODES or other conditions specified therein; except that failure to meet the SPECIFICATIONS requires that the associated ACTION requirements shall be met.

5.2.2 Noncompliance with this procedure chall exist when the require-ments of the SPECIFICATION and/or associated ACTION requirements are not met within the *pecified time intervals. If the SPECIFICATION is restored prior to expiration of the specified time intervals, completion of the ACTION requireme..ts is not required. +

5.2.3 Surveillance Requirements shall be applicable during all OPERATIONAL MODES or other conditions specified for individuni systems unless otherwise stated in an individual Surveillance Requirement.

5.2.4 ' Each Surveillance R'equirement shall be performed within the specified time ' interval with:

5.1.4.1 A maximum allowable extension not to exceed 25% of the surveillance interval.

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Ad2inistrative Procedure UNT*005-014 Offsite Dose Calculation Manual . Revision 0 5.2 SPECITICATIONS AND SURVEILLANCE REQUIREMENTS a'

5.2.5 Tailure to perform a Surveillance Requireme,r4) within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Specific System for Operation. Exceptions to these requirements are stated in

, the individual specifications. Surveillance Requirements do not have to be performed on luoperable equipment.

5.2.6 -Failure to comply with the compensatory ACTION requirements or failure to complete the survei1~.ance requirements within

. ' the specified time shall be documented and evaluated in .

acecrdance with Ref erence 2.9.

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t.dainistrative Procedure UNT-005-014 Revision 0 Offsite Dose Calculation Manual 1

5.3 LIQUID EFFLUENTS 5.3.1 Concentrat. ion Specification The concentration of radioactive material released in liquid effluents to UKRESTRICTED AREAS (see Attachment 6.1) shall be limited to the concentrations specified in 10 CTR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 microcurie /ml total ac'.ivity.

APPLICABILITY:- At all times .

ACTION ,

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the

, above limits, and describe the events leading to this condi-tion in the next Semiannual Radioactive Effluent Release Report. ,

SURVEILLANCE REQUIRDIENTS

a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 5.3-1.

b. The results of the ra!.ioactivity analyses shall be ured in accordance with the methodolo;y and parameters in section 5.3.5 to assure that the concentrctions at the poi.n. of release are maintained within the limits of Specification 5.3.1.

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Administrative Procedure UNT-005 014 9ffsite Dose Calculation Manual ,

Revision 0 TABLE 5.3-1 I%DIOACTI\T. LIQUID WASTE SAMPLING AND ANALYSIS PROGRUj LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)

A. Batch Waste P P Each Batch Each Batch PrincipagGamma 5x10 7 Releasg'I't,h,i Tanks Emitters 1-131 1x10 6

1. Boric Acid Condensate 4 P M Dissolved and 1x10 6

- . Entrained Gases

2. Waste One Batch /M (Gamma Emitters)

Condensate P M 11 - 3 1x10 6  ;

d Each Batch Composite 1

3. Laundry Gross A)pha 1x10 7 Waste P Q Sr-89, Sr-90 5x10 5 d

4. Turbine Each Batch Composite Building .

Industrial Waste , Te-55 1x10 6 Sumps *

5. Dry Cooling Tower Sumps

1. 1 and #2*

6. Regenerative Waste

7. Filter Flush

. 8. Vaste

• When release from this source is batch in nature.

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Administrctive Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 TABLE 5.3-1 (Continued) i LOWER LIMIT l MINIMUM OF DETECTION i LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a l TYPE FREQUENCY TREQUENCY ANMNSIS (pC1/mL)

, B.

Continupug W W Release Grab Sample PrincipagGamma $x10 7 Emitters l

1. Turbine I-131 1x10 6 i

Building Indust ria l Waste Sumps **h

. M . M Dissolved and 1x10 6

2. Dry Cooling Grab Sample Entrained Gases Tower (Gamma Emitters)

Sump #1**g '

W M H-3 1x10 6 d

3. Dry Cooling Grab Sample Composite _

Tower .

Sump #2**i Gross Alpha 1x10 7 W Q' d Sr-89, Sr-90 5x10 6

4. Circulating g Grab Sample Composite Water Discharge- Fe-55 1x10 6 ,

Steam Gene-rator Blow-down IIX .

9

$. Auxiliary Component Cooling Water g Pumps

~

• • When release from this source is continuouc in nature.

18

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 a

TABLE 5.3-1 (Continued) ,

LOWER LIMIT MINIMUM OF DETECTION ,

LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a l TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)

B. Continuguy W W PrincipagGama k d Release Continuous Composite Emitters 5x10 7

6. Steam Generator

• I-131 1x10 6

• l Blowdown l Discharged 'I  !

M M Dissolved and 1x10 6 Grab Sample Entrained Gases (Gamma Emitters)

W k

H H-3 1x10 6 J

Continuous Composite

, Gross Alpha 1x10 #

W k 9 d Sr-89, Sr-90 5x10 6 Continuous Composite Fe-55 1x10 6 4

1 4

4 4

e 19

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 4

TABLE 5.3-1 (Continued)

TABLE NOTATION

• The LLD is defined, for purposes of these specifications, as the s:aallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical

- separation:

LLD = 4.66 s b E . V . 2.22 x 106 . Y , exp (;Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, shis the standard deviation of the background counting rate or of the ebunting rate of a blank sample as appropriate, a's counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fraction radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.

Typical values of E, V, Y, and At should be used in,the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement, b

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in Section 5.3.6 to assure represen-tative sampling.

20

Administrative Procedure UNT-00$-014 Off site Dose Calculation Manual- .

Revision 0 4

l l

5 i

i TAB 11 5.3-1 (Continued)

TABLE NOTATIONS i The principal gamma emitters for which the LLD specification applies include

, the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity. of liquid waste discharged and in which the i method of sampling employed results in a specimen that is representative of p- the liquids released.

'A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release, I

Prior to analyses, all samples taken for the composite shall be thoroughly +

mixed in order for the composite sample to'be representative of the effluent release.

8

! 1f the contents of the, filter flush tank or the regenerative waste tank

. contain detectable ~ radioactivity, no discharges rom these tanks shall be made to the' UNRESTRICTED ApIA and the contents of tb ,e tanks shall be directed to'the liquid radwaste treatment system.

l. h Turbine Building Industrial Waste Sump (TBIWS)

Th6 TBIWS shall be required to be sampled and analyzed in accordance with this. "

table if any of the following conditions exist:

(1)- Primary to secondary leakage is occurring; or, (2) Activity is present in the secondary system as indicated by either the SGB monitors or secondary sampling and analysis; or, t (3) Activity was present in the TBIWS during the previous 4 weeks. .

If none of the above situations exists, then the sampling and analysis of this' ,

stream need not be performed. i I Sampling and analysis of the dry cooling tower sumps and the auxiliary >

component cooling water pump discharge will be required only when detectable  !

activity exists in the CCW.

l Sampling and' analysis of the circulating water discharge-steam generator blowdown heat exchanger discharge (CWD-SGB) will be required only when detectable activity exists in the secondary system.

21 i

i Administrative Procedure UNT-005 014 Offsite Dose Calculation Manual Revision 0 I TABLE 5.3-1 (Continued)

TABLE NOTATIONS d

Sampling and analysis of the steam generator blowdown will,be required only when the blowdown is directed to the circulating water system or Waterford 3 waste pond.

Steam generator blowdovn to the Waterford 3 waste pond will be limited to situations requiring secondary chemistry control where the Circulating Water 4

System is not available or the secondary chemistry is outside the requirements for Circulating Water System disr,'arge. Blowdown to the waste pond will be terminate upon direction of sampit & activity greater than the LLD levels of Table 5.3-1.

To be representative of the quantitles and concentration of radioactive materials in liquid effluents, samples shall be collected continuously in i proportion to the rate of flow of the effluent stream.

I Steam generator blowdown discharge to the waste pond is not available unless radiation monitoring and automatic isolation capabilities are added to the waste pond discharge path.

6 4

e

?

4 i

22

Administrative Procedure UNT-005-014 Offsite Dose Calculation M:nual -

- Revision 0

~

5.3 LIQUID EFTLUENTS (cont'd) -

5.3.2 Dose Specification The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to l UKRESTRICTED AREAS (see Attacttment 6.1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid . effluents exceeding any of the above *

^

. limits, prepare and submit to the Commission within 30 i

days, pursucnt to Technical Specification 6.9.2, a Special Report that identified the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduc'e the releases and the proposed corrective actionJ to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radio-logical impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.

23

Administrctive Procedure UNT-005-014 Offsite Dose Calculation M:nual Revision 0 5.3 LIQUID ErrLUENTS (cont'd)

SURVE7LLANCE REQUIREMENTS:

a. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with methodology and parameters in Section 5.3.7 at least once per 31 days.

t 24

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual -

Revision 0 I

1 5.3 LIQUID ETTLUENTS (cont'd)

SURVEILLANCE REQUIREMENTS:

a. Cumulative dose contributione from liquid effluents for the current calendar quarter and the current calendar ,

year shall be determined in accordance with methodology and parameters in Section 5.3.7 at least once per 31

. . days.

6 9

et e

0 0

.i

=

4 24

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

. A Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 t

5.3 LIQUID EFFLUENTS (cont'd) , ,

5.3.3 Liguid Radwaste Treatment System Specification The liquid radwaste treatment system shall.be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Attachment 6.1) would exceed 0.06'arem to the total body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste trearment system not in operation, prepare and submit to the Commission within 30 dsys pursuant to Technical Specification 6.9.2 a Special Report that ine'ludes the following information.

1. Explanation of why liquid radwaste was being discharged i without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

25

Administrative Procedure UNT-005-014 Offsite Dose falculation Manual -

Revision 0 5.3 LIQUID EITLUENTS (cont'd)

SURVEILLANCE REQUIREMENTS

a. Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least>once per 31 days in accordance with the methodology and parameters in Section 5.3.7.

~ '

b. The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by meeting Specifications 5.3.1 and 5.3.2.

4 d

P 4

9 26 l

Administrctive Procedure UNT-005-014 Offsite D0se C:1culation Manual Revision 0 5.3 LIQUID ErrLUENTS (cont'd) 5.3.4 Liquid Effluent Dose Calculation 5.3.4.1 The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Section 5.3.2 using the following expression:

n Dtg = At Fggg{3ftgg A C (3) m Dt =g[3 D tf (2)

Where:

D tg = the cumulative dose commitment to the total

' body or any organ (t) from the liquid effluents for each liquid release in mrem during time perio'd (t) t = the cumulative dose :ommitment to the total body or any organ (t) from the liquid effluents for all (1) time period 6 at t= the length of the 1 time period over which

, the release is made, in hours C,e j the concentration of radionuclide (1) in a ndiluted liquid effluent during time period 6t g from any liquid release, in pCi/ml 27

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.3 LIQUID EFFLUENTS (cont'd)

A gt

= the site-related liquid ingestion dose commitment factor to the total body or any j organ (t) for each identified nuclide (i) in mrem-ml/hr-pCi (Attachment 6.3) i Fg = the near field average dilution factor for C

gg during any liquid effluent release.

Defined as the ratio of the undiluted liquid 1

waste flow during release to the average flow from the site discharge structure to site boundary receiving waters.

4 F = liquid radioactive vaste flow f

discharge structure exit flow The liquid radioactive waste flow is the maximum flow from the effluent release. The discharge structure, exit flow is the flow during disposal from )

the discharge structure release point into the receiving water body. For radionuclides .not determined in each batch or weekly composite', tne dose contribu-tion to the current calendar quarter cumulative i summation may be approximated by using a ratio of

! concentrations based on the previous monthly or quar , composite analyses, i.

l 28

Administrotive Procedure UNT-005-014 Offsite Doss Calculation M:nual Revision 0 I

S.3 LIQUID EFFLUENTS (cont'd) 5.3.4.2 Equation (1) above for calculating.the dose contribu-tions required the use of a dose factor, Ag , for each nuclide (i) which embodies the dose factors and dilution factors for the points of pathway origin.

. The adult total body dose factor and the adult organ dose factor for each radionuclide will be used from Table E-11 of Ragulatory Guide 1.109; thus the list contains critical organ dose factors fer various organs. The dose factor is written:

.A g = K0(UW /UW*Uf BFg ) DCF gt (3) where:

Uy = 730 1/yr adult water consumption, Dy = Dilution factor from near field area to potable water intake,

= 220 for discharges from the circulating water '

discharge into the Mississippi River (based on 'the ratio of the average Misst snippi River flow to the niaximum discharge flow),

=-1 for discharges into the 40 Arpent Canal (based -

on the assumption that dilution from the near field area to a potable water intake is negligible),

A g

= Composite dose parameter for the total body or critical organ (t) of an adult for nuclide (1) for all appropriate pathways (arem-ml/hr-pCi),

29

Administrativa Procedure UNT-00$-014 Offsite Dose Calculation Manual '

Revision 0 '

.s 5.3 LIQUID EFFLUENTS (cont'd)

= Unit conversion factor, K,

U f

= 21 kg/yr, adult fish consumption, p.

BFg= Bioaccumulation factor for nuclide (i) in fish (pCi/kg per pCi/1) from Table A-1 of Regulatory Guide 1.109, DCF g = Dose conversion factor for nuclide (1) and organ (t) for adults (mrem /pci). Values are from Table E-11 of Regulatory. Guide 1.109, NOTE For other liquid pathways, the appropriate dose factors ,

will be utilized. ,

4 .

4 4

30

[,

Administrativa Procedure UNT-005 014 Offsite Dose Calculation Manual -

Revision 0 -

\

5.3 LIQUID EFFLUENTS (cont'd) 5.3.5 Liquid Effluent Monitor setpoint Calculation Methodology l

Specifications 5.3.1 and 5.6.1 require that the liquid effluent monitoring instrumentation alarm / trip setpoints' be set so that the concentration of radioactive material released from the site is limited to 10CFR20, Appendix B, Table II, Column 2 for  !

, radionuclides other than dissolved or entrained noble gases.

(For. dissolved or entrained noble gases, the concentration .

shallbelimitedto2E-4pCiIm1totalactivity). This section presents the method to be used for determining setpoints in. '

accordance with Surveillance Requiremer.ts 5.3.1 and 5.6.1.

1 5.3.5.1 The calculated setpoints for the liquid effluent  !

i monitors-satisfy the following equation:  !

. n' g,

(SF)(RF)(F+f)g[3g C (4)

TMPC (f) where; ,

, i

.n- ,

.gf3gC = the undiluted effluent gamma concentration pCi/ml for all radionuclides (1). The value will be derived from radioanalysis of liquid j effluent to be released. This value will.be ,

supplied for each liquid release.  !

F c = the setpoint, in pCi/ml, of the liquid effluent.

. monitor measuring the radioactivity concentra-tion in the effluent line prior to dilution and subsequent release. This setpoint repre-sents a value which, if exceeded would result in concentrations exceeding the limits of 10CFR20, Appendix B Table II. Column 2, to an UNRESTRICTED AREA.

31

Administrative Procedure UNT 005-014 Offsite Dose Calculation Manual Revision 0 J -

l -<

i. 5.3 LIQUID EFFLUENTS (cont'd)

i = the liquid effluents flow as measured at the liquid effluent monitor location in gpm.

F = the dilution water flow as determined via pump curves or other appropriate measures that determine correct plant operating 4 configuration in gpm 1 l

M m

NOTE

)

e IF F is large compared to f then F + f E F.

. i SP =, Safety factor to ensure that the effluent limit is not exceeded. Actual value is set by procedure (in the range 0.5 - 0.9).

RF = Release fraction allocated to this release (to be used only in. situations of .

simultaneous or concurrent release). ,

n a '

TMPC = g[3 Cg , j{3 1 MPC g -

MPC) 5

, s

^

=

} the. undiluted nongamma MPC) fraction for all ,

nongainma emitting radionuclider (i)

MPC) ,

Cg = undiluted gamma MPC g fraction for all gamma fiPC g emitting radionuclides (1)  ;

MPC) = Maximum Permissible Concentration for the j applicable nongamma-emitting isotope (j) from 10CFR20, Appendix B Table II, Column 2.

i MPCg= Maximum Permissible Concentrat.an for the applicable gamma-emitting .sotope (i) from 10CTR20, Aprendix B, Table II, Column 2.

32

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual -

Revision 0

~

5.3 LIQUID EFFLUENTS (cont'd) g 5.3.5.2 The values of C g and C) will be measured for each release as appropriate and the parameters for f and F will be supplied based on current plant operating i.. configurations. The setpoint will be calculated in terms of pC1/ml and the liquid effluent monitor will be adjusted as necessary to ensure that liquid releases. are secured prior to exceeding limits specified in 10CFR20, Appendix B, Table II, Column 2 to an UNRESTRICTED AREA.

4 4

i 4

9 6

0 9

9 a

e e

4

't 0

9 I

33

Administrctive Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 9

5.3 LIQUID EFFLUERTS (cont'd)  ;

5.3.6 Representative Liquid Sampling Prior to grab sampling liquid waste tanks, methods should be used to guarantee representative sampling. Large volumes of liquid vaste should be mixed in as short a time as possible and uniformly distributed prior to sampling. To determine the minimum mixing time for tanks from which releases are made, the following tests were performed prior to initial use for release purposes.

. a. The tank was filled to a known volume.

b. A specific quantity of a selected chemical and/or sediments was added to the tank.

c. Recirculation was initiated through the normal patt .

d. ' Periodic samples were taken until equilibrium is reiched.

e. The time observed to completely mix the tank is use d as a minimum recirculation time prior to effluent sa'epling.

Records of the test will be maintained.

34

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

Ad2inistrative Procedura UNT-005-014 l Offsite Dose Calculation Menual Revision 0 I 5.3 LIQUID ErrLUENTS (cont'd) i 5.3.7 Do,se Projection for Liquid Ef fluents Specification 5.3.3 requires that appropriate subsystemn of the liquid radvaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid 4 effluent from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided '

foe performing this dose projection. i At least once every 31 days, the total dose from all liquid releases for the quarter-to-date vill be divided by the number of days into the quarter and multipited by 31. If this projected dose exceeda 0.06 mrem total body or 0.2 mrem any organ, and the Liquid Waste Hanagement System has not been operating, it shall be operated, if operation would reduce the monthly projected doses below 0.06 mrem total body or 0.2 mrem any organ. - (This is preformed in accordance with .the Surveil-lance Requirements of.5.3.3.)

U , .

4 r

i 35

- , - ,a.-.-.-

Administrative Procedure UNT-005-014

'Offsite Dose Calculation Manual -

Revision 0 -

5.3 LIQUID EFFLUENTS.(cont'd) 5.3.8 Liquid Effluent Bases

. a. CONCENTRATION (Section 5.3.1) <

This' specification'is provided to ensure that the concen-tration of radioactive materials released'in liquid waste effluents to UNRESTRICTED AREAS will be less than the <

~

concentration levels specified in 10 CFR Part 20. Appendix .

B, Table II, Column 2. This limitation provides additional [

assurance that the levels of radioactive materials in '

bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives lof Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC.and (2) the limits of 10 CFR Part 20.106(e)Lto the population.

, The concentration limit for dissolved or entrained noble gases is based upon the assumption that'XeJ135 is the *

, controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration is water.

,, using the' methods described in International Commission on-Radiological Protection (ICRP) Publication 2.

.The sampling and analysis of the contents of the regenera-tive vaste tank and the: filter flush tank is. performed if i

primary to secondary leakage occurs in a steam generator.

The contents of these tanks cannot be discharged to the . I UNRESTRICTED AREA if any radioactivity is detected in-these tanks since the discharge from these tanks is unmonitored. When radioactivity is detected in these tanks, the contents from these tanks must be discharged to

. the liquid radwaste system where the contents may then be monitored upon discharge.

36 J

____ - ~ . . _ = - -- . _ - - - .. ..

Administrctive Procedure UNT-005-014 Offsite Dose Calculation Manual * ,

Revision 0 5.3 LIQUID EFFLUENTS (cont'd)

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discus-sion of the LLD, and other detection limits can be found

. in HASL Procedures Manual, HASL-300 (revised annually),  !

Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry,"

Anal. Chem, 40, 586-93 (1968), and Hartwell, J.K., j

" Detection Limits for Radioanalytical Counting Techniques,"

Atlantic Richfield Handford Company Report ARH-SA-015 l (June 1975). .

b. DOSE (S'ection 5.3.2)

This specification is provided to implement the requirements-of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The' Limiting Condition for Operation' implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operatfag flexibi-lity and at the same, time implement the guides set forth

• in S'ection IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED 1 AREAS will be kept "as low as is reasonably achievable."

Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, '

there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in i

the finished drinking water that are in excess of the requirements of 40 CFR Part 141.

t 37

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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual -

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-l 5.3 LIQUID EITLUENTS (cont'd) ,

b. DOSE (Section 5.3.2) (cont'd)

The dose calculation methodology and parameters implement the requirement in Section III.A of Appendix I that confor-mance with the guides of Appendix I be shown by, calculational  !

procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways.is unlikely to be substantially underestimated.

The equations specified for calculating the doses' due to the actual release rates of radioactive materials in liquid .

p effluents are consistent with the methodology provided in

Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases or Reactor Effluents for the purpose of

- Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.113,

" Estimating Aquatic Dispersion of Effluents from Accrfental ,

and Routine Reactor Releases for the Purpose of Implement-ing Appendix I," April 1977.

c.- LIQUID RADWASTE TREATMENT SYSTEM (Section 5.3.3)

The OPERABILITY of the liquid radwaste treatment system ,

ensures that'this system will be available for use whenever liquide5fluentsrequiretreatm'entpriortoreleasetothe

, environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid efflu-ents will be kept "as low as is reasonably achievable." This -

specification implements the requirements of 10CFR Part'50.36a,-

General Design Criterion 60 of. Appendix A 10 CFR Part 50 and the design objective given in Sect. ion II.D of Appendix I to-10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix J, 10 CFR Part 50, for liquid effluents. >

38 4

,v 4 ,

.. , v n. + y ~,-,a-..,-e,, n ,.w . wm ,_m.,-n., ,w -

, + , . . . . , _ , , rw~_n,-.---,-n.-<

Administrative Procsdure UNT-005-014 Offsite Dose Calculation Manual .

Revision 0 I l

l 1

5.4 GASEOUS EFFLUENTS 5.4.1 Dose Rate Specification The dose rate due to radioactive materials released in gaseous effluents from the site to ar;4s at and beyond the SITE BOUNDARY (see Attachment 6.1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b.

For iodine-131, iodinea133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. '

APPLICABILITY: At all tienes 9

ACTION: .

9 With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s), and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.

l l

l i

l l

39 '

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

Administrative Procedure UNT-005-014 Offsite Dose, Calculation Manual Revision 0 i

l 5.4 GASEOUS LFFLUENTS (cont'd) 1 l

SURVEILLANCE--- REQUIREMENTS:

l 1

a. The dose rato due to noble gases in gaseous effluents j shall be determined to be within the above limits in l accordance with the methodology and parameters in Section 5.4.5.

b. Representative samples and analysis of gaseous effluents shall be obtained in accordance with the sampling and analyses program specified in Table 5.4-1.

c. Based upon the sampling and analysis performed in Table 5.4-1 the dose rate due to 1-131, I-133,11-3, and all other radionuclides in particulate form with half-lives greater than 8 days shall be , determined to be within the above limits in accordance with the methodology and parameters in Section 5.4.5.

s 6

40

-Surveillance Procedure '

UNT-005-014 Offsite Dose Calculation M:nual _

.. Revisian 0 TABLE 5.4-1 .

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM IhWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTINO (LLD)*

GASEOUS RELEASE TYPE FREQUENCY -FREQUENCY - ACTIVITY ANALYSIS (pCi/mL)

P P A. Waste Gas Holdup Each Tank Each Tank Principal Gama Emitters 1x10

• Tanks Grab Sample i P P l

1. C "

B. Containment PURGE Each PURGE Each TURGE Principal Gama Emitters 1410 4 (Flant Stack) Grab Sample -

M H-3 Ix10 6 I i

C.1 Plant- Stack M*' 'I Principal Noble Gas Gama 1x10 4  :

Grab Sample M Emitters  !

H-3 1x10 6 ,

C.2 Fuel- Handling M**' Principal Noble Gas Gama b

Ix10 4 Building Ven- Grs. Sample M Emitters tilation (Normal) H-3 1x10 6 t Exhaust i

i i

j 41 i

=

p. s -

UNT-005-014' Surveillance'Procedute Revision 0 Offsite Dose Calculation Manual TABLE 5.4-1 (Continued)

RA)IOACTIg GASEGUS WASTE SAMPLING AND ANALYSIS PROGRAM IOWER LIMIT OF (

MINIMUM TYPE 9F DETECTINO (LLD)*

SAMPLING ANALYSIS ACTIVITY M ALYSIS (pCi/mL)

GAEEOUS RELEASE TYPE FREQUENCY FREQUENCY f 'l 'W8 I-131 1x10 12 D.1 All Release Types ~ Continuous '

Charcoal as listed in Sample I-133 1x10 10 B., C.1, and C.2 above -

1x10 11 D.2 Main Condenser Continuous ' '3 'KE PrincipagParticulateGamma Emitters Particulate Evacuation and -

Sample Turbine Gland -

Sealing System f

M Grost Alpha Ix10 11 Continuous 'h'3 Composite ,

Particulate Sample ,

'l Sr-89, Sr-90 1x10 11 Continuous ' Q Composite Particulate -

Sample Continuousf ,h,j Noble Gas Noble Gases 1x10 8 Monitor Gross Beta or Gamma 42

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.4-1 (Continued)

TABLE NOTATION "The LLD is defined, for purpose of these specifications, as.the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

.66 s b LLD =

E.V. 2. 22 x 10' . Y , exp (- AAL)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s is the standard deviation of the background counting ra+e or of the b

counting rate of a' blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disiategration, V is the sample size in units of mass or ' volume, 2.22 x 106 is the number of di. integrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the. radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample

~

collection and the time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the fact) limit for a particular measurement.

43

i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual

. Revision 0 d

5.4-1 (Continued)

TABLE NOTATIONS b

The principal gamma emitters for which the LLD specification applies include the'following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and '

Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, 1-133, Cs-134, Cs937, Ce-141, and Ce-144 in iodine and particulate releases. This list des not mean'that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of

'the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.8.

cSampling shall also be' performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following shutdown, startup, or a TIERMAL p0WER change exceeding 15% of RATED TIERMAL POWER within a 1-hour

. period. Analysis for principle gamme emitters as defined in (b) above shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sampling.

d Tritium grab samples rhall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the '

refueling canal is flooded.

" Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust front the spent fuel pool area, wheners spent fuel is in g the s. pent fuel pobl.

I The ratio of the sample

• flow rate to the sampled strcam flow rate shall be ,

known for the time period covered by each dose'or dose rate' calculation made

=in accordance with Section 5.4.1, 5.4.2, and 5.4.3.

f 8

Samples shall be chaaged a,t least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Sampling.-shall also.be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days ' following each shutdown, startup or TIERMAL POWER change exceeding 15% of RATED TIERMAL POWER in I hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.; When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs'may be-increased by a factor of 10. This' requirement does

.not apply if (1) analysis:shows that the DOSE EQUIVALENT I-131 concentration ,

in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of'3. -

' If no primary to secondary leakage exists, then only the gross beta or gamma 5 noble.. gases analysis need be performed for the main condenser evacuation and

. turbine gland sealing system. If a primary to secondary leak exists and the t release from the main condenser evacuation and turbine gland sealing system

-has not been released via the plant stack, then the sampling and analysis must

.be performed.

i Note-(c)'above is not applicable for the plant stack unless the noble gas monitor shows that effluent activity has increased by a factor of 3.

dFuel Handling Building sampling is required whenever irradiated fuel is in the storage pool.

44 j 1

. Administrative Proc.edure - UNT-005-014 Offsite Dose Calculation Manual' m

- Revision 0 S '. 4 GASEOUS EFFLUENTS-(cont'd) i 5.4.2 Dose-Noble Gas Specification The air dose due.to noble gases released in gaseous effluents l to'arcas at and beyond the SITE BOUNDARY (see Attachment _-

6.1) shall be limited to the following:

.t

a. During any calendar quarter: Less-than or equal to 5 [

mrads for gamma radiation and less than or equal to 10 .

mrads for beta radiation and,

b. During any' calendar year: Less than-or equal to 10 mrads for gamma radiation and less,than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times. -

1 ACTION:

With the' calculated air dose from. radioactive noble gases-in gaseous effluents exceeding any of the above limits,' prepare and submit to the Commission within 30. days, pursuant to

' Technical Specification 6.9.2, a Special' Report'that

- Identifies the;cause(s) for' exceeding the~ limit (s) and defines.the~ corrective actions that-have been taken to reduc'e

- the releases and the proposed' corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS:

Cumulative dose-contributions for the current calendar

. quarter and current-calendar year for noble gases shall be determined in accordance with the methodology and parameters in Section 5.4.6 at least once per 31 days.

45

, . ~ -

Administrative Procedure UNT-005-014 Offsite Dose Calculation. Manual Revision 0 4

5.4 GASEOUS EFFLUENTS (cont'd) 5.4.3 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form Specification The dose to MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents rsleased 3 areas at and beyond the SITE BOURDARY (see Attachment 6.1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During'any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times ACTION:_,

With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commissien within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the. releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

46

Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual -

Revision 0  ;

i 4

5.4 GASEOUS EFFLUENTS (cont'd) e SURVEILLANCE REQUIREMENTS:

Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in Section 5.4.7 at least once per 31 days.

t 6

D 9 9

9 4

4 0

47

. l Administrative Proc.edure UNT-005-014 i Offsite Dose Calculation Manual Revision 0 l 4

5.4 GASEOUS EFFLUENTS (cont'd) 5.4.4 Gaseous Radwaste Treatment Specification The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Attachment 6.1) would exceed either:

a. 0.2 mrad to air from gamma radiation, or

b. O 4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times. .

ACTION:

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

48

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 J

5.4 GASEOUS EFFLUENTS (cont'd)

SURVEILLANCE REQUIREMENTS:

a. Doses due to gaseous releases to areas at and beyond the SITE B0UNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in Section 5.4.9.

b.- The installed Gases Radwaste Treatment System shall be demonstrated operable by meeting Specifications 5.4.1, 5.4.2 or 5.4.3.

l t

N 9

9 g

94 i

e 5

-4 4

I 49 .

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.4 GASEQUS EFFLUENTS (cont'd) 5.4.5 Calculational Methodology for Gaseous Effluent Dose Rate This section presents the calculational methods used for calculating gaseous effluent doses in fulfillment of Specification 5.4.1.

5.4.5.1 The dose rate due the radioactive materials released in gaseour effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following values and expressions:

Release rate limit for noble gases:

n K' (X/Q)y g[3 K gQgy $500 mrem /yr total body (5) n K' (X/Q)y g{3(L1 + 1.1H )g Qgy $3000 mrem /yr. skin (6)

Release rate limit for Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days:

n P 9 1v $1500 mrem /yr any organ (7)

(X/Q)y ib1 it Where:

K' = a constant of unit conversion, IE6pCi/pCi.

Kg = the total body dose factor due to gcmma emissions for each identified radionuclide 3

(i) in units or mrem /yr per pCi/m (Attachment 6.4).

50

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

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.4 GASEOUS EFFLUENTS (cont'd)

I.g

= the skin dose factor due to beta emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m3 (Attachment 6.4).

Mg = the air dose factor due to gamma emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m3 (Attachment 6.4).

The constant 1.1 converts air dose to skin dose.

P gt

= the thyroid dose parameter f.or Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days (i) for the inhalation pathway only, in mrem'/y.r per pCi/m 3 (Same as R g values for the child receptor listed in

' Attachment 6.5). The dose factor is base on the most restrictive age group (child) and most restrictive organ (thyroid) at the SITE BOUNDARY.

P g

= (child breathing rate of 3700 m /yr)(DFA 3 )g (K') whare DFA. is the inhalation dose factor for each radionuclide from Table E-9, Reference 2.4 n

I = summation for all identified radionuclides i=1 1

51

9 Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 l f

5.4 GASEOUS EFFLUENTS (cont'd)

Q gy = the average release rate of radionuclides (1) (either noble gas or Iodine-131, Iodine-133, tritium, and radionuclides in the particulate form with half-lives greater than 8 days, as appropriate) during the time of release from all vent releases (v).

Value is averaged over one hour and is in units of pCi/sec.

l 3

(X/Q)y = 1.1E-5 sec/m .in the ESE sector at 0.6 mile for all vent releases (v) (the' highest calculated annual average dispersion factor at.the SITE BOUNDARY based on historical data). The actual X/Q for the time of release may be determined and used under certain circumstances.

l ,

NOTE -

All radioiodines are assumed to be released in elemental form.

9 l

52

- e r -

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.4 GASEOUS EITLUENTS (cont'd) 5.4.6 Calculational Methodology for Noble Gas Doses This section presents the calculational methods used for calculating noble gas effluent dose in air in accordance with Surveillance Requirement 5.4.2.

5.4.6.1 The air. dose due to noble gases released in gaseous ,

effluents to areas at or beyond the SITE BOUNDARY will be determined by the following expressions:

- a. During any calendar quarter, for gamma radiation:

n m D = (1.14E2) (X/Q)y g{3(H)){3 g (At)> (Qg )y ) (8) and for beta radiation:

n m Dp = (1.14E2) (X/Q)y 3{1(N)){3 g (At)) (Q g)y ) (9)

b. During any calendar year, for gamma radiation:

n m D = (1.14E2) (X/Q)y{.{M,3(At](Q g)y)

                                                                         ,                                                    (10) and for beta radiation:

n m D p = (1,14E2) (X/Q)y{_3(N}},3(At](Q g)y) (11) Where: D = the total gamma (y) air dose from gaseous effluents for the total time period and not to exceed 5 mrad quarterly and 10 mrad yearly. 53

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

i

                                                     '                                                    l Ad3inistrative Proc.edure                                                     UNT-005-014          I Offsite Dose, Calculation Manual                   -                          Revision 0           l 5.4- GASEOUS EFFLUENTS (cont'd)

D p

                                             =  the total beta (p) air dose from gaseous effluents for the total time period and not to excer;d 10 mrad quarterly and 20 mrad yearly.                                                 >

t Qggy

                                             =  the average release rate of radionuclides               '
                                               - (i) in gaseous effluent from all vent releases (v) in pCi/sec during the time period at j-( !9}v = 1.1E-5 sec/m       3 in the ESE sector at 0.6 mile for all vent releases (v). The actual X/Q for the time.of release may be determined and used under certain circumstances.

At = the length of the j th time period over 3 which Q g3y are accuaulated for all gaseous releases in hours. M1 and Ng= the gamma and beta air dose factors (respectively) for a uniform semi-infinite cloud of radionuclide (i) in mrad /yr-per pCi/m3 (Attachment 6.4). t 1 l 54

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.7 Calculational Methodology for Doses Due to Radioiodines, Tritium, and Radioactive Materials in Particulate Form This section presents the calculational methods used for calculating doses due to Iodine-131, Iodine-133, tritium, and radionuclides in particulate form in accordance with Surveil-lance Requirement. 5.4.7.1 The dose to an individual from Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY will be determined by the f'oll.owing expressions: During any calendar quarter: n Dgg, = 1.14E-4 At I R yg, WQ y gy. (12) i=1 During any calendar year: n Dig, = 1.14E-4 At I R gg, WQ y fy (13) i=1 55 L.

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 1 5.4 GASEOUS EFFLUENTS (cont'd) Where: 1.14E.4 = a constant of units conversion

                                     =  lyr/8760 hr D gt, =. the cumulative dose to an organ (t), age group (a), due to radionuclides (i) in gaseous effluents; not to exceed 7.5 mrem quarterly or 15 mrem yearly.

W = the dispersion parameter for estimating the y dose to an individual at the controlling location for long term vent releases (v). W = y (X/Q)y for the inhalation pathway from vent releases (v) in sec/m3 , from historical data, at the location of the critical receptor (Attachment 6.2). Wy = (D/Q)y for the food and ground plane pathways-from vent releases (v) in m 2 , from historical data at the location of the critical receptor (Attachment 6.2). 56 -

Administrative Procedure UNT-005-014 Offsite Dose. Calculation Manual Revision 0 I 5.4 GASEOUS EFFLUENTS (cont'd) R gt, = the dose factor from each, identified radio-nuclide (i), for each applicable organ (t), and age group (a), in mrem /yr per uC1/m 3 for the inhalation pathway (Attachment

             -                                        6.5) and in mrem /yr per uCi/m2 -see for the food and ground plane pathways (Attachments 6.6, 6.7, 6.8, 6.9, and 6.10).      For sectors with real pathways within 5 miles of the-               .

plant, the values of R are g used based on these real pathways; for sectors with no

                                                  -   real pathways within 5 miles from the plant, Rg is used assuming that the cow grass-milk pathway exists at the 5-mile distance.

(Rg 's were calculated using the methodology. , found in Reference 2.5, pages 31-36.) Q gy = the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec. . At = the time required for the release in hours for all releases per quarter or per year. 4 I 57 l l

Administrative Procedure UNT-005-014 Uffsite Dose Calculation Manual Revision 0 t 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.8 Gaseous Effluent Monitor Setpoint Calculational Methodology 5.4.8.1 Specification 5.6.2 requires that the radioacti'e gaseous effluent monitoring instrumentation alarm / trip setpoints be set to ensure the limits of Specification 5.4.1 are not exceeded. 5.4.8.2 The calculated high alarm / flow termination setpoint is the maximum value for that particular release. For conservation, an administrative safety factor (SF)sof usually 10% will be utilized in the setpoint calculation. To allow for simultaneous releases from common or different release points a Release Fraction (RF) may be used to allocate percentages of the total allowable release. . 5.4.8.3 Since the noble gas dose rates are more limiting than

      .                                    .the radiciodine dose rate, gaseous setpoints will be based on noble gas dose rates (less than or equal to 500 mrem /yr total. body, and less than or equal to 3000 mrem /,yr skin), Specifically, gaseous setpoints will be based on the most limiting of the following equations:                                                 -

a. Total' body (Qtb)

(500 mrem /yr.)(RF)(SF) (14) q , (X/Q)y(1E6 pCi/pCi) n - 1 i=1 1 91v n 9 iv i=1 58 j l

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 a 5.4 GASEOUS EFFLUENTS (cont'd) Where: n I i=1 = summation of all nuclides considered. Q tb : maximum release rate allowed to give a limiting total body dose rate of 500 mrem /yr in pCi/sec. K.;

                                   =   the total body dose factor due to gamma emissions for each identified radionuclide (i) in units of erem/yr per pCi/m    3 (Attachment 6.4).

Q gy = average release rate of isotope (i) from the release point (v) in pCi/sec. RF = release fraction allotted to re'. ease point in consideration.

                   ,         (X/Q)y = 1.1E-5 sec/m3 (in the ESE sector at 0.6 mile). The sector with highest value of annual average atmospheric dispersion factor at the site boundary for the release point (v) in question.

SF = administrative safety factor to account for uncontrollable variables (sampling, monitoring errors, etc.). Usually, the SF takes on a value of 0.9. 59 l

m .. . . . , _-_. _. . _ _ _ . . ., . _ _ _ . . . _ , _ . . _ _ _ _ . . . .m.- _ _ _ _ , _ .~ _ 4 JAdninistrative Procedu're- UNT-005-014 Offsite' Dose Calculation Manual - Revision 0 1 5.4 GASEOUS. EFFLUENTS (cont'd)! +

b. For Skin (Q skin):

                                                                                 -Qskin = (3000 mrem /yr.-)(RF)(SF)                                                   (15)

(X/Q)y(IE6 pCi/pci) n

                    ,                                                                                                                      I (Lg + .1.'IM g)Qgy i=1 n

I Q gy i=1 where all terms are as defined above uscept: Qskin = maximum release rate allowed to give a limiting skin dose of 3000 mrem /yr in

                                                                                          .pCi/sec.

Lg = skin. dose. factor due to beta emissions for. , each identified radionuclide (i)-in units , 3

                                                                                         ,of mrem /yr per pCi/m (Attachment 6.4)                                                      !

1.1 = conversion-factor to convert from air to skin-dose. .

                                                                           'M g       =    air dose factor due to gamma emissions-for
                           ,                                                               identified noble gas isotope (1) in units.

of mrad /yr per pCi/m3 (Attachment 6.4). 5.4.8.4 The monitor.setpoint is calculated is the following manner: SN =- Q -(16) _. max 60

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.4 GASEOUS EFFLUENTS (cont'd) Where: SN = maximum monitor setpoint in pCi/cm 3 F max

                                       * ""*i""" *III"*"' II " #8t" (#* /8* )

Q = Minimum value of Q tb #O skin 5.4.8.5 Since Kr-88 is the noble gas with the highest dose rate conversion factors, for conservation, the preceeding calculations may be computed using Kr-88 , only. Total body dose becomes more limiting than skin and the release limit is:- QKr-88 = (500 mrem /yr.)(RF)(SF) (17)

                                                      -(X/Q)y(IE6 pCi/pCi)(KKr-88)'

where: QKr-88 = the maximum release rate, based on Kr-88, , allowed to give a limiting total body dose rate of 500 mrem /yr in pei/sec. K r-88 = the total body dose factor due3 to Kr-88 in units of mrem /yr per pC1/m (Attachment 6.4), All other terms are previously defined. The monitor setpoint can be calculated as: SN = QKr88 (18) F max and all terms are previously defined a 61

                     ~n-                     .    . - . . .-- - - - - ...                        .~.     . - - . . . . - - - - - - . - . -               --

Adminib+.rative Procedure UNT-005-014 Offsite Dese Calculation Manual . Revision 0 1 . i 5.4: GASEOUS EFFLUENTS (cont'd) 5.4.9 Dose Projection due to Gaseous Effluents 5.4.9.1 . Specification 5.4.4_ requires that appropriate subsystems of the Gaseous Radwaste Treatment System be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE BOUNDARY would exceed, in a

                                                                                                                                                                +

31-day period, any of the following: ., 0.2 mrad to air from gamma radiation; or

                                   .                                              0.4 mrad to air-from beta radiation; or-O.3 mrem to any organ of'a-MEMBER OF THE PUBLIC.

5.4.9.'2 The following calculational method is provided for

                                     .                                            performing this dose projection.

At lease onc,e every 31 days the gamma air dose, beta j

air dose and the maximum organ dose for'the' month-to-t quarter will be divided'by.the number of days into the quarter and multiplied by:31.- If these projected-

                                                                                  . doses exceed any of the values listed.above and the-Gaseous Waste Management System has-not been operating, it shall be operated to< reduce radioactivity levels:

prior-to release. -(This is performed.in'accordance-

                                                                                                                    ~

with the Surveillance Requirements of' Specification

                                                                                  .5.4.4.                                            ,

.. c e

                                                                                                                                                                .l 62
       ~ . ..             ,, .         ._       . - .            _ , . _ .           .

Ad2inistrative Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 I i 1 5.4 OASEOUS EFFLUENTS (cont'd) 5.4.10 Gaseous Effluent Bases

a. DOSE RATE (Section 5.4.1)

This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous , effluents will not result in the exposure of a MEMBER OF TIE PUBLIC in a UNRESTRICTED AREA, either within or ontnide the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II'of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF TIE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF TIE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS 0F TIE PUBLIC, with the appropriate occupancy factors, I ' shall be given in the ODCM. The sp cified release rate l limits restrict, at all times, the corresponding gamma - l and beta dose rates above background to a MEMBER OF TIE PUBLIC at or beyond the SITE , BOUNDARY to less than or equal to 500 mrems/ year to the skin. .These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the l inhalation pathway to less than or equal to 1500 mrems/ year. 63

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 s 5.4 GASEOUS EFFLUENTS (cont'd) The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed i discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qua'litative Detection and Quantitative Determination - Application to Radio-chemistry," Anal. Chem, 40, 586-93_(1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlant'ic Richfield Hanford Company Report ARH-SA-215 (June 1975).

b. DOSE - NOBLE GASES (Section 5.4.2) ,

The Specification is provided to implement the requiremen of' Sections II'.B, III.A and IV.A of Appendix I, 10.CFR Part 50. It implements the guides set forth in Section II.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to assure that the releases of radio-active material in gaseous effluents to UNRESTRICTED AREAS will be kept "as ' low as is reasonably achievable." The Surveillance Requirements implement the requirements . in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is

    ,                            unlikely to be substantially underestimated. The dose 64

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

Adninistrativef Procedure UNT-005-014 J Offsite Dose Calculation Manual Revision 0 N'.. 5.4 GASEOUS EFFLUENTS (cont'd) calculation' methodology and parameters established for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology:provided in Regulatory Guide 1.109, [

                                                       " Calculation of Annual Doses to Man from Routine Releases of Reactor Effl'uents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"= Revision"1, October 1977 and Regulatory Guide 1.111 " Methods for                               .

Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.. Sections 5.4.2 and 5.4.3 equations provided for determining the air: doses at and beyond the SITE BOUNDARY are based upon the historical .averag'e. atmospheric conditions. Grab sampling of effluents from the main condenser evacuation and turbine gland' sealing system;is not required when this. source hes.been continuously dis-charging to the plant stack over the past 30 days. If no primary to sec,ondary leakageLin.the steam generator exists, then there should be no radioactive release from the main condenser evacuation and turbine. gland sealing system and-the gross beta or-gamma. monitoring for noble-j gases will be sufficient to determine if any radioactivity. is-present in the release.. If a primary to secondary leak exists, then the release from the main condenser ll evacuation and turbine gland sealing systems will be sampled and analyzed in accordance with Table 5.4-1. t-65

LAdministrative Proc,edure. UNT-005-014 Offsite-Dose Calculation Manual. . Revision 0 l' 5.4 GASEOUS EFFLUENTS (cont'd) .

c. 10 DINE-131, 10 DINE-133, TRITIUM,-AND RADIONUCLIDES IN PARTICULATE FORM (Section 5.4.3)

This specification-is provided to implemen't the require-ments of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Specifications are the guides set .; forth in Section II.C of Appendix I.- The ACTION state-ments provide the required operating flexibility and , at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to URRESTRICTED AREAS w3ll-be kept "as low as is reasonat<ly achievable." The calculational methods specified in the Surveilla,nce Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be:shown by' calculational procedures based on models and. data, such that the actual exposure of a KEMBER OF THE PUBLIC through appropriate pathways is unlikely to be -

                                                                               $ubstantially underestimated. The calculational.methodo-logy.and parameters for" calculating the doses due to the-actbal release rates of:th'c subject materials are con--

sistent with the methodology provided~in Regulatory Guide - 1-109, " Calculation of Annual' Doses to Man from Routine

                                                                                                                                                                                         ~

Releases of Peactor Effluents _-for the Purpose of Evaluating. Compliance with 10 CFR Part 50, Appendix I," Revision 1, . October 197 and. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-

 ,                                                                         . Cooled Reactors,' Revision 1, July 1977. These equations also provide 'for _ determining the actual doses based upon th'e historical average atmospheric conditions.

66

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

Administrative Proc.edure. UNT-005-014-Offsite Dose Calculation Manual -

Revision 0

                                   - 5.4' GASEOUS EFFLUENTS (cont'd)

The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in-particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and. beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing - animals graze with consumption of the milk and meat by

                                      .             . man, and (4) deposition on the ground with subsequent

exposure'of man.

                                                'd. GASEOUS RADWASTE TREATMENT (Section 5.4.4)

The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the 1 VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release.to the environment. ,The discharge'from the main condenser

evacuation and turbine gland sealing' system-shall.be '

l l required to be directed to the plant stack when the release- rate of I-131 from this source is > 2 x 10 4 pCi/s. The requirement that the appropriate portions of-

                                                                                                                                                                                                  ~

these systems be-used, when specified, provides' reasonable.: , assurance that the releases of radioactive materials in. L gaseous effluents will be kept "as low as is-reasonably achievable". This specification implements the require-ments of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50.and the design objectives given in Section II.D of Appendix I-to 10 CFR Part 50. The specified limits governing the use of appropriate portions j- of the systems were specified as a suitable fraction of the  ; dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 67 m '+---+,y t- w+ - - -*- p. 9 sig--g , y , ,-wv-- y , .w - - - - - - - - - - - - - - - - - . - - - . - - - - - - - - - - -

  +

Administrative Procedure UNT-005-014  ; Offsite Dose , Calculation Manual - Revision 0  ! l 1 5.5 . TOTAL DOSE - 5.5.1 TOTAL DOSE SPECIFICATION  ! i The annual (calander year) dose or dose commitment to any MEMBER OF THE PUBLIC due-to release of radioactivity and to  ! radiation from uranium fuel cycle sources shall be limited to less than or equal.to 25 mrems to the total body or any organ,

                                                                                                             .}

except the thyroi,d, which shall be limited to less than or

• equal tp 75 mrems.

APPLICABILITY: At all times.  ! ACTION: With'the.calchlated doses from the release of radioactive materials in liquid or. gaseous' effluents. exceeding twice the limits of. Specification.5.3'.2.a 5.3.2.b, 5.4.2.a, 5.4.2.b, 5.4.3.~a, or 5.4.3.b calculations shall be made including. ' direct. radiation contributions from the~ reactor units and from outside storage tanks to determine-whether the above limits of Specification 5.5.1 have been exceeded.

                                                                                 ~

This-evaluation.should be done in accordance with guidance in Section 5.5.2. If such is the case, prepare and submit'to the Commission within 30 days, pursuant to Technical Specifi-cation-6.9.2, a Specia' Report that defines the corrective

                                      ' action to be taken to reduce. subsequent releases to prevent
                                                                                     ~

j a recurrence of exceeding the above limits and includes the L.. schedule for achieving'conformance with the above. limits. L- This Special Report, as defined in-10 CFR 20.405c, shall include an analysis that estimates the radiation exposure i (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathwayc and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and 68 i_ . - .-

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

                      ' Administrative Procedure                                                         UNT-005-014 4
                       'Offsite Dose Calculation' Manual                       .

Revision 0 t

           ,t 5.5 TOTAL DOSE 5.5.1  TOTAL DOSE SPECIFICATION (cont'd) concentration of' radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated
       +'                           '

dose (s) exceeds the above limits, and if the release condition resulting in. violation of 40 CFR Part 190 has not already been corrected, the Special' Report shall include a request for a

                                                ' variance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is granted until- staff action on the request is f complete.

                    ,                            SURVEILLANCE REQUIREMENTS:

a. Cumulative dose contributions from liquid and gaseous effluents shall be-determined'in accordance with Specifi-

                                             ,          cation 5.3.2, Si4.2, and 5.'4,3 and in accordance with the methodology and parameters in the ODCM.

I

b. Cumulative dose contributions frem 'irect radiation from the reactor units and from'radwaste storage tanksishall

be' determined in accordance with the methodology'and parameters'in the ODCH. This requirements is applicable -

only.under condition' set forth in Specification 5.5.1. L L 69

Adainistrctive Procedure UNT 005-014 Offsite Dose Calculation Manual Revision 0 5.5 TOTAL DOSE (cont'd)

                $.S.2  40 CFR 90 DOSE EVALUATION This section demonstrates compliance with Spreification 5.5.1 Surveillance Requirements. Specifically, ' he dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

Dose evaluations to demonstrate compliance with the above dose

          ,'            limits need to be performed only if quarterly doses exceed:

(1) 3 mrem to the total body (liquid releases). (2) 10. mrem to any organ (liquid releases). } (3) 15 mrem to the thyroid or any organ from radiciodines and particulates (gaseous releases). otherwise no esaluations are required. For the evaluation of doses to real individuals f rom liquid releases, the same calculational methods as employed in Section 5.3.4 vill be used. Ilowever, more encompassing and ' realistic assumptions will be made concerning the dilution and ingestion of radionuclides by individuals who live ar.d fish in the Waterford 3 area. The results of the Radiological Environ-mental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide concentra-3 70

Administrative Procedure UNT-005-014 Offsite Dose Csiculation Manual - Revision 0 5.5 TOTAL DOSE (cont'd)

                                           ..   .s . For the evaluation of dose to real individuals from gaseous releases, the same calculational methods as employed in sections 5.4.6 and 5.4.7 will be used. The total body dose factor should be substituted for the gamma air dose factor (Mg ) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals,
                                         ' the meteorological conditions, and the consumption of food.

Data obtained from the latest land use census should be used to determine locations for evaluating doses. The results of the Radiologica.1 Environmental Monitoring Program will be included in determining more realistic doses based on actual

                    ,                      measured radionuclide concentrations.                             ,

Cumulative dose contributions from direct radiation, from the reactor' unit, and from Radwaste Storage Tanks shall be deter-mined utilizing the results of routine plant perimeter surveys,' T;D data, or a combination of both when necessary. f p p l l l l 71

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

Administistive Proceduee UNT 005-016 Offsite Doac Calculation Manual ' Revision 0 4 5.5 TOTAL DOSE (cont'd) 5.5.3 Total Dose Bases The specification is provided to meet the dose limitations of j 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose.to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individuni reactors remain within twice the dose design objectives if Appendix 1, and if direct radiation doses from 1 the re, actor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the anrnal dose to a

   .                       MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

For the purposes af the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium feel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to excee'd the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. 72

Ad2inistrative Procedure UNT-005 014 Offsite Dose Calculation Manual - Revision 0 5.5 TOTAL DOSE (cont'd) 5.5.3 Total Dose Bases The variance only relates to the limits of 40 CTR Part 190, - I and does not apply in any way to the other requirements for 1 dose limitstion of 10 CFR Part 20, as addressed in Specifications 5.3.1 and 5.4.1. An individual is not considered a met!BER OF THE PUBLIC during in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. l e 4 t e 4 5 e 73

      ,,_,_.........,_.,,_.._.,__,..___..,_,,_m.___._,,                             . , . . , , , , _ _ , _ _ . , , _ . _ , , _ , , . , , , , , . . . , . , _ _ , . . , , . _ , . , _ . , ._.

i Ad2inistrative procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 d 5.6 INSTRUMENTATION 5.6.1 Radioactive Liquid Ef fluent Monitoring Instrumentation Specification The radioactive liquid effluent monitoring instrumentation channels shown in Table 5.6-1 shall be OPERABLI with their alarm / trip setpoints set to ensure that the limits of Specification 5.3.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the method' ology and parameters in Section 5.3.5. APPLICABILITY: At all times. ACTION:

a. With radioactive liquid e'ffluent monitoring instrumentation channel alarm'/ trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive liquid effluents monitored by the ,

affected channel, or declare the channel inoperable. '

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 5.6-1. Restore the inoper-able instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Technical Specifien-tion 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.

74

3 Ad2it. strative Procedure UNT 005 014 Offsite Dose Calculation Manual - Revision 0 t 5.6 INSTRUMENTATION (Cont'd) SURVEILLANCE REQl'IREMENT Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CilANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the irequencies shown in Table

                           +

5.6-2. .

                              ,                                                   f                          4 9

4 a 4 9 1 6 4 i-t 1 75

Surveillance Procedure UNT-003-014-Offsite Dose Calculation M: ual - Revision 0: TABLE 5.6-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRLMENTATION MINIMUM CHANNELS INSTRUMENT - OPERABLE ACTION

1. 'RADIOACTIVITT MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF PELEASE

a. Boric Acid Condensate Discharge . I 28

b. Waste, Waste Condensate.and Laundry Discharge 1 28

c. Dry Cooling Tower Sumps. . 1/ sump 29

d. Turbine Building Industrial Waste Sump 1 29

e. Circulating Water Discharge (Blowdown Heat Exghanger 1 29 and Auxiliary Component Cooling Water Pumps)

2. CONTINUOUS COMPOSITE SAMPLERS -

                                                                                                                                  ^

a. Steam Generator Blowdown Effluent Line 1 29'

3. FLOW RATE MEASUREMENT DEVICES

a. Boric Acid Condensate Discharge .

                                                                                                                                                    .                                   I                 30

b. Waste, Waste Condensate and Laundry Discharge 1 30

c. Turbine Building Industrial Waste Sump *' N.A. N.A.

d. Dry Cooling Tower Sumps *- -

N.A. N.A.

e. Circulating Water Discharge * (Blowdown and Blowdown Heat.

Exchanger and Auxiliary Component Cooling Water Pumps) N.A. N.A.

1. Automatic termination of blowdown discharge only 76

                                                     . _ . , . .  .r._.- .__... ._ e-.._       - . . .   . - - . .         . . . . _ _ _ _            _              -                                                          )

Administ rative Procedure UNT-005-014 Of'foite Dose Calculation Manual Revision 0 TABLE 5.6-1 (Continued) TABLE NOTATIONS

• Pump performance curves generated in place shall be used to estimate flow.

ACTION STATEMENTS ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that prior to initiating a release:

a. At least two independent samples are analysed in ,

     .                            accordance with Specification 5.3.1, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to rep' air the instrument and that grab samples are analyzed '

             ~

for radioactivity at a lower limit of detection of at least 10-7 microcurle/ml. i

a. At least once per 12 hours when the specific activity of the secondary coolant is grater than 0.01 microcuric/ gram 4

DOSE EQUIVALENT I-131, or

b. At least once per 24 hours when the specific activity of ,

the secondary coolant is less than or equal to 0.01 , microcurie / gram DOSE EQUIVALENT I-131.

 .              ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flow.

77

UNT-005-014 Surveillance Procedure _ - Revision 0 Offsite Dose Calculation Manual . TABLE.5.6-2 RADIOACTIVE LIQUID EFFLUENT: MONITORING INSTRUMENTATION SLM'EILIANCE REQUIREMENTS CHANNEL SOURCE CHANNEL R'NCTIONAL CHANNEL CHECK CALIBRATION TEST CHECK INSTRUMENT ,

1. RADIOACTIVITT MONITORS PROVIDING ALARMS AND AIJTOMATIC TERMINATION OF RELEASE P P R(3) Q(1)

a. Boric Acid Condensate Discharge ,

Q(1) P P R(3)

b. Waste, Waste Condensate and Laundry Discharge M R(3) Q(5)

D

c. Dry Cooling Tower Sumps M R(3) Q(5)

Turbine Building Industrial Waste Sump D - d.

c. Circulating Water Discharge (Blowdown Heat Exchanger D M R(3) Q(5)

           , Auxiliary Component Cooling Water Pumps)                                                                 .

2. CONTINUOUS COMPOSITE SAMPLERS D(6) N.A. R Q

a. Steam Generator Blowdown Effluent Line

3. FLOW RATE MEASb7EMENT DEVICES D(4) N.A. R Q

a. Boric Acid Condensate Discharge N.A. R Q

b. Waste, Waste Condensate and Laundry D(4)

                                       ~                                 .

Discharge. N.A. N.A. N.A. N.A.

c. Turbine Building Industrial Waste Sump N.A. N.A.

Dry Cooling Tower Sumps N.A. N.A. d.

c. Circulating Water Discharge (Blowdown and Blowdown Heat Exchangers and Auxiliary N.A. N.A.

Component Cooling Water Pumps) N.A. N.A.

1. Automatic termination of Blowdown discharge only 78

Administrative Procedure UNT-00$-014 Offsite Dose. Calculation Manuel - Revision 0 1 TABLE 5.6-2 (Continued) TABLE NOTATION

1. The CllANNEL TUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists.

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Qircuit failure

3. Instrument indicates a downscale failure.

2. The CllANNEL TUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

 .           2. Circuit failure.,

3. The initial CilANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the Natiunal Bureau of Standards or using standards that have been obtained from sul. pliers that participate in -

measurement assurance activities with NBS. These standards shall permit calibrating the system for over its intended range of energy and measurement range. For sabsequent CilANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

4. CilANNEL CllECN shall consist of verifying indication of flow during periods .

of release. CllANNEL,CIIECN shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made.

5. The CilANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolstion of this pathway occurs if the instrument indicates measured icycle above the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm set.

/ 2. Circuit failure.

3. Instrument controls not set in operate mode.

6. CllANNEL CilECK shall be made at least once per 24 hours on days on which continuous releases are made to the Circulating Water System or Waterford 3 waste pond.

79 l __ _ A

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

l UNT-005-014 l Adainistrative Procedure Offsite Dose Calcu1Ltion Manual . Revision 0 f l l 5.6 INSTRUMENTATION (cont'd) 5.6.2 Radioactive Gaseous Effluent Monitoring Instrumentation Specifications The radioactive gaseous effluent monitoring instrumentation channels shown in Table 5.6.3 shall be OPERAllLE with their alarm / trip setpoints set to ensure that the limits of

                     .         Specification 5.4.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section

5.4.8. APPLICAlllLITY

As shown in Table 5.6-3 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous

           -                        effluent's monitored,by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, .

take the ACTION shown in Table 5.6-3. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report, pursuant to . Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated af ter 30 days provided the specified ACTIONS are continued. 80 -- - - - - . - . . , , ,.n.- c , . , , - . - , . ,

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 t 5.6 INSTRUMENTATION (cont'd) SLET.ILLANCE REQUIREMENTS: Each radiot.ctive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the s CllANNEL CIECN, SOURCE CIECN, CilAhTEL CALIBRATION, and CilANhTL FUNCTIONAL TEST operat. ions at the frequencies shown in Table 5.6-4. . 4 4 e e d 6 e 81

                                                                ~           -        ,                                               .       . .     -

TABLE 5.6-3 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

                                                                                                                                                                               )

IflNIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY- ACTION  !

1. WASTE GAS HOLDUP SYSTEM -

a. Noble Gas Activity Monitor,- .

Providing Alarm and Automatic ^

• 35 Termination, of - Release ~1

b. Effluent System Flow Rate

                                                      '

• 36 Measuring Device 1

2. MAIN CONDENSER EVACUATION AND TURBINE ,

       - GIAND SEALING SYSTEM 1

• 37

a. Noble Gas Activity Monitor 1

• 39 ,

b. Iodine Sampler

• l 39

c. Particulate Sampler

• 36

d. Sampler Flow Rate Monitor 1

 #If a primary to secondary leak exists or if the noble gas monitors in the main condenser evacuation and turbine gland sealing system or if the steam generator blowdown monitor indicates the presence of radioactivity in the secondary system, the flow from this release point shall be divertad inanediately to the plant stack. These instruments are in the plant stack and sampling for radioiodines and particulates shall occur at the plant vent when this occurs.

e 4 82

                                     *^       ' ' "                                    ~-       -~^                                                       -

se 4 _ _ _ _ __ _ _ _ _ _ _ __-..-_..---_-__J

                                                                                        ~

TABLE 5.6-3 (Co2tinued) ' RADIOACTIVE GASEOUS EFFLUENT MONITORING' INSTRUMENTATION' k l MININUM CHANNELS l INSTRUMENT OPERABLE ' APPLICABILITY ACTION

4. REACTOR AUXILIARY BUILDING ,

VENTILATION SYSTEM i (PLANT STACK) a, Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Releasef - 1

• 37 j

                                                                                    ~

b. Iodine Sampler 1

• 39 [

c. Particulate Sampler -

I

• 39  ;

d. Flow Rate Monitor 1

• 36 l

e. Sampler Flow Rate Monitor 1

• 36 -

l

5. FUEL HANDLING BUILDING VENTILATION SYSTEM (NORMAL)

a. Noble Gas Activity Monitor 1 *** 37

b. Iodine Sampler 1- *** 39  !

c. Particulate Sampler I *** 39

d. Flow Rate Monitor 1 *** 36

                                                                                                                                                                    ~

e. Sampler Flow Rate Monitor 1 *** 36

                             #Atatomatic termination o f containment purge only.

83

AdQinistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 l l . l TABLE 5.6-3 (Continued] TABLE NOTATIONS I

                             *At all times.
                            **During WASTE GAS HOLDUP SYSTEM operation.
                           ***With irradiated fuel in the storage pool.

ACTION STATEMENTS l l ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of j the tank (s) may be released to the environment provided best' ) efforts are made to repair the instrument and that prior to  ! initiating the release:

a. At least two independent samples of the tank's contents l

are analyzed, and i l l

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; t

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair'the instrument and that the flow rate is estimated at least once per 4 hours. For the waste gas holdup tank this action. item is applicable only during periods of release. For the main condenser evacuation and turbine gland scaling systems, this action item applies only during release ! via the discharge silencer and only during turbine gland sealing operations and/or vacuum pump operation. l-ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases j via this pathway may continue provided best efforts are made t to repair the instrument and that grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. However, containment purging of radioactive ef fluents must be inanediately suspended during this condition for the plant stack only. l l 84 ,

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

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0

       .                                                - TABLE 5.6-3 (Continued)

TABII NOTATIONS ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the af fected pathway may continue provided best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment as required in Table 5.4-1. 4 6 9 4 6 0 8 9 4 44 9 9 t 9 e 85

TABLE 5.6-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTELMENTATION EURVEILIANCE REQUIREMENTS 5 CHAN3EL MODES IN MIICH CHANNEL SOCRCE CHANNEL FUNCTIONAL INSTRUMENT SURVEILIANCE CHECK CHECK CALIBRATION TEST IS REQUIRED

1. WASTE GAS HOLDUP SYSTEM Noble Gas Activity Monitor -

i a. Providing Alarm and Automatic Termination of Release P P R(3) Q(I) *

b. Effluent System Flow Rate Measuring Device P N.A. R Q *

2. MAIN CONDENSER EVACUATION ANT TURBINE GLAND SEALING SYSTEM

a. Noble Gas Activity Monitor D M R(3)

• Q(2) *

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler V N.A. N.A. N.A. *

d. Sampler Flow Rate Monitor D N.A. R Q

• 86

                                                                                                                                                ~

t _ TABLE 5.6-4 (Continued)  ; RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS , CHANNEL MODES IN WICH t CHANNEL SOURCE CHANNEL. FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION. TEST IS REQUIRED , I 4 '. REACTOR' AUXILIARY EUILDING ' VENTILATION SYSTEM ' (PLANT STACK) ,

a. Noble Gas Av ' ity Monitor - '

Providing A .in and Automatic * [ Termination of Release D M R(3) Q(6) i i .a W N.A. N.A. N.A.

• j j b. Iodine Sampler f

j c. Particulate Sampler W' N.A. N.A. N.A. *- - j 4

d. Flow Rate Moi.itor D N.A. R Q N.A. * -

e. Sampler Flow Rate Monitor D R Q

! 5. FUEL HANDLING BUILDING - j VENTILATION SYSTEM (NORMAL)

t D M R(3) Q(2) *** I I a. Noble Gas Activity Monitor i  !

Iodine Sampler W N.A. N.A. N.A. *** i l b. i Particulate Sampler W N.A. N.A. N.A. *** [

c.  ;

d. Flow Rate Monitor D N.A. R Q . *** t' l

Sampler Flow Rate Monitor D N.A. R Q ***

e. , l l-  !

     # Automatic termination of' containment purge only.                                                                                                                    !

i t i tt 87 i

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 TABLE 5.6-4 (Continued) TABLE NOTATIONS

                          *At all times.
                        **%' hen irradiated fuel is in the spent fuel pool.

1. The CilANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

2. The CllANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1' Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. The' initial CllANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards .

shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CIIANNEL CALIBRATION, sources. that have been related to the initial calibration shall be used.

6. The CIIANNEL FUNCTION TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above '

the alarm /. trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm set.

          '2. Circuit failure.

3. Instrument controls not set in operate mode.

88 l - ... - - .

Administrative Proceduto UNT-005-014 Offsite Dose Calculation Manual Revision 0 i 5.6 INSTRUMENTATION (Cont'd) 5.6.3 Instrument'ation Bases i, 4 a.- RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ($.6.1) , The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents

                                         -                                      during~ actual or potential releases of liquid effluents.'

The alarm / trip setpoints for these instruments.shall be , calculated and adjusted in accordance with the methodology

                                                                               .and parameters in Section 5.3.5 to ensure that the alarm / trip will occur prior to exceeding the limits. of 10
                                           .'                                   CFR Part 20.          The OPERABILITY and'use of this instrumenta'                                -

tion is consistent with the requirements of General-Design Criteria 60, 63, and 64 of Appendix A to 10 CFR ,

                                            .                                   Part $0.
     .                                                                                                                                             .                                         t
                                                           ,       b.           RADI0 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION (5.6.2)

The-radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseour effluents during actual or potential release,s of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology-and parameters-in Section 5.4.8 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also include provisions for monitoring (and controlling) the concen-trations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumenta' tioni 's consistent with the requirements of General DesignLCriteria 60, 63, and 64 of Appendix A to 10 CTR Part 50. . 89

                                                                                                                                                                                            -t
 . ~ . . . - . .. _            - . _ . .          e          -.

__...,__,..m. _ , _., ..... _ . .. - ~._ _ ,- a . . .,...,my,,,.- . , , . , . . , _ 4, , . .r..__._ , .

Administrctive Procedure UNT-005-014 Offsite Dose Calculation Manual - Revision 0 i 5.7 LIQUID AND GASEOUS RADWASTE PROCESSES The block flow diagrams of the radwaste systems are shown in Attachments 6.11 and 6.12. In order to obtain a more detailed description, see the appropriate sections of the TSAR. 4 s t 5 6 9 9 4 90

Ad2inistrative Procedure UNT-005-014 Off site Dose Calculation '.sanual

• Revision 0 t

5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS 5.8.1 Radiological Environmental Program Specification The radiological environmental monitoring program shall be conducted as specified in Table 5.8-1. APPLICABILITY: At all times. ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 5.8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. *

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a speci-fled location exceeding the reporting levels of Table 5.8-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to

                      "                                  Technic'a1. Spr:cification 6.9.2, a Special Report that identifiec the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose *                                           .

to a MEMBER OF THE PUBLIC is less than the calendar year , limits of Specitreations 5.3.2, 5.4.2, and 5.4.3. When more-than one of the radionuclides in Table-5.8-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) , concentration (2) , ... > 1.0 reporting level (1) reporting level (2)

                   *The methodology and parameters used to estimate the potential annual dose to A MEMBER OF THE PUBLIC shall be indicated in this report.

91 l n , - - - - - - . , - - . . - - - --

Administrctiva Procedure

• UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.8 RADIOLOGICAL ENVIRONMENTAL MONITCRING PROGRAM REQUIREMENTS (Cont'd)

   .                            When radionuclides other than those in Table 5.8-2 are detected and are the result of plant effluents, this report shall be submitted if the p<>tential annual dose

• to A MEMBER OF THE PUBLIC is equal to or greater than the calerdar , year limits of Specifications 5.3.2, 5.4.2, and 5.4 3. This report is not required if the measured level of tadioactivity was not tne result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 5.8-1, identify locations for obtaining replac.cm.cnt samples and add them to the radiological environmental monitoring program within 30 days, The specific locations from which samples were unavailable may then be deleted from the monitoring program; Pursuant to Technical Specification 6.9.1.8, identify t.he cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Relear Report and also include in the report revisions of Attachments 6.13, 6.14, 6.16, 6.17 and 6.18 reflecting

• the new location (s). ..

l l l l 92 i L

Administrative Procedure UNT-005 014 1 Offsite Dose Calculation Manual

• Revision 0 l i

      .                                                                                                             \

5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS (Cont'd) i SURVEILLANCE REQUIREMENTS: The radiological environmental monitoring samples shall be collected pursuant to Table 5.8-1 from the specific locations given in Attachments 6.13 and 6.14, and shall be analyzed pursuant to the requirements of Table 5.8-1 and the detection capabilities required by Table 5.8-3. 9I e 48 e 9 1 t-9 9 ge

• b 4

1 e 93

TABLE 5.8-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

• NUMBER OF- -

                                                                                   ~

REPRESENTATIVE EXPOSURE PATHVAY SAMPLES AND - SAMPLING AND TYPE ANb FREQUENCY

                                                                                                              @                OF ANAMIS AND/OR SAMPLE                SAMPLE IDCATIONS *        .

1. DIRECT RADIATION 31 routine monitoring stations Quarterly Gamma dose quarterly.

either with 2 or more dosimeters or with one instrument for measuring and recording dose rate concinuously, placed as follows: an inner rin? of stations, one in

                                ~

each meteoroligical sector in the general area of the SITE BOUNDARY, .

                               .                  an outer ring of statiet s, 1 ja
                                                                                                                                                +

10 of the meteorological sectors in the 6 - to 8-km range '. rom the site; the balance of the stations to be placed in special inter.est areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control. stations .

                    *The number, media, frequency, and location of samples may vary from site to site. -This table ptesents an acceptable minimum program for a site at which each entry is :.pplicable. Local site characteristics must be examined to determine if pathways not-covered by this table may significantly contribute to an individual's dose and should be included in the sampling program.

94

TABLE 5.8-1 (Comtinued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRArrt NUMBER OF.

                                                                                 '    ~

REPRESENTATIVE

                                                                    ~

EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS a ION NQEm 0F MAMSIS

2. AIRBORNE Radioiodine and Samples from 5 locati'ons Continuous sampler Radiciodine Canister Particulates operation with sample I-131 analysis weekly.

3 samples from close to the collection weekly, or 3 SITE BOUNDARY locations, in ' more frequently if different sectors, of the required by dust Particulate Sampler: highest calculated annual average loading. Gross beta radioactivity ground-level D/Q. analysis following filter change; I sample from the vicinity of a Gamma isotopic analysis' community having.the highest of composite (by calculated annual average location) quarterly. , ground-level D/Q. I sample from a control location, as for example 15-30 km - distant and in the least prevalent wind direction.'

3. VATERBORNE

a. Surface I sample upstream Composite sample over Gamma isotopic analysis

• I sample downstream I-month periods monthly. Composite for tritium analysis quarterly.

b. Ground Samples from 1 or 2 sources h

Quarterly Gamma isotopic

• and tritium only if likely to be affected analysis quarterly.

95

N

                                           ~

TABLE 5.8-1 (Contieued)- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPRt* N1RIBER OF  : . REPRESENTATIVE

 - EXPOSURE PATHVAY         SAMPLES AND                                        SAMPLING AND      TYPE AND FREQUENCY AND/OR SAMPLE           SAMPLE LOCATIONS

• COLLECTION FREQUENCY OF ANALYSIS

c. Drinking 1 sample of each of 1 to 3 of Composite sample I-131 analysis on each the nearest water supplies that over 2-week period s composite when the dose could be affected by its when I-131 analysis calculated for the l discharge. -

is performed, monthly consumption of the water composite otherwise is greater.than 1 mrem per year.

• Composite for  !

gross beta and gamma , isotopic analyses-

                                                                                          .      monthly. Composite n r tritium analysis quarterly.

d. Sediment I sample from downstream area Semiannually Gamma isotopic analysis" + f from with existing or potential semiannually.

shoreline recreational value. -

4. INGESTION

      -a. Milk            Saraples from milking animals                  Semimonthly when      Gama isotopic" and I-131 in 3 locations within 5 km                     animals are on        analysis semimonthly when distance having the highest                    pasture; monthly at   aninals are on pasture; dose potential. If there are                   other times           monthly at other times.     ,

none, ther,, 1 sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated.to be greater than 1 arem per yr.# 1 sample from milking animals at a control location 15-30 km distant and in the least - prevalent wind direction.c , e I 96 A

• TABLE 5.8-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

• NUMBER OF -

REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS * , COLLECTION FREQUENCY OF ANALYSIS

b. Fish and I sample of each commercially Sample in season, 9r Gamma isotopic analysis

• Inverte- and recreational important semiannually if they on edible portions.

brates species in vicinity of plant are not seascaal discharge area. 1 sample of same species in areas not influenced by plant discharge. ,

c. Food I sample of each principal class At time of harvest) Gamma isotopic analysis' Products of food products from any area on edible portion.

that is irrigated by water in ,

which liquid plant vastes have l discharged. . f Samples of 1 to 3 different kinds Monthly when Gamma isotopic" and I-131 of broad leaf vegetation grown available analysis. nearest each of two different offsite locations of highest pr-dicted annual average ground- < level D/Q if milk sampling is not < performed. . I sample of each of the similar Monthly when Gamma isotopic" and 1-131 broad leaf vegetation grown available analysis. 15-30 km distant in the least prevalent wind direction if milk sampling is not performed. 97

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

i l, TABLE 5.8-1 (Continued) TABLE NOTATIONS

        " Specific parameters of distance and direction sector from the centerline of one ree tor, and additional description where pertinent, shall be provided for each sc4 every sample location in Attachments 6.14, 6.16, 6.17 and 6.18.

Refer to NUREG-0133, " Preparation of Rt.diological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, corrective action shall be completed prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating

         ' Report pursuant to Specification 6.9.1.7. It is recognized that, at timeri, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.      Pursuant to Specification 6.9.1.8, identify 1

the cause of the unavailability of samples for that pathway and identify the , new locat. ion (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table reflecting the new location (s). One or more instruments, such as a pressurized ion c w her, for measuring and recording dose rate continuously may be used in place v., or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is consi,dered to be one phosphor; two, or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. d Airborne particulate sample filters shall be enalyzed for gross beta radioactivity 24 hours or more after sampling to allow for random and thoron b aghter decay. If gross beta activity in air particulate samples is grener Unn 10 times the yearly mean of control samples, gamma isotopic analysis shall ne performed on the individual samples.

         " Gamma isotopic analysis means the identification and quantification of gamma-emitting radionucli us that may be attributable to the effluents from the faci? 4 ty, s

98

   ~ w nnmenn                               -

                               ^
   . i.            .
                  ~           V'
       ,.                                                                 TABLE 5.8-1 (Co'ntinued)    ,

TABLE NOTATIONS I The " upstream samp1'e" shall be taken at a distance beyond significant  ; influence of the discharge. The " downstream" sample shall be taken in an area  : beyond but near_the mixing' zone. "Upst.retm" samples in -an estuary must be_ taken far enough upstream to be beyond the plant influence.- Salt water,shall

 '-                         - be sampled.only when the receiving water is utilized for recreational-activities;                                                                                          -

8 A. composite sample _is one in which the quantifyx(aliquot) of liquid sampled is-proportional to the quantify of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. _In this program composite sample ~ aliquots shall be collected at time ~ 1 intervals that are very short -(e.g., hourly) relative to the compositing - j period _(e.g'., monthly) in order to assure obtaining a representative sample.  ; U Groundwater samples shall be taken when_this source is tapped for drinking or

                                    . irrigation purposes lin a. mas where the hydraulic gradient or recharge       ~

properties are suitable for contamination. I IThe dose:shall be calculated-for the maximum organ and age group, using the methodology and parameters in this document. If harvest occurs more than once -a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be _ monthly. Attention shall be paid to-including samples of tuberous and roo,t' food products, 9 e i -! 8 I E

      ' t-9 9

4 99

TABLE 5.8-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIR0hMENTAL SAFJLES Reporting-Levels. WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/E) .OR GASES (pCi/m3 ) (pCi/kg, wet) (pCi/f) '(pCi/kg, wet) H-3 20,000 Mn-54 - '1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000

                                                                                                ~

Co-60 300 10,000

                                                                                                    ~

Zn-65 300 20,000 Zr-Nb-95 400 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cst137 50 20 2,000 70 2,000 Ba-La-140 200 300

                                                                                                          ^

6 100

TABLE 5.8-3 - DETECTION CAPABILITIES -FOR ENVIRONMENTAL SAMPIE ANALYSIS ' ~ Lower Limits of Detection (LLD) C WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/f) OR GASES (pCi/m3 ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry) gross beta 4 0.01 11 - 3 .2000 Mn-54 15 .130 . Fe-59 30 260

                                                                  ~

Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95

                                                                                                                ~

15 I-131 1 0.07 1 60 Cs-134 15 0.05 .130 15 60 150 Cs-137 18 0.06- 150 18 80 180

        ~

Ba-La-140 15 15 l t 101

                                                      .                                         I Administrative Procedure                                                 UNT-005-014   l Offsite Dose Calculation Manual                                          Revision 0 TABLE 5.8-3 TABLE NOTATIONS a

This list does not mean that only these nuclides are to be considered, Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7. 3 b Requirsd detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. C The LLD l's defined, for purposes of these specifications, as the smallest ' concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: 4.

              'LLD =

E V . 2.22 x 106 . Y , exp(A AT) Where: LLD is the "a priori',' lower limit of detection as defined above, as microcuries per unit inass or volume, , 8 b is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per' minute, E is the counting efficiency, as counts per disintegration, V is the' sample size in units of mass or volume, 2.22 x'100 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y and at should be used in the calculation. l 102

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 TABLE 5.8-3'(Continued) TABLE NOTATIONS i It should be recognized that the LIS is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances niay render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1,7. d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used. 4 9 4 103

            ..+.    - --        .-. _-.             - - . . -

l

                                  -E:

• Administrative Procedure UNT-005-014 l Offsite Dose' Calculation Manual- -

Revision O' ]

            - 4 u

5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.2; Interlaboratory Comparison Program Specification Analyses shall.be" performed'on all; radioactive materials supplied.as part of an Interlaboratory Comparison Program.

that has been approved by-the Commission.  :

APPLICABILITY: At all times.

                                                      ' ACTION:-                                                                                                       ,

a. . With analyses not being performed as required above, oreport'the-corrective actions taken to. prevent a ',

                                                                   . recurrence to the Commission in the Annual Radiological                                           '
                                                                  ! Environmental Operating Report pursuant to' Technical-Specificaiion 6.9.1.7.                                                                     ,

t SURVEILLANCE. REQUIREMENTS j s

                                                      .The Interlaboratory comparison Program shall be described in-1
                                                      .Section 5'.6.5. .A, summary of the results obtained as.part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report p'ursuant to Technical Specification 6.9.1.7.                                            ,

9

                                                                                                                                                                       )

b 104

        ,              ' Adainistrative Procedure -                                                                           UNT-005-014 0'ffsite Dose' Calculation Manual-                                          -

Revision 0 - to 5.8' RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd)

                                     '5.8.3 Land Use census-Specification A land'use census shall be conducted and shall identify.

within a distance of_8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

• of= greater _than 50 m2 (5000 ft )2 producing broad leaf vegetation.

APPLICABILITY: At all times. ACTION: > ta.; With a land use census identifying a location (s) that- -

               , _                                           yields-a calculated dose or dose. commitment greater than the values currend v being calculated in_ Specification.

5,4.3, identify the new location (s) in the next-Seiniannual' Radioactive Effnent Release Report, pursuant to Specification 6.9.1.8.

b. With'a land:use' census identifying.a location (s) that yields'a calculated dose or dose commitment (via the same-exposure pathway) 20% greater than at a location from which samples are currently being obtained-in accordance-with' Specification 5'.7.1, add. the new location (s) to the - .

radiolEgical environrental monitoring program _within 30:

                                                            ' days. The sampling location (s), excluding the control station.' location, having the lowest calculated dose ~or-

dose commitment (s), via the same exposure pathway, may_be.

_ deleted from this monitoring program after_ October 31 of-

                                                            .the year--in which'this land use census was conducted.

Pursuant to Technical Specification-6.9.1.8 identify the new-location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report 4 revision of Attachments 6.13, 6.14, 6.16, 6.17, and 6.18 reflecting the new locations (s). 105

Administrative Procedure UNT-005-014 Offsite-Dose Calculation Manual - Revision 0 S.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) SURVEILLANCE REQUIREMENTS The land use' census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant-to Technical Specification 6.9.1.7.

                        *Brono leaf vegetation sampling of different kinds of                                                                    ,

vegetation may be performed at the SITE BOUNDARY in each of

              ,             two different direction sectors with the highest predicted D/Qs in, lieu of the garden census. . Specifications for broad leaf vegetation sampling in Table 5.8-1 Part 4.c. shall be followed, including analysis of control samples, s

106 ,

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.4 Discription of the Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is expounded on in. Attachment 6.13, and the Sample Location Table, Attachment 6.14. Attachment 6.15 explains the sector and zone designations for the sample locations'. Attachments 6.16, 6.17 and 6.18 show the sample locations within the 2,10, and 50 mile radius of Waterford 3. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment 'and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end'of the next sampling ' period. All deviations from the sampling schedule'shall be documented in the Annusl Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Programs. - 107

Administrative P'rocedure UNT-005-014 Offsite Dose-Calculation Manual

• Revision 0 i

5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.5 Description of the Interlaboratory Comparison Program As described in Section 5.8.2 the quality assurance in radiological environmental sampling will be maintained through participation in the Environmental Protection Agency's Radiological Laboratory Quality Assurance Program.

                      .               The summary of results will be presented in tabular form and will include the type of analysis, the preparation (collection) date, the date the results are returned, the mean of the analyses (usually triplicate), the standard deviation, the date the values are released for information,_

the known value, the three standard deviation limit, and a two standar'd deviation /three standard deviation warning / action flag. If the sample' analysis indicates

                        ,             results outside the three standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along with all results when the Annual Radiological Environmental Operating Report is submitted.

5 t 4 4 108

Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual ' Revision 0 I 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.6 Dispersion l'arameters For Critical Locations As per Requirements 5.8.3, the dispersion parameters for the site boundary and where necessary, as identified by the Annual Land Use Census, are listed in Attachment 6.2. This table will be subject to changes based on the Annual Land Use

              .                                                 Census and historical data.

P E e 4 0

                                                                                                                                                  *u e

e b 109

                                                                  ~
            ' Adsinistrative Procedure                                                                    UNT-005-014
            ? Offsite Dose Calculation Manual                               -

Revision-0

y ,

5'.8! RADIOLOGICAL ENVIRONKENTAL MONITORING (Cont'd; 5.8.7 Radiological Environmental Monitoring Bases e a.- INTERLABORATORY COMPARISON PROGRAM (Section 5.8.2) The requir'ement for participation in an approved Inter-laboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental . sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Pr.rt 50.

b. LAND USE CENSUS (Section 5.8.3)

This specification is provided to ersure that changes in ,

                ,                             the use of areas at and beyond the SITE BOUNDARY are f                                             identified and that modifications to'the-radiological 4                                             environmental monitoring program are made if-required by the results of'this census. The best information fromithe                     -

door-to-door survey, from aerial; survey or from consulting

                                           ,with local agricultural authorities shall be used.                  This
                                            ; census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census: to'                 ,
                                            . gardens of greater than 50 m2 provides assurance that.

significant exposure pathways via leafy. vegetables will be identified and monitored since a. garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for l consumption by a child. To determine.this minimum garden .) size, the-following assumptions were made: (1) 20%1of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2, 110 l

                                                                                               ._-_______________L

Administrative Proceduro UNT-005-014 -

Offsite' Dose-Calculation Manual - Revision 0 1 5.9 _ TECHNICAL' SPECIFICATION CROSS-REFERENCES

                               " Changes.to the Technical Specifications (TS) recommended by Generic
                               -Letter 89-01 (Reference 2.8) resulted in programmatic controls for, radiological effluents, radiologica1' environmental. monitoring, and effluent radiation monitoring instrumentation being relocated to the Offsite Dose Calculation' Manual. All references of the former version of the TS-that'are contained in current plant operating                      ,
                                'proceduresfshall be cross-referenced to specifications contained in the ODCM using Attachment 6.20. Relocated requirements set forth in the ODCM should be incorporated into current plant operating proce-dures as1 they undergo routine review and revision.

6.0 ATTACHMENTS- - 4 1

                          -Refer-to Table.of Contents 6

9 9 0 4 4 e

                                                                                                                                                        .?

e e 9 9 111 4: - , -_ . _. . . . - . . .- . - - ._ - - - _ . _ . . _ _

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

r SITE BOUNDARY TOR , sMDI0 ACTIVE CASEOUS AND LIQUID EFFLUENTS . J V i Litsi. Cvoiv 1.2&3 i I

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F b .5',5) LEGEND ,

                                                                                                                                     - Site Boundry
              .'                                                (

La. 3rn

                                                                                                                                   ---E.,9 vaion    1          Aree uoundry
                                                                                                                          "'-N".;*ki,es.e

{ oro.:8.eoiie.,nrs,.tst si jL - a.i.... u. . j Ollt.". 5'tCmrs.#st t- @ oi..s c.e.i .e. L y! . sir-v.

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[~2 1 1 8 rs -e UNT-005-014 Fevision 0 , Attachment 6.1 (1 of 1) 112

HISTORICAL' AVERAGE DISPERSION AND DEPOSITION i PARAMETERS FOR AREAS AT OR BEYOND THE s UNRESTRICTED AREA BOUNDARY j M84AL AVDIAGE ADOSMORIC D15I934S13 A@ EE3MIT1311%IUMn3tS BASED W ICRfWICAL IE29Gritry:TCAL DN!h MC C158BC INED IBE CD8RE

                                                 !!DEC1*IW       fEC!tst          DISIN G               X/Q        t/Q Rt3PIUt Tf7E                                                               ID IEERY     (per m2 )

CR LDCATIN FXM SI'!E 10CfCIW FInt SI'!E (miles) (asters) A 0.80 1287 1.0E-05 2.4E-08

                      . SI'IE ICD 4DhRt                   N(a)                                                  3.4E-08 184E(a)        B         0 60         966      1.6E45 C         0.60          966     1.5E-05     2.8E-06 NE(a)                                                   2.5E-08 D         0.60          966     1.6E-05 DEE(a)                                                    1.3E-08 E         E         0.80        1287      6.9E-06 F         0.60          966     1.1E-05     2.3E-08 ISE SE          G         0.60          966     1.1E-05     3.1E-08 H         0.80        1287      6.3E-06     2.4E-08 SSE S         J         1.60        2575      8.9E-07     2.7E-09               <

E 3.10 4989 3.0E-07 7.9E-10 SSW SW L 3 40 5472 3.3E-07 9.1E-10 SEW M 1 50 2414 1.7E-06 4.9E-09 W H 1.00 1609 2.3E-06 7.3E-09 18W P 0.80 1287 7.5E-06 2.7E-08 NW Q 0.80 1287 1.0E-05 3.2E-08 98W _ R 0.90, 1448 9.4E-06 2.4E-08 H' A 0.90 1'448 7.8E-06 1.8E408 RESIDDG 3.0E-06 5.8E-09 78(E B 1.30 2092

• NE C 0.90 1448 6.3E-06 1.2E-08 DIE D 0.90 1448 6.8E-06 1.1E-08 '

E E 2.20 3541 7.4E-07 1.0E-09 ESE F 3.10 4989 3.7E-07 4.8E-10 SE O 4.00 6437 2.3E-07 3.6E-10 W H 1.00 1609 2.3E-06 7.3E-09

                                                 ' ' 18W             P          0.90       1448      5.6E-06     2.0E-08 NW          C          0.90       1448      7.7E-06     2.3E-08 18W           R          3.00       4828      7.7E-07     1.3E-09 0          0.90        1448     7.7E-06     2.3E-08 MIIK CDW                         NW(b)

NW Q 4.90 7886 2.F-07 4.1E-10 . D 1.00 1609 5.3E-06 8.2E-09 MIIK OtRT BEE (b) 3.6E-07 3.9E-10

                                                           *E(b)      E         3.30        5311 N        A          1.00 -      1609     6.1E-06      1.4E-08 VICE21BLE GA3EEN ISE           B         1.30        2092     3.0E-06     5.8E-09 DE          C         0.90        1448     6.3E-06     1.2E-08 INE           D         0.90        1448     6.8E    1.1E-08 E         E         2.20        3541     7.4E-07      1.0E-09 IEE           F         2.20 , 3541          7.0E-07      1.1E-09

• SE G 2.30 3701 6.2E-07 1.3E-09 '

law M 1.50 2414 1.7E-06 4.9E-09 W N 1.10 1770 1.9E-06 5.7E-09 teW P 0.90 1448 5.6E-06 2.0E-08 NW D 0.90 . 1448 7.7E-06 2.3E-08 18W R 3.00 - 4828 7.7E-06 1.3E-09 . E 3.20 5150 3.7E-07 4.2E-10 IEEF CDW E 3.6E-10 F 3.50 5633 3.OE-07

• EEE 2.8E G 4.50 7242 1.9E-07 SE 8.6E-09 leW M 1.20 1931 2.7E-06 P 0.90 1448 5.6E-06 2.0E-08 18W 2.3E-08 O 0.90 1448, 7.7E-06 NW 2.4E-09 R 2.30 3701 1.3E-06 18W

a. The sita boundary in this sector is loontal mer water. 'the locaticri comot be ocuplad cxrmira-ly fcr the life of the plart.

b. '!he animals at this 1ccation do not pantr= milk for innan cxximspelen.

i UNT-005-014 Revision 0 Attachtnent 6.2 (1 of 1) 113

                                                                                                                                                  +

l f SITE RELATED LIQUID INGESTION DOSE COMMITMENT , -

                                               -FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES                                                           ,

AGE GROUP: ADUL1 OllCRAAGE POINil CIRCULAflNG Wfit (Inte Nigeltelppi River) NUCLIDE - ORGAN Dose ComVER$10N FACTORS 00NE LIVER 1.000Y TNYR010 EIDuET LUNO Gl LLI N3 0.00E40 2.66E 01 2.66E 01 2.6M 01 2.66E 44 2.6M 01 2.6M 01 ' C 14 3.1M*04 6.2M+03 6.2M+03 6.26t+03 6.26E+03 6.2M*03 6.2M*03 NA 24 4.00E*02 4.00E*02 4.00E+02 4.00E 42 4.0E +02 4.00E+02 4.00E *02 P 32

• 4.62E 47 2.s7t+06 1.79E+06 0.00E 00 0.00E*00 0.00E + 00 5.tM+06 Ca.51 0.00E*00 0.00E +00 1.27E*00 7.62E 01 2.41E 01 1.HE*00 3.21E*02 let 54 0.00E+00 4.30E+03 8.3H +02 0.00E+00 1.30E*03 0.00E*00 1.34E+04 Ice 96 0.00E*00 1.10E*02 1.95E+01 0.00E+00 1.40E+02 0.00E+00 3.52E+03
• FE 55 6.59E*02' 4.564+02 1.064+02 0.00E+00 0.00E+00 2.54E+02 2.61E+02 FE 59 1.04E+03 ' t.4M+03 9.3eE+02 0.00E+00 0.00E+00 6.83E+02 8.15E+03 CO 54 0.00E+00 8.95E+01 2.01E*02 0.00E+00 0.00E+00 0.00E+00 1.81E+03 Co 60 0.00E*00 '2.57E+02 5.6M+02 0.00E+00 0.00E*00 0.00E+00 4.83E+03 M43 3.12E+04 2.1M43 1.0M43 0.00E+00 0.00E+00 0.00E +00 4.51142 53 45 1.2M42 1.64E+01 7.51Ee00 0.00E+00 . 0.00E40 0.00E*00 4.1M*02

                            ,    CU44 -      - 0.00t+00 1.00E+01 - 4.70E+00 0.00E+00 2.5M+01 0.00E*00 8.53E+02 IN 65          2.3M+04 7.3M+04 3.3M+04 0.00E+00-4.93E+04 0.00E+00 4.64E+04
                              .2N 69            4.93E+01 9.43E+01 6.564+00 0.00E+00 6.1M +01 0.000+00 1.4M+01 1 0R 4 -          0.00E+00. 0.00E*00 4.04E+01 0.00E+00 0.00E40 0.00E+00 5.82E+01 BR M         '0.00E 40. 0.00E+00 5.24E+01 0.00540 0.00E+00 0.00E+00 4.11E 04 OR 05       - 0.00E*00 0.00E+00*2.1H+004 0.00E+00 0.00E40 0.00E+00 0.00E+00-na 06          0.00E+00' 1.01E+05 .4.71E+04 0.00E+00 0.00E*00 0.00E+00 1.99E+04                 .

a0 08 - 0.00E40 2.90E+02. 1.54E 42 0.00E+00 0.00E+00 0.00E+00 4.00E 09

                              'A0 09            0.00E+00 1.98+02 1.3M42 0.00E 00 0.00E+00 0.00E+00 1.1M 11 OR 09         -2.22E+04 0.00E+00 6.30E*02 0.00E*00 0.00E4 0 0.0ct+00 3.57t+03 08 90          5.4M+05 0.00E+00 1.34E*05 0.00E+00 0.00E 40 0.90E+00 1.5AE+04
                               -OR 91           4.00E42 0.00E 40 1.65E 41 0.00E*00 0.00E+00 0.00E40 1.9M+03                                          .

OR 92: 1.5M42 0.00E40 6.71E+00 0.00E+00 0.00E40 0.00E+00 3.00E+03 T 90 5.79E 01 0.00E+00 1.5M 02 0.00E+00 0.00E40 0.00E+00 6.14445' T 91st 5.4M 03 0.00E*00 ' 2.1M 06 0.00E+00 0.00E*00 0.00E+00 1.61E 02 Y 91- 8.49E*00 0.00E+00 2.2M 01 0.00E40 0.00E+00 0.00E+00 4.6M+03 Y 92 5.00E 02 0.00E*00 ~ 1.49E 03 0.00E+00 0.00E*00 0.00E+00 8.91E+02 Cerweralm f acters are in mitt of aren/yr per WCl/el a j

        .UNT-005-014 Revision 0                                                                 '

Attachment 6.3 (1 of 6) 114

O SITE RELATED LIQUID INGESTION DOSE COMMITMENT . FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES AGE GAQUP ADULT DISCNARGE Poluf: CIRCULAfluG WAlta (Into Mississippi River) NUCLlDE DaGAN DOSE COINEtl10N FAC10tl t0NE LIVER 1.t(BY fuYt010 KIDNEY LUNG cl.LLI Y 93 1.61E 01 0.00E 40 4.AM 03 0.00E*00 0.00E 40 0.00E40 5.12E*03 IR 95 2.528 01 C OM 02 5.46E 02 C.00E*00 1.2M

• 01 0.00E+00 2.56E42 It 97 1.39E*02 2.81E 03 1.2SE*03 0.00E*00 4.24E*03 0.00E+00 8.69t+02 No.95 4.47E*02 2.4aE *02 1.34E*02 0.00E+00 2.4M +02 0.00E+00 1.51E+06 '

se0 99 0.00E*00 1.0H+02 1.99E+01 0.00E+00 2.3M*02 0.00E*00 2.43E42 TC 99u 8.96E 03 2.5M 02 3.23E 01 0.00E40 3.85E 01 1.24E 02 1.50E 01 TC 101 9.22E 03 1.3M 02 1.30E 01 0.00E+00 2.39E 01 6.79E 03 3.99E 14 RU 103 4.50E*00 0.00E+00,1.94E+00 0.00E+00 1.72E41 0.00E+00 5.2H42 RU 105 3.75E*01 0.00E 40 1.44t+01 0.00E+00 4.84E+00 0.00E+00 2.29E+02' au 106 6.69E*01 0.00E+00 8.4M*00 0.00E+00 1.29E+02 0.00E+00 4.3M +03 AC 110M 8.2M 01 7.6M 01 4.54t*01 0.00E*00 1.50E+00 0.00E*00 3.12E+02 TE 125M 2.57t+03 9.3M+02 3.44E42 7.72E+02 1.04E+04 0.00E+00 1.0M *M TE*127N ' 6.49E+03 2.32E43 7.90E+02 1.ME+03 2.63E+04 0.00E*00 2.1M+M TE=127 1.05E+02 3.7BE+01 2.20E+01 7.81E+01 4.29t+02 0.00E40 8.32E+03 , TE*129M 1.10E+04 4.11E+03 1.74E+03 3.7eE+03 4.60E+04 0.00E40 5.5H+04 TE 129 3.01E+01 1.1M+01 7.'3M+00 2.31E+01 1.2M +02 0.00E 40 2.27t+01 TE 131M 1.NE+03 8.10E+02 6.75E42 1.20E*03 8.21E+03 0.00E +00 8.05E+04 TE 131 1.89E*01 7.seE+00 5.966+00 1.5M+01 C.2M41 0.00E+00 2.6M +00 TE.132 2.41E+03 1.56t+03 1.4M+03 1.72E+03 1.50E +04 0.00E*00 7.3*E+04 l*130 2.74E+01 8.00E41 3.19E+01 6.NE+03 1.26E+02 0.00E+00 6.9M +01

                                                         .                             1 131                   1.51E+02 2.16E42 1.24E*02 7.00E+04 3.70E+02 0.00E+00 5.70E41 I 132                   7.3M +00 1.9M41 6.09E*00 6,89E*02 3.14E+01 0.00E+00 3.70E+00 1*133                  5.15G41 8.96E+01 2.73E+01 1.32E44 1.56E42 0.00E+00 8.0M +01 3.35E+63 1.05E+01 3.76t+00 1.81E+02 1.ME+01 0.00E+00 9.11E 03 l'.134 l'135                  1.61E+01 4.21E*01 1.55E 41 2.78E+03 6.75E41 0.00E+00 4.7M+01 CS 134                  2.90E+05 7.09E+05 5.79E*05 0.00E+00 2.29t+05 7.61E+04 1.24E44                         .

Cs 136 3.12E 44 1.2M*05 8.86E+04 0.00E+00 6.05E +04 9.39E+03 1.40E+04

• Cs 137 3.82E+05 5.22E+05 3.42E+05 0.00E+00 1.7M+05 5.09E44 1.01E*04 Cs 138 2.64E42 5.22E+02 2.59E+02 0.00E+00 3.NE 42 3.79E41 2.23E 03 BAa139 9.66E 01 6.00E 04 2.8M*02 0.00E40 6.43E 04 3.90E 04 1.71E+00 Conversion f actors are in units of aren/yr per Wl/et UNT-005-014 Revision 0 Attachment 6.3 (2 of 6) 115

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

4 i SITE RELATED LIQUID INGESTION DOSE COMMITMENT 1 FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES , v ACE GROUP: ADULT DIlchARGE Poltis CIRCULAflho WATER (into Mittl64lppi River) NUCLIOE ORGAN DOtt CouvER$10N FACTOR $ tout LIVER 1.b(BY fMTR010 KIDutf LuuG 01.LLI f BA 140 2.02E*02 2.54E 01 1.32E+01 0.00E+00 8.6M 02 1.45E 01 4.1M+02 SA 141 4.69E 01 3.54E 04 1.54E 02 0.00E*00 3.29E M 2.01E M 2.21E 10 BA 142 2.12E 01 2.18E 04 1.3M 02 0.00E+00 1.84E 04 1.23E 04 2.99E 19 LA 140 1.$1E 01 7.59E 02 2.01E 02 0.00E+00 0.00E+00 0.00E*00 5.57E+03 LA 142 7.71E 03 3.51E 03 8.7M 04 0.00E+00 0.00E+00 0.00E+00 2.5M+01

                ,         CE 141       2.59E 02 1.75E 02 1.99E 03 0.00E+00 8.15E 03 0.00E*00 6.71E*01 CE*143       4.57E 03 3.38t*00 3.74E 04 0.00E*00 1.49E 03 0.00E+00 1.2M+02 CE*144 1.35E+00 5.6M 01 7.2M 02 0.00E*00 3.3H 01 0.00E+00 4.57E+02 PR 143       5.54E 01 2.22E 01 2.7H 02 0.00E+00 1.20E 01 0.00E+00 2.4M+03 PR 144 1.81E 03 7.53E 04 9.21E 05 0.00E+00 4.2H 06 0.00E+00 2.61E 10 u0 147       3.79E 01 4.3aE 01 2.62E 02 0.00E+00 2.5M 01 0.00E+00 2.10E+03 W 187        2.9M+02 2.47E*02 8.65E+01 0.00E*00 ,0.00E+00 0.00E + 00 8.10E+04 WP D9        2.09E 02 2.aH 03 1.57E 03 0.00E+00 8.est 03 0.00E+00 5.84E+02 Conversten fectore are in mits of aravyr per et/et R

UNT-005-014 Revision 0 Attachment 6.3 (3 of 6) 116

A e SITE RELATED LIQUID INGESTION DOSE C0!OfITMENT FACTORS (Ag ) FOR. INDIVIDUAL NUCLIDES

                      ' AGE GROUP: ADULT 018ChAAGE Poluis ALL 01httt (into 40 Arpent Canal)

NUCL10E ORGAN DOSE CONVEt$10N FACfott 00NE LIVEE 1.92f TNYR010 KIONEY LUNG Cl

• L'LI N3 0.00E+00 8.9M*00 8.9M 40 8.96E+00 8.9M *00 8.9M+00 8.9M*00 C 14 3.15E+04_6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 # 30E+03 NA 24 5.4aE*02 5.4aE+02 5.44E42 5.4aE+02 5.4aE+02 5.4aE+02 3.4aE+02 P 32 4.62E+07 2.87t+06 1.79E+06 0.00E+00 0400E *00 0.00E+00 5.20E+06 Ca 51 0.00E+00 0.00E+00 1.49E+00 8.94E*01 3.29E 01 1.90E+00 3.7M*02 let 54. 0.00E+00 4.7M *03 9.00E+02 0.00E+00 1.42E+03 0.00E*00 1.4M *t4

                .,       Int 56        0.00E.00 1.20E+02 2.12E+01 0.00E+00 1.52E+02 0.00E+00 3.82E+03
                .        FE 55         8.87E42. 6.1M+02 1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02
              .          7E 59         1.40E+03 3.29E+03 1.2M+03 0.00E40 0.00E+00 9.1M+02 1.10E+04 Co 54         0.0'0E+00 ' t.51E+02 3.39E+02 0.00E+00 0.00E 40 0.00E+00 3.0M43 Co 60         0.00E+00 4.ME 42 9.58t+02 0.00E40.0.00E+00 0.00E+00 8.1M +03 ul*63-        4.19E+04 2.91E+03 1.41E+03 0.00E+00 0.00E*00 0.00E40 6.0?t+02 N145          1.70E+02 2.21E+01 1.01E 41 0.00E +00 0.00E+00 0.00E+00 5.61E*02 CU 64         0.00E+00 1.HE+01 7.93E+00 0.00E+00 4.2M +01 0.00E+C0 1.44E+03
                       '2N 65          2.36E+04 7.5C*+04 3.39E+04 0.00E+00 5.02E+04 0.00E+00 4.7M44
                         ................e............, .................................................

2N 69 5.02E+01 9.60E41 6.6,4 4* a nas+an 6.24E+01 0.00E+00 1.44E+01

                      ' 0s 85        . 0.00040 0.00E+00 4.30E+01 0.00E+00 0.00E+00. 0.00E+00 6.30E+01 BA N          0.00E+00 0.00E*00 5.67E41 0.00E40 0.00E*00 0.00E+00 4.4M 04 08 05         0.00E+00 0.00E+00 2.33E+00 0.00E+00 0.00E+00 0.00E*00 ' O.00E40 Re t6         0.00E+00 1.03E+05 4.79E+04 0.00E*00 0.00E+00 0.00E+00 2.0M*04 R0 88 '       O.00E+00 2.950+02 1.56t+02 0.00E+00 0.00E+00 0.00E+00 4.07E 09
                       -08 89          0.00E+00 1.9H+02 1.37t+02 0.00E+00 0.00E+00 0.00E+00 1.13E.11 en 09         4.70E+44 0.00E*00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 9A*90         1.1M+06 0.00E*00 2.85+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04 te*91         8.79E42 0.00E+tc 3.55E+01 0.00E+00 0.00E+00 0.00E+00 4.19E+03 l                         SR 92         3.33E+02 0.00E+00 1.44E41 0.00E+00 0.00E+00 0.00E+00 6.60E43 I:                        Y 90          1.3M+00 0.00E*00 3.69E*04 0.00E+00 0.00E 40 0.00E+00 1.46E+04 T 91st       1.30E.02 0.0dE*00 5.044 04 0.00E+00 0.00E+00 0.00E+00 3.82E 02 T 91         2.32E41 0.00E+00 ;5.39E.01 0.00E+00 0.00E+00 0.00E+00 1.11E+04
                        ,Y.92          1.21E 01 0.00E+00 3.5M 03 0.00E+00 0.00E+00 0.00E*00 2.13 43 Conversten factors are in units of ersWyr per uCl/el l

I UNT-005-014 Revision 0 , Attachment 6.3 (4 of 6) 117

SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES Act GROUP: ADUI.T DitchARGE PolNT: ALL OTWtts (into 40 Arpent CaneO NUCLIDE ORGAN post Convit$10h O ctatt 80NE L1Ytt T.83)Y INYkOID KIDNEY LUNG Gl LLI \ V 93 3.838 01 0.00E*00 1.0M 02 0.00E+00 0.00E*00 0.00E+00 1.22t+04 2R 95 2. 7?E +00 8.8M 01 6.01t 01 0.00E*00 1.39E*00 0.00E*00 2.82t+03 . 2R 97 1.5M 01 3.09E 02 1.418 02 0.0C4+00 4.671 02 0.00E*00 9.57E+03 ht 95 4.47t +02 2.49E+02 1.34142 0.00E *00 2.4M+02 0.00E*00 1.51t+06

• M0 99 0.00E 40 4.62t+02 8.79E*01 0.00E*00 1.05t+03 0.00E+00 1.07E+03 TC 99M 2.94t 02 8.32E 02 1.0M +00 0.00E+00 1.26t+00 4.073 02 4.92E41

             ,                       TC 101                                 3.03E 02 4.36E 02 4.28E 01 0.00E+00 7.854 01 2.23t 02 1.315 13
                           .         20-103                                 1.98E+0] 0.00E+00 ' 8.54t+00 0 00E+00 7.57E+01 0.00E+00 2.31E+03 t0 105                                 1.65t+00 0.00E+00 6.521 01 0.NE+00 2.1M +01 0.00E*00 1.01E*03 ku-106                                 2.954 42 0.00E+00 3.73E+01 0.00E+00 5.69E+02 0.00E*00 1.91E+04 A0 110M                                1.41t+01 ' 1.30E+01 7.74t+00 0.00E+00 2.5M +01 0.00E+00 5.32E+03 ft 125M                                2.79E+03 1.01t+03 3.74t+02 8.39E+02 1.1M +04 0.00E*00 1.11E+M TE 127H                                7.05t+03 2.52E+03 8.59E 42 1.80E+03 2.8M +M 0.00E+00 2.365+04                                                                                        .

it 127 1.14E+02 4.11E+01 2.48E+01 t.48E+01 4.6M *02 0.00E*00 9.03t+03 TE.129H 1.20E+04 4.47E+03 1.89t*03 4.11E 43 5.00E+04 0.00E+00 6.03E+04 ft.129 3.27E+01 1.23t+01 7.9M+00 2.51141 1.37t+02 0.00E+00 2.47E*01 ft 131M 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E*03 0.00E+00 8.74E+M TE 131 ' 2.05t41 8.57t+00 6.475+00 1.69E+01 8.98E*01 0.00E+00 2.90E+00 TE 132 2.62E+03 1.70E*03 "1.59E+03 1.8M+03 1.63t+04 0.00E+00 8.02t*04 1 130 9.01E*01 2.6M+02 1.05E+02 2.25t+04 4.15t+02 0.00E+00 2.29t+02 I*131 4.96E+02 7.09E+02 4.0M+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 1 132 2.42E+01 6.4?E41 2.2M+01 2.2M*03 1.03E+02 0.00E+00 1.22E+01 1 133 1.69E42 2.94t+02 8.97t+01 4.32E+04 5.13t+02 0.00E+00 2.Ht+02 1 154 1.2H41 3.43E+01 1.23t+01 5.94t+02 5.4M*01 0.00E+00 2.99E 02 l.135 5.28E*01 1.38E42 5.10E+01 9.11t+03 2.22E+02 0.00E+00 1.5M*02 CS 134 3.0M+05 7.21E45 5.89t*05 0.00E+00 2.33E+05 7.75t+04 1.2M +04 CS 136 3.17t 44 1.25t+05 9.01t+M 0.00E+00 6.97t+04 9.55t+03 1.42E+04 Cs.137 3.88E+05 5.31E45 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.01E+04 CS 138 2.69E+02 1.31E+02 ',63E+02 0.00E*00 3.90E+02 3.85t+01 2.271 03 8A 139 9.00E+00 6.41E*03 2.648 01 0.00E +00 5.99E 03 3.645 03 1.60E*01 Conversion f actors are in units of arem/yr per LCl/mi UNT-005-014 Revision 0 , Attachment 6.3 (5 of 6) 118

SITE RELATED LIQUID INGESTION DOSE COMMITMENT FACTORSg (A ) FOR MMM NES 4GE GROUP: ADOLT DittnAaGE Polut ALL Of#tts (late 40 Arpent Const) NUCLIDE ORGAN DoSt CONVittl0N iACTOR$ BONE LIVtt 1.90DY 1NYt01D KIDuff Luna Cl LLI I BA 140 1.8eE+03 2.3M+00 1.23t+02 0.00t+00 8.05t 01 1.35t+00 3. tee +03 BA 141 4.3M +00 3.30t 03 1.40E 01 0.00E*00 3.075 03 1'.871 03 2.0H+09 BA 142 1.90E*00 2.03E 03 1.248 01 0.00E+00 1.72t 03 1.1M 03 2.?tt 18 LA 140 3.58E 01 1.80E 01 4.7M 02 0.00t+00 0.00t+00 0.00E+00 1.32t+M - LA 142 - 1.834 02 8.33t 03 2.071 03 0.006+00 0.00E+00 0.002 60 6.00t*01 CE*141 8.011 01 5.42t 01 6.15t 02 0.00t+00 2.525 01 0.00t+00 2.07t+03 CE 143 1.415 01 1.Mt+02 1.iet 02 0.00E+00 4.60E 02 0.00F*00 3.90t+03

                           .CE 144                           4.18t+01 1.75t+01 2.24t+00 0.00E+00 1.Mt+01 0.00t+00 1.41t+04                                                               2
                           -Pe 143                            1.32t+00 5.20E 01 6.52t 02 0.00t+00 3.05t 01 0.00t+00 5.77t+03 -

Pe 144 4.31t 03 't.79t 03 2.19t 04 0.00t+00' 1.01t 03 0.00t+00 6.19E 10 10 147 ' 9.00E 01 1.04t+00 6.22t 02 0.00t+00 6.00t 01 0.00t+00 4.99t+03 V 107 3.Mt+02 2.55t+02 8.90t+01 0.00E+00 0.00t+00 0.00E+00 8.34t+04 IIP 239 1.20tt01 1.2H 02 6.918 03 0.00t+00 3.91t 02 0.00t+00 2.57t+03 Conversion factors are in mits of area /yr per W:l/mL 4 UNT-005-014 Revision 0 Attachment 6.3 (6 of 6) 119 i . ..

DOSE FACTORS FOR EXPOSURE TO'A SEMI-INFINITE CLOUD'OF NOBLE OASES = ll

                  .Nuclide-                   E-air *(Ng )         E-Skin **(Lg )                        y-Air * (Mg )              y-Body **(Kg )

Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08

Kr-85tn '1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88, 2.93E-03 2.37E-03 1.52E 1.47E-02 Kr .1.06E-02 1.01E-02 1.73E-02 1.66E Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02

                  'Xe-131m                     1.11E-03            4.76E-04                                  1.56E-04                9.15E-05
                  -.Xe-133m                    1.48E           9.94E-04                               -3.27E-04                  2.51E-04 Xe-133'                    1.05E-03            3.06E-04                                 3.53E-04                 2.94E-04 Xe-135m                 ' 7.'39E-04,           7.11E-04                                 3.36E-03                 3.12E-03
                  /Xe-135.                    2.46E-03             1.86E                                 1.92E-03                1.81E-03
                   .Xe-137       .

I'27E 1.22E-02 '1.51E-03 1.42E-03 Xe-138' 4.75E-03  : 4.13E-03 9.21E 8.83E-03 Ar-41 3.28E-03 2.69E-03 -9.30E-03 8.84E-03 4

• 3 mrad-m '

pCi-yr 3 mrem-m - '

                      = pCi-yr .-                                                                                                                             -

Extracted from Table B-1 of Regulatory Guide 1.109, Revision 1, 1977 UNT-005-014 Revision 0 Attachment 6.4 (1 of 1) 120

INHALATION PATINAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g AGE GROUP ADUti ( 1 Of 3 )

                                     . NUCL!DE                                   ORMN DOSE CONVERElcol f Act0R$                   .

SONE L1VER 1.t(BY TNYR010 KIDNEY LUNO Cl*LL] , t 43 0.00E*00 1.26E+03 1.2H+03 1.2M +03 '1.2M+03 1.2M*03 1.26E+03 C.14 1.82E*04 3.41E

• 03 3.41E+03 3.41E*C3 3.41E+03 3.41E+03 3.41E+03 NA 24 1.02(+04 1.02E*04 1.02E*04 1.02E+04 1.02E+04 1.02E*04 1.02E*04 P.32 1.32E+06 7.71E W 5.01E*04 0.00E 40 0.00E+00 0.00E+00 8.64E 04 CR 51 0.00E+00 0.00E*00 1.00E+02 5.95E+01 2.20E+01 1.44t
• 3.32E +03 mm 54 0.00E+00 3.9M+04 6.30E+03 0.00E*00 9.84E+03 1.40E*06 7.74E+04 MM 56 0.00E+00 1.24E+00 1.83E 01 0.00E40 1.30E+00 9.44E+03 2.02E+04

                                        'FE 55            2.46t+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E*03 ft 59         1.18t+04 2.7tE *04 1.0M*04 0.00E*00 0.00E+00 1.02E*06 1.88t*05 CO 58         0.00E+00 1.54E +03 2.07E+03 0.00E+00 0.00E*00 9.2eE+05 1.0M +05 Co.60         0.00E+0d 1.1M+04 1.4aE +04 0.00E+00 0.00E+00 5.97t+M 2.85E45                                                       '

N1*63 4.32E +0* 3.14E+04 1.45E +M 0.00E*00 0.00E +00 1.7tE+05 1.34E+04 N1 65 1.54E+00 2.10E 01 9.1M.02 0.00E+00-O M0E+00 5.60E+03 1.23E+04 CU 64 0.00E+00 1.4M *00 6.1M 0,1 0.00E+00 .*..e28+00 6.7eE+03 4.90E+04

• zu 65 3.24E+04 1.03E+05 4.66t+04 0.00E+00 6.90E+M 8.64E45 5.34E*M Zu.69 3.46E.02 6.51E 02 4.5M.03 0.00E+00 4.22E.02 9.20E+02 1.63E+01*

se 83 0.00E+c0 0.00E+00 2.41E+02 3.00E+00 0.00E+00 0.00E 40 2.32E*02 38 84 0.00E+00 0.00E+00 3.13E+02 0.00E+00 0.00E+00 0.00E+00 1.64E 03 I: - ta R$ 0.00E40 0.00E+00 1.2AE +01 0.00E+00 0.00E+00 0.ft0E+00 ' O.00E+00 ,

                                       , RS 06             0.00E+00 1.35E+05 5.90E+04 0.00E +00 0.00E+00-0.00E+00 1.66t+04 Re 88         0.00E+00 3.87E42 1.93E+02 0.00E+00 0.000+00- 0.00E+00 3.34E 09 Re.09        0.00E+00 2.56E+02 1.70E+02 0.00E+00 0.00E*00 0.00E+00 9.2st.12 sa 09        3.04E+05 0.00E+00 8.72E+03 0.00E*00 - 0.00E+00 1.40E+46 3.50E+05 9R 90        9.9M *07 0.00E+00 6.10E+06 0.00E*00 0.00E+00. 9.60E+06 7.22E45 SR 91         6.19E+01 0.00E+00 2.50E+00 0.00E+00 0.00E+00 3.6M *04 1.91E+05 sa 92         6.74E+00 0.00E+00 2.91E.01 0.00E+00 0.00E+00 1.6M +04 4.30E+04                                                                          '

T 90 2.0N+03 0.00E+00 5.61E+01 0.00E+00 0.00E+00 1.70E+05 5.06t+05

            +-                                 Y.914        2.61E41 0.00E+00 1.02E 02 0.00E+00 0.00E 4 0 1.93+03 1.3M+00 Y.91         4.62E+05 0.00E+00 1.24E+M 0.00E+00 0.00E+00 1.70E+06 3.tM+05
                                             ' Y 92         1.03E+01 ' O.00E+00 3.02E.01 0.00E+00 0.00E+00 1.57t+04 7.35E+04 Corwersion f actors are in units of aren/yr per Wl/cels meter.

UNT-005-014 Revision 0 Attachment 6.5 (1 of 12) 121

INHAI.ATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, Rg , 40E GROJPt ADVL1 ( 2 Of 3 ) NuttIDE ORGAN 005E c0NVER$10N Fact 0RS DONE LIVER f.htsf TNYR010 E!!Hett LUNG st.LLI f.93 9.44E*01 0.00E+00 2.61E+00 0.00E 40 0.00E+00 4.85E +M 4.22E+05 2E.95 1.0M +05 3.44E+04 2.33E +M 0.00E+00 5.42E+04 1.77E +M t.50E+05 2R.97 9.6eE+01 1.9M *01 9.ME+00 0.00E+00 2.9M*01 7.8M *M 5.23E+05 No.95 1.41544 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.0$E+05 1.ME+05 M0 99 0.00E*00 1.21E+02 2.30E*01 0.00E+00 2.91E+02 9.12E +M 2.4eE+05

• W+03 TC.99M 1.03E 03 2.91E.03 3.70t *02 0.00E*00 4.42E.02 7.64E+02 TC.101 4.tet.05 6.02E.05 5.90E 04 0.00E*00 1.00E.03 3.99E+02 1.09E.11 tu.103 1.53E +03 0.00E+00 6.5eE+02 0.00E+00 5.83E*03 5.05E+05 1.10E +05 RU 105 7.90E.01 0.0eE+00 3.115 01 0.00E*00 1.02E+00 1.10E44 4.82E+04 RU.106 6.91E+M 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36t+06 9.12E*05 4G 110M '1.00E+04' 1.00E*04 5.94E+03 0.00E+00 1.9M44 4.63E+M 3.02E+05 3 42E+03 1.5eE43 4.6M+02 1.05E+03 1.24E+04 3.14t*05 7.0M +04 TE.125M TE.127M 1.2M44 5.7M+03 1.5M43 3.29E+03 4.5eE+04 9.60E45 1.50E+05 TE.127 1.40E+00 6.42E.01 3.10E.01 1.06E+00 5.10E+00 6.51E+03 5.74E+04 9.7M +03 4.6M +03 1.5eE+03 3.444 03 3.'65E +M 1.1M+M 3.83E+05 TE.129M TE.129 4.9eE.02 2.39E.02' 1.24E.02 3.90E 02 1.8M .01 1.94E+03 1.5M+02 TE.131M 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E*02 1.4M45 5.5M+05 TE.131 1.11E.02 5.95E*03 3.59E.03 9.36E.03 4.3M.02 1.39E+03 1.84E+01 TE.132 .2.60E*02 2.15E+02 1.62E42 1.90E +02 1.46E+03 2.seE+05 5.10E+05 '

1 130 4.SeE+03 1.34E+04 5.2eE+03 1.14E Hl6 2.09E+04 0.00E+00 7.69E+03 I.131 2.5M+04 3.5eE+04 2.05E+04 ' 1.19E*07 6.13E+04 0.00E+00 6.2eE+03 1 132 1.168+03 3.26E+03 1.1M43 1.14E+05 5.18t+03 0.00E+00 4.0M+02

                  .               I.133         8.64E+03 1.4eE+04 4.52E+03 .2.15E+06 2.5eE+04 0.00E+00 8.seE+03 1 134         6.44E+02 1.73E+03 6.15E*02 2.9eE+04 2.75E+03 0.00E*00 1.01E 40 l.

I~ 1 135 2.68t+03 6.9eE+03 2.5M+03 4.4eE+05 1.11E+.'4 - 0.00E+00 5.25E+03 Cs.134 3.73E*05 8.4eE+05 7.20E 45 0.00E+00 2.30E+05 9.7M +04 1.04E+04 l cs.136 3.90E+04 1.4M45 1.10E+05 0.00E+00 8.564+04 1.20E44 1.1M +04 l ................................................................................ cs.137 4.7eE+05 6.21E+05 4.2eE 45 0.00E+00 2.22E45 7.55 44 8.40E+03 Cs.138 3.31E*02 6.21E+02 3.24E+02 0.00E+00 4.00E+02 4.e6E41 1.e6E.03 l. l- -SA.139 9.36E.01 6.66E.04 2.744 02 0.00E+00 6.22E 04 3.76E+03 8.96E*02 l- ................................................................................ Conversion f actors are in mits of aremfyr per WCf/ cubic meter. UNT-005-014 Revision 0 Attachment 6.5 (2 of 12) 122

1 1 INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g j l AGE OROUPs ADUL1 ( 3 0F 3 ) NUCLIDE ORGAN 00$t CorVittl0N FACTORS DONE LIVtt 1.DCWY THYROID . KIDuty LUNO OI.LLI sA.140 3.90E+04 4.90E*01 2.57t+03 0.00E+00 1.67t+01 1.27t+06 2.18t+05 4A.141 1.00t 01 7.135 05 3.3M 03 0.00t+00 7.00E 05 1.94E+03 1.1M.07 SA 142 2.638 02 2.708 05 1.664+03 0.00E+00 2.29E 05 1.19t+03 1.57t 16 LA 140 3.44E+02 1.74t+02 4.54E+01 0.00t+00 0.00t+00 1.364+05 4.54E+05 LA*142 6.838 01 1.10E 01 7.72t 02 0.00f+00 0.00E.00 6.33t+03 2.11E+03 Ct.141 1.9et+04 1.35t+04'1.53t+03 0.00E+00 6.2M+03 3.62E+05 1.20f*05 Ct*143 1.eM+02 1.3aE+02 1.53E+01 0.00t+00 6.00E+01 7.9et+04 2.2M+05 Cta144- 3.'43t*06 1.43t+06 1.84E+05 0.00t+00 8.48t+05 7.7eE+06 8.1M +05 Pea 143 9.36t+03 3.75E+03 4.64t*02 0.00E*00 2.1M*03 2.81t+05 2.00E+05 Pea 144 3.01t 02 1.258 02 1.53t 03 0.00E+00 7.058 03 1.02E+03 2.15t 08 No 147 5.27t+03 6.10E*03 3.65t+02 0.00E+00 3.56t+03 2.21t+05 1.73t+05 W 187 8.4aE+00 7.00t*00 2.4aE+00 0.00t+00 0.00E+00 2.90t+04 1.55t+05 No*239 2.30E+02 2.2M*01 1.24t+01 0.00E*00 7.00:t0*. L.7M+04 1.19t+05 Corwerelen "fectors are in units of aren/yr por uCl/cela noter. UNT-005-014 Revision 0 Attachment 6.5 (3 of 12) 123 .

       =

INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN' NOBLE CASES, R g 6 AGE GaWP: TEEN ( 1 Of 3 ) NUCLIDE onGAm Oost couvERElcu FACTORS tout L1, vet f.000Y tWYt0!D KlosET LLMG Cl*LLI m3 0.00E+00 1.2M +03 1.2M 43 1.2M *03 1.2M +03 1.2M +03 1.2M +03 C 14 2.60E+04 4.87E +03 4.8M *03 4.84+03 4.87E+03 4.8M *03 4.8?E+C3 mA 24 1.3he+04 1.34E+04 1.30E*06 1,3eE44 1.38t+04 1.3aE*04 1.34t*04 P*32 1.99E+06 1.10E+35 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.20E+04 Ca 51 0.00E+00 0.00E+00 1.35442 7.50E+01 3.07E+01 2.10E+04 3.00E*03 mm*54 0.00E*00 5.11E*04 8.40E*03 0.00E+00 1.2M*04 1.90E t06 6.64E*04

                 ,           un 56          0.00E*00 1.7aE,+00 2.52E 01 0.00E*00 1.79E+00 1.52E+04 5.744*04 FE 55 3.34444 2.34E+04 5.54E+03 0.00E *00 . 0.00E *00 1.24E+05 6.39E*03 FE*59       ;1.59E+01 3.70E44 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.7sE*05 '

CO 54 0.00E+00 2.0M+03 2.78t+03 0.00E+00 0.00E+00 1.344+06 9.52E+04

• Co 60 0.00E+00 1.51444 1.9eE+04 0.00E*00 0.00E 40 8.72E*06 2.59E*05 ul 63 5.00E45 4.34E 44 1.90E+04 0.00E+00 0.00E40 3.0M+05 1.42E*04
• u t 45 2.taE+00 2.934 01 1.27E 01 0.00E.00 ;0.00E*00 9.36E+03 3.6M+04
• CU44 0.00E*00 2.03E+00 8.44E 01 0.00E+00 6.41E+00 1.11E*04 6.14E+04 2m 65

                                          '3.86t+04 1.34E+05 6.24t*04 0.00E*00 ' 8.64344 1.24E+06 4.66t+^4         .          '

Zu49 4.83442 9.20E 02 6.46E 03 0.00E+00 6.03E 02 1.5aE+03 2.854+02 BA 83 0.00E+00 0.00E*00 3.44E+02 0.00E*00 0.00E*00 0.00E+00 0.00E*00 04 84

             .                         . 0.00E+00 0.00E+00 4.33E+02 0.00E+00 0.00E40 0.00E+00 0.00E+00 8R 85 0.00E+00 0.00E+00 1.83E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00
                           #8 86
                                       - 0.00E+00 1.90E45 8.40E+04 0.00E+00 0.00E*00 0.00E+00 1.TM+04 A8 88

• 0.00E+00 5.46E+02 2.7M+02 0.00E+00 0.00E+00 0.00E+00 2.92E 05 00 89 0.00E+00- 3.52E+02 '2.33E+02 0.00E*00 0.00E+00 0.00E+00 3.3aE*07 sa.09 4.34E+05 0.00E*00 1.25E+04 0.00E*00 0.00E*00 2.42E+06 3.71E+05 Stato '

1.00E+08 0.00E*00 6.6AE+06 0.00E+00 0.00E+00 1.65E+07 7.654+05 sa 91 8.goE+01 0.00E+00 3.51E+00 0.00E+00 0.00E+00 6.07E*04 2.59E+05

• sa+92 9.53E+00 0.00E+00 4.064 01 0.00E*00 0.00E *00 2.74E +04 1.19E+05 Y.90 2.90E43 0.00E+00 8.00E+01 0.00E+00 0.00E+00 2.93E+05 5.59E+05 Y 91m

                                        .3.70E 01 0.00E 40' 1.42E*02 0.00E *00 0.00E+00 3.20E+03 3.02E+01 Y 91           6.61E+05 0.00E+00 1.77E *04 0.00E+00 0.00E,+00 2.94E+06 4.09E+05 Y 92 1.47E41 0.00E+00 4.29E*01 0.00E+00 0.00E+00 2.68t+04 1.65E+05 Cerwersten f acters are in mits of uren/yr per W:l/c@lc meter, i

UNT-005-014 Revision 0 Attachment 6.5 (4 of 12) ] 124 l l l 1

1 INHALATION PATWAY DOSES DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R g, . 'l 4GE Ge0UP: fits ( ! Of 3 ) NUCtl0E Ca pa 0064 CONVIt$10N FACT 0R$ DONE Livtt f.9001 TWYt010 KIDuff LUNG Gl.Ltl 1 T.93 1.35t+02 0.00E +00 3.72t+00 0.00t+00 0.00t+00 8.32t+04 5.79t+05 28 95 1.4M+05 4.54E+M 3.15t+M 0.00t+00 6.74E+04 2.69t+06 1.49t+05 28 97 1.34t *02 2.72t*01 1.26E+01 0.00t*00 4.12t+01 1.30t+05 6.%E +05 N6 95 1.bM*04 1.03E+M 1.66E+03 0.00t*00 1.00t+04 7.51t*05 9.6aE *M NO 99 0.00t+00 1.6M+02 3.22t*01 0.00E*00 4.11t+02 1.54t+05 2.69t+05 TC.99N 1.34t.03 3.8M.03 4.99t.02 0.00E+00 5.7M.02 1.15E*03 6.13E+03 ft.101 5.921 05 8.40t.05 8.248 04 0.0M*00 1.525 03 6.67t+02 8.72t.07 RU 103 2.10E+03 0.00t+00 8. M +02 0.00t*J0 7.43E +03 7.83t+05 1.09t+05

           ,.                    RU.105         1.12t*00 .0.00E+00 4.345 01 0.00t+00 1.41t+00 1.82t+04 9.04t+04 80 106        9.84E+M 0.00t+00 1.24t+04 0.00E+00 1.90t+05 1.61t*07 9.60t+05
                               . A0 110N        1.3et* M .1.31t+04 7.99t*03 0.00E+00 2.50t+04 4.75E+06 2.73E*05 ft.125N        4. tee *03 2.24E+03 6.67t+02 1.40t+03 0.00t+00 5.3eE+05 7.50t*04 Tt.127M        1.80E+M 8.1M+03 1.78t+03 4.3eE+03 6.54t+M 1.6M+06 1.59t+05 TE*127         2.018 40 9.1M .01 4.42E.01 1.4M+00 7.28t+00 1.12E+M 8.Det+04 it.129N        1.39E+04 4.54E+03 2.25E +03 4.54E+03 5.19t+04- 1.90E+06 4.05E+05 ft.129        7.10E.02 3.3at.02 1.76t.02 5.18E.02 2.NE.01'3.30t+03 1.62E+03
                               .ft.131M         9.44E+01 6.01E+01 4.02E +01 7.25E+01 4.39t+02 2.30E+05 6.21E+05 TE.131        1. Sat.02 8.32E.03 5.04t.03 1.24E.02 6.18E.02 2.34E+03 1.51t+01 TE*132        3.60t+02 2.90E+02 2.jM42 2.46t+02 1.95E+03 4. +M+05 4.63E+05
                       ..         1 130         6.24E*03 1.'79E46 7.17t+03 1.4M+46 2.75E+04-0.00E+00 9.12E+03                        e 1 131         3.54E+04 4.91E*04 2.64E+04 1.46E+07 8.40E*04 - 0.00E+" 4.4M +03 1 132        1.5M+03 4.30E+03 1.SaE+03 1.51E+05 6.92E+03 6. e du 1.27t+03 1 133        1.2M+04 2.05E *04 6.22E43 2.92E+06 3.5M+06 0.00t+00 1.03E+04 1 134        8.00E+02 2.3M+03 8.40E+02 3.95E*04 3.66E+03 0.00E+00 2.04E+0?

1 135 3.70t+03 9.44E+03 1.40E+03 6.21E+05 1.49E+04 0.00E*00 6.95t+03 Ct.134 5.0M+05 1.1M+0e J .4M *05 0.00E+00 3.75E+05. 1.4M +05 9.7M+03 Cs.136 5.15E+M . 1.94E+05 1.37E+05 0.00E+00 1.10E+05 . 1.7eE +04 1.09E+04 C8 137 6.70E+05 8.44t45 3.11t+05 0.00E+00 3.04E+05 1.21E+05 8.4aE+03

                                 .C3 138         4.NE+02 8.5eE42 4.4M+02 0.00E+00 6.62E*02 7.87141 2.708 01 SA.139        1.34E*00 9.44E 04 3.90E.02 0.00E+00 8.001.M 6.46E43 6.45E+03 Carwersion f actere are in imits of ares /yr per uCl/c4(c meter.

UNT-005-014 Revision 0 Attachment 6.5 (5 of 12) 125

INHALAT)0N PATHVAY DOSES DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R, I AGE W 41P: tith t 3 08'3 i WCLit! 0A ug 0068 towWieltok IACTOR$ Otad Livtt 1.0001 fry 0010 tienti Luut Cl;LLI t W 140 - 1.47t +M 6.70t+01 3.5M43 0.00;+00 f.20t 41 2.03t +06 2.29t +M Maint 1.4N 01 1.0M M 4.748 03 0.00t+00 9.ht 05 3.29643 7.4M M

                       . M 142       3.? tit 02 3.70t M 2.27t 03 0.00t+00 3.14t M i.01t+03 4.795 10 LA 140      4.79t42 2.L*02 6.tM 41 0.00t+00 0.00t+0p

• 44t+05 4.07t45 .

LA 142 9.60t 01 4.tSt 01 1.0M 01 0.00540 0.00t+00 1.02t+04 i. M an' ttai41 2.Mt+M 1.90t+M f.17t*03 0.00t+00 0.00t+03 6.14t+M 1.tM 45 Ct 143 2.We+02 1.Mt+02 2.1M+01 0.00t+00 0. kt 4 1 1.30t+05 I.55t+M ct.144 4. M *06 2.02t+M 2.6at+M 0.00f 40 1. tit +46 1.34t+07 0.pt+05 M 143 1.34t+M l.3tt+03 6.62t+02 0.00t+00 3.0443 4.0M *05 2.145*05

                   .       .........................s......................................................
         .                 Pe.144      4.30t 02 1.7M 02 2.10t 03 0.00t+00 1.018 02 1'.75t+03 2.3M M e 147       7.0M43 0.Ht+03 1.1M +02 0.00t+00 5.02t+03 3.72t+05 1.0ft+05 W 107       1.20t 41 9.76t+00 3.43t+00 0.00t+00 0.00t+00 4.76t +M 1.77t+05 NP*239      3.30t 42 3.19E41 1.771+01 0.005+M 1.00t+02 6.49t+M 1.328+05 c     reie vect.c. re in mit. .e w.wyr 0.c ucifeets               i.e.

UNT-005-014 Revision 0 Attachment 6.5 (6 of li) 126

                       =

O INHALATION l'ATWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE CASES, R g , W OkiPt Cull 0 t 1 07 3 ) NJCilDt Det.6a tK5t towviellom f4Ciots tout Litit 1.000Y 197000 ElDatt t($ $1 al u4 0.00s+W 1.12t+03 1.121+03 1.12t+03 1.12t+03 1.12t+03 1.12t +03 C 14 3.59t *M 4.7M*03 6.73843 6.73t +03 6.7M+03 6.7M+03 6.7M43 hA 24 1.61t+M 1.61t+06 1.61t+M 1.618 4 1.61t+06 1.61t +04 1.61t +0 e P 32 2.606 4 1.14t+05 9.tSt +M 0.00t+00 0.00t+00 0.00t+00 4.12t+06 CR 41 0.00t*00 0.00t+00 1.56t+02 8.llt41 2.4M *01 1.M.04 1.00f+03

                            ,ew 44         0.00t*00 4.29t +M 9.518*03 0.00t+00 1.00t

• 1.508+06 I.29t*04

                    .       an46           0.00t+00 1.6M*00 3.12t 01 0.00t*00 1.671 40 1.31t+M 1.ZM*05 ttall         4.748+04 I .52t +M    7.771+03 0.00t+00 0.00t+00 1.11t*05 3.471+03 9849          1. 071+M 3.34t+06 1.67544 0.00t+00 0.00t+00 1.27t +M 7.07t +M
                                                ~

CD48 0.00t+00 1.771 03 1.iM+03 0.00t*00 0.00t*00 1.11t+M 3.W+M . C040 0.00t+00 1.31t+04 2.2M+M 0.00t+00 0.00t+00 7.07t +M 9.62t %4 81 63 4. tit *05 4.63t+04 2.00844 0.00t+00 0.00t+00 2.75t*05 6.3M *03

• sl*65 2.99t+00 2.9et 01 1.ME 01 0.00t+00 0.00t40 B.10t+03 4.40t *H tv*64 0.00t+00 1.99t+00 1.07t+00 0.00t+00 6.0M 40 9.50t+03 3.67t +M 26 65 4.tet +M 1.1M *05 7.0M +04 0.00t+00 7.14t +M 9.9H+05 1,6M *M

                              ........................................................a*....*..*******.*******

tu 69 6.701 02 9.6M 02 8,9M 03 0.00t+00 S.0H +02 1.42t+03 1.0M*04 M.83 0,WE+00 0.00t+00 4.74t+02 0.00t+00 0.00t+00 0. At +00 0.00s+00 08.M 0.00E+00 0.00E+00 S.40t+02 0.00t+00 0.00t*00 0.00t+00 0.00t*00 00 35 0.00t+00' O.00t+00 2.lM+01 0.00t+00 0.00t+00 0.00t+00 0.00E+00 00 M 0.00f+00 1.90t+05 1.1M +05 0,00t+0C 0.00t+00 0.00t+00 7.MI*03 00 00 0.00t+00 3.63E+02 3.64t+02 0.00t+00 0.00t+00 0.00f+00 1.72t+01

1. Del +00 80 M 0.00t+00 3.4M+02 3 90t+02 0.00t+00 0.00t+00 0.00t+00 M.M l.9et+05 f Mt*00 1.73E +M 0.00E+00 0.00840 2.16t+06 1.671 45

• M.90 1.01148 0.00t+00 6.44f+46 0.00t+00 0.00t+00 1.40E47 3.4M 45 00 41 1. tit *02 0-00t+00 4.59t+00 0.00t+00 0.00t+00 5.3M44 1.74t+05 M 92 1.31841 0.00840 5.tH.01 0.00t+00 0.00t+00 2.40t+06 2.42t+05 f.90 4.11843 0.00t+00 1.11t+02 0.00t+00 0.00t+00 2.62545 2.60t+05
• t 914 S.07 41 0.00t+00 1,048 02 0.00t+00 0.00t+00 2.01t*03 1.72t43 T41 9.14t+05 0.00E+00 2.44t+M 0.00t+00 0.00t+00 3.6M +06 1.Mt+05 f.92 2.Mt41 0.00t+00 S.01t.01 0.00t+00 0.00f*00 2.39t+M 2.39t+05 twwersten f actere are lh mits of aren/yr per WUcela meter.

UNT-005-014 Revision 0 Attachment 6.5 (7 of 12) 127

i . INRALATION PATINAY DOSES DUE TO RADIONOCLIDES OTHER TRAN NOBLE CASES, R g 3 AGE GACUP C#1LO t 2 0F 3 ) IWCLIM Ottata DoSt CturWttllom FACTOR $ tout LlWit 1.021 fpf0010 KiDutt Lune Cl*Lil f.93 1.0M*02 . 00t+00' l.11t*00 0.00t+00 0.00t*00 7.664+M 3.04 41 20 95 1.90t+05 4.1st+ u 3.70t+06 0.00t+00 1.tet+M 2.2M*06 6.11846 ta.97 1.ett*02 2.7tt+01 1.60t 41 0.031+00 3. tot di 1.1M 45 3. lit +M me.95 2.3H+M 9.18t+03 6.lH +03 0.00t*00 0.62443 6.16t*05 3,70t *M up 95 0.00t+00 1.73t*02 4.26t 41 0.00t+00 3.Mt 42 1.3H*M 1.27t4S 1.7st.03 3.6at.03 5.m.02 0.00t+00 5.0M.02 9. lit *02 4.81t +03 tC.ppu ft 101 4.108.M s.ltt M 1.005 03 0.005 00 1.458 03 5.Mt+02 1.6M 41 au.103 2.79t+03 0.00t+00 1.0M +03 0.00t+00 7.0M+03 6.68t

• H 6.488 +M 91M 1.5M40 0.00t+00 5.lM41 0.00t+00 1.Ml+00 1.99t+M 9.95t+M 1.ht.05 0.00t+00 1.60E46 0.00t+00 1.0M +M 1.4M+07 4.2964 hp.106

     .        .                                        A411W          1.HE+04 1.164+04 9.168+03 0.001+00 2.1M+04 S.40s M 1.00545 6.73843 2.3M +03 9.16t+02 1.93t+03 0.00t+00 6. m *05 3.30t+04 ft.120m Tf*127W       3.49t +M    8.55t43 3.03t+03 6.0M+33 6.36046 f.68t+M 7.164+04 15 127        2. m +00 9.514 01 6.11t*01 1.90t+00 7.0M+00 1.00f*04 l.63t+04 ft+128N       1.98t +M 6.05443 3.Mt+03 6.3M 43 S.0M+M 1.768+46 1.03t45
                               .                        if 1M         9. m .02 3.508 02 2.30t.02 7.168 02 2.bM.01 3M3t<3 2.S$t+04

• ft.131u 1.ht+02 $.9N 41 5.07t 4 1 9.77t+01 4.0pt42 2.0st45 3.tet+05 18 131 2.1M.02 8.64443 6.99E*03 1.7.18 02 9.88t.02 2.0H43 1.33t @

ff*132 4.010+42 2.78842 2.63042 3.1M 42 1. m +03 3.m45 1.30t+05

                            ..**                                       9.181+E3 1.Ma*46 8.64t+03 1.0be+46 2.4M*06 0.00t+00 1.11t+03 1 130 1 131         4.01t+M 4.01t+M 2.73t+46 1.6at47 7.RIR+46 0.00t 4 0 2.868+03 1 132         2.1N+03 4.07t43 1.ast+43 1.Mt+05 6.29843 0.00t+00 3.20e 03 1 133        1.6e4+04 2.03t+44 7.70843 3.850+46 3.30t46 0.000+00 1.6at45 l.1M         1.17t43 2.16t+03 9.9M42 5.0M*M 3.30E*03 0.00t+00 9.95842 1 135        4.5N43 4.73843 4.16443 7.98t+05 1.3M+06 0.00t40 4.44843                          **

Ct.1M 6. lit *05 1.01t+06 2.2M+05 0 00040 3.30t+0S 1.21846 3.05t43 C81M 6.518+44 1.710+05 1.16t +M 0.00t+00 9.5M+44 1.4H+M 4.18t43 .. C8 137 9.07t+05 8.29045 1.30f*06 0.00E+00 2.83846 1.ht 45 3.63t+03

• Io Ct.1M 6.330+02 8.60542 S.5M4 0.00t+00 6.23842 4.01t+01 2.7st42 M 1M 1.ht+40 9.444.M l.3M.ek 0.00t+00 8.638. k 5. m +13 5. m +04 comersion vectore ere in ette of erevyr Der ucinete aster.

1 UNT-005-014 Revision 0 - Attachment 6.$ (8 of 12) 128

e INHALATION PATWAY DOSES DUE TO RADIONUCLIDES OTl;ER THAN NOBLE CASES, R g AGt OROLPs talLO ( 3 Of 31 IUCLIM Ost.Aa post conviestem f aticas Sout Llytt 1.0ceY fure010 E10sti LLas4 41.LLI M.140 7.60t+N 6.60t+01 4.33t+03 0.00t+00 2.11841 1.76t +M 1.02t +0! k.141 1.cet.01 1.096.M 6.3M.03 0.00:40 9.67t M 2.92t+03 2.75t+0;' 0A 162 S.00t.02 3.60t.05 2.79t.03 0.00t40 ' 2.911.M 1.64t+03 2.74t+00 LA.140 6.66t+02 2.2H+02 7.llt*01 0.00t+00 0.00t+00 1.0M + M 2.26t+M e LA.142 1.30t+00.4.111 01 1.298 01 0.00E+t0 0.00t+00 6.70t+03 7.19t +M tt.141 3.92t-04 1.Mt*M 2.90t*03 0.00t+00 0.l H +03 5.64t +M l. MON Ct.143 3.Mt+02 1.9st+02 2.07t+01 0.00t+00 0.3eE41 1.1H +M 1.2W+M tt.144 6.m+M 2.12t*M 3.61t+M 0.00t+0D 1.17t+06 1.20t+07 3.0M+M Pa.143 1.05t+M l.lbt+03 9.14t+02 0.00t+00 3.000+03 6.33t+0S 9.73D N 164 S.968 02 ,1.0H 02 3.00t.01 0.00t+00 9.771 03 1.l?t*03 1.97t+02 ND.147 1.00t+M 0.73t+C3 6.01842 0.00t+00 4.01t+03 3.20t +M 0.21t+06 W.107 1.63t+01 9.MI+00 4.33t+00 0.00t 40 0.00t+00 4.11t+N 9.10E+04 up.239 4.Mt42 3.Mt+01 2.3H41 0.00t+00 9.73041 5.01t+N 6.40E+M terwerelen factere are in units of eremryt per utt/este ester.

                                    .,                                                                                                  s.

4 I UNT-005-014 Revision 0 , Attachment 6.5 (9 of 12) 129

                                                                                                                               /

INHALATION PATWAY DOSES DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R 1 AGE LA:UP thf MT t 1 Of 3 ) wcttet ont.As post convitslam f atttes Saut LIVtt f .DCD1 TWYR010 ElDuff LUNG tl LLI

                 . M3           0.00t+00 6.47t+02 6.4M+02 6.4M *02 6.4M +02 6.4M42 6.47t42 C 14         2.65t +M l.31t+03 5.3't+03 5.31t*03 5.31843 5,31t+03 1.31843 p.24         1.062*04 1.0st +N 1.06t +M 1.0M*M 1.0mE+M 1.06t +M 1.ht+M P 32         2.03t+06 1.12f+05 7.744+04 0.00t+00 0.00t*00 0.00t+00 1.618+04 tt 51        0.00t+00 0.00t 40 8.95t+01 5.75t 41 1.32t 41 1.20E+04 3.5M 42 eut 54       0.00t40 2.13t*04 4.W0t+03 0.09E*00 4.90t+03 1.00E*06 7.06t+03                             .

nu 54 0.00: 4 0 1.54t+00 2.21t 01 0.00t+00 1.10t40 1.25t +M 7.1M +04 Ft il 1.9M +M 1.17t+04 3.33t+03 0.00t+00 0.vot+00 8.69t+M 1.09t*03 FE 59 1.36t *M 2.35t+M 9.40t 43 0.00t+00 0.00E+00 s.02t 46 2.40t+04 to SS 0.00E 40 1.22t+03 1.62t+03 0.00t*00 0.00t40 7.7M +0S 1.114+04 CD 60 0.00t+00 8.023 43 1.10t +M 0.00t+00 0.00t+00 4.11t*06 3.1M+04

     .         .      0l43         3.39E45 2.044+04 1.16t+04 0.00t+00 0.00t*00 2.098+05 2.425+03 0145         2.39t+00 2.044 01 1.23t 01 9.pp M 0 0.00t+00 8.12t43 5.01E+M Cu 64       -0.00t+00 1.00t+C0 7.748 01 0.00t+00 3.90E+00 9.30t43 1.50t+M                     .

In45 1.93444 6.36E+M 3.11644 0.00t+00 3.$.H+04 6.47t45 S.14e44 Im49 5.39t 02 9.6M 02 7.1N 03 0.00E40 4.02E 02 1.47t+03 1.32* +M ri 83 0.00t+00 0.00t40 3.81t+02 0.00t+00 0.00t+00 0.00E+00 0.0ut*00 M*M 0.00t+00 0.00t+00 4.00t +02 0.00t+00 0.00t+00 0.00t+00 0.00t*00 et 05 0.00s40 0.00E+00 2.04441 0.00540 0.000+00 0.00E+00 0.00t+00 ' 00 06 0.00E*00 1.0ut+05 8.02t+04 0.00t+00 0.00t+00 0.00t+00 3.04t+03 .. De 08 0.00s+00 5.57t 42 2.0M+02 0.00t+00 0.00t+00 0.00t+00 3.395+02 00 09 0.00t40 3.21t+02 2.0M 42 0.00t*00 0.00t+00 0.000+00 6.02t+01 St 09 3.90t+05 0.00E+00 1.144+04 0.00E40 0.00t40 2.03E+06 6.40E+04

        ;             De 90        4.09t+07 0.00E*00 2.S9t +M 0.tJt 40 0.00E 40 1.12t47 1.31t+05
                       .,+.............................................................................           .

OR 91 9.56t+01 0.00E+GO 3.46t+00 0.00t+00 0.00t*00 5.26t+M 7.34E+04 OR 92 1.05t+01 0.00E+00 1.918*01 0.00140 0.008+00 2.30E+04 1.40E+05 Y.90 3.29t+03 0.00t+00 8.02t41 0.00E*00 0.00t+00 3.69t+05 1.06t+05 V 41m 4.OM 01 0.00840 1.39t 02 0.00t+00 0.00E+00 2.79843 2.35443 f.91 5.00t+05 0.00r+00 1.5 M +04 0.00E*00 0.00C40 2.45t+06 7.03t+04 T42 1.64441 0.00E 40 4.41t 01 0.00t+00 0.00t+00 2.4M44 1.27t+05 Corwersten f acters are in mits of eres/yr per wCl/cel4 meter. 1 ( l l UNT-005-014 Revision 0 Attachment 6.5 (10 of 12) l l 130 .

                                        ,n---                                            -                      w

                                                                                                                                                                                                                       '                                         t 1h'5tALATION PATWAY DOSES DUE TO RADIOh'UCLIDES OTHER THAN NOSLE GASES, R i

AGE Geoups latomi i 2 0F 3 ) ' i uucLIDI ORG4m post convtalltud f atteel I test Livtt f.uet frYtcl0 Eleutt LUNO Cl*LLI 1 l T.93 1.50E+02 0.00t.00 4.0?f+00 0.00t+00 0.00E 40 7.66t +M 1.6M 45 28 95 1.1H +05 2.79t+M 2.0M +04 0.00t+00 3.11t *M 1.75t+06 2.1M +06 te.97 1.$08 02 2. Set *01 1.17t+01 0.00t+00 2.59t41 1.10t*05 1.40t+05 me.95 1.5 M +M 6.4M*03 3 670t +03 0.00t+00 4.72t+03 4.79t+05 1.27t +M seo.99 0.008+00 1.6St+02 3.2M 41 0.00t+00 2.65t+02 1.35t*05 4.87t+M ' tc.99N 1.40t.03 2.00t.03 3.72t.02 0.00t+00 3.118 02 8.11142 2.0M+03

                                                                                                           ................................................u....'...........................

ft.101 6.518 05 8.Dt.05 8.128.M 0.00t+00 9.79t .M l.kt42 4.44t+02 Ru 103 2.02t+03 0.00t+00 6.HE*02 0.00t+00 4.24t+03 $.52t45 1.61t+04 80 105 1.22t+00 0.00t+00 4.10t.01 0.00t*00 8.99t.01 1.l?t *M 4.Gr+04 90 106 8.68t+M 0.00t+00 1.09t+04 0.00t*00 1.07t+05 1.16t+07 1.64t+05 AS.110M 9.90t 03 7.tM +03 5.00t+03 0.00t+00 1.09t +M 3.67t+06 3.30t+M It*1:SH 4.76t+03, 1.998+03 6.$8t+02 1.62t+03 0.00t+00 4.47t45 1.29t +M 13 127W i .67t +M 6.90t+03 2.07t+03 4.47t+03 3.7M44 1.311+06 2.73t+04 78 127 2.Dt +00 9.5M.01 4.098 01 h05t+00 4.868+00 1.0M +M 2.44t+k it.129N 1.41t+04 6.09t+03 2.Dt+03 5.4M43 3.1st+M 1.6et46 6.90t+04 ft.129 7.00t.02 3.4M.02 1.tet.02 6.7M.02 1.5841 3.00E+03 2.63t+04 ft.131N 1.07t+02 S.50841 3.63441 8.9M41 2.6H+02 1.99545 1.19t+05 ft.131 1.768*02 8.2M .05 $.00t.03 1.SEE.02 3.99t.02 2.0M+03 8.22E+03 ff.132 3.738+02 2.37542 1.7ef+0! 2.79t42 1.03643 3.40t+05 4.418+04 . 1 130 6.34043 1.38t+06 5.57543 1.60t+06 1.5M+06 - 0.00t+00 -1.99t+03 1 131 3.79t+06 4.44t+44 1,9et+04 1.48t+07 5.1444 0.00E+00 1.06t 43 1 132- 1.695+03 3.Ht+03 1.ht+03 1.60t+05 3.95E43 0.00s+00 1.90E43 1 133 1.3at+04 1.9N+06 5.60s 43 3.54t*06 2.Mt+04 0.00E+00 2.16t+03

                                                                                                .          I .1H        9.21842 1.00143 6.65842 4.45t+06 2.09t43 0.00t+00 1.2W+03
                                                                                                           ...........................................................................c....

3 135 3.tet43 7.6M43 2.775+03 6.tet45 8.47t43 0.00E+00 1.838 43 Cs.1M 3.968+05 7.0M+05 7.4M *06 0.00t+00 1.90E+05 7.97t+06 1.3M43 ts.136 4.8M +06 1.3M*05 S.29t+04 0.00t+00 S.644+04 1.10t+04 1.4M43 ca.137 S.49t+05 6.1M 05 4.Sk+04 0.00t+00 1.73845 7.tM+04 1.3M43 CS.134 $.05f+02 7.01842 3.9eE42 0.00t40 4.19842 6.M641 8.76t+02 e4 139 1.400 00 9.ht.M 4.30t.02 0.00E+00 5.935.M 5.95t+03 5.10E+04 Corwersten f acters are in mits of aren/yr per Wl/4 Ms wts. . l Attachment 6+5 (11 of 12) UNT-005-014 Revision 0 l 131 l l

INilALATION PATINAY DOSES DUE TO RADIONUCLIDES OTHER DIAN NO3LE GASES, R . g

                        &&E Gacups infest ( 3 07 3 )

mKLIDt ORW 0058 Carvitslam f actDal 6: Int Livtt i NY fpft010 ElDut? LUNG Cl.LLI u.140 u.141 1.60t+04 5.60t*01 2.90t+03 0.00t+00 1.34t+01 1.60t +M 3.kt +M I p.142 1.l?t.01 1.084.M 4.975 03 0.0nt+00 6. lot.M 2.97t+03 4.Mt+03 j 3.9et.02 3.30t.05 1.ht .03 0.00t+00 1.90 1 l'4*03 6.93t+02

                       ..................................+.....................t.05 L4 140                                                     ................. ......

L4 142 1.05t+02 2.00t+02 1.tSt+01 0.00t+00 0.00t*00 1.68t+05 8.4 N +M Ct.141 1.03t+00 3,77t 01 9.MI 02 0.006-00 0.00t+00 8.27t+03 $ .95t + 04 t.M +M 1.67t +M 1.99t +03 0.00t+00 1.171*05 2.iM*04

                      ................................................... 5.25t+03 tt.143 C4 144        2.Mt*M 3.19t     +02 1.Mt+02 2.21t+01 0.00t+00 1.64t+01 1.tM+05 4.97t+04 Nete:          1.40t +M 1.21t+M 1.7M +05 0.00e+00 1.34t+05 9.ht +M 1.44t+0$

l.24t*03 6.99t+02 0.00

                     .................................. ...........t+00       1.97t+03 4.3M+05 3.721*M N.144 12 147        4.79t.02 7.964+03        1.854 02 2.418 03 0.00t+00 4.72t.03 1.6tt+03 4.2M*03 W-187                       8. tM +03 S.00t+02 0.00t+00 3.15t+03 3.2.f+05 3.12t+04 t.30t+0i 9.02t+00 3.12t+00 0.00            0.00t+b0 3.96t+M 3.5M*M
                     ..............................................t+00 up 89                                               ..................................

3.71 +02 3.32 +01

1. set 41 0.00s+00 6.621+01 S.958+M 2.49t+04

• i cowereton vectors er. in mite ., erwyr per u:veele e.ter.

r I - l I . UNT-005-014 Revision 0 Attachment 6.5 (12 of 12) 132

e CROUND - h.ANE DEPOSITION PATWAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 1 AGE GROUP: ALL ( 1 08 3 ) NJCLIM Otf.At Oost CcwVittl0N # Attoes a

1. Scot scle m3 0.008+00 0.00s+00 C 16 0.00t+00 0.00t+00

         ,                                       hA*24         1.19t+07 1.39t+07 P 32          0.00t+00 0.00t+00 Ct 51         4.M1+M S. lit +M lw 54         1.39t*09 1.6M +09 em le         9.C3t +M     1.07t+M Ft il         0.00t+00 0.00t+00 ft $9         2.73t+08 3.21t+08 Co 58         3.79t+08 4.44t+08                                    s Co 60         2.15t*10 2.lM *10 al*63         0.00t*00 0.00t+00 st*65         2.97t +M 3.4St+M
                         ,                       CU M          6.07t+05     6. bet +M
                                                  !s*H         7.47t+08 8.$9t+0B tu H         0.00f*00 0.00t+00 te 03        4.87t+03 f. gee +03 Be N          2.03t+05 2.34t+05 34 85          0.000+00 0.00t+00 90 06         8.99t+06 1.03f+07 08 08         3.31t+04 3.7m+06                                                 ,

Re 09 1.230+05 1.40E+05 ga W 2.140+04 2.l1E+46 3R 90 0.00E+00 0.00t+w0 en*91 2.15t+05 2.51t+06 se 92 7.77t+05 8.Of+05 f*90 4.49t+03 1.31t+01 T.91st 1.00t+05 1.14t+05 T 91 1.07t+06 1.21t+06

• 1 92 ' 1.000+05 2.14E+05 Carwereien f acters are in mits of eenre unter eremryr per Wl/sec.

                                                             .          g UNT-005-014 Revision O'                                                                  Attachment 6.6 (1 of 3) 133

I CROUND - PLANE DEPOSITION PATINAY DOSE FACTORS DUE TO RADIONUCLIDES.0THER THAN NOBLE GASES, Rg A M GROUP ALL ( 2 08 3 ) esJCLIM 00GAe D0tt totYttllom f attoks T. DODY SEla iaf3 1.834 +M 2.$18 +M 28 M 2.6St+08 2.kt*08 , 28 97 ' 2.960 +M 3.66t+06 me 99 1.37t+08 1.61t+08 eso 99 3.99t+06 4.6M+M tt 99M 1.kt*05 2.11t +M ft 101 2.Mt 46 2.2R i% , au.103 1.0et 08 1.tM +0e tu 1M 6.3M +M 7.21t +M RU 1M 6.22teet 8.07t*06

• A4 110M 3.64t+ M 4.010 49 ft 129st 1.$5t+46 2.1M+06
• 18 12791 9.iM+04 1.00t45 Yt.127 2.9eE43 3.28R+03 .

tI 129ee 1.90s47 2.31t47

                                               . ft 129         2.63t+04 3.19846 f t.131el      4.030+46 9.64046 ft*131        2.93t+04 3.4M+07 it 132        4.238*06 4.90t+06 1 130         S.51t+46 6.NE+06 l.131         1.73t47 2.00547 l.132         1.250+46 1.440+46 1 133         2.4M+46 2.tet+46 1 1M         4.47t+05 S.30t+05 1 135        2.5M+46 2.95f+06 Cs 1M         6.0M+09 4.00049                                                            ,

C8*136 1.510+48 1.718+48 . C8 137 1.03t+10 1.20R*10 C6 138 3.59E*05 4.1N+05 SA*139 1.060+05 1.19t+05

• Comerslen f acters seg in wilts of emere meter wearyr per dl/sec.

UNT-005-014 Revision 0 , Attachment 6.6 (2 of 3) 134 -

                                                                                                                                                              )

t

                 . . _ _ _ _ _ _ _ _ _                   ._ ~ ~ _                ... _ _ _                                   _ _ . _ _ . _ . _ _ _ _ _ _ _ _ . . . _

1 GROUND - PLANE DEPOSITION PATHWAY DOSE PACTOR$.DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g AM EdMi ALL ( 3 Of 3 ) i IWCLIM tf' . tut CatWit$10m f atitel .

1. 037 Mle  ;

M 160 2.0H +07 f.3St+07 M.141- 4.17t ek 4.798 +M M 142 4.49t +M l.110+M L4 140 1.98t+0? 2.30f+0? LA 162 F.60t +M 9.11t+M Ct.141 1.371*07 1.54t*07 Ct.143 2.31t+M i6M+M Ct+144 6.Mt+0F 8.06t*07 Pe.143 0.00t+00 0.00t+00 Pt.144 1.83t+03 2.iit+03 m.147 ' 8.Mt+M 1.01t+07 , I W.187- 2.3M +06 2.7N +06

                  +                                                         WP.239              1.71E+06 1.900+06
                                       .          temerolen factees are in mits of sewee seterwearyr por Wl/sec.

4. L 4

                 ' UNT-005-014 Revision 0                                                                                                                Attachment 6.6 (3'of 3) 135

4 COW's MILK PATHWAY DOSE TACTORS DUE TO j RADIONUCLIDES OTHER THAN NOBLE GASES,.T g,  ; i AGE Getup 40W T ( 1 07 3 )

                                                                                                                                           ;e estilet                                                caras 00st ta vtetion fattool 00st             Livte                 f .t@t    1Nfeel0 tteelt      Lune      Cl*LLI h3              0.00t40 7.63t+02 7. m +02 7. m *02 7. m +02 7.631+02 7.63442 C+14            2.m+0s 5.2M+07 S.27t+0? 1.27547 S.2M+0? S 27t+07 1.27t*07 mA 24            2.ut +M 2.44t

• M 2.Mt *M 2.64t +06 2.46t+46 2.44t+06 2.64t*M P 32 1.7'.t*10 1.064+09 6.61t*08 0.00t M 0.00t*00 0.008 40 1.92849 te 51 0.00E*00 0.00t+00 d.ht +06 1.7tt+W 6.30843 3.79t+04 7.19t *M Ma 54 0.00t+00 S.stido 1.61t*06 0.00t+00 2.50t+06 0.00t+00 2.58t*07 en 54 0.001 00 4.158 03 7.3et.M 0.00t+00 5.27t 03 0.00E+00 1.3M*01

 ,                                  Ft 55           2.51t+07 1.76447 4.05t+06 0.00t+00 0. bot *00 9.60t+06 9.95t+M Ft 59 '         2.97t +0? 6.90t+07 2.60t+07 0.00t+00 0.00t+00 1.99t+07 2.33t*08 Co.50           P JOE +00 4.71546 1.06847 0.00t40 0.00t40 0.00t 40 9.S$t47 C0 40           0.00e+0C 1.ht47 3.247 0.00t+00 0.001 40 0.00t+00 3.00t 48 el 63            6.73t+09 4.46t+08 2.24t+4B 0.00E+00 0.000+00 0.00E*00 9.73t+07 0145      .

3.708 01 4.0tt*02 2.19t 02 0.00E+00 0.00t+00 0.00f 40 - 1.2M+00 to-M 0.000+00 2.3eI+04 1.1M +04 *0.000+00 6.01t+46 0.00t+00 2.03t+M ' , te el 1.37t+09 4.37t49 1.97t +09 0.00140 2.92t+09 0.00t+00 2.75e+09

                                   ............................s...................................................                                            .

tu 69 2.get.12 6.008 12 2.70E.13 0.00l+00 2.608 12 0.00t+00 6.018 13 08 03 0.00t+40 0.00E 40 1.17E.02 0. gee 40 0.00B+00 0.00840 1.eGE*02 M*M 0.0eI40 0.00t+00 i.938.H 0.00E+40 0.00t+00 0.00E40 1.lM

• 29 M 05 - 0.00E+00 0.00e+00 0.000+00 0.00040 0.00t+00 0.000+00 0.00t+00 00 06 0.00B+00 2.998+09 1.210+09 0.00E+00 0.00E40 0.000 40 S.1M +4I he*00 0.00140 0.00t+00 0.00t+40 0.00E40 0.00I 40 0.000+00-0.0st*40 00 89 0.006 00 0.00E40 0.00E+00 0.00E+00 0.000+00 0.001 40 0.00t+00 08.M ' 1.45t+09 0.0et+00 4.14t47 0.00e+00 0.00I 40 0.00E+M 2.33t+0S 08 90 4.eN+10 0.00E40 1.1SE*10 0.00e 40 0. tee +40 0.00t+00 1.3St+49 se 91 2.08t+M 0.00E*00 1.17t*03 0.teI+00 0.00040 0.00E+00 1.30E+05 08 92 4.00t.01 0.00E+00 2.118 02 0.00E+00 0.00g*40 0.00t+00 9.48E40 t*90 7.tet+01 0.See+00 1.0ge+e0 0.0se+e0 0.0es40 0.0es40 7.51045

                                   ...... .......................+ ...............................................

V 9tm 5.988 20 0.00t+00 2.3M

• 21 0.00E*40 0.00E+e0 0.00E*e0 1.76t 19 V41 0.99E+03 0.00E+00 2.30842 0.00t*00 0.00540 0.0eE+00 4.73846

                                 - V 92             S. net.05 0.00E+00 1.63t N 0.00e+00 0.00t+00 0.00t+00 9.77E 01 Converslen f actere see in mite of todere seter erea/yr per Wl/sec for all macltest eacept #*3 eMan le in units of arearyr per Wl/Mic ester.

UNT-005-014 Revision 0 ' Attachment 6.7 (1 of 12) 136 _ - _ _.- _ _ _- .. _ _ _ _ _ _ _ _ _ . _ - _ ~ , . _ _ . . - ____

O COW s MILK PATHWAY DOSE h' ACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GA3ES, R i e AGE Ge p : 4DULT ( 2 Of 3 ) l l

                                               .                                                                                                                                I muCLIDI                       -                       Op6As 0084 Cturviellom FACTORE                                               1 tout        LIWtt                 t.00DY               TNTt010 Eiget? LUuG    Gl*LLI T 93                 2.2M 01 0.00t+00 6.1M 03 0.00t+00 0.00t+00 0.00t+00 7.00t+03 ft M                 9.4M42 3.0M+02 2.05t+02 0.00t+00 4.7M +02 0.00t 40 9.59t +M 24 97                4.3M 01 8.748 02 4.006 02 0.00840 1.3M 01 0.00t 40 2.71t +M as M                 B.Mt*04 4.He+M 2.4M+M 0.00t+00 4.54444 0.00s+00 2.79t+0s ND 99                0.00t*00 2.44t*07 4J1t+06 0.00t+00 5.61E+07 0.00t+00 $.74t+07 ft 9eu               3.3M+00 9.34t+00 1.20t+02 0.00t+00 ? .4M +02 4.60t+00 S .5 M *03 M 101                0.006+00 0.00t*00 0.001+00 0.008+00 0.008+00 0.00t 40 0.00t+00 RU 1bl               1.0M*03 0.00t+00 4.39t*02 0.00t+00 3.09t *03 0.00f*00 1.19t +M nu 1M                8.54 M 0.00040 3.382 M 0.00t+00 1.118 02 0.000+00 S.248 01 hu 106               2.04t+04 0.00t 40 2.54E+03 0.00E*00 3.94t+04 0.00t+0c 1.3M+C6
                          .               60'11 tut             5.82 47 $.39E 47 3.20t+07 0.00t+00 1.06t+08 0.00E+00 2.20t+10
                        .                 Tt *125st             1.63E+07 5.90s+06 2.10e+06 4.90s 4 6 4.W47 0.00t+00 6.505+07 ff 12Mi              4.58E 47 1.Mt47 $.50t+06 1.1M +07 1.064+4e 0.00t+00 1.544+0s TE*127                6.lM+02 2.34E+02 1.41642 4.ht+02 2.Ht43 0.00t+00 5.1M+04 78 1294              4.02t47 2.25047 9.5M+06 ' 2.07E47 2.51t+00 0.00t+00 3.03t+08                                           '

T5 129 2. tat *10 1.948 10 4.tet=11 2.17t 10 1.19E 09 0.00E*00 2.13t*10 ff = 131st 3.61t+05 1.7M+0! 1.4M+05 2.00E+05 1.79t+06 0.00840 1.7M+07 , , it.131 3,60s.33 1.51t.33 1.148 33 2.H4 33 1. Set 32 0.00t+00 5.10t M 78 132 2.40E+06 1.SM+46 1.46t+06 1.73E+46 1.$0t+07 0.00t+00 7.35t+07 1 130 4.20t45 1.Mt+06 4.09t+05 1.05t+08 1.93E+46 0.00t+00 1.07846 . l'131 2.984+48 4.23E+4B 2. W +08 1.Me*11 7.368+08 0.00E*00 1.13t+08 - 12132 1.ME 01 4.395 01 1.54t 01 1.S4441 7.00E 01 0.00t40 8.3St 02 l'133, 3.8M+46 6.73t+e6 2.05tfe6 9.0st+es 1.1M+07 0.00e+00 4.05t+e6 la1M 2.0at.12 5.485 12 1.teta12 9.498 11 8.71t*12 0.00E 40 4.7M all 18135 1.20t+44 3.3eE+04 1.Mt+04 2.22E+06 5.30t*04 0.00t+00 3.80E +M C8 *1M l.6M49 1.3M+10 1.10t+10 0.00040 4.3M49 1.4M+09 2.3St+0s ts.136 2.W a8 1.064+09 7.48t+08 0.00E+00 S.70E*08 7.93t+07 1.18t+08 CS*137 7.30049 1.01t*10 6.614 49 0.00t+00 3. W +09 1.14449 1.95t+08 C8 138 -9.Mt M 1.795 23 8.0M.M 0.00E+40 1.318 23 1.30E* M 7.63t*29 M 139 4. W 08 3.1M*11 1.29t 09 0.000+00 2.Mt*11 1.79E*11 7.ht 08 Convereien facters are in mits of eSaore aster aremryr por dt/sec for ett maclides oncept s.3 unten le in mite of aremryr per Wl/sels ester. ' UNT-005-014 Revision 0 Attachment 6.7 (2 of 12) 137 .

             . _ - ,        .,_..,,..v._,         , . , . .          ,       y.,___., . . , ., _ , , .y,

i + CCM'sMILKPATHWAYDOSEh'ACTORSDUETO RADIONUCLIDES OTHER THAN NOBLE GASES, Rg, Act encur Acutt ( 3 op 3 ) NVCLIN 08GAu Dost towVltt!0u 'Attomt g 00mt Livtt 7.0cet twYR0tD E10sti LuuG tl*LLI bA 140 2.69t+07 3.34t+04 1.76t+06 0.00t+00 1.1M+04 1.9M +04 $.$3t+07 BA*141 0.00t+00 0.00t+00 0.00t+00 0.00E *00 0.00t+00 0.00t+00 0.00t+00 64 142 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 LA 140 4. lit @ 2.27t+00 6.018 01 0.00t+00 0.00t.00 0.00t+00 1.67t+0S LA*142 1.htt *11 8.4$t.12 2.10t*12 0.00t+00 0.00t+% 0.00t*00 6.1?t 06 ' tt.141 -4.44t+03 3.20t+03 3.7M+02 0.00t*00 1.5 M *03 0.00t*00 1.25t*07 Ct 143 4.iM +01 3.07t+04 3.40t+00 0.00t*00 1.35t+01 0.0Je+00 1.15t+06

                        ~

CE*144 3.58t *M 1.50t *M 1.9M+M 0.00t+00 8.87t +M 0.00t+00 1.21t+08 M 143 1. Set *02, 6.33t+01 7.83t+00 0.00t*00 3.66t+01 0.00E+00 6.92t+M M 144 0.00t+00 0.00t+00 0.OnE+00 0.00t+00 0.00t+00 0.00E+00 0.00t+00 I up.147 9.4M +01 1. Opt +*4 6.51t+00 0.90t+00 6.36t+01 0.00t+00 S .22t +M W 107 6.11t+33 S.4M*03 1.90t*03 0.00t+00 0.00E*00 0.00t+00 1.70t+06 NP 239 4.60t+01 4.52t+00 2.49t+00 0.00t+00 1.41t+01 0.00t+00 9.27t+M - - 9 Camerslen f actors are in mits of essere aster ereWyr per utt/sec for ett nuell4se eacept NC dish is in mite af aremfyr per W:l/sels ester. UNT-005-014 Revision 0 . Attachment 6.7 (3 of 12) , 138 i

COW's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R g, , AGE 000#: tita i 1 of 3 ) eUCLlDi ce6As DOSI Corvtttt0N FAC10pl Doet LIVtt 1.0001 fufD010 E!Dett LueG Gl*LLI h3 0.00t*00 9.kt*02 9.kt+02 9.Mt +02 9.ht 42 9.94t*02 9.ht *02 C+14 4.tM *08 9.72t*07 9.77t* / 9.72t+07 6.72847 9.12447 9.72t+07 h4 24 4.2M*06 4.2M+N 4.2e c 4 4.2M+06 4.2M4 4.2M.06 4.2M4 P 32- 3.15t+10 1.95t +M 1.22t*09 0.00t+00 0.00t+00 0.01+00 2.65t 99 . Ca lt . 0.00t*00 0.00E+00 4 99t+04 2.77t +M 1.09t +M 7.1H+M 8.39t+06 sen 64 0.00t+00 1.40t47 2.70t +W 0.00t+00 6.10t*06 0.00t+00 2.87t47

• Iow 54 0.00t+00 '.3M 03 't.318 03 0.00t+00 9.31E 03 0.00t*00 4.kt 01

                      -  FE 55                4.4H47 3.1M+07 7.3M+06 0.00t+00 0.00t*00 2.00t*07 1.37t 47 ft $9                $.18t+07 1.21148 4.67147 0.00E+00 0.00t+00 3.81t*07 2.4M+08 Co 54                0.00t+00 7.M4+06 1.83t 47 0.000+00 0.00t+00 0.00t +'JO 1.09t+08 C0 60                0.00t+00 2.70t+07 6.2M +07 0.00t*00 0.00E+00 0.00t+00 3.621 08
           ,             al 63                1.18t+10 8.3H OS 4.01t+04 0.00t+00 0.00t+00 0.00t*00 1.33E+08
             .                                                                                                                   a ul 65 -              6.775 01 8.6St.'02 3.ht 02 0.00t+00 0.00t+00 0.00t+00 4.69t*00 CU 64                0.00t+00 4.25t+M 2.0Jt+04 0.00t+00 1.07t+05 0.00t+00 3.29t*06 2e 65                2.11E+09 7.32t+09 3.41t+09 0.00t+00 4,'9149 0.00t*00 3.10t*09
                         .................~...................................                                 ..........................

In 69 , 3.058 12 7.348,12 l.1H 13 0.00E+00 4.79t*12 0.00t+00 1.3H 11 M 83 0.008+00 0.00E+00 2.158+02 0.000+00 0.008+00 0.008+00 0.00t 40 4A M 0.00t+00 0.00E+00 3.4H 34 0.00t+00 0.00t 40 0.00t+00 0.00t+00 M 85 0.00E*00 0.00t40 0.00540 0.00F+00 0.00t+00 0.00t+00 0.00E+00 00 06 - 0.00t+00 4.73t+09 2.3at+09 0.00t+00 0.00t+00 0.00E+00 7.00t+08 he 88 0.00t+00 0.00t+00 0.00t 40 0.D* BOO 0.00E*00 0.00t+00 0.00t@ Be 89 0. tut +00 0.00s+00 0.00s 40 0.00P+00 0.00t+00 0.00t+00 0.00t+00 en 09 2.67t*09 0.00f+00 7. Mt 47 0.00t+00 0.00t 40 0.00t*00 3.19t+00 OR 90 6.41t+10 0.00t+00 1.G *10 0.000+00 0.00E+00 0.00t*00 1.tM*09 M 91 5,31t+04 0.00E49 2.11t+03 0.00t+00 . 000+00 0.00E+00 2.41845 M 92 8.94+01 0.00840 3.818 02 0.00t+00 0.000+00 0.00E*00 2.20t+01 T 90 1.30f+02 0.00E+00 3.51E*00 0.00t+00 0.00E+00 0.00t*00 1.07t+06 f 91st 1.10t.19 0.00t+00 4.19E 21 0.00E+00 0.00t+00 0.00t+00 3.175 18 f.91 1.95+04 0.00t*00 4.34t+02 0.00t+00 0.00E+00 0.00t+00 6.4M +06 T 92 1.038 M 0.000*00 2.908 06 0.00t+00 0.00E+00 0.00t 40 2.03E+00 Camerslen f actors are in mits of emere meter areWyr per df/see for ELL mellese eacept B 3 iAlch is in mits of aren'yr per utt/ sele ester.

     - UNT-005-014 Revision 0                                                                                                  Attachment 6.7 (4 of 12) 139

COW's MILK PATHWAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R g 4r4 HCUh Tits ( 2 0F 3 ) sMCLlDI Det.4a DOSI Couvttsl0m f 4ttons tout LIVlt f.t(et TNYkotD ElDat? Lum 4 Cl LLI f.93 4.12t 01 0.00t 40 1.1M42 0.00E40 0.00t40 0.00t+00 1.2M.04 28 95 1.65f+03 S.20t+02 3.50t 42 0,00t+00 7.65t +02 0.00t+00 1.20t M I 20*97 7.001 01 1.5et 01 7.195 02 0.00t*00 2.3M 01 0.00t40 4.22t+04 h6 95 1.41t+05 7.81t*04 4.30t+04 0.00t+00 7.57t+04 0.00t+00 3.34t 48 no 99 0.00t+00 4.47t+0F It.$3t *06 0.00t+00 1.02t+08 0.00t+00 8.01t+07 tC 99u 5.7M *00 1.61841 2.00t+02 0.00t+00 2. m +02 8.92t+00 1.05t+04 ft.101 0.00t+00 0.00E40 0.00t+00 0.00t+00 0.00t*00 0.0M+a0 0.00t+00 au 103 1.81843 0.00t40 7.74t*02 0.00t40 6.ME*03 0.00t .0 1.ltt+05 hu 105 1.54t 03 0.00E*00 6.07t 04 0.00t+00 1.94 02 0.00t+00 1.2M40 av.106 2.09144 0.00t+00 4.734+03 0.00t 40 7.244+04 0.00t+00 1. tot +06 44 110N 9.63E+07 9.11t+07 5.544 47 0.00t+00 1.7d*00 0.00E+00 2.5M+10 ft 125M 3.00E47 1.00t+07 4.02t+M 8.39E*06 0.00t 40 0.00l+r" 8.tM+07 ft 12FN 8.44t*J7 2.99047 1.00147 2.0tt*C7 3.42t+08 0.00t+00 2.10t+08 ft 127 1.21t+03 4.29t+02 2. ult +02 8.3M*02 4.90E*03 0,00t*00 9.34t+M ft 129u 1.10f+08 4.09t 47 1.74 47 3.lH47 4.61t+08 0.00t+00 4.13t 4 8 ft*129 5.20t.10 .1.Mt*10 1.1M 10 3.71t*10 2.1st49 0.00f+00 2.848 09 , it 131n 6.l?t+05 3.15t45 2.00+05 4.7445 3.29e46 0.00s*00 2.53847

                              'ft.131          6.lat 33 2.718 33 2.06t.33 3.0M

• 23 2.tet 32 0.00t 40 5.40t
• H

                            ' ff=132           4.29t+06 2.7M+06 2.54t+06 2.BM+06 2.61847 G.00t+0D 8.61847
             ..                 I.130          7.30t45 2.148 46 8.5M +d5 1.74+08 3.29t+06 0.00t+00 1.H4+06

• l=131 S.37t+08 7.5M +08 4.0W +08 2.19t*11 1.29t+09 0.00t+00 1.498 08 1 132 2.91841 7.638 01 2.74441 2.lM41 1.20t+00 0.00E+00 3.3M*01 1*133 7.0M+06 1.20t47 3.ME*06 1.67t+09 2.10t+07 0.00t+00 9.0?t+06 1 134 3.582 12 9.508 12. 3.418 12 1.50t*10 1.50t*11 0.00t+00 1.258 13 1 135 2.38t+04 5.8M+M 2.10t+04 3.7st+06 9.27t+04 0.00t+00 6.51t+04 Cta134 9.83t*09 2.310+10 1.07t+10 0.00840 7.34049 2.00t+09 2.87t+08 C8 1M 4.4M+08 1.70t+09 1.10t+09 0.00t40 9.6aE+08 1.51t+08 1.4M +08 1.340+10 1.7st+10 6.20t+09 0.00t+00 4.06t+09 2.3M +09 2., A+08 C8 137 C8 138 1.Nt*23 3.1M 23 1.175 23 0.00t40 2.338 23 2.71444 .1.4M 36 84*139 8.111att 5.758 11 2.30E 09 0.00t+00 S.45 11 3.94 11 7.398 07 Corwesten tectors are in mits of swore meter *areWyr per uC1/sec for all nuctlelse eacept 5*3 edilon is in mita of erem/yr per st/cels seter.

UNT-005-014 Revisio. O' Attachinent b.7 (5 of 12) 140

COW's MILK PATHWAY DOSE TAC' TORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rg , AGE SM MPs felt ( ) Of 3 ) . eMCLIDI On&As post C0edR$10u iAct0DS 00mt Livit 1.0001 TWYt010 LIDett Luut Cl+LLI Da.140 4.Mt +07 8 95t+N 3.1M W 0.00t+00 2.0N+04 4.00t+N 7.40E+07 l p.141 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.00E+00 0.00t*00 0.00t+00 M 142 0.00E*00 0.00t+00 0.00t+03 0.00t+00 0.00t+00 0.00t+00 0.00t+00

                      . LA 140      8.10t+00 3.90f+00 1.06t +00 0.00t+00 0.00t+00 0.00t @ 2.29t+M LA.142      3.35t.11 1.4M.11 3.718 12 0.00t*00 0.00t+00 0.00t+00 4.$H 07 CE*141      8.00t+03 5.9M+03 6.81t+02 0.00t+00 2.79t*03 0.00t*00 1.70t*07                                       .

Ct.143 7.64t+01 S .568 +k 6.21t+00 0.00t+00 2.49t*01 0.00t+00 1.67t+06 Ct.144 - 6.$0t *M 2.72t+M 3.54f +N 0.00t+00 1.63E+M 0.00E*00 1.66t+08 Pe=14) 2.90t*02 1.1M+02 1.44t+01 0.00E*00 6.7M+01 0.00t+00 9.54t *M Pe 16 0.00t*00 0.00E+10 0.00t+00 0.006+00 0.000+00 0 00t*00 0.00t*00 ND*147 1.01t*02 1.97t+02 1.10E*01 0.0W*00 1.16t*02 0.00E*00 7.11t *M W 187 1.1M +N 9.71t+03' 3.60t+03 0.00t*00 0.00E*00 0.00t*00 2.63t+0t OP'2M 8.70t+01 8.20t+00 4.60t+00 '0.00t+00 2.60t+01 0.00t+00 1.338 06 Converslen facters are in witte of somre esteraeren/yr por uCll'eE for all facileios oncept 0 3 dish is in mite of eren/yf per dl/tels wter. l l i l l-A UNT-00! 414 Revision 0 Attachment 6.7 (6 of 12) 141

                                                                                                                                   )

COW's MILK PATWAY DOSE hACTORS DUE TO RADIONUCLIDES OTHER TRAN'NOBl.E CASES, R g, 4GE GecuPt C#1LO I 1 Of 3 ) NJCLIDil DeGAa 0088 CowVittl0h f atical DONE LIVlt t 0007 fuYS010 Elbuti LUuG $1.LLI

                                                                                ~

N3 0.00t+00 1.57143 .1.571+03 1.571+03 1.lTE+03 1.l?t43 1.57143 t 14 1.19t*09 3. m +06 2. M *08 2.39t +00 2. M *06 2. m *06 2.39t+06 hA

• N $.Mt*06 8.0$147 8.05t +N 8.M4 M $.0$4*06 8 Ml+06 8.0$4 +M 9 32 7.70t*10 3.kt 49 3.00t+09 0.00t.00 0.00t+00 0.00t*00 2.15t*09

                          , CR 51         0.00t+00 0.00t*00 1.024 05 S .65t +M 1.54t *N 1.03t+05 5.40t +M sin 54     -

0.006 40 2.10847 5.59t*06 0.00t*00 l .00E +M 0.00t+00 1.7M +07 sis 56 0.00t+00 1.20E 02 2.90ta03 0.00f*00 1.514 02 0.00t+00 1.ht e Ft 15 1.071+0e S.93847 1.04E+07 0.00t+00 0.008+00 3.35647 1.10t+07 fI*19 1.20s+08 1.958+08 9.69647 0.00E+00 0.00t*00 5.64447 2.03t+06 CD S8 0.00t+00 1.21847 3.71t+07 0.00t*00 0.00t+00 0.00t+00 7.07t+07 Co 60 0.00t+00 4.33t*07 1.!71+08 0.008+00 0.008+00 0.00t+00 2.39E+08 mI+63 2.968+10 1. m +09 1.04E+09 0.00s+00 0.00t+00 0.00t+00 1.071+08 c

                            ..................................................e.............................

el*65 1.ht +00 1.SM 01 9.10E 02 0.00t+00 0.00t+00 0.054+00' 1.91t41 CV M 0.00t+00 7.46t*04 4.51t+M 0.000+00 1.00E*05 0.005*00 3.50t+06 In 65 4.13t+09 1.10t*10 6.05t+09 0.00t+00 6.Mt49 0.00E*00 1.93t+09 tu M 9.475 12' 1.375 11 1.hta12 0.00t+00 8.30t=12 0.00t+00 8.625 10 et 83 0.00s+00 0.00s+00 5.ast 02 0.Det+00 0.00t<00 0.00s+00 0.00s*00 Os rN 0.tet+00 0.00s+00 7.01t:M 0.00s*00 0.0n0+00 0.00s+00 0.00E+00

                            ..............+.................................................................

On 05 0.08t+00 0.00t+00 0.00t w0 0.00f 40 0.00t+00 0.00t+00 0.00t+00 De M 0.tet+00 8.TM*09 5.395+09 0.00s+00 0.00s+00 0.00E+00 5.He+08 04 M 0.000+00 0.00t+00 0.00E*06 0.00t+00 0.00t+00 0.00t+00 0.00t+00 he 89 0.See+00 0.00s+00 0.00s+00 0.008+00 0.00s+00 0.00s+00 0.001+00 04 M 6.elt+09 0.00t+00 1.00t*08 0.00t+00 0.00E 40 0.00t+00 2. Set +08 St 90 1.13t+11 0.00t+00 2.03t+10 0.00t+00 0.00t+00 0.00t+00 1.51849 Oa 91 1.30t+05 0.008 40 4.9?t+03 0.00t+00 0.00t*00 0.00t+00 2.00t+0$ te.92 2.10t+00 0.00t+00 8.758 02 0.000+00 0.00E+00 0.00t+00 4.13t+01 Y 90 3.23e+02 0.00E+00 8.63 40 0.tes*00 0.084+00 0.00s+00 9.17145 t*tta 2.6et.19 0.00s+00 9.748*21 0.00s+00 0.00s+00 0.00s+00 5.248+16 1 91 3.90f +M 0.0040 1.04E43 0.00s+00 0.00s 4 0 0.00E+00 5.20s+06

 +                          t*tt          2.55t k 0.00t to 7.248 06 0.00t+00 0.00t+00 0.00t+00 7.31t+00                           ,

Camerelen facters are in mits of somre meter areWyr per wC1/ses for ett . ruclides eacept 0 3 iAlch is in mits of ureWyr per utt/cdic meter. UNT-005-014 Revision 0 Attachment 6.7 (7 of 12) 142

e e COWS MILK PATWAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER TIUS NOBLE GASES, R g , Mit th0Jh CulLO ( 2 Of 3 ) NUCLIDit cata Dost couvttslam fettets DONE LIVit f.00DY TNYt0!D KIDutt LUNG Gl*LLI

           ,                143           1.01t+00 0.00t+00 2.7et 02 0.00t+00 0.00t+00 0.00t+00 1.51t+04 2t M          3.tM +03 8.4M *02 7.50t 42 0.00t40 1.21t+03 0.00t*00 8.79t+05 2047          1.9M +00 2.778 01 1.kt 01 0.00t+00 3.9et 01 0.00t+00 4.20t*04 us 95         3.10t45 1.24t*05 4.ht+04 0.00f+00 1.1M 45 0.00t +00 2.29t +08 N0 99         0.00t+00 8.14t*07 2.01147 0.00t+00 1.74t+08 0.00t*00 6.7M 47 it 99M        1.12t+01 2.59t+01 4.29t+02 0.00t+00 3.7H +02 1.32t*01 1.4 M +04 1C:101        0.00s+00 0.00s+00 0.00s+00 0.00t+00 0.00t+00 0.00t+00 0.001+00 80 103        4.20t+03 0.00t+00 1.6H 43 0.00t*00 1.00t*04 0.00t+00 1.11t*05 00 105        3.htt 03 0.00t*00 1.39t 03 0.00t 4 0 3.Mt 02 0.00t+00 2.49t+00 Au 1M         9.24t+04 0.00t+00 1.1H +M 0.00t*00 1.25t+05 0.00t+00 1.44t +M A411mt        2. Opt +08 .1.41t+00 1.1M +48 0.00t+00 2.6M*08 0.00t+00 1.68t*10 tt.129m       7.3N+07 2.00t47 9.ht+06 2.0M +07 0.00t+00 0.00t+00 7.1M 47 ft 1t?W       t.0ef*00 S.60147 2.47t47 4.9M47 5.9M 08 0.00t+00                   1. tat *0s .

ft.1t? 2.9et 4 3 8.03t+02 6.308 4 2 2.06443 8.47t+03 0.00t*00 1.iM+05

                          ' tt.1Mu        2.71t*00 7. lee +07 4.21847 4.7M47 7.9M+0e 0.00t+00 3.31448                                                                   .
                  .         ft.itt        1.ast M 3.lat.10 3.04410 9.1M*10 3.?H+09 0.00t+00 7.90f 08                                                            ,
                          .ft.131m       .1.60t+06 5.5M +05 S.0Et+05 1.14t+06 5.3M+06 0.00t*00 2.24t+07 ft 131        1.63E 32 4.9M 33 4.814 33 1.ht*32 4.09t.32 0.00t+00 8.4M 32 ft.132        1.0M47 ' 4.lM*06 S.45 +06 4.Me46 4. tit +07 0.00t+00 4.5M+0?

1 130 .1.7M *06 3.49t+06 1.00e+46 3.84048 5.ta+46 0.00E+00 1.63f+06 1*131 1.30e+09 1.31t+09 7.4M48 4.338*11 2.1M+09 0.000+00 1.1M+0s 1 132 4.088 01 1.2M40 9.830 01 S.BM+01 1.Mt+00 0.00t+00 1.49t+00

                        ' l 133           1.73s+07 2.1547 8.eas46 3.94t+09 3.54447 0.00t+00 8.54f+06
         .                  l*1M          8.4at.11 1.let.11 7.tM *12 3.6Br*10 2.418 11 0.00t40 1.kt 11 l'135         $.40844 9.78t+06 4.60t+06 8.61t+e6 1.4M +05 0.00t+00 7.40t+M                                                            .

C8 1M 2.36t+10 3.73t*10 7.Et 4 9 0.00t+00 1.1M+10 4.1M+M 2.00t 48 C8+136 1.01t+09 2.84t+09 1.Nf+09 0.00t+00 1.48t+09 2.ttt+0e 9.7M*07 . 08 137 ' 3.230+10 3.0M+10 4.lM+09 0.00t+00 1.01t+10 3.6at+09 1.93t+0s

• C8 138 3.90E 23 S.5M 23 3.518 D 0.00t+00 3.08t*23 4.198 H 2.lM
• 23 W1M 2.018 07 1.0M.10 S.838 99 0.00E 40 9.344 11 6.ME*11 1.1M 05 Carwoesten factors are in mite of somre metee oree/yr per Wl/sec for all easiltes escept # 3 elsh le in mits of areWyr per uti/cels meter.

f UNT-005-014 Revision 0 ' Attachment 6.7 (8 of 12) . 143

e COW's MILK PATINAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER TRAN' NOBLE GASES, R 1 AM DatkPa CalLD ( 3 Of 3 ) 4 sucklett car.Aa Doet towvtesica FAttoes 00mt LlVIt 1.02Y fNYe010 E10st? Lunc $1 LLi 1 04 140 1.17t*08 1.0M *M 6.84t+06 0.00t+00 3.344 04 6.12t+04 5.9M+07 i SA.141 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.00t*00 0.00t+u0 l 6A 142 0.00t*00 0.00t+00 0.00s+00 0.00t+00 0.00s+00 0.00s*00 0.00s*00 l

                                   ................................................................................                                                          I l

g 'LA 140 1.04641 6,70t+00 2.11I+00 0.00t+00 0.008+00 0.000+00 1.098 +05 - LA 142 8.10t 11 2. Sat 11 6.004 12 0.00t*00 0.00t+00 0.00t+00 5.11t*06 Ct.141 2.19t+04 1.09t +M 1.Ht+03 0.00E*00 4.70t*04 0.00t+00 1.36t+07 Cta143 1.871 02 1.02E*05 1.47 41 0.00t+00 4.2M 41 0.00t+00 1.49t+06 Ct*144 1.Ht+06 1.09t*05 8.Mt+M 0.00t+00 f.Nt*05 0.00t*00 1.3M

• 08 M.143 7.10E+02 2.1M *02 3.56t+01 0.00t+00 1.17t+02 0.00E*00 7.75t+05 M*144 0.000 00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t*00 0.00t+00
• up=147 4.He*02 3.60E+02 2.79t+01 0.00t+00 1.90t+02 0.00t+00 5.70t+05

                         .       W*107            2.09E+04 1.715+04 7.688+03 0.00s+00 0.00s+00 0.00t+00 2.40t+06 I**239           2.iM*02 1.15f 41 1.09t 41 0.00t+00 4.48t 41 0.00t+00 1.15t+06
                       .         Corwoesten factere are in mite of e4Nore meter.wantyr per W:l/see for ett nucLtdee oncept W 3 editch le in mits of aren/yr per WCI/ cele seter.

t l-i UNT-005-014 Revision 0 Attachment 6.7 (9 of 12) 144 , L- . _ - - . ~

COW's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN'liOBLE CASES, R g W GROLP thr4st ( t of 3 ) ,, WCLIDt Ger.4m post cowyttston f 4ttaal BCut LIVtt f.Bev TNft010 EIOutt Lune Cl.LLI u3 0.00t+00 2.Mt 43 2. Me*03 2.Mt+03 2.Mt+03 2.30t+03 2.30t+03 Ca14 2.34f+09 5.00s+08 5.00t*0s 5.008+0s 5.00 +0s 5.00t e s 5.00s+0s h4 24 1.$4t+07 1.54447 1.$4t*07 1.$44+07 1.5'.f 47 1.54t+07 1.54447 P 32 1.60ti11 9.434+09 6.21t*09 0.00t+00 0.00t+00 0.00t+00 1.17t +09 ca 51 0.00t*00 0.00540 1.61145 1.0St 45 2.30s+06 2.05 +05 4.70s+06 mm 54 0.00t+00 3.90t+07 8. kt+06 0.00t40 8.64t

• 0.00t 40 1.43447

          .              NN*$6             0.00t+00 3.161 02 S.42t*03 0.00t+00 2.70E 02 0.00t*00 2.05t+00 PI St             1.354+0B 8.73t 47 2.33t 47 0.00t+00 0.00t+00 4.27147 1.118*07 fI $9            2.248*DB 3.928+0B 1.541+0e 0.00t+00 0.00t+00 1.164+08 1.8M+08 C0 58            0.00t+00 2.42t*07 6.05t*07 0.00t*00 0.00E+00 0.00t+00 6.04t+07 to 60             0.00t+00 8.82t+0F 2.00t*06 0.00t+00 0.00t+00 0.00t*00 2.10E+08 ut.63             3.49t+10 2.16t+09 1.21849 0.00t+00 0.00t40 0.00t+00 1.0M +04 ul 65             3.50t.00 3.9M 01 1.00E 01 0.00t 40 0.00t 40 0.00t+00 3.02E+01 ObH               0.00E+00 1.ht+05 8.59t+06 0.000+00 ).148+05 0.00t+00 3.ttt+06 25 65            5.llt+09 1.90E*10 8.70t+09 0.00t+00 9.23E+09 0.00t+00 1.61t*10 tu 69            2.02E.11 3.63t*11 2.70t.12 0.00t+00 1.$18 11 0.00t+00 2.96t 09 De 83            0.00t+00 0.00E40 1.12t*01 0.001+00 0.00t+00 0.00t+00 0.008+00 De M             0.C'Je+00 0.00t+00 1.51,t 23 0.00t+00 0.00t+00 0.00t+00 0.00t+00 OR.0$            0.00E+00 0.00E.00 0.00E+00 0.008+00 0.00s+00 0.00t+00 0.00t+00 00 06            0.00t+00 3.23t+10 1.10t+10 0.00E*00 0.00t+0C 0.00t 40 5.60E+08 00 00            0.00t+00 0.00840 0.00f *00 0.00E+00 0.00E*f? 0 00t+00 0.00t+00
                 -         00 09            0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00tra 0.00t+0) 0.00t+00 08 89            1.Ht+10 0.00t+00 3.61848 0.00t+00 0.00t'.W 0.00t+00 2.59t+0e 08 90            1.32t*11 0.00t+00 3.10E*10 0.00t+00 0.00E+00 0.00t+00 1.52t49 Se 91            2.72E+05 0.00s+00 9.03t43 0.001+00 0.00t+00 0.00t+00 3.21t*05 08 92            4.64t+00 0.00t+00 1.73E 01 0.00E*00 0.00t+00 0.00t+00 5.00t41 f.90             6.81t+02 0.00t+00 1.83G+01 0.00t+00 0.00E*00 0.00t+00 9.61845 f.91m            S.6M 19 0.00t*00 1.93t*20 0.00t*00 0.00t+00 0.00t+00 1.005 15 f.91             7.33t*06 0.00t+00 1.954 43 0.00t+00 0.00E+00 0.00t+00 5.2SE46 f.92             S.30E 06 0.00t+00 1.518 05 0.00E+00 0.00E+00 0.00t+00 1.03t41 Conversten f acten are in mits of essere metee areWyr Der Wl/see for ett fmactless oncept 0 3 iAlch is in mits of areWyr per uti/cels ester.

I 1 l i UNT-005-014 Revision 0 Attachment 6.7 (10 of 12) 145 l

o COW's MILE PATWAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rg, AGE GACLP Inf 4WT t 2 08 3 I MuttIDE C# gas Dolt COWWillou F AC10RS tout Livte f tapf 1NTR010 E10stt LUNG Ol*LLI

                     . 143                2.iM*00 0.00t*00 S.84 02 0.00t+00 0.00t+00 0.00t+00 1.70t+04
           .             It'95              6.80E+03 1.664+03 1.108+03 0.008+00 1.79E+03 0.008+00 8.2M*05 2047               4.0M +00 6.9M 01 3.1M 01 0.0Ct+00 7.034 01 0.00t+00 4.45t+M
               .          W4 95             S.93t 45 2.44t45 1.41t+05 0.00E*00 1.75t+05 0.00t*00 2.Mt.08 No 99             0.00t+00 2.0e4+00 e.06t+07 0.00t*00 3.11t+08 0.00t 40 6.05t+07 TC+9eu            2.75t+01 S.67541 7.30E*02 0.00t*00 6.10t*02 2.9M41 1.65t *M ft 101            0.00t+00 0.00E+00 0.;*4*00 0.00t*00 0.00t*00 0.00t+00 0.00t+00 ku 103            8.6M *03 0.00t+00 2.9064) 0.00t+00 1.00t +M 0.0ut *00 1.05t+05 00 105            8.05t 03 0.00t+00 2.71103 0.00t+00 5.92t*02 0.00t+00 3.20t+00 4

00 106 1.90t+05 0.00t+00 2.30E+04 0.00t+00 2.2H+05 0.00t+00 1.44t +M , Ata t ta 3.Mt+08 2.82t+08 1.864 08 0.00t+00 4.03t*00 0.00t40 1.4M*10

• 11 1254 1.51t*06 5.Mt47 2.04E47 S.07147 0.00t+00 0.00t*00 7.iet+07 ft.12?N 4.21t+M 1.40t+08 5.10t47 1.27t+08 1.04t +M 0.00t+00 1.70t*06 ft.127 6.3M*03 2.12t*03 1.3ef+03'$.14t+03 1.54t +M 0.00t*00 1.3M *05

                 -           it+129u         l.175+08 1.911+08 8. Set +07 2.144+08 1.39E+09 0.00s+00 3.33E+08 ft.129          2.72t.09 9.375 10 6.3M 16 2.20t 09 6.77t 09 0.00E+00 2.175 07
   .                     ,fIa131m            3.384*06 1.360+06 1.128+06 2.75t+06 9.3M+06 0.00t+00 2.2947 ft 131         3.4M 32 1.27t 32 9.62t:33 3.0et*32 8.7M 32 0.00t40 1.5et 30 ft.132          2.11t+07 1.04E47 9.75E+M 1.54t*07 6.5M47 0.00t+00 3.87t+07 1 130          3.5M.06 7.018 4 3.1M4 8.75t+0s 4.58E4 0.00E+00 1.67t+06                          '

l'131 2.7M+09 3.20E+09 1.41t+09 1.0H+12 3.74449 0.00t+00 1.14t+08 l'132 1.4M +00 2.900+00 1.0M+00 1.ht 42 3.24t+00 0.00t+00 2.35t+00 l'133 3.6M *07 5.tet+07 1.5M+07 9.60t+09 6.218 47 0.00E+00 8.9M 46

          .                     la1M           1.7M 11 3.608 11 1.20E.11 8.40E*10 4.0M*11 0.00E+00 3.738 11 l 13$          1.12E+05 2.25t*05 8.14t+04 2.00t+07 2.49t+05 0 Det+00 8.0st+04 CS 1H          3.6M*10 6.00t+10 6.87t+09 0.00t+00 1.75t+10 7.18t+09 1.0H +08 Cl*136         1.98t+09 5.01849 2.17t+09 0.00E+eo 2.32t+09 4.74E+as 8.82t+07 CS 137         S.1H+10 6.02t+10 4.2M40 0.00E 40 1.628 10 6.5M*09 1.ast+08 Cs.138        8.3et.23 1.3M 22 6.615aD 0.00t+00 6.00t=23 1.0M.23 2.18t 22 4A*139        4.27t*07 2.8M 10 1.244 84 0.00t+00 1.70E.10 1.72t + 10 2.714 05 Corwersten f actors are in mits of emere seter.aren/yc per Wl/sec for all ruellees ektept R 3 elch is in WMts of aremryr per Wl/cels meter.

9 UNT-005-014 Rev!.ston 0 Attachment 6.7 (11 of 12) 146

I I 1 e i CO'*"s MILK PATWAY DOSE TACTORS DUE TO  ; i

                                                                                                                         ~

RADIONUCLIDES OTHER THAN NOBLE GASES R g 4Gt Gaoups tapest ( ) 0F 3 ) , uJ tIDI ORGAs DOtt COWWttl0N f 4Cfo#8 Dont Livtt 1.0 31 tut 90!D E! Duff LLB66 Ol*tti M.140 2.411*00 2.41t+M 1.24t+07 0.00t+00 S.72t*04 1.40t +M l 92t+0? M 141 0.00t+00 0.00t+00 0.008+00 0.000+00 0.00s+00 0.00t+00 0.00s+00 M.142 0.00t+00 0.008+00 0.008+00 0.00t+00 0.00 +00 0.00t+00 0.00t+00

• L4 140 4.05t+0i 1.60t+01 ,4.11t+00 0.00t+00 0.00t+00 0.00t+00 1.00t +M a

ta.142 1.79t.10 6.248 11 1.49t.11 0.00t+00 0.00t+00 0.00t+00 1.06t.03 Ct.141 4.34t*04 2.64E+04 3.11t+03 0.00t+00 0.15t*03 0.00E+00 1.37t+07 , Ct.143 3.97t*02 2. ut* M 3.00t+0' O.00t+00 7.67t+01 0.00t+00 1.54t+06 Ct.144 2.3M*06 9.52t+M 1.30t+fi 0.00t+00 3.05t +M 0.00t+00 1.3M+00 Pt.143 1.40t+03 S.35t+G2 7.34t +( f 0.00t+00 2.06t+02 0.00t+00 7.04t +M

        .        Pt.144 -       0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t'00 0.00t+00 0.00t+00 ND.147         0.01t+02 9.0H+t ; l.15t+01 0.00t+00 3.49t+02 0.00t*00 5.74t +M
                'W.107          6.00E*04 4.23tkO4 1.468+04 0.00t+00 0.00t+00 0.00E+00 2.40t+06 eP.239         4.57t*02 4.00t+01 2.31t+01 0.00E+00 0.1H+01 0.00t*00 1.10t*06 Conversten f acters are in mite of espere meter.oreWyr per 'di/sec for ett ruelleet oncept 8 3 dich to in mits of areWyr per Wl/s@ic enter.

UNT-005-014 Revision 0 Attachment 6.7 (12 of 12) 147

i

                             ' MEAT PATWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g 4Gt M:UP: ADJL1 1 1 0F 3 )

suCL198 ont.As 0054 CGrvit410N FAttces Oca( Livtt 1.037 fuTD010 8 1 rut t Luse Gl.LLI p.3 0.00t+00 3.25t+02 3.25t+02 3.Mt +02 3.25t+02 3.Mt +02 3.25t+02

         .              C.14         2.41t*08 4.ut*07 4.83t+07 4.83t+0? 4.8M *07 4.Ut*07 4.4M.07 eA 24        1.364 03 1.344 03 1.3M 03 1.368 03 1. W 03 1.344 03 1.364 03 p.32         4.ht+09. 2.90t')$ 1.00t*08 0.00f*00 0.00t*00 0.00t+00 $.24t+08 ca.51        0.00t+00 0.00t @ 7.05t*03 4.21t+03 1.$5t+03 9.35t+03 1.T7t +M ser.54       0.00t+0J 9.10t+06 1.5t+06 0.00t+00 2.73t+06 0.00t +00 2.81t+07 sur S6       0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.008+00 78 55        2.9M4 2.0M*08 4.72t*07 0.00E+00 0.00t+00 1.1M *08 1.iet*08 Ft 59        2.Mt *08 6.248+08 -2.39E+08 0.00t+00 0.00t+00 1.74E+08 2.00f+09 CD Se         0.00t+00 1.82t+0? 4.09E*07 0.00t+00 0.00t+00 0.00t+00 3.69t+08 Co 60         0.00t+00 7.52f+07 1.Mt+08 0.lGE*00 0.00t+00 0.00t +00 1.41t+09 bl*63         1.Det+10 1.31t+09 6.3M*08 0.00t*00 0.00t*00 0.00t+00 2.73t 08 81 65        0.00E*00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 tu M         0.00E*00 2.718 07 1.275 07 0.00f*00 4. M -07 0.00t+00 2.31t 05

• 20 65 3.5M*04 1.1M *09 5.12t>00 0.00t+00 7.57t+08 0.00t+00 T.1M +08 le 69 0.00t*00 0.00E+00 0.00E+00 0.00t+00 0.00E+00 0.00t +00 0.00t+00 M 83 0.00t+00 0.00E+00 0.00E+00 0.00t*00 0.00E+00 0.00E+00 0.00E+00 ,

te M 0.005+00 0.01't +00 0.00E+00 0.00E+00 0.00s+00 0.00s+00 0.00E+00 M OS 0.005+00 0.006+00 0.00s+00 0.00s+00 0.00t+00 0.00t+00 0.00t+00 n 06 0.00t*00 4.07t+48 2.27t+08 0.00t+00 0.00t+00 0.00t+00 9.60E+0? 08 08 0.00t+00 0.000+00 0.00E+00 0.00t+00 0.000+00 0.00t+00 0.00t+00

• 08 99 0.00t*00 0.00t*00 0. tee +00 0.00E+00 0.001 00 0.00t*00 0.00t+00 M 09 - 3.ON+08 0.00t+00 8.Mt+96 0.00t+00 0.00t+00 0.00t+00 4.044+07 M 90 1.24E+10 0.008+00 3.0$4+09 0.00E+00 0.00E+00 0.00t+00 3.598+48 80 91 1.52t.10 0.00E*00 6.148 12 0.00t+00 0.00t+00 0.00E*00 7.2M 10 M
• 92 0.00E+00 0.00E+00 0.00E+00 0.00t+00 0.00t*00 0.008+00 0.00s+00 Y 90 1.00t+02 0.00E*00 2.00E+00 0.0Ge*00 0.00t+00 0.00t+00 1.14t+06 f.9ta 0,00t+00 0.00E*00 0.00t+00 0.30t+00 0.00t*00 0.00t+00 0.00t+00 f.91 1.1M+06 0.00E *00 3.0M+04 0.000+00 0.00t+00 0. Jot +00 6.238 4 f.92 0.00E+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 Carwerelen f acters are lh mits of agenre meter *ereWyr per WCl/6ec for ett mellees except 0 3 dich it th mitt of aremfyr per WCl/ celt meter.

UNT-005-014 Revision 0 Attachment 6.8 (1 of 9) 148

e MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g 4f.E CACMP ADutt ( 2 0F 3 ) WCLlH out.aa post tarvtestem #Actens 4 1N?t0!D KtDatY I 00nt LIWit 1.0ST Lum 0 st.LLI f 93 4.695 12 0.00t+00 1.30t 13 0.00t*00 0.00t+00 0.00t+00 1.49t 07 2t 95 1.87t +N 6.01t+05 6.07t*05 0.Det*00 9.4M+05 0.00t+00 1.90t+09 18 97 2.0N 05 4.171 M 1.91t*06 0.0M+00 6.308 4 0.00t+00 1.29t+00 me 95 2.30t *h 1.20t +M 6.87t+05 0.00t+00 1.2H +M 0.00t+00 7.7H+09 ND 99 0.00t*00 1.00t*05 1.90t*H 0.00t+00 2.2N+05 0.00t+00 2.32t45 ft 994 4.45t 21 1.2M au 1.60t 19 0.00t 40 1.91t*19 6.iM*21 7.44t*18

• TC+101 0.00t+00 0.00t*00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 au 103 1.05t+08 0.00E*00 4.lM47 0.00t+00 4.01t+08 0.00t+00 1.23t*10 to 105 5.70E+28 0.00t+00 2.20E*28 0.00t+00 7.668*27 0.00t 40 3.538 25 90 106 2.00t+09 0.00t+00. 3.54t*08 0.00t+00 S.40t+09 0.00t+00 1.81t+11 a A4 11tBI 6.60t+06 6.10t +M 3.67t+06 0.00t+00 1.22847 0.00t+00 2.52t+09 ff*129m 3.59t+08 1.30t+08 4.81t47 1.00t+08 1.664+09 0.00E*00 1.4M*09 ft.127M 1.12t+09 3.99t+08 1.3M*06 2.0H+08 4.5M +09 0.00G+00 3.74t 49 ft*127 2.1M
• 10 7.628 11 4.595 11 1.57t*10 8.648 10 0.00t+00 1.67t*08 ' j ff 120M 1.13t+09 4.23t+08 1.79t+0B 3.90t+08 4.7M+09 0.00t+00 5.716 49 fI*129 0.00s+00 0.00t+00 0.00s.00 0.008+00 0.00t+00 0.008+00 0.00E+00 ft 131m 4.51t+02 2.21t+02 1.ht+02 3.49842 2.2M43 0.00E+00 2.19t +M 78 131 0.00t+00 0.000+00 0.00E+00 0.008+00 0.001+00- 0.008+00 0.00E40

                                       ................+...............................................................

TE.132 1.42t+06 9.10t+05 8.62E+05 1.01E+06 8.ht+06 0.00t+00 4.344+07 1 130 2.11f 4 6.2M 4 2.45E 4 5.275 4 9.718 4 0.00840 5.3M 06 1+131 1.07t+0? 1.54447 8.00t+06 5.0M +09 2.63t+07 0.00t+00 4.050+06 ' l'132 0.00t*00 0.00E+00 0.00040 0.00040 0.00t*00 0.000+00 0.00t+00 I 133 3.60t*01 6.3SE*01 1.968 01 9.34t+01 1.11840 0.000+00 5.71t*01 lath 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 1 135 4.438 17 1.1M *16 4.208 17 7.ME*15 1.06t*16 0.00t+00 1.318 16 C8 1M 6.50E*08 1.56t+09,1.20t+09 0.00t+00 5.ON+08 1.60t'+08 2.744+07 0$=136 1.21t+0? 4.76t+07 3.4 M +07 0.000+00 2.65t+07 3.6M+06 5.41t+06 C8 137 8.72t+08 1.19849 7.81t+08 0.00E40 4.05t48 1.350+08 2.31847 0$*138 0.00t*00 .0.00t+00 0.00!40 0.00t+00 0.00t+00 0.000+00 0.00640

       .                               84 139       0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00E+00 0.00t+00 Carwersten f acters are in mite of assaare ester areWyr per uC1/sec for ell swellees encept a 3 uhich to in unite of areWyr per gl/cela ester.

UNT-005-014 Revision 0 Attachment 6.8 (2 of 9) 149 h.

                            . . - .         . - . _ =                   - - _ ~ .               . - - .___               _ _ _ - . - .

MEAT PATINAY DOSE FACTORS DhE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R g AGE pcuP 40utt ( 3 Of 3 ) NJCilpt cards 00st Ceuyttildu f atical Sout Livtt f.StBT INT 9010 tibutY LUuG Cl LLI , l M*160 2.8M *07 3.61t +N 1.00t+06 0.00t+00 1.2M+04 2.0M+04 5.9Ft*07  ! 04*141 0.00t+00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 04 142 0.00t+00 0.00t+00 0.00t+00 0.00f+00.0.00t+00 0.00t+00 0.00t*00 , L4 140 3.714 02 1.87t 02 4.94t 03 0.00t+00 0.00t+00 0.00E+00 1.37t+03 LA t42 0.00t+00 0.00t*00 0.00t+00 0.00E+00 0.00s+00 0.00t+00 0.00t+00 Cl*141 1.40t+04 9.50t*f3 1.00t+03 0.00E+00 4.41t+03 0.00t+00 3.63t+07

• Ct.143 2.0it 02 1.40E+01 1.648 03 0.00t*00 6.5 M 03 0.00t+00 5.55t+02 Ct=144 1.44t+06 6.00t+05 7.BM*06 0.00t*00 3.61t*05 0.00t+00 4.nt+08

                     .              M*143                  2.10t+06 8.41t+03 1.06t+03 0.00t*00 4.05t+03 0.00t+0c 9.10t+07 M *144                 0.00t+0L

• 000+00 0.00R+00 0.000+00 0.00t*00 0.00t+00 0.00t*00 mai47 7.07t+03 8.17t+03 4.0ei+02 0.00E+00 4.70t+03 0.00t*00 3.92t+07

               .                    v 187          ' 2.07t 02 1.7M 02 6.064 03 0.00t+00 0.00t+00 0.00E+00 5.66t+00 OP 239                 6.5M+02        42t+01 3.54t+01 0.00E+00 2.00E+02 0.00E+00 1.32t+07                              .

Corwerslen facters are in units of esmre meter aremrye per Wl/see for ett , enscliese encept 0 3 d ish is in W ite of w em/yr per WCl/c stc meter. 4 \ Ukn.005-014 Revision 0 Attachment 6.8 (3 of 9) 150

   ,             ,     ,.                           . . , , . . . .                 a               .....    ,         ,                               ..,

1 Mr.AT PATHWAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R

     .                                                                                         1 AGE GROLP tite i 1 07 3 )

euCLIDE OncAs post couvttstou #4Cical l I l l tout Livte f.topf leftetD EIDett Luns St Ltl e.) 0.00t 40 1.kt+02 1.kt*02 1.ht42 1.Mt+02 1.kt+02 1.ht 42

          .                      c.14         2.Mt+00 4.00E *07 4.08t+07 4.00t+07 4.Det+07 4.00t+07 4.00t.07 ma.to        1.Det.03 1.0st.03 1.00E.03 1.00t.03 1.00t 03 1.006 03 1.006 03 P.32        3.93t+09 2.44t*06 1.5M+08 0.00t*00 0.00t 40 0.00t *00 3.41t+08 ca.51       0.00t+00 0.00t+00 7.64f+C3 3.1N+03 1.24t+03 8.05t+03 9 4M*05 sue 54      0.00t 40 7.00t 46 1.39t+06 0.00f*00 2.09t+06 0.00440.1.44147                                   ,

etw.56 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 0.00t*00 0.00E*00

   ,                             78 55       2.30t+06 1.69t*0s 3.Mt+07 0.00t+00 0.00E*00 1.0M+08 7.31t*07 ft.59       2.12t+0e 4.95t+08 1.91t*08 0.00t 40 0.00t+00 1.5H+08 1.1 M *09 Co.54        0.00t+00 1.41t+07 3.24t+07 0.00t+00 0.00t*00 0.00t+00 1.Mt +00 Co-60        0.00t+00 5.83t+07 1.31t+08 0.00t*00 0.00t+00 0.00840 7.60t+00 si.63        1.52t+10 3.0M49 5.1H+0e 0.00t+00 0.00t+00 0.00t+00 1.71t+0s a1 65        0.00s*00 0.00t+00 0.000+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 tM H -       0.00E+00 2.21t.07 1.ht.07 0.00E40 5.60t.07 0.00t+00 1.725 05 2m 65        2.50t+0B 8.6et+08 4.05t+0s *0.00t+00 S.5M 08 0.00E*00 3.Ht+0s a

tu.69 0.00E*00 .0.f,ut+00 0.00t*00 0.00e+00 'O.00t40 0.005 40 0.00t+00 M.83 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 '. . te.N 0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00E+00 0.00t*00 0.00t+00 ca.05 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00E+00 0.00t +00 0.00E 40

                               #8 N          0.00t+00 4.0M+08 1.91tes 0.005 00 0.000+00 0.00t+00 6.02E+07              -

Re.08 0.00t+00 0.00t +00 P.00E+00 0.00t+00 0.00t+00 0.00f+00 0.00t+00 .

                               ............................u..-................................................

et.09 0.00t+00' O.00t+00 0.000+00 0.00t40 0.00s+00 0.000+00 0.00t40

                              ,BR.09         2.55t*00 0.00t+00 7.29t +06 0.00E+00 0.00E+00 0.00t*00 3.0M47 34 90         8.05t+09 0.00t+00 1.99t+09 0.00E40 0.00t40 0.00t+00 2.36t+48
                               .................................. 4............................................

sa41 1.208 10 0.00t+00 5.00E.12 0.00t+00 0.00E40 0.00t 40 5.79t.10 ta 42 0.00t+00 0.00E+00 0.00E+00 0.00E+00 0.00E.00 0.00t+00 0.00t +00 f.90 9.06t+01 0.00E*00 2.44t+00 0.00t+00 0.00t+0C 0.00t 40 7.4M45 141st 0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00040 0.00t40 Y41 9.54E+05 0.00t+00 2.560+04 0.00E*00 0.00t+00 0.00t+00 3.91t+0S Y*92 0.00E+00 0.00t40 0.00t*00 0.00t*00 0.00t*00 0.00t+00 0.00t*00

                               ................................................................z...............

towereien f acters are in mite of somre meter.srevyr per uct/see for ett swells *1e encept W 3 dich is in ette of arevyr per utt/cete meter. 0

 .       UNT-005-014 Revision 0                                                                         Attacht0ent 6.8 (4 of 9) 151                                 .

O

                                                                            .                                                     1 MEAT PATHWAY DOSE FACTORS DUE TO RADIOh'UCLIDES OTHER THAN NOBLE GASES, R i            .

AGE MtW1 tite ( 2 Of 3 )

• I WCLIDt car.As post travtallau f atteel Ocut Livtt f.Dief tuva0lb ElDuff LuuG Gl*LLI t.93 3.tet.12 0.005+00 1.08E*13 0.00E 40 0.00s+00 0.000+00 1.218 07 2a.95 1.HE*06 4.7M 45 3.2H 45 0.00840 6.9M*05 0.00t+00 1.Mt +M 2e 97 1.728 05 3.414 4 1.5M 06 0.00E40 5.1M 06 0.00t+00 9.2M.01 l

                             ................................................................................                     a n0 95        1.79t+06 9.95t+05 5.40t+05 0.000+00 9.6M*05 0.00t-00 4.260 +M mo 99       0.00t+00 0.2Ft+04   1. Set +04 0.00t+00 1.09t+05 0.00t+00 1.40t+05 TC 99N      3.lM.21 9.84f.21 1.208 19 0.00t+00 1.47t.19 5 47t.21 4.4N 18 TC.101      0.00t*00 0.00t+00 0.00t+00 0.00t+co ' b.00t+00 0.00t*00 0.00t+00 00 103       0.57t+07 0.00E+00 3.Mt 47 0.00t+00 3.02t+08 0.00E+00 7.16t +09 to 10b       4.8M 30 0.00t+00 1 "M 28 0.00t+00 6.09t 27 0.00s+00 3.908 25
                 .*         RU.106       1.88t+09 0.00t*00 2.97t+08 0.00t+00 4.5M*09 0.00E+00 1.1M*11 A0 110m      5.00046 4.79E+06 2.918+0A 0.00s+00 9.1M46 0.00s+00 1.344+09                             I ft*125m      3.030 08 1.09t48 4.0M +07 8.47t+07 0.00E*00 0.00t+00 8.04t+08 ff=127M       9.'41t+00' 3.34t 48 1.13E*08 2.Mt+08 3.02t+09 0.00t+00 2.Ht+M ff*127        1.00E=10 6.30E.11 3.00t.11 1.248 10 7.29t*10 0.00t*00 1.398 00 ft.129u       9.HE+08 3.5M48 1.$0t+08 3.0M+08 3.9M +09 0.00t+00 3.5M+09
                      . f8 129        0.00s40 0.005+00 0.008+00 0.00540 0.00640 0.00t+00 0.00t+00 ft.131m       3.Nt42 1.00t+02 1.50t+02 2.71E 42 1.00E+03 0.00t*00 1.4M44
                        .ft.131                                                                                                 1 0.00E40 0.00t+00 0.00840 0.00t+00 0.00t*03 0.00t+00 0.00t+00
                           ..............s.................................................................

ft.132 1.Me+06 7.360+45 6.908+05 7.748+05 7.Det+06 0.00t+00 2.336+07 1 130 1.70s 4 4.918 4 1.9ef4 4.00E 4 7.56f 4 0.00t 4 0 3.7M 4 f*131 0.93*06 1.29047 4.71t+06 3.6SE*09 2.1M4r 0.00E+00 -2.4M+06

• 1 132 0.00E+00 0.0Pf+00 0.00E40 0.00l*00 0.00t+00 0.00E+00 0.00t+00 1 133 3.0M 01 5.10E 01 1.50s.01 7.23t+01 9.08E.01 0.00t*00 3.92t 01 l 1 1M 0.00E+00 0.00t+00 0.000+00.0.00E+00 0.00E+00 0.008 40 0.00040 1 135 3.60s.17 9.27t.17 3.44E.17 5.908 15 1.468 16 0.00t+00 1.036 14 i C8 134 5.2M48 1.23549 5.710+08 0.00t+00 3.910+08 1.49t+08 1.53t+07 CS 1M 9.40t+06 3.70E47 2.40t+07 0.00t+00 2.01847 3.1M+06 2.90E+06 C8a137 7.Mt+08 9.63f+08 3.34848 0.00540 3.30t*08 1.2M48 1.3M*07 t8 138 0.00E+00 0.00E+00 0.00t+00 0.00840 0.00t40 0.00t+00 0.00E +00  !

04 139 0.00840 0.00E+00 0.00E+00 0.00t*00 0.00840 0.00840 0.00E*00

                        . Cowereien f actees are in unite of somre seter.oremfyr per dl/see for all fastlose encept 0 3 iAlan is in mits of aremtre per uct/sels meter.

UNT-005-014 Revision 0 Attachnient 6.8 (5 of 9) 152 t

MEAT PATHk'AY DOSE TACTORS DUE TO RADIONUCLIDES i

                                                                                                                                        )

OTHER THAN tiOBLE GASES, R g , AGE GecuP titt ( 3 Of 3 3 mutttbt Degas Dost couwststou fActons , I i tout Livtt f .021 tutto!0 tt0sti tuwG st La l l M*140 2.30t+07 2.91t+04 1.5M*06 0.00t*00 9.87543 1.96t+M 3.ht +0? M 141 ] 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 M*142 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00E*00 0.00E 40 LA*140 3.0H 02 1.50t 02 3.99t 03 0.00t*00 0.00t+00 0.00t*00 8.61842 LA 142 0.00t*00 0.00t*00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 (t.141 1.10t*04 7.8M+03 9.04442 0.00t+00 3.71t +03 0.00t+00 2.Dt+07

                       ...............................s...............'.................................

Ct 143 1.69t 02 1.23t+01 1.371-03 0.00t+00 5.51t 03 0.00t+00 3.69t+02 Ct 144 1.23t+06 l.00t*05 6.60t+04 0.00t+D0 3.04t+05 0.00t+00 3.09t +06

     ,                 Pt 143        1.7M +04 7.04t+03 0.70t+02 0.00t+00 4.09t43 0.00E+00 5.00t+07 Pe*144        0'.00f+00 0.00E+00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 uD 147        6.23t+03 6.77t +03 4.6et+02 0.00E+00 3.901 43 '0.00t+00 2.44447 W 187     . 1.73E 02 1.418 02 4.9H 03 0.00t+00 0.00t 40 0.008 40 3.02t*00
                       .........................s......................................'................

up 239 l.70t+02 5.3st*01 2.99t+01 0.00E+00 1.69542 0.00t+00 8.6M +46 Corworsten factors are in units of espero esterasurein/yr per di/ set for elf rucitales eacept W 3 iAlch is in witts of aree/yr per uct/sels meter. 9 I l i l L l P UNT-005-014 Revisiot) 0 153

MEAT PATINAY DOSE FACTORS DUE TO RADIONUCLID::S OTHER THAN NOBLE CASES, R g AGE GROUP CNILD E 1 0F 3 ) muCLIDE- 08G4m DOSE COINER 110N F4Cical saWE LivtE 1.t(BY 1pV90!D EIDutY LUM w LLI tr3 0.00t+00 2.34E*02 2.34E*02 2.34E+02 2.34E+02 2.34E +02 2.34E +t 2 C 14 3.8M +08 7.67E 07 7.6M 47 7.67E+07 7.6M*07 7.6M47 7.6M +07 mA*24 1.72E 03 1.72E 02 1.72E 03 1.72E 03 1.72E 53 1.7H 03 1.725 03 P.32 7.42E*09 3 4M +06 2. tee +08 0.00E+00 0.00E+00 0.00E+00 2.05E+06 ca.!1 0.00E *00 0.00E +00 8.79E+03 4.NE+03 1.3M +03 8.91E+03 4.6eE+05 suoS4 0.00E*00 8.01E*06 2.13E +M 0.00E*00 2.25E+M 0.00E+00 6.72E+06 seu 56 0.n0E' 00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 FE 55 4.3M *06 2.42t+06 7.51E47 0.00E+00 0.00E+00 1.37E+04 4.49E+07 FE 59 3.7H+08 6.09E+06 3.03E*08 0.00E 40 0.00E+00 1.7M*08 6.34E+08 Co 50 0.00E*00 1.64E+07 5.02E47 0.00E*00 ' 0.00E+00 0.00E*00 9.54E+07 Co 60 0.00E+00 6.9M *07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 uta&3 2.91E+10 1.5M+09 1.02E 09 0.04E +00 0.00E +00 0.00E *00 1.05E+Go kl*65 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E40 0.00E+00 CU 64 0.00E40 2.9M.07 1.00E 07 0.00E+00 7.19E.07 0.00E+00 1.40E 05 tua65 3.7H+08 1.00E+09 6.22E+08 0.00E 4 0 6.30E*08 0.00E+00 1.76E+08 Zu 69 0.00E+00 0.00E+00 0.0M+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

                         < 0A 03           0.00E+00 0.00E+00 0.000 00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0A 04         0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,'.0E40 02 05        0.00E +00 0.00E+30 0.00E+00 0.00E+00 0.00E+00 0.0dE+00 0.00E+00 R0 46         0.00E +00 5.7M+08 3.55E+08 0.80E+00 0.00E+00 0.00E+00 3.71E+07 ReaOS         0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E +4M 0.00E+00 0.NE+00 80 09         0.00E *00 0.00E +00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 38 89         4.825*0t 0.00E*00 1.3M47 0.00E*00 0.00E+00 0.00E+00 1.87E+07 82 90         1.04E*10 0.00E *00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 38 91         2.401 10 0.00E+00 9.054 12 0.00E+00 0.00E+00 d.00E+00 5.29E.10                     ,

sa d2 0.00E +00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 T 90 1.71E*02 0.00E *00 4.59E+00 0.00E*00 0.00E+00 0.00E+00 4.00E+05 *

                              ....................................... ........................................                       j I'                             f.91st        0.00E+00 0.00E*00 0.00840 0.NE*00 0.00E*00 0.00E+00 0.00E+00

• T 91 1.00E*06 0.00E+00 4.02E+04 0.00E+00 0.00E*00 0.00E+00 2.40E+08 f.92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 j'

Carwersten facters are in mite of esNere meter erentyr.per dl/sec for ett twelldes sacept N 3 elch is in mite of prem/yf per Wl/cnelt meter. 4

• o UNT *$05-014 Revision 0 - Attachinent 6.8 (7 of 9) 154 l

fMEAT PATINAY DOSE TACTORS DUE- TO RADIONUCLIDES m OTHER THAN NOBLE CASES, R ) 1 -

          .r ACE 01 UPI CNito ( 2 Of 3 )

MUCL'. M OR64N 000E CouvEtllou FACTOR $ i tout LlWEE 1.tef TNYeolo KIDutf LuuG Gl LLI T 93 7.44E 12 0.00E+00 2.04E.13 - 0.00E40 0.00E+00 0.00E+00 1.11E 07  ! 28 95 2.HE N 5.85E*05 5.21E*05 0.00t+00 8.38445 0.00E+00 6.11E+08 28 97 3.21E 05 4.aM 06 2.73E 06 - 0.00E+00 6.65E 06 0.00r:40 7.02E 01 h6 95 3.1M +M 1.21E+06 8.62E*05 0.00E *00 1.13E*06 0.00E40 2.23E49

                         +

MD 99 0.00E+00 1.15E 05 2.84E*04 0.00E*00 2.46E*03 0.00E*00 9.51E*04 f TC 99M 6.20E 21 1.22E*20. 2.01E.19 0.00E+00 .1.7M

• 19 6.14 21 6,91E.18. ,

T C

• p'. 0.00E*00 0.00E40 0.004 00 0.00E+00 0.00E+00 0.00E*00 0.00E*00 au 103 1.5M *08 0.00E+00 5.964+07 0.00E+00 J.90E+08 0.00E+00 4.01E*09 1 4 RU 105 . 9.02E 28 0.00E+00 3.2M 28 .0.00E+00 7.93E.27 0.00E+00 5.tet 25 l au 106' 4.44E+09 0.00E *00 5.54E+08 0.00E+00 5.9M+49 0.00E+00 6.90E*10 A0 110M ~ 8 394+06 5.6M+06 4.5M *06 0.00E*00 1.064 07 0.00E+00 6.74E*J TE*125N ti.HE 08 1.54E+08 7.59E+07 1.60E*08 ' O.00E+00 0.00E+00 5.49E+08 TE.12M 1.7FE+09-4.7BE+08 2.11e 08 4.2w+08 5.06E 49 0.00E+00 1.448*09

 -                              TE 127         3.39E*10 9.1M*11 7.26E.11 2.344 10 9.63E 10 V.00E+00 ' 1.3T08                                     i TE 129M '      1.79E+09 5.00E +08 2.FaE+08 5.7M+08 5.264+09 0.00E+00 2.1aE+09                                    '

tea 129 . 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE *131N - 7.00E+02 2.42E+02 2.5eE+02 4.9eE+02 2.34E+03 0.00E+00 1.BaE+03

                               'it 131         0.00E40 0.00E+00 0.00E+00 0.30E+00 0.00E+00 O X e+00 0.00E+00 TE*132         2.15+06't.3aE+05 1.1M+06 1 3M+06 4.71E+06 0.0 b . 9.45E+06 e VJ          3.048 06 6.1M 06 3.16E 06 6,.!6C N 9.17E*06 0.00E+0C 2.8M 06
                               -1 141          1.65E+07 1.HE+07 9.46E+06 ' 5.50E+09 2.73E+07 0.00E*00 1.4aE+06 l*132         0.30E+00 0.00E+00 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I 133 -       5.67E 01 7.02E 01 2.HE*01 1.30E*02 .1.1M+00 0.00E+00 . 2.83E 01 1 134          0 AGE +00 . 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00 0.00E+00 I 135         6.52E 17 i.17E 16 5.5 M 17 1.044 14 1.80E 16 0,00t+00 8.NE *17
    -                           Cs 134         9.22E+08 1.51E+09 3.19e+0B-0.00E+00 4.60E*00 1.6AE+08 8.1H+06 CG 136         1.62E+07. 4.58E+07 2.00E+07 0.00E+00 2.3M47 3.54E+06 .1.5M+06 C8a137 '       1.15E+09 1.20E+09 1.0AE+08 0.00E+00 4.16E48 1.50E+08 7.99E+06 Cs 138        0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E*00 0.00C+00 BA 139 -      0.00E+00 0.00E*00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00                                    '

Corwerslen factors are in mits of espaere meter eren/yr pee uCl/sec for att raztless encept B 3 uhich is in mits of uree/yr per LCl/celc seter. l I l- . . l-UNT-005-014 Revision 0 Attachment 6.8 (8 of 9) (; 155 i l

1 l

                                                                       =
                                                                                                                                         \
                           ' MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES                                                              !

OTHER THAN NOBLE CASES, R g , A0t GROUP CulLD ( 3 of 3 ) . NUCL10E8 Os&As Dott C0eNtell0N FAC10ftl tout Livtt f.00DT tuft 0!D E10mEY LUM 0 Ol*LLI 6A 140 4.3aE+07 3.Et+04 2.56t+06 0.00t*00 1.25t+N 2.29t+04 2.222+07 BA 141 0.00t+00 0.00E+00 0.00t*00 0.00t+00 0.00t+00 0.00E+00 0.00t*00 SA + 112 0.00t+00 0.6Jt*00 0.00t*00 0.0 F 00 0.00E*00 0.00E*00 0.00E+00 LA 14 5'.59t 02 1.954 02 6.08t 03 0.00t+00 0.00t+00 0.00t+00 5.44E+02 LA*142 0.00E*00 0.00t+00'O.00E+00 0.00E*00 0.00E+00 0.00t+00 0.00t+00 Ct*141 2.22t+04 1.11t+04 1.64t+03 0.00t+00 4.NE *04 0.00t+00 1.38t+07 . Ct.143 3.175 02 1.72t+01 2.49t.03 0.00t+00 7.215 03 0.00E*00 2.52t+02 CE 144 2.32t+06 7.2EE+05 1.24t+05 0.00t+00 4.0Zt+05 0.00E+00 1.89t+08 Pe=143 3.34t+04 1.00t+04 1.NE*03 0.00t+00 5.43t+03 0.00t+00 3.60E*07 PR 144 0.00E+00 0.00E*00 0.00E*00 0.00t+00 .0.00E*00 0.00t+00 0.00t+00 10 147 1.17t+04, 9.47t+03 7.33t+02 0.00t+00 5.19t+03 0.00E+00 1.50E*07 W 187 3.218 02 1.90E 02 8.53E 03 0.00t+00 0.00t+00 0.00t+00 2.67t+00 WP 239 1.07t+03 7.71t+01 5.42t+01 0.00E*00 2.23E+02 0.00t+00 5.70t+06 Corwerslen factors are in mite of somre ester aren/h per ucl/sec fe" ett .

         .                      raslides except N 3 which is in mite of ares /yr per Wl/Mic motet.
     +
           -UNT-005-014 Revision 0                                i Attachment 6.8 (9 of 9) 156

        .I; O

LEAFY VEGETABLE PATHWAY DOSE FACTORS <DUE TO RADIONUCLIDES OTHER THAN' NOBLE CASES, R g , Ar.t GROUP: ADUL1 ( 1 Of 3 ) muCLIDE on4Am Dost couvEtslam f ACTces acut LivEt f .Smf frYRote KIDutY LUuG Gl*LLI N3 0.00E*00 2.2M+03 2.2M*03 2.2M*03 2.2M*03 2.2M ,03 2.2M *03 C 14 2.2eE+08 4.55t*07 4.55E+07 4.55E*07 4.55E*07 4.55E+07 4.55E+07 WA 24 2.69E*05 2.69E*05 2.69t+05 2.69t+05 2.69E*05 2.69E*05 2.69E*05 P 32 1.40E+09 8.73E+07 5.43t+07 0.00E*00 0.00E*00 0.orM 1.58E+06

                      ,        CR 51           0.00E+00 0.00E+00 4.64t+04 2.70E*04 1.02E+04 8 .oE+04 1.1M +07 Mu 54            0.00E+00 3.13E+06 5.9M*07 0.00E*00 9.31E+07 0.00E+00 9.59E+08 Mu 56            0.00E*00 1.59t+01 2.82E+00 0.00E+00 2.02E+01 0.00E+00 5.07E u FE 55           2.10E*06 1.45E*06 3.38E+07 0.00E*00 0.00E*00 6.00E*07 6.31E +0 r
    .                          FE 59           1.2M *06 2.9M *06 1.14t*08 0.00F+00 0.00E*00 8.20E +07 9.88E+06 Co 58            0.00E * *J0 3.07t+07 6.39E*07 0.00E+00 0.00E+c 0.00E*W 6.2M*06 co-60            0.00E+00 1.6M *00 3.69E*06 0.00E+00 'O.00E+00 0 W +00 3.ist*09 NI 63            1.04t+10 7.21Eo06 3.49t+08 0.00E*00 0.0ct+00 0.00E+00 1.50E+06
             .                 ..................................................................z,............

kt 65 6.15t+01 7.99E*00 3.64t +00 0.00E+00 0.00E*00 0.00E+00 2.03E+02 CU 64* 0.00E*00 9.20t+03 4.32E+03 0.00E+00 2.32E+04 '0.00E+00 7.84t*05 2N 65 3.1M+08 1.01t*09 4.56E+06 0.00E+00 6.75E*06 0.00E+00 6.3M*08

                            ' 2n 69 '          5.49E 06 1.05E 05 7.311 07 0.00E+00 6.8M 06 0.00E+00 1.58E 06 SE a3            0.00E+00 0.00E+00 3.11E*00 0.00E+00 0.00E+00 0.00E+00 4.47t+00
      .                    ,e4 84              0. M +00 0.00E+00 2.48E.11 0.00E+00 0.00E+00 0.00d+00 1.94E.16 84 85            0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 R8 86            0.00E+00. 2.19E+08 11.02E+06 0.00E+00 0.00E+00 0.00E*00 4.3M*C7 Re 86            0.00E+00 3.4M 21 1.82E 22 0.00E+00 0.00E+00 0.00E*00 4.748 33
                              'Re 89           0.00E+00 3.89E 26 2.73E 26 5.00E+00 ~ 0.00E+00 0.00E*00 0.00E+00 SR 89            9.97t+09 0.00E'00 2.86t+08 0.00E+00 0.00E+00 0.00E*00 1.60E+09 se 90            6.0H+11 0.00E+00 1.40E+11 0.00E*00 0.00E+00 0.00E+00 1.75tv10 sa 91           3.0$E+05 0.00E+00 1.23E+04 0.00E+00 0.00E+00 0.00E+00 1.4H+06 se 92           4.2M+02 0.00E *00 1.85E+01 .0.00E+00 0.00E*00 0.00E 00 8.45t+03                             ,

Y 90 1.33E+04 0.00E+00 3.5M+02 0.00E+00 0.00E+00 0.00E+00 1.41E+08 Y 91M 5.22E 09 0.00E+00 2.02E 10 0.00E+00 0.00E+00 0.00E+00 1.53E 06 Y 91 5.11t*06 0.00E*00 1.3M +05 0.00E+00 0.00E+00 0.00E+00 2.81E+09 . Ya92 9.1H 01 0.00E+00 2.68E 02 0.00E*00 0.00E+00 0.00E+00 1.60E+04 terwersion f actors are in mits of emance meter aree/yr per uCl/see for ett maclimes except u 3 eelch * . In units of eren/yr per w:l/cshic meter. UNT-005-014 Revision 0 Attachment 6.9 (1 of 9) 157

_. . - . - - . . .. _ - - - ._ ~ _. . - y . t e

                -.c                                                                                          ,                                                                        ,

LEAFY VEGETABLE PATHWAY DOSE FACTORS,DUE TO

• i

_ RADIONUCLIDES OTHER THAN NOBLE CASES.- R -

              +                                                                                                                      i w
  ?i.                                                AGE 0807: ADULT ( 2 of 3 )

NUCLIM CaG4a post CouvER$10m FACf(R$ Bout LIVEE f .BCDT TRYROIO : ElDutf LUNG 81 LLI ~~ Y 93 1.70E*02 0.00E+00 4.68E*00 0.00E*00 0.00E+00 0.00E*00 5.30E46 y IR 95 1.17t+06 3.77E*05. 2.55p05 0.00E+00 5.91E+05 0.00E+00 1.19E * *J9 " 2a 97 3.37E*02 6.81E*01 3.11001 0.00E*00 1.03E+02 0.00E+00 2.11E+07 Me 95 1.42E+05 7.9dE*04 4.2M+04 0.00E *00 7.83E *M 0.00E+00 4.81E*08

                                           .      . MD 99             0.00E+00 6.1H+06

• 1.17t+06 0.00E+00 1.39E47 0.00E+00 1.43E+07 - -

FC 99M 3.10E40 8.77t+00 1.12E+02 0.00E*00 1.3M 42 '4.30E*00 5.19E43 TC+101 4.22E 31 1.18E 30 1.1M 29 0.00E+00 2.13E 29 6.05E 31 0.00E+00 RU 103 ' 4.77E 06 0.00E+00 2.0M +06 0.00E 40 f.82E*07 0.00E+00 5.57t+08 au 105 5.39t+01 0.00E+00 2.13E 41 0.00E+00-6.96E+02 0.00E+00 3.29t+04-80 106 1.9M*08 0.00E+UO 2.44E+07 0.00D00 3.72E+08 0.00E+00 1.25E+10 AS 111st 1.0H+07 9.75E+06 5.79E*06 . 0.00E*00 - 1.92E+07 0.00E+00 3.90E+09

                  .                                 TE 125m           9.66007 3.50E+07. 1.29t+07 2.90E +07 3.93E+0B 0.00E+00 3.06E+08 TE*127M           3.49E*08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 0.tv O 1.17t+09 TE*127            5.NE*03'.2.03E+03 1.22E+03 ,4.19E+03 2.31904 0.00E+00 4.4M45                                          ,

TE 129M 2.11E*08-#.30E+07 3.90E47 8.247 1.05E+09 0.00E+00 1.2M + ' TE 129 7.2 M 2.BM 04 1.06E M 5.85E M 3.20E 03 0.00E+00 5.75E M . TE 131M 9.12E+05 4.468+05 3.73E*05 7.0M+05 4.52E 46 0.00E+00 4.43E47 . TE 131 1.50E 15 6.27E*16 4.74Ea16 1.23E*15 6.5M 15 0.00E+00 2.13E 16 TE 132 4.30E+06 2.7tE+06 2.61E+06 3.07t+0e 2.60E+07 0.00E+00 1.32E+08 l 130 3.92905 1.1M+06 ' 4'.5M*05 9.81E+07. 1.81E*06 0.00E+00 9.96E+05 ' I 131 8.00E+07 E1.1M+08 6.62E+07 3.79E+10 1.9eE+0B 0.00E+00 3.05E47 .

                                         .           1 132            5.76t+01 1.54E+02 5.39E+01 5.39E+03 2.4M*02 0.00E+00 2.8eE+01 1 133            2.00E+06 3. m +46 1.11906 5.33E+08 6.3390610.00p00 3.3M+06
                      .         .                   't .134 --        9.6M 05 2.62E 04 9.30E 05 4.54E 03 4.1M 04 0.00E+00 2.29E*07 3 135            3.90E+04 1.02E+05 3.7M+04 6.73E*06 1.HE+05 0.00E+00 1.15005 Ct.134            4.67t+09 1.11E+10 9.00E+09 0.00E+00 3.59E+09 1.19E+09- 1.94E+08 CS 136            4.2M+07 1.6AE+08-1.21E+08 0.00E+00 9.30E+07 1.29E47 't.91547 C8 137            6.36E*09 8.74E+09 5.70E+09 0.00E+00 2.95E+09 9.81E*08 1.6AE+08 -

ts*138 3.91E 11 7.73E 11 3.8M 11 0.00E+00 5.6tE 11 5.61E 12 3.30E 14 8A 139-- 2.06E 02 2.03E 05 8.36E M 0.00D00. 1.90E 05 1.15E 05 5.07E 02 Corwereien f actors are in mits of essere meter erem/yr per wcl/sec for ett enactidos emcept e 3 shich is in mits of eree/yr per uCI/ cele seter.

                ,UNT-005-014 Revision 0                                                                                    ,

Attachment 6.9 (2 of 9) 158 . a-- , .--. - , 4 - q -r-

LEATY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAd NOBLE GASES, R g A06 GAGJP ADULT ( 3 Op 3 ) NUCLlH ceGAN D055 CONytestou 7 ACTORS tout LIVlt f.DCDT TRYt010 KIDatT LUNG Gl LLI hA 140 1.20f*08 1.61t+05 8.42f +06 0.00t+00 5.49t+04 9.24t*04 2.65t*06 SA 141 1.1H 21 8.70E 25 3.89C 23 0.00t+00 8.095 25 4.94t 25 5.43E 31 SA 142 0.00t+00 0.00t*00 0.00E*00 0.00t+00 0.00E+00 0.00t+00 0.00t*00

                            . LA 140      1.98t+03 9.97t*02 2.6M *02 0.00t+00 0.00t+00 0.00t*00 7.32t+07 LA 142      2.0M 04 9.19t 05 2.29E 05 0.00t+00 0.00t+00 0.00t+00 6.71t 01
                                 !s 141      1.97t*05 1.33t*05 1.51t+06 0.00t+00 ,6.19t+04 0.00t+00 5.10t+08
                              . Ct 143       9.90t+02 7.38t*05 8.1M +01 0.00t*00 3.25t*02 0.00t+00 2.7M+07 CE*144      3.29E+07 1.3at+07 1.775+06 0.00E+00 8.1M +06 0.00t+00 1.111+10 PR 143      6.2M+04 2.51E+04 3.10t+03 0.00t+00 1.45t+04 0.00t+00 2.74t*06
                                 .............................s .................................................

Pa.144 3.09E 26 1.20E 26 1.57t 27 0.00t+00 7.23e 27 0.00t*00 4.44t 33 mo 147 3.33E+04 3.85t+E 2.31t+03 U.00E*00 2.25t+04 0.0nt+00 1.85t+08 W 187 . 3.80t+04 3.'18t +M 1.11t+04 0.00E+00 0.00t+00 0.00E+00 1.04t+07 NP 239 9.54t+04 9.38t+03 3.17t+03 0.00t+00 2.93t+04 0.00t+00 1.92t+09 Conversion f actors are in mits of somre meter eresVyr per cl/sec for att rumildes except M 3 uhleh is in unlts of eree/yr per utt/scic meter. . . i ,: , UNT-005-014 Revision 0 Attachment 6.9 (3 of 9) 159 l

i r 4 LEATY VEGETABLE PATHWAY DOSE FACTORS <DUE TO- > RADIONUCLIDES OTHER THAN' NOBLE GASES, R g

        . a..

AGE ta0#: TEEN ( 1 0F 3 ) u NUCLIN OscAN Oost couvtalion f Actons tcWE LivEt 1.00DT TNfa01D KIDutY LUNG Gl*LLI p.3 0.00E*00 2.59E+03 2.6M+03 2.59E*03 2.59E+03 2.59E+03 2.59E*03

                =.,                 c.14           3.69E*06 7.3eE+07 7.38t+07 7.3eE+07_7.3eE+07 7.3aE+07 7.362+07 mA.24           2.39E*05 2.39E*05 2.39E+05 2,3M+05 2.39E+05 2.39E+05 2.39E+05                                               ,

p.32 1.61E+09 9.97E*07 6.24E+07 0.00E+00 '0.00E+00 0.00E*00 1.35E+08

                                'Ca.51              0.00E*00 0.00E+00 6'.17t+04 3.43E+06 1.35E+04 8.81E+04 1.04E+07 m .54           0.00E+00 4.54t*08 9.01E+07 0.00E*00 1.36E+08 0.00E+00 9.32E+08 m.56            0.00E+00 -1.43E+01 2.55E+00 0.00E+00 1.81E+01 0.00E+00 9.4.E*02 FE 55          3.2M+08 2.31E*06 5.39E+07 0.00E+00 0.00E+00 1.47t+08 1.00E*06 FE 59          1.79E+08 4.19E+08 1.62E+08 0.00E*00 0.6*M+00 1.32E+08 v.90E+f
                          .          Co 58          0.00E+00 4.36dO7'1.00e+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08
                      .              Co 60          0.00E+00 2.49E*08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 NI 63 -         1.61E+10 1.13E+09'5.45E 4 0.00E*00 0.00E+00 0.00E+00 1.81E+08 v

NI 65 5.72E+01 7.31E*00 3.3M+00 0.00E+00 0.00E+00 0.00E+00'3.97t+02 CU 64 0.00E+00 8,34E+03 '.92E+03, 0.00E+00 2.110+04, 0.00E+00 6.47t+05 ' 2m 65 -4.24t+08 1.47t+09 6.87E*08 0.00E+00 9.42E+0B 0.00E+00 6.23E+08 Zu 69 5.15E 06 9.00E 06 6. tee 07 0.00E+00 '6.41E 06 0.ulE+00 1.81E 05 B8 83 0.00E+00 0.00E+00 ~ 2.91E+00 0.00E*00' O.00E+00 0.00E+00 0.00E+00 ' 84 84 0.00E+00 0.00E+00 2.25t*11 0.00E+00 0.00E+00 0.00E+00 0.00E+00

          ^'                                         O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 as.05 '

33 36 0.00E+00 2.74E+08 1.29E+08~ 0.00E*00 0.00E+00 0.00E+00 4.05E+07 0.00E+00 3.17E*.22 1.60E 22 0.00E+00 0.00E+00 0.00E+00 2.71E 29 as 88 as 89 .0.00E+00 .3.50E 26 2.47E M 0.00E+00 0.00E+00- 0.00E*00 5.36E 35

                                    ,sa.st            1.51E+10 0.00E+00 6.34E+08 0.00E+00. 0.00E+00 0.00E+00 1.80E*09 sa.90           7.51E+11 0.00E+00 1.056+11 0.00E+00 0.00E+00 0 10E+00 2.11E+10
                                      ....................................- a..a a a a.a a a a. a a a a " " " " " .

3a.91 2.85E+05 0.10E+00 1.13E+04 0.00E+00 0.00E+00 -0.00E+00 1.2M+06 go.92 3.97t+02 '0.00E+00 1.69E+01 0.00E+00 0.00E+00 0.00E*00.1.01E+04-y.90 1.24E+04 0.00E*00 3.35E+02 0.00E+00 J 00E+00 0.00E+00 1.02E+08

                                       ..............................................** *=. .***** ********************

y.,w . 4,36E.09 0.00E+00 1.tM*10 -0.00E+00 0.00E+00 0.00E+00 2.29E 07 y.91 7.34E+06 0.00E+00 2.10E+05 0.00E*00 0.00E*00 0.00E+00 3.21E+09 Y.92 8.60E 01 'O.00E+00 2.49E 02 0.00E+00 0.00E+00 0.00E+00 2.36E+04 Corwersten facters are in mits of opere meter aren/yr per uti/sec for ett nuctidos oncept N 3 uhtch is in mito of aren/yr per uct/c@te meter. i

               -UNT-005-014' Revision 0                                                                 ,

Attachment 6.9 (4 of 9) . I 160  !

LEATY VEGETABLE PATHWAY DOSE TACTORS.DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R 4 . l' AGE SAOUP 1EEN ( 2 0F 3 ) muCLIDE. *. ORGAN DOSE Comvttsl0m f AC10kl sont 4tyte- 1.00DT futt010 KIDmET. Lune Cl LLI f 93 1.5M *02 0.00E 4 4.3M+00 0.00E+00 0.00E+00 0.00E+00 4.aM*06 28 95 1.72E+06 5.43E*05 3.73E+05 0.00E+00 7.90E*05 0.00E*00 1.2M+09 RE 97 - 3.120*02 6.10E*01 2.85E*01 0.00E+00 9.37t+01 0.00E*00 1.6M*07 me 95 1.92E+05 1.0M

• 05 5.87E*04 0.00E+00 1.03E+05 0.00E+00 4.56E*08 MD 99 0.00E*00 5.65E*06 4.0eE+06 0.00E*00 1.29E47 0.00E*00 1.01E*07 TC 99M 2.74E+00 7.6M*00 9.09E+01 0.00E*00 1.14E+02. 4.24E+00 5.01E*03-TC+101- 7.64E 31 1.09E 30 1.07E 29 0.00E*00 1.97E 29 6.62E 31 0.00E+00 RU 103 6.82E*06 0.00E40 2.92E*06 0.00E +00 2.40E47 G.00E+00 5.70E+08 RU 105 ~5.00E 01 0.00E+00 1.94E+01 0.00E+00 6.31E42 0.00E*00 4.04E+04 RU 106 2.30E+0B 0.00E+00 3.90E+07 0.00E+00 . 5.97t+08 0.00E+00 1.40E+10

                         ..                      A4 110m         1.52E+07 1.43E+07 8.72E+06 0.00E 40 2.74E+07 0.00E+00 4.0M+09
                        ,                         TE*125M        1.44E+08 5.34E+07 1.90E+07 4.14E+07 0.00E+00 0.00E 40 4.37t+0e ff *127M '      5.51E'es 1.96E+0s 4.5M+07 1.31E+08 2.24E+09 0.00E+00 1.3M +09
                 .,                             'TE 127          5.34E+03 1.895+03' 1.1 M 4 3 3.6aE+03 2.168+04 0.00E+00 4.12E+05 TE.129M =      3.62E+08 1.34E+08-5.73E+07 1.1M+08 1.51E+09 0.00E*00 - 1.368+09                                                                       -
                            . 1 TE 129          7.14t*N ,2.6M 04 ~1.59E 04 5.10E 04 3.00E 03 - 0.00E+00 3.90E 03 TE 131M.        8.44E+05 4.05E+05 3.30E+05 6.00E+05 4.22E+06 0.00E+00 3.2M+07 TE*131          1.39E 15 5.7M 16 4.36E 16 1.07E 15 6.10E 15 0.00E+00 1.14E.16
                                          , ' ' TE 132           3.91E+06 2.4M+46 2.3M+06 2.41E+06 2.3M+07 0.00E+00 7.84E+c7 l 130           3.51E+05 1.01E+06 4.05f+05 8.3eE+07 1.56E+06- 0.00E+00 7.00E+05 l 131;                                                                                                                                                   -

7.60E+07 1.00E+08 5.78E+07 . 3.14E+10 1.05E+04 0.00E+00 2.1M+07 3 132' 5.19E+01 1,36E*42 4.00E+01 4.50E+03 2.14E+02 0.00E+00 5.92E+01 l*133 1.NE+06 3.29E+06 1.00E46 4.59E4B 5.7H+06 0.0ut+00 2.49E+06 1 134 ' 4.73E*05 2.31E.04 8.31E 05 3.8M 03 3.68E N 0.00E+00 3.0M 06 1 135 3.5m+04 9.CM+04 3.36E+04 5.83E+06 1.43E+05 ' O.NE,+00 - 1.00E+05 Cs 13 7.10E+09 1.67t+10 7.75E+09 0.00E+00 5.31E+09 2.0M+09 2.0eE+08 CS 136 4.37t+07 1.72E+08 1.16E+08 0.00E+00 9.37E47 1.48E+07 1.38E*07 C8 137 - 1.01E+10 1.35E+10 4.69E+09 V.00E+00 4.59E+09 1.7BE+09 1.92E+08 Cs.138 3.61E*11 6.93E 11 3.47E 11 0.00E+00 5.125 11 5.9M 12 7 1M 14 SA 139 2.695 02 1.89E 05 7.83E 04 0.00E+00 1.70E 05 1.30E 05 2.40E 01 Corwerslen facters are in mits of egare meter. area /yr per uct/sec for ell , ructiese eacept e 3 uhleh le in mite of ureatyr per utt/celc aster. UNT-005-014 Revision 0 Attachment 6.9 (5 of 9) 161

              -k-   ,           - - - -

LEAIT VEGETABLE PATWAY DOSE TACTORS +DUE TO MDIONUCLIDES OTHER THAN NOBLE GASES, R g , AGE OR(UPs 1EEN ( 3 0F 3 ) t IlucklDE ORGAN DOSE CC HEtlicu FACTUIL4 Soest LIVER 1.t(DY fuYRCID E1Dutt LuuG Cl.LLI 5 SA.140 1.30E+08 1.69t*05 8.90E *06 0.00E+00 5.74E+04 1.14t+05 2.13E*08 4A.141 1.00E.21 8.ME.25 3.59E.23 0.00E*00 7.46E.25 5.50E.25 2.29E.27

• sA 142 0.00E+00 0.00E*00 0.00E+00 0.00E*00 0.00E*00 0.00E*00 0.00E+00 LA.140 1.81E*03 8.88E*02 2.36E+02 0.00E+00 0.00E+00 0.00E+00 5.10E*07 LA.142 1.85E.04 8.2M .O 2,05E 05 0.00E*00 0.00E*00 0.00E+00 2.51E+00 CE.141 2.8M +05 1.89E*05 2.17E*04 0.00E*00 8.89E+04 0.00E*00 5.40E+08 ..

y CE.143 9.3M+02 6.79E+05 7.53E+ni 0.00E*00 3.04E+02 0.00E +00 2.04E+07

   .                           CE.144        5.27t+07 2.18E+07 2.83k.G 0.00E*00 1.30E+07 0.00E*00 1.33E+10 M.143         7.00E*04 2.00E+04 3.49E43 0.00E+00 1.63E+04 0.00E *00 2.30E+08 M.144 -       2.89E.26 1.18E.26 1.47E 27 0.00E+00 6.80E.27 0.00E+00 3.19E.29 N0 147        3.42E+04 3 94E+04 2.36f.01 A.00E *00 2.31E+04 0.00E*00 1.42E*08

• W l'~ 3.5&E+04 2.88E*04 1.01g+M bWW 0.00E+00 0.00E*00 7.80E+06 W4 II60E+05 1.51'c .= .38t+03 0,20E *00 4.74t*04 0.00E+00 2.43E+09 Corwrsion f actors are in mits of essee meter.orem/yr per' dt/sec for ett .

ructidos except W.3 elch is in units of area /yr ter uCl/c@ic meter. 4

  ;+
 .          UNT-005-014- Revision 0                                                                                  Attachment 6.9 (6 of 9) 162

LEAFY VEGETABLE PATHWAY DOSE FACTORS.DUE TO RADIONUCLIDES OTHER THAN'NOBLC GASES, R g AGE Ga3JPs CNILD ( 10F 3 ). auCLIDES DRr.M tioSE CouvEtl10N FAC10al . 1 . tome LIVER I h0DY INYR0!0 KIDutY 8.UNG Cl*LLI W3 0,00E+00 4.01E+03 4.01E+03 4.01E+03 4.01E*23 4.01E+03 4.01E+03

                                -  C 14 -       8.89E*08 1.7tE+08 1.79E*08 1.7BE*08 1.70E+08 1.78t+08 1.7BE+08 NA 24        3. M +05 3.73E+06 3.7M.C5 3.73E+05 3.7M+05 3.73E+05 3.73E+05 P 32         3.37E*09 1.54E48 1.30E*06 0.*0E+00 0.00E *00 0.00E *00 9.11E+07 Ca*31        0.00E*00 0.00E*00 1.17E*05 6.50E+04 1.78E+04 1.19E*05 6.21E*06 sus 54 '     O.00E*00 6.65E.06 1.77E+08 0.00E+00 1.8eE+08 0.00E*00 5.58E+08 Mu 56        A.00E+00 1.88E*01 4.24E*00 0.00E+00 2.27E*01 0.00E*00 2.72E+03 FE*ll        7.66t+08 4.25808 - 1.32E+08 0.00E+00 0.00E+00 2.40E*06 7.87t +07 FE 59        3.90E+08 6.43E*08 3.20E+08 0.00E+00 0.00E40 1.tM *08 6.79E*08 F.r 58       0.00E*00 6.44E+07 1.97E+08 0,00E+00 0.00E+00 0.00E*00 3.7M+08 Co f t       0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E*00 0.00E*00 2.10E*09 ul43         3.9u,;    y,j ig g,  g,3ag q9 0.00E+00 0.00E40 0.00E+00 1.42E+08 Nie65        1.05E+02 9.89E*00 5.77t+00 0.00E+00 0.00E+00 0.00E+00 1.21E+03.
                                  'CU 64        0.00E*00 1.10E+04 6.kt+03 0.00E*00 2.6M+04 0.00E*00 5.16E*05 2W45         0.1M+08 2.1M+09 1.3M+09 0.00E+00 1.36E*09 0.00E*00 3.00E+08 Zu 69        9.49E 06 1.37E*05 1.27E=06 0.00E+00 8.32E 06 0.00E+00 8.65E 04 M 83         0.00E+00 0.00E+00 5.37E+00 0.00E+00 0.00E40 0.00E+00 0.00E+00 M 84         0.00E+00 0.00E+00 3.82E*11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M 85         0.00E *J'0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.000+00 Re 86        0.00R+00 4.52E+08 2.70E46 0.00E+00 0.00E+00 0.00E+00 2.91s+07 R8 88        0.00E+00 4.37E*22 3.34E 22 0.00E*00 0.00E+00 0.00E+00 2.15E 23 08 89        0.00E+00 4.61E 26 4.10E*26 - 0.00E+00 0.00E+00 0.00E+00 4.02E.28 SR 09        3.60E+10 0.00E+00 1.0M49 0.00E 40 0.00E+00 0.00E40 1.39E+09 M 90         1.24E+12 0.00E+00 3.1M*11 0.00E+00 0.00E+00- 0.00E+00 1.67E*10 '

42 91 5.24E+05 0.00E+00 1. J0E44 0.00E+00 0.00E+00 0.00E+00 1.%E+06 M 92 7.20E+02 0.00E+00 2.93 +01 0.00E+00-C.00E+00 0 ?1E+00 1.30E+04 - Y 90 2.31E+04 0.00E*00 6.18E42 0.00E+00 0.00E+00 0.00E+00 4.57E+07 Y.91n 4.91E*09 0.00E+00 3.24E.10 0.00E+00 0.00E+00 0.00E+00 1.74E 05 Ya91 1.8W47 '0.00E+00 4.99E*05 0.00E+00 0.00E+00 0.00E.00 2.44E+09 Y 92 1.5aE+00 0.00E+00 - 4.$M 02 0.0Gr+00 0.00E+00 0.00E+00 4.50E+04 Cerwersion f actors are in mits of meere seter erem/yr pu utl/sec for ELL rwcLtdoe encept u 3 dich is in mits of aren/yr per ucl/cete meter. I l t' r-l UNT-005-014 Revision 0 Attachment 6.9 (7 of 9) 163 1 l

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

v i

                                                                                             ..                                                                            j 1
                .                                                                                  .                                                                       l LEATY VEGETABLE lx                             DOSE FACTORS.DUE TO-RADIONUCLIDES OTEE                     DAN' NOBLE GASES, R i

H AGE OkcLS Culto ( 2 Of 3 ) muCLlott OneAs cost couvEpslam f acites IONE LIVER 1.937 1sYt010 EIDNEY LusG Cl*LLI r i Y.93 2.9M42 : 0.00E*00 8.04E*00 0.00E+00 0.00E+00 0.00E 40 4.37E+06

                    ,                       2a.95 '        3.ud +06 8.48E*05 7.55E*05 0.00E+00 1.ItE+06 0.00E'00 6.05E+06                                                  I 2a.97          5.70E*02 8.24E 01 4.ht*01 0.00E+00 1.1CE+02 0.00E+00 1.25E+07 me 95          4.1M*05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.9M48 mo 99          0.00E+00 7.71E46 1.91E+06 0.00E*00 1.65E47 0.00E+00 6.3aE*06 ft.99u         4.71E40 9.24E+00 1.5M+02 0.00E+00 1.34E42 4.69E+00 5.2M+03
                                                                                                                                                                   . i g                                            TC+101         1.41E 30 1.47E 30 1.87E*29 0.00E+00'2.51Ea29 7.70E 31 4.64E 30
                                                                                                                                                                         ^

s au 103 1.5M 47 0.00E+00 5.90E+06 0.00E+00 3.06E47 0.00E+00 3.9M400 EU 105 9.1M +01 '0.00E*00 3.32E41 0.00E+00 8.0$E+02 0.00E+00 5.90E+04

                                    '       RU 106         7.45Efes 0.00E+0'0 9.30E*07 0.00E+00 1.01E 49 0.00E+00 1.16t+10 AG 110M         3.21E47-2.17E47 1.73E*07 0.00E40 4.04E+07 0.00E*00 2.5tE+09 TE 125M        3.51E+08 9.30E 47 d.67t+07 9.NE 47 0.00E+00 ' O.00E*00 3.30E48 1E.12m ,       1.32E+09 3.5M+08 1.57t+08 3.1M+0S . 3.77t+09 0.00E+00 1.07t+09
                                          -TE*127          9.85E+03. 2.65E+03. 2.11E+03 6.81E+03 '2.00E+04 0.00E+00 3.85E45 1E 129M        8.41E+0B 2.35E+08 1.31E*08 2.71E+0B 2.47t+09 0.00E+00 1.0M49 TE.129         1.32E 03 3.69E M 3.14E M 9.43E.M 3'.87E.03 0.00E+00 8.2M *02
                                          'TE*131m         1.54E+46. 5.3M+05 5.4AE+05 1.10E+06 5.ieE+06 0.00E+00 2.16".47 TE.131          2.57E15 7.BM.16 7.M,E.16 1.97E.15 7.77E.15 0.00E40 1.35E.14 1E.132 c       7.00E+46 3.10E+06 3.742+46 4.51E+06 2.8st+07- 0.005 40 3.12E+07
                                          =1 130           6.168+05 1.24E+06 6.41E+05 1.3M*f5 1.068+06 0.00E+00 5.82E*05 1 131          1.t3E+08 1.44E+08 8.17t+07 4.75E+10 2.3eE+0s 0.00E*00 1.2eE47                                    .

I 132 - 9.22E41' 1.40E42 7.NE*01 7.86E+03 2.59E+02' O.00E+00- 1.99E+02 1 133 3.5M+06 4.3M+06 1.46 S 06 8.11E+08 7.2W+06 0.00E+00 1.NE+06 1 1M 1.55E.M . 2.ges.M 1.32E M 6.42E 03. 4.40E M 0.00E+00 1.91E M s 1 135 6.NE+04 1.1M+05 5.33E+04 9.9M*06 1.73E*05~0.00E+00 8.5aE+04 C8*134. 1.40E+10 2.63E+10 5.55E+09-~0.00E*00 8.15E+0p 2.93E49 1.42E+08 CS 1M 8.NE+07 2.33E+08 1.47t+0B 0.00E+eo 1.21E+0s 1.80E+07 7.968+06 CS*137 2.39E*10 -2.29E+10 3.3M+09 0.00E+00 7.44E+09 2.40E+09 1.4M+0S - C8 138 - 6.57E.11 9.13E.11 5.79E 11 0.00E+00 6.43E.11 6.918 12 4.21E 11 M.139 4.9M*02 2.64E 05 1.44E 03 0.00E*00 2.31E 05 1.54E.05 2.86E+00 !' Corwerolen factors are in mits of opere meter.aren/yr por Wl/sec for ett i' restidos onceM N 3 dire le in mits of aremryr.per Wl/edic meter. 4

     ,          UNT-005-014. Revisior 0                                               '

Attachtnent 6.9 (8 of 9) 164 l.. _ , .- . . _

t i LEAFY VEGETABLE PADNAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R g I AGE samJP tutte ( 3 Of 3 ) Mutt 10tl ORGAN Dost Couvittlou FACTOR $ 1 tout LIvti 1.00DT 1NYRO10 El0st? - LUNG Cl LLi SA 140- 2.77t*08 2.42t+05 1.61t+07 0.00t+00 7.99t*04 1.45E+05 1.40E+08 SA *141 1.995 21 1.115 24 6.475 23 0.00E+00 9.62E 25 6.53t 24 1.13t 21 BA 142 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.00t+00 0.00t*00 0.00t+00 LA 140 3.25t+03 1.1M*03 3.53t+02 0.00E+00 0.00E+00 0.00f*00 3.16t+07 LA 142 - 3.36E M 1.071 04 3.3H 05 0.00t*00 0.00t+00 0.00E*00 2.12t+01 Ct 141 6.564+05 3.27t+05 4.06t+04 0.00E*00 1.4M *06 0.00t+00 4.0eE+08

 .                          Ct 143         1.72t+C3 9.31t+05 1.35t+02 0.00E*00 3.91t+02 0.00E+00 1.36t+07 CE 144 '       1.27t+08 3.90E*07 6.7N *06 0.00t+00 2.21t+07 0.00E*00 1.04E+10 P9 143         1.46t*05 4.37t+04 7.23t+03 0.00t+00 2.37s*04 0.00t+00 1.57t*08 PR 144         5.371 26 1.66E 26 2.70E 27 0.00t+30 8.79t 27 0.00t+00 3.54E 23 u0 147         7.15E+04* 5.79t*04 4.44E+03 0.000+00 3.10E*04 0.00E+00 9.17t+07 W 187          6.43E+04 3.81t+04 1.71t+04 0.00t+00 0.00t+00 0.00t+00 5.35t+06          .

up 239 3.86t+05 2.77t+04 1.95t +M 0.00E+00 8.01t*04 0.00t+00 2.05t+09 , , Comoralen f actore are in mits of ogJere meter *erge/yr per Wl/sec for VL reacLtdes except N 3 uhleh le 16 mits of erem/yr per WCl/ cele meter. l UNT-005-014 Revision 0 Attachment 6.9 (9 of 9) i 1 165 .

COAT's MILK PATHWAY DOSE FACTORS DUE TO

;                                           . RADIONUCLIDES OTHER THAN' NOBLE GASES, R i
                                                                                                                                        -           l AGE GACUPs ADU(1 ( 1 Of 3 )
                                                                                                                                                   )

NUCLIDE onGAN Dost CONVER$10m FAC10Rt souE LIVER T.stmY fuYeoit E!DNEY LuuG Cl LLI p3 0.00E*00 1.5M*03 1.ME+03 1. ME*03 1.ME*03 1.5M+03 1.5M

• 03 C 14 2.63E+08 5.27E+07 5.ZM+07 5.27t+07 5.2M +07 5.2M+07 5.2M+07 NA 24 2.93E+05 2.9M+05. 2.93E+05 - 2.93E*05 2.93E+05 2.93E+05 2.93E+05 P 32 - 2.05E*10 1.20E49 7.9M+08 0.00E 40 0.00E+00 0.00E*00 2.31E*09 Ce 51 0.00E*00 0.00E+00 3.43E43 2.05t*03 7.55E*02 4.55E*03 8.62E*05 MW 54 0.00E*00 1.01E*06 1.9M*05 0.00E+00 3.00E*05 0.00E+00 3.09E +06 NN % 0.00E*00 4.9eE 04 8.84E45 0.00E+00 6.32E 04 0.00E*00 1.59E 42 PE 55 3.2M + 05 2.2M *05 5.2M+04 0.00E+00 0.00E+00 1.2H45 1.29E*05 FE 59 3.bM*05 9.07E+05 3.48E+05 0.00t*00 0.00E *00 2.54E+P5 3.02E+06 '!

C0 58 0.00E+00. 5.6M *05 1.2M+06 0.00E+00 0.00E*00 0.00E+00 1.15E +07 Co 60 0.00E+00 1.9M+06. 4.34t*06 0.00E*00 0.00E+00 0.00E+00 3.70E*07 ut.63 8.07E*08 5.60E47 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E*07 ut 65 4.44E 02 5.7M 03 2.63t*03 0.00E+00 G.00E+00,0.00E+00 1.46E 01

                 .                   CU 64              0.00E+00 2.6M +03 1.25E+03 0.00E+00 6.70E*03 0.00E+00 2.2M+05
                       ,             Zu 65              1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.50E+08 0.00E+00 3.30E+08 t'

ku 69 2.51E 13, 4.00E.13 - 3.34E.14 0.00E+00 3.12E 13 0.00E40 7.21Ei 14 38 83 0.00E+00 0.00E+00 1.40E 03 0.002+00 0.00E+00 0.00E+00 2.02E 03

                                 ' 9a.84 0.00E+00 0.00E+00 2.32E.25 ' O.00E+00 0.00E+00 0.00E+00 1.82E.30 64 85              0.00E+00 0.00E 40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 28 86              0.00E+00 3.11E+08 1.45E+08 0.00E+00 0.00E+00 0.00E*00 6.14E+07 Re 08              0.00E+00 0.00E40 0.00E+00 0.00E+00 0.00E+00 -0.00E+00 0.00E+00 Re 89              0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00          .

sa.09' 3.0M+09 . 0.00E+00 8.75E+07 0.00E+00 0.00E+00 0.00E40 4.09E+08 88 90 9.83E*10 0.00E*00 2.41E+10.0.00E+00l0.00E*00 0.00E*00 2.84E+09 se 91 f .0M *04 0.00E+00 2 45E43 0.00E+00 0.00E+00 0.00E+00 2.89E+05 SR 92 1.0M40 0.00E+00 - 4.44E 02 0.00E+00 0.00E+00 0.00E+00 2.03E 41 Y 90 8.50E+00 0.00E**a 2.2eE 01 0.00E+00 0.00E+00 0.00E+00 9.01E+04 Y 91M 7.10E*21 0.00E+00 2.7BE.22 0.00E+00 0.00E*00 0.00E*00 2.11E 20 Y.91 1.03E+03 0.00E+00' 2.7M 41 0.00E+00 0.00E+00 0.00E+00 5.67E45 Ye92 6.69E.06 0.00E+00 1.9M 07 0.00E+00 0.00E+00 0.00E+00 1.17E 01 Corwersion factors are in units of somre meter.oreWyr per uct/sec for ett twelles sacept 3 3 dich is in unite of areWyr per WCl/ cele ester. UNT-005-014 Revision 0 Attachment 6.10 (1 of 12) 166

0 I i GOAT's MILK PATHWAY DOSE FACTORS DUE TO l RADIONUCLIDES OTHER THAN' NOBLE GASES, R i AGE GAOUP1 ADULT ( 2 0F 3 ) NUCLIDE ORGAN Dolt COWyttllDN FACTORS GONE Livtt f.00DT TNYt0!D KIDuff LuuG Cl tti Y 93 2.6eE 02 0.00t+00 7.406 06 0.00t+00 0.00t+00 0.C0E+00 8.50t+02 28 95 1.1M*02 3.635*01 2.4M+01 0.00t+00 5.70E+01 0.00E+00 1.15t+05 28 97 5.20E 02 1.05t 02 4.80E 03 0.00E*00 1.58t 02 0.00t @ 3.25t+03 Ne 95 - 9.91t+03 5.51t+03 2.9M+03 0.00t+00' 5.45t+03 0.00E*6C 3.34t+07' MD 99 0.00E+00 2.97t*06'5.6M*05 0.00t+00 6.73E+06 0- % ? e.89t+06 ft 99M 3.9et 01 1.13E+00 1.4M *01 0.00t+00 1.71t*01 5.528 01 6.66t+02 ,

                            .................................................f..............................

TC 101 0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 RU 103 1.7.*;+02 0.00t+00 5.2M *01 ,0.00E +00 4.66t+02 0.00E+00 1.43t+04 RU 105 1.03t4 , 0.00E+00 4.0M 05 0.00E+00 1.33t 03 0.00t+00 6.2?1 02 RU 106 2.45t+03 0.00t+00 3.10t+02 0.00t+00 4.73t+03 0.00t+00 1.5N+05 A0 110M 6.99t+06 6.4M+06 3.84E+06 0.00E+00 1.27t+07 ,0.00E+00 2.64t+W TE 125M 1.95t+06 7.00t+05 2.62E+05 5.tet+05 7.95t406 0.00E*00 7.80E+06

                            ................ f..... ........................................................

it 127M ' 5.49t*06 1.9M +06 6.69t+05 1.40E+06 2.23f+07 0.00E+00 1.84t+07 TE*127. - 7.8M *01 2.81t+01 1.70E+01, 5.00t+01 3.19t+02 0.00t+00 6.18t+03 . TE 129M 7.22t+06 2.69t+06 1.14t+06 2.48t+06 3.02t+07 0.00t+00 3.64t+07 TI 129 3.39E 11 1.27E 11 8.25t 12 2.60E 11 1.42E 10 0.00t+00 2.56E 11

                          -TE 131M        4.33t+04 2.12E+04 t.77t+04 3.36t+04 2.15f+05 0.00E+00 2.10E*06 TE 131        4.321 34 1.81t 34 1.37t 34 3.568 34 1.09E 33 0.00E+00 1.121 35 Tt*132       1.80t+05 1.86t+05 1.75E+05     2.0M+05 1.80t+06 0.00t+00 8.82t+0L 1*130         5.04E+05 1.49t+06 5.87t+05 .1.2M +08 2.32E+06 0.00E+00 1.28t+0.

1 131 -3.5M+08 5.00t+08 2.91t+08 -1.67t+11 8.71t 4 0.00E+00 1.34t+08 - l s............................................................................... 1 132 1.97E 01 5.27t 01 1.84E 01 1.84E+01 8.40E 01 0.00E+00 9.90E 02

                          .f*i33          4.64t+06 8.00E+06 2.4M+06 1.194+09 1.41t+07 0.00t+00 7.2M+06 1 134         2.425 12 6.57E 12 2.35E 12 1 144-10 1.V>t 11 0.00t+00 5.7M 15 1 135         1.54t+04 4.03t+04 1.49t+04 2.66t+06 6.47t+04 0.00t+0* ' 4.56t+04 C1 134         1.70t+10 4.04E+10 3.30t+10 0.00E+00 1.31t+10 4.34t+09 7.0M+08 CS 136         7.90t+08 3.12t+09 2.24E+09 0.00E+G3 1.73E+09 2.30E+08 3.54E+08 l                            ................................................................................

cs 137 2.21E+10 3.03t+10 1.9et+10 0.00t+00 1.0M+10 3.42t+09 5.8M+08 CS 138 2.71E 23 5.3M 23 2.6M 23 0.00t+00-3.94E 23 3.89E-24 2.29t 28 GA 139 5.30E 09 3.70F*12 1.5 M 10 0.00t+00 3.5M 12 2.14412 9.40E 09 Corwersion f actw are in mits of soaere meter arovyr per uCl/sec for ELL reacLtdee except m 3 e M. !: In mits of aren/yr per gl/ cele meter. 1 I ! UNT-005-014 Revision 0 Attachment 6.10 (2 of 12) 167 t l

1 GOAT's MII.K PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN~NOELE GASES, R i . AGE SkSJPs ADUL16 3 09 3 ) IEJCLIDt cacAs DOSE Couvltttou # ACTORS tout LiviP 1.800T TNTR010 EIDetY Luut C l .'.L 1 SA 140 3.ZM *06 4.05t+03 '2.11t+05 0.00t*00 1.38t*03 2.32t+03 6.64E+06

                ~'

BA.141 0.00E*00 0.00t+00 0.00E*00 0.00E+00 0.00E.00 0.00t+00 0.00t*00 SA.142 0.00E*00 0.00t+00 0.00E+00 5.00E*00 0.00t+00 0.00t+00 0.00t+00 LA.140 5.418 01 2.7M.01 7.218 02 0.00E*00 0.00t+00 0.00t+00 2.00E+04 LA.142 2.2M 12 1.01t*12 2.5M 13 0.00t+00 0.00t+00 0.00t+00 7.40t.09 CE.141 5.81t+02 3.9M+02 4.46t+01 0.00E+00 1.83t+02 0.00E*00 1.50t+06 CE 143 4.99t+00 3.69t+03 4.00t.01 0.008+00 1.621+00 0.00t+00 1.34E+05

• Ct.144 4.29E*04 1.79t+04 2.30t+03 0.00:>00 1.06t+04 0.00t+00 1.45L+07 Pt.143 - 1.89t+01 - 7.60t+00 9.39t 01 0.00t+00 4.39t+00 0.00t+00 8.30t+04 Pt.144' O.00E+00 0.00E*00 0.00E*00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 ND.147 1.1M*01 1.31t+01 7.81t 01 0.00t+00 7.6M*00 0.00t+00 6.27t+04 L147 7-82t+02 , 6.53t+02 2.28td2 0.00E+00 0.00t+00 0.08t+00 2.14t+05 ap.239 ' 5.52E +00 . 5.4M.01 2.99E.01 0.00E+00 1.69t+00 0.00E+00 1.11t+05 Conwesten fsetors are in mits of agante seter eren/yr per uti/sec for ett nuclides except N*3 iAlch is in mits, of aren/yr per iti/ cele meter.

4 4 N Li-

UNT-005-014 Revision 0 Attachment 6.10 (3 of 12) 168

r e 4

                                        .c                                                                                       ..

GOAT's MILK PATHWAY DOSE TACTORS.DUE TO-

           .                                                                RADDNUCLIDES OTHER THAN NOBLE GASES. Rg ,

f Att saapi TEEN ( ) of 3 ) i NUCLIDE? ORGAN 008E CouvEttl0m FACTORE SOME LIVEE- f.StBT INTROIO ' ElonET Luu4 Gl

• LLI -

u3 0.00E+00 2.038*03 2.03E*03 2.03E+03 2.03E+03 2.03E+03 2.03E*03 C.14 4.SeE*06 9.72E*07 9.72E+07 9.72E+0? 9.72E+07 9.72E+07. 9.72E+07 l 5.11E*05 5.11E45 5.11E*05 5.11E+05 5.11E+05 5.11E+05 5.11E 05 mA.24 - l p.32 3.70E.10 2.34E49 1.47E*09 0.00E+00 0.00E+00 0.00E+00 3.10E+09 Ca.51 0.00E+00- 0.00E 40 5.99E*03 3.3M+03 1.31E+03 0.55E*03 1.01E*06 e a 54 0.00E+00 1.60E*06 3.34E+05 0.00E+00 5.02E+05 0.00E+00.3.45E*06 sur46 - 0.00E+00 B.83E.04 1.57E.04 0.00E+00 1.12E.03 0.00E+00 5.81E.02

                                                                 . FE.55             - 5.79E+05 4.11E+05.9.57E+04 0.00E+00 0.00E*00 2.60E*05 1.70E*05-FE.59               6.74E+05 1.57t+06 6.07t+05 0.00E+00 0.00E+00 4.9eE+05 3.72E+06 Co.54               0.00E+00 9.52E*05 2.19t+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 Co 60               0.00E+00 3.34E+06?7.52E*06 0.00E*00 0.00E+00 '0.09E+00 4.35E+07
                       ,                                            N1 63               1.42E+09 1.00E*00 4.81g+07 0.00E+00 0.00E+00 0.00E+00 1.59E+07 y                                    L................................................................,................
                                                                  - Nt 45            - 8.12E 02 1.04E.02 4.73E.n3 0.00E+00 0.00E+00 0.00E+00 ' 5.63E41 '
                                                  +

CU 64 0.00E+00 4.73E +03 2.23E+03 0.00E+00 1.20E+04 0.00E+00 3.677 05 2m.65- ' 2.53E+0B . 8.70E+08 4.10E+08 0.00E 40 5.62E+08 - 0.00E40 - 3.72E+os 2m 69 4.62E.13 0.00E.13 6.tet.14 0.00E40 5.75E.13 0.00E+00 1.62E.12

                                            ,                    - OR.03                0.00E+00- 0.00E 40 2.50E 03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 be.04            - 0.00E 40' O.00E+00 4.14E.25- 0.00E 40 0.00E+00 0.00E+00 0.00E+00 08 05               0.00E*00 0.00E+00 0.00E+00 0.00E40 0.00E+00 0.00E*00 0.00E+00 me e .           ^ 0.00E+00'5d70+08'2.67E48 0.00E+00 0.00E+00 0.00E+00 8.40E+07 See '               O.00E+00 0.00E+00 0.00E40 0.00E+00 0.00E+00'O.00E+00 0.00E+00 30 09               0.00E+00 0.00E+00 0.00E+00 .0.00E+00 0.00E+00 0.00E+00 0.00E+00               .

On 09 5.62E+09. 0.00r40 1.61E48 0.00E+00 0.00E+00 0.00E+00 6.e#E+08 On.90 - 1.ME+11. 0.00E+00 - 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 OR.91 1.12E+05 'O.00E+00 4.44E+03 0.00E+00 0.00E*00 0.00E+00 5.0eE+05

             -.                                                     Os.92               1.00E+00 0.00E+00 8.00E.02 0.00E*00 -- 0.00E+00 0.00E+00 4.70E*01
                                                                 - Y.90               ' 1.54E41 0.00E+00 '4.21E.01 0.00E40 0.00E+00 0.00E40 1.29E+05 Y.91el '            1.31E.20 0.00E+00 5.02E.22 0.00E+00 0.00E+00 0.00E+00-6.21E*19                                                           '

t 91 1.90E+03 0.00E+00 5.00E+01 0.00E*00 0.00E+00 0.00E+00 7.77E*05

                                                                 ' V.92                 1.24E 05 0.00E+00 3.50E.07 0.00E+00.0.00E+00 0.00E+00 3.39E.01
                                                                  - Corwerslen facters e*e in mits of emere aster.areatyr per WCl/sec for.att nuclides eatet W.3 which is in units of aremrye per uCl/ sele amter.

x . R UNT-005-014 Revision 0- Attachment 6.10 (4 of 12) 169-w- rp ,-ww,e,yu p- - y- y-.,t-  % v- 7 , -- - " - - - 77--' -TT

• q
• l GOAT's MILK' PATWAY DOS TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 1

      ,-                                                                                           i                                      ,

1 1 4GE cacurs TEEN ( 2 of 3 ) .

                                                                                                                                        ]

muttIDE CeGAs Oost couvEastou IActeas Ocut LivEt f .etmV TNYeotD KIDmEY tuuG Cl*tt! Y *' 4.ME 02 0.00E+00 1.36E 03 0.00E*00 0.00E+00 0.00E+00 1.51E*03 24 95 1.9eE+02 6.2M+01 4.30E *01 0.00E*00 9.18t+01 0.00E+00 1.44E*05 2A 97 9.4M 02 1.8?E 02 8.62E*03 0.00E+00 2.N E 02 0.00E*00 5.03+03 me 95 1.HE *04 9.37E+03 5.1M*03 0.00E+00 9.0eE*03 0.00E*00 4.01E+07 no 99 0.00E +00 5.37E+06 1.02E+06 0.00E*00 1.23E*07 0.00E+00 9.61E+06

                              *C+99M        6.91E 01 1.9M*00 2.30E *01 0.00E+00 2.87E*01 1.0M +00 1.27E+03                         .

TC 101 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E*00 -0.00E+00 0.00E+00 RU 103 2.17E*02 0.00E*00 9.29E*01 0.00E *00 7.46E*02 0.00E*00 1.81E+04 ' a0 105 - 1.80E 04 0.00E +tn, 7.29E 05 0.00E+00 2.37E 03 0.00E+00 1.52E.01

                              ...........................q..................................................

RU 106 3.47E*03 0.00E+00 5.6M+02 0.00E+00 8.6aE+#3 0.00E*00 2.1M*05 A4 110M 1.1M +07 .1 09E+07 6.6H +06 0.00E+00 2.00E+07 0.00E*00 3.07t+09 TE 125M 3.60E*06 1.30E*06 4.82E +05 . 1.01E *M 0.00E*00 0.00E*00 1.0M*07 TE 127M 1.01E+07 3.59E+06 1.20E +06 2.41E+N 4.10E*07 0.00E+00 2.52E+07 TE 127 1 A M +02 5.1M+01 3.12E+01 1.00E+02 5 8eE*02 0.00E+00 1.12E+04 . TE 129M- 1.32E+07, 4.90E+06 2.09E +06 4.26t+06 5.5M+07 0.00E+00 4.96t+07 TE 129 6.24E.11 2.33E.11 1.39E.11 4'.46E*11 2.62E.10 0.00E+00 3.41E*10 TE 131M 7. tee +04 3.7eE+04 3.15E+04 5.HE+04 3.ME+05'O.00E+00 3.03E+06 . TE 131 7.90E 34 3.2M.34 2.47E 34 6.09E 34 3.45E 33 0.00E+00 6,49E 35-TE 132. 5.1M +05 .3.26E+05 3.07t+05 3.44E+05 3.13E+06 0.00E+00 1.03E+07 1*130 8.86E+05 2.56E+06 1.02E+06 2.00E+08 3.9H+M 0.00E+00 1.97E+06-1 131 6.45E +08 9.0M *08 4.8H +08 2.63E*11 1.5H +09 0.00E+00 1.79E+08 l 1 132- 3.50E 01 9.1M 01 3.2eE 01 3.00E +01 1.44E+00 0.00E +00 3.get 01

                            . 1 133          8.4aE+06 1.44E+07 4.3M+06 2.01E+09 2.5M+07 0.00E+00 1.09E+07 l.134         4.30E 12 1.14E 11 4.00E 12 1.90E*10 1.00E 11 0.00E+00 1.50E 13
                             '!*135          2.74E+M 7.04E+M 2.61E+04 - 4.5M+06 1.11E+05 0.00E+00 7.81E+04 CS*134        2.ME+10 4.93E+10 3.22E+10 0.00E*00 2.20E*10 8.41E+09 8.62E+08 CS 136        1.34E+09 5.29E*09 3.5M+09 0.00E+00 2.att+09 4.54E+08 4.26E+08 Cs 137        4.02E+10 5.NE*10 1.8M+10 0.00E+00 1.82E+10 7.06E+09 7.60E+08
    .                          Csk138'       4.92E 23 9.45E 23 4.72E 23 0.00E+00I 6.9et 23 8.12E.24 4.29E 26 BA 139        9.81E 09 6.90E 12 2.84E*10 0.00E+00 6.50E 12 4.75E 12 8.75E 08 Conversten f actere are in mite of soaere seter.orum/yr per LCf/sec for ett nuclides except N.3 4Alch le in mits of arem/yr per uCf/c@f c ever.

l' l UNT.005-014 Revision 0 Attachment 6.10 (5 of 12) 170 l 1 _ _

e.

                                                                             . p GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Rg AGE GROUP TEtu ( 3 Of 3 )

WUCLIDE caEAm 00SE CouvEt$10N Facions tout liver 1.00DY TNYt010 E10NEY tuuc Gl.LLI BA.140 5.6M+06 7.13E +03 3.75E +05 0.00E+00 2.42E*03 4.80E+03 8.9eE*06 4A.141 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.00E+00 0 bOE+00 0.00E+00 SA.142 0.00E *00 0.00E+00 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.00E+00 LA.140 9.72E.01 4.79E.01 1.2M .01 0.00E*00 0.00E*00 0.00E+00 2.74E+04 LA.142 4.02E.12 1.79E*12 4.45E.13 0.00E*00 0.00E+00 0.00E+00 3.44E.08 ' CE.141 1.0M +03 7.12E+02 8.1M+01 0.00E*00 3.35E+02 0.00E+00 2.04E+06 CE*143 9.17t+00 6.67E*03 7.45E.01' O.00E+00 2.99E+00 0.00E+00 2.00E *05 CE.144 7.90E*04 3.27E*04 4.24E+03 0.00E*00 1.95E+04 0.00E*00 1.99E*07 Pt.143 3.4aE+01 1.39E+01 1.7M *00 0.00E+00 8.00E+00 0.00E*00 1.15E+05' Pt.144 0.00E+00 0.00E+00 0.00E*00 0.00E*00' 0.00E+00 0.00E*00 0.00E*00 MD.147 2.1M*01, 2.36E+01 1.42E+00 0.00E *00 1.39E*01 0.00E*00 8.53E+04 W.187 1.OE+03 1.17t+03 4.00E+02 0.00E*00 0.00E*00 0.00E+00 3.15E+05 m*.239 1.05E+01 9.9M .01 5.52E.01 0.00E*00 3.12E+00 0.00E+00 1.60E*05

• 1 w

Corwersion f actors are in mits of ocuare meter re'en/yr per Wl/sec for att

• tuclides except u.3 iAlch is le units of arem/yr per Wl/ cele meter. . .

k INT-005-014 ~ Revision 0 Attachment 6.10 (6 of 12) 171

p GOAT's MR% -PATHWAY DOSE FACTORS DUE TO

                             %DIONUCLEDES OTHER THAN NOBLE GASES, R g,

AGE Ga0UP: ENILOE1of3) NUCLIDES ORf.AN 005E CONVERl10N FACTORS 40NE LIVER f.80DT TNWol0 KIDNEY LUNG Ol LLI N3 0.00E *00 3.20E+03 3.20E*03 3.20E +03 3.20E*03 3.20E+03 3.20E+03 C 14 1.19E *09 2.39E+08 2.3M + 08 2.39E+08 2.39E*06 2.39E*08 2.39E*06 NA 24 1.06E*06 1.06E*07 1.0M *06 1.0M *06 1.0M*06 1.0H+06 1.0M+06 P 32 9.33E+10 4.37t Mr9 3.60E*09 0.00E *00 0.00E*00 0.00E+00 2.58E*09 Ca 51 0.00E+00 0.00E 05 1.22E +04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN*54 0.00E*00 2.52E*M 6.70E+05 0.00E *00 7.0M *05 0.00E+00 2.11E*06 o NN 56 0.00E*00 1.54E.03 3.48E 04 0.00E+00 1.86E.03 0.00E+00 2.23E 01 FE 55 1.39E*06 7.71E*05 2.39E+05 0.00E*00 0.00E+00 4.36t+05 1.43E+05 FE So 1.5M + 06 2.53E+06 1.26t+06 0.00E+00 0.00E +00 7.33E +05 2.63E*06 C0-58 0.00E*00 1.45E+06 4.45E+06 0.00E+00 0.00E+00 0.00E +00 8.49E

• 06

           ,'        CD 60           0.00E*00 5.,18E*06 1.53E+07 0.00E+00 0.00E+00 d.00E+00 2.87E+07
   .                 NI 63           3.5M+09 1.90E*08 1.24E+08 0.00E+00 0.00E+00 0.00E*00 1.28E+07 kl.65           1.99E 01 1.8M.02 1.09E 02 0.00E*00 0.00E+00. 0.00E+00 2.29E*00 CU f4           0.00E+00 8.32E+03 5.02E*03 0.00E+00 2.01E+04 0.00E+00 3.90E+05 IN 65           4.96E+08 1.32E*09 8.22E*06 0.00E+00 8.33E+08 0.00E+00 2.32E*08 2N 69           1.14E 12 1.64E.12 1.52E 13 0.00E+00 9.9M.13 0.00E+00 1.03E 10 84 83           0.00E*00 0.00E*00 6.34E 03 0.00E+00 0.00E+00 0.00E*00 0.00E*00 84 84           0.00E+00 0.00E+00 9.375 25 0.00E+00 0.00E*00 0.00E+00 0.00E+00 8R 85           0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 88 86           0.00E+00 1.05E+09 '6.4M+08 0.00E*00 0.00E+00 0.00E+00 6.7M+07

• 88 88 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E*00 0.00E *00 88 89 0.00E+00 0.00E+00 0.00E*C0 0.00E+00 0.0Gd*00' O 00E+00 0.00E+00 '

Sa.89 1.39E+10 0.00E+00 3.9M+08 0.00E+00 0.00E+00 0.00E+00 5.38E+08

     .               8a.90           2.35E+1' 3.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.1M+09
                   '84 91            2.74E+05 0.00E+00 1.03E*04' O.00E*00 0.Os1E +00 0.00E+00 6.04E+05 8e 92           4.58t+00 0.00E+00 1.84E*01 0.00E*00 0.00E*00 0.00E+00 8.68E*01
                    'Y.90            3.87E+01 0.00t+00 1.03E+00 0.00E*00 0.00E+00 0.00E+00 1.10E+05 Y.91M           3.21E 20 0.00E+00 1.1M 21 0.00E+00 0.00E+00 0.00E+00 6.29E.17 Ya91            4.68E+03 0.00E+00 1.25E+02 0.00E*00 0.00E+00 0.00E*00 6.24E+05 Y 92            3.04E 05 0.00E +00 8.69E.07 0.00E*00 0.00E*00 0.00E+00 8.77E 01                   ,

Corwersion f actore are in mits of agere meter.oresvyr per uCl/see for ett twctidos except N 3 shich is in mits of aresVyr per uCl/ctelt ester. UNT-005-014 Revision 0 , Attachment 6.10 (7 of 12) 172 ,

GOAT's MILK PATHWAY DOSE FACTORS DUE TO. RADIONUCLIDES OTHt.R THAN NOBLE GASES, R

           ,                                                                                           f AGE group CNILD ( 2 Of 3 )                                                           ..

NucLIDEs. DeGan 00sE comytestou FAgT0as 00NE Livet f.tcDY TWYROID KIDNEY LUNG El.LLI Y.93 1.21E 01 0.00E*00 3.3M.03 0.00E*00 0.00E+00 0.00E +00 1.81E*03 2a.95 4.60E*02 1.01E42 9.00E+01 0.00E*00 1.45E+02 0.00E+00 1.05E+05 te.97 2.30E.01 3.338 02 1.9M.02 0.00E+00 4.73E.02 0.00E+00 5.04E+03 N6 95 3.81E+M 1.49E44 1.0M +04 0.00E+00 1.60E+04 0.00E40 2.75E*07

                        *. . no.99           0.00E+00 9.7M+06 2.42E*06 0.00E+00 2.09E*C7 0.00E+00 8.00E +M 1C.99M         1.59E+00 3.11E+00 5.15E*01 0.00E+00 4.52E+01 1.58E+00 .1.7M*03

• TC.101 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 tu.103 5.14E+02 0.00E +00 1.90E*02 0.00E+00 1.29E+03 0.00E+00 1.33E+04 av.105 4.54E.04 0.00E*00 1.NE .04 0.00E+00 4.03E.03 0.00E+00 2.99E.01 RU.106 1.11E*04 0.00E+00 1.30E+03 0.00E+00 1.50E+04 0.00E+00 1.72E+05 AC.110M 2.51E+07'1,69E*07 1.35E+07 0.00E*00 3.15E+C7 0 00E*00 2.01E+09 TE.125M 8.tSE46 2.40E+06 1.18E+06 2.44E+06 0 WE 00 . 0.0W+00 8.54E+06 TE.127M ' 2. w +F f. m +06 2.96is06 5 5rE+06 7.12E+07 0.00E+00 E 02E+07 TVit7 - 3.5M+02 9.63E41 7.* L o1 2.47t+02 1,02E 43 0.00E+00 1.4 W O4 ft.129M 3.2M*07 9,09E+06 5.06E46 1.05E+07 9 36E+07 0.00E+00 3.9M-07

                              .......................................................~.C.*.....................

- TE.129 1.54E.10 4.30E.11 3.65t*11 1.10E.10 4.50E.10 0.00E+00 9.58E.09 l 1.92E+05 6.NE+04" 7.0M +04 1.364+05 6.42E45 0.00E+00 2.69t+06 it.131M ft.131- 1' 94E.33 5.91E.34 5.7M.34 1.48E.33 5.au.33 0.00E 40 1.02E.32 TE.132 ~ 1.2M+06 5.44E45 6.5M+05 7.93E+05 5.05E+06 0.00E+00 5.4at 06 1 130' 2,0M*96 4.19E*06 2.1M*06 4.61E+08 6.26E+06 0.00E*00 1.96E+06

                            .1 131            1.564+09 1.5M+09 8.94E4B 5.20E+11 2.SaE+09 0.00E40 1.40E+08
                               .................q.............................................................

1 132 8.2M.01 1.52E+00 6.99E.01. 7.05E+01 2.33E+00 0.00E+00 - 1.79640 1 133 2.06t+07 2.55E+07 9.ME+06 4.73E+09 4.25E+07 0.00E*00 1.03E+07

             ..                1 134          1.02E.11 1.09E.11 8.70E.12 4.35E.10 2.09E.11 C.00E40 1.2H.11 1 135 ..       6.40E+04 1.1 M+05 .5.52E*04 1.03E47 .1.79E+05 0.00E+00 8.00E+04
         '                     cs.1M          6.79E+10 1.11E+11 2.35E+10 0.00E+00 3.45E+10 1.24E+10- 6.01E+08 l

j cs.136 3.03E+09 8.5aE+09.5.40E+09 0.00E+00.' 4.44E+09 6.63E+08 2.93E+08 (; ................................................................................ CSI 137 9.6M+10 9.26t+10 1.3M+10 0.00E+00 3.02E*10 1.09E+10 ~ 5.00E+08 I-l cs 138 1.19E.22 1.66E.22 1.05E.22 0.00E+00 1.1 M.22 1.2M.23_ 7.NE.23 8A.139- 2.41E.08 1.29E.11 6.90E.10 0.00E+00-.1.12E.11 7.5M 12 1.39E 06 Camerslen facters are in wilts of espere seter.arem/yr per ist/sec for ett nuclidos except N.3 dich is in units of aren/yr per ucl/ cele ester. UNT-005-014 Revision 0 Attacnment 6.10 (8 of 12) 173

GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g AGE OtouP Cull 0 t 3 of 3 ) NUCLICE$ ORGAN Dost COWytt$10N f Acipts 50Nt Livtt f.800Y TNYt010 Kl0Ntf LUNG Ol*LLl sA.140 1.41t+07 1.23t+04 8.20t*05 0.00t+00 4.01t*03 7.34t+03 7.12t+06 gA.141 0.00t+00 0.00t+00 0.00E*00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 sA.142 0.00t+00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00E+00 0.00t+00 ,

                     ...............................r................................................

LA.140 2.33t+00 8.144 01 2.54t.01 0.00t+00 0.00E+00 0.00t+00 2.27t+04 LA 142 9.721 12 3.10t.12 9.70t.13 0.00t+00 0.00t+00 0.00t+00 6.14t.07 CE.141 2.62t+03 1.31E*03 1.94t+02 0.00t+00 5.74t+03 0.00t+00 1.63E+06 Ct.143 2.25t+01 1.22t+04 1.77t+00 0.00t+00 5.12t*00 0.00t*00 1.79t+05 Ct.144 1.95t+05 6.11t+04 1.04t+04 0.00E*00 3.38t+04 0.00t+00 1.595+07 Pt.143 8.62t+01 2.59t*01 4.28t+00 0.00t+00 1.40E+01 0.00t*00 9.30t+04 Pt*144 0.00t*00 0.00E*00 0.00t+00 0.00t+00 d.00C+00 '0.00t+00 0.00t*00 N0 147 5.33E+01 4.32t*01 3.35t+00 0.00t+00 2.37t+01 0.00E+00 6.85t*04 W 187 3.47t+03 2.05t+03 9.21t+02 0.00t+C4 0.00t+00 0.00t+00 2.84t+05 WP.239 2.59t+01 1.86t+00 1.31t+00 0.00t+0S 5.38t+00 0.00t+00 1.38t+05 Corwersion f actors are in mits of agante meter.aree/yr per ul;l/see for att mucLtdes except N.3 which is in urrits of aram/yr per u't/celc seter. e UNT-005-014 Revision 0 , Attachment 6.10 (9 of 12) 174

GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES. R i

                                       ~ 4GE group 8 INf 4N1 ( 1 Of 3 )

muCtlDE OR44m Dost CouvEttI0N f 4Cf0R$ tout Livt3 1.94WT TWYROID EIDuET LUNG Gl.LLI u3 0.00E*00 4.8M +03 4.NE+03 4.8M+03 4.NE43 4,.8M+03 4.8M*03 j C.14 2.34E+M 5,0M+08 5.00E*08 5.00E *08 5.00E+08 5.00E+08 5.00E+08 M4 24 1.85p06 1.85E+06 1.8H+06 1.8H+06 1.85E*06 1.85E*06 1.8H +06 ) P 32 1.92E*11 1.13E*10 7.4M *09 0.00E+00 0.00E+00 0.00E+00 2.60E+a9 Ct 51 0.00E *00 0.00E*00 1.94E+04 1.2M*04 2.7M+03 2.4M+04 5.64E45 Mu 54 0.00E*00 4.68t+06 1.0M*06 0.00E+00 1.04E+06 0.00E+00 .1.72E d6 ** Mu 56 0.00E+00 3.77E.03 6.50E.04 0.00E+60 3.24E.03 0.00E*00 3.43E 01 fE 55 1N +06 1.1M*06 3.03E +05 0.00E40 0.00E+00 5.55p 05 1.44E +05 FE 59 - 2.92E+06 5.10E +06 2.01E*06 0.00E *00 0.00E+00 1.51E+06 2.43E*06 CO 58 - 0.00E+00 2.91E+06 7.26E+06-0.003+00 0.00E+00 0.00E*00 7.25E+06

                                       .C0 60          0.00000 1.0M *07 2.50D07 0.00E *00 0.00E+00 ' 0.00E*00 2.52E+07 Lt.63         4,19E+09 ' 2.5M+08 1.45E*08 0.00E+00 0.00E+00 0.00E+00 1.2M*07 b l .65 .-    4.21E.01 4.7M 02 2.17E 02 0.00E+00 0.00E 40 0.00E+00 3.62E+00 CU 64         0.00E.00 2.07E+04 9.57E*03 0.00E+00 3.50E44 0.00E*00 4.24E+05 In 65 '       6.66E*08 2.20E49 1.05E49 0.00E+00 1.11E+09 0.00E+00 1.93E49                 .

tu 69 - 2.42E.12 4.36E.12 3.24E 13 0.00E+00 1.81E.12 0.00E40 3.55p10 l~ , 04 83 0.00E+00 0.00E+00 1.34902 0.00E+00 0.00E+00 0.00E40 0.00E+00 M 84 ,0.00E+00 0.00E+00.1.81E.24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P. 85 - 0.0nE40 0.00E+00 0.00E+00 0.00E+1k 0.00E+00 0.00E+00 0.00E+00 R8 86 0.00E+00 2.67t+09' 1.32E+09 0.00D00 0.00E+00 0.00E+00 6.83E+07

• R8 88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A8 99 0.00E+00 0.00E 40 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ER 89 2.64E+10 0.00E+00 7.50008 0.00E+00 0.00E+00 0.00E+00 5.43E+08 OR 90 2.55E+11 0.00E*00 6.50E+10 0.00E+00 0.00E 40 0.00E 00 3.1M HP9 98 91 5.70E+05 0.00E 40 2.06E+04 0.00E+00 0.00E+00 0.00E+00 4.75E+05 SR 92 9.75E+00 0.00E+00 3.62E*01 0.00E+00 0.00D00 0.00E+00 1.05E42 Y *90 - 8.17E+01 0.00000 2.1M +00 0.00D 00 0.00E+00 0.00E+00 1.13E+05 T 91m 6.81E.20 0.00E+00 2.32E*21 0.00E+00 0.00E+00 0.00E+00 2.27E 16

                                        - T 91 -       8.79p03 0.00E+00 2.34902 0.00000 0.00D00 0.00Et00 6.30E+05 Y 92         6.45E 05 0.00E+00 1.81E 06 0.00000 0.00E+00 0.00E+00 1.23p00 I                                          Corwerelen factors are in mits of espaare meter.aren/yr per uCl/nec for ett nuctidos except u 3 dich le in units of urge /yr per Wl/ cele aster.

l l-i

             - INT-005-014 Revision O'                                                                Attachment 6.10 (10 of 12) 175                                                                ;

sL~ -,- + 4 m >-? *A.-e -mr+m*h- = . + + 44 e *G4 4 -a- >-m--- a,---~ -a -aA--- w,b, -_+*- GOAT's MILK PATHWAY DOSE FACTORS DUE TO + RADIONUCLIDES OTHER THAN' NOBLE GASES, R f AGE GROUPS IbfAst ( 2 Of 3 ) unIDE ' Onsam cost couvEaston iActons 80ut LivEt f.80DY TNYROID KIDatt LuuG Cl LLI T 93 2.59E 01 0.00E*00 7.0H 03 0.00E *00 0.00E+00 0.00E+00 2.04E+03 2a*95 8.17E 42 1.99E*02 1.41E*02 0.00E40 2.14t 42 0.00E+00 9.91E+04

                       -                 2R*97          4.87E 01 8.37E *02 3.82E 02 0.00E+00 8.43E 02 0.00E+00 5.34E+03 We*95          7.12E*04 2.93E*04 1.70E+04 0.00E*00 2.10E+04 0.30E 40 2.48E*07 MD 99           0.00E *00 2.50E+07 4.87E+06 0.00E +00 3.7M*07 0.00E*00 8.22E+06 1C 994         3.30E*00 6.80E+00 8.76E41 0.00E+00 7.32E+01 3.56E+00 1.90E+03 TC 101         0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E*00 RU+103         1.04E*03 .0.00E+00 3.48E*02 0.00E+00 2.17E+03 0.00E+00 1.27E*04 RU 105         9.6M 04 0.00E+00 3.25E 06 0.00E*00 7.11E 03 0.00E+00 3.84E 01 8U 106         2.20E+04 0.00E*00 2.85E*03 0.00E+00 2.'r0E +04 0.00E+00 1.73E+05 AG 110M        4.63E+07 3.30E+07 2.24E+07 0.00E+00 4.tM+07 0.00E+00 1.75E+09 TE 125M       1.81E+07 ,6.0M+06 2.4H+06 6.09E *06 0.00E+00 0.00E +00 8.62E*06                                       .

f t.12m 5.05E+07 1.68E+07 6.12E+06 1.4M+07 1.24E+08 0.00E+00 2.04E+07 TE 127 7.58E+02 2.54E+02 1.63E+02 6.1M42 1.85E+03 0.00E+00 1.59E+C4 TE 129M 6.69E+07 2.29E+07 1.0M *07 2.57E+07 1.67E*08 0.00E+00 3.99E+07

                                          ................s. . ...............e.............................................

TE*129 3.2M *10 1.12E 10 7.62E*11 2.73E.10' 8.12E 10 0.00E*00 2.61E 08 TE 131M 4.0H45 1.63E45 .1.35E+05 3.31E+05 - 1.12E+06 0.00E+00 2.7M+06 TE*131 4.11E-33 1.52E 33 1.15E 33 3.67E*33 1.0M 32 0.00E+00 1.6M 31

• TE*132 2.53E+06 1.25E+06 1.17E+06 1.8H+06 7.84E+06 0.00E+00 4.64E+06
• 1 130 ~ 4.26E+06 9.3?E 06 3.76t+06 1.05E+09 - 1.03E+07 0.00E+00 2.01E+06' 1*131 ~ 3.2H +09 3.8M+09 1.69E+09 1.2M+12 4.49E+09 0.00E+00 1.37E+08 ,

l'132 1.72E+00 3.48E+00 1.24E+00 1.6M42 3.89E40 0.00E+00 2.82E+00 - 1+133 4.35E+07 6.34E47 1.8M47 1.15E+10 7.45E+07 0.00E+00 1.07E+07 l*1M 2.11E.11 4.33E 11 1.5M 11 1.01E 09 4.84E 11 0.00E+00 4.47E 11 l 135 1.35E+05 2.68E*05 9.77E+04 2.40E+07 2.99E+05 0.00E+00 9.70Ee04 .

      .                                    Cs 134        1.09E+11 2.04E+11 2.0M+10 0.00E40 5.25E+10 2.1M+10 5.54E+08 Cs 136        5.9M+09 1.74E+10 6.51E+09 0.00E+00 6.9M+09 1.42E+09 ' 2.6M+08 CS*137        1.54E+11 1.81E+11 1.20E*10 0.00E*00 4.8H+10 1.9M*10 5.05E+08 Cs 138        2.52E*22 4.09E 22 1.98t*22 0.00E*00 2.04E*22 3.19E*23 6.54E 22 8A*139        5.13E 08 3.40E 11 1.48E 09 0.00E+00 2.04E 11 2.Det 11 3.2M 06 Corwereien f actere are in mits of seance meter erem/yr per ucl/sec for ett maclides eacept W 3 Wtich.is in mits of arem/yr per uC1/c@lc aster.

i

   .         UNT-005-014 Reviaton 0                                                                            Attachment 6.10 (11 of 12) 176

 .c s

GOAT's MILK PATHWAY LOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R i AGE C40lP8 lNFAN1 ( 3 0F 3 ) NUCL1H ONGAN Dost CONVER$1Cu fACIONS tout LIVEE 1.9E1 INYkol0 El0tCT LUuG Gt LLI 8A*140 2.89E *07 2.89E+04 1.49E*06 0.00E*00 6.87E* .. 04 7.10E *06 BA 141 0.00E+00 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 SA 142 0.00E*00 0.00E *00 0.00E *00 0.00E+00 0.00E+00 0.00E +00 0.00E*00 LA*140 4.8H +00 1.92E*00 4.93E*01 0.00E*00 0.00E*00 0.00E+03 2.25E+04 LA*142 2.040 11 7.49E *12 1.7VE 12 .0.00E*00 0.00E+00 0.00E+00 1.2M .06 CE*141 5.20E*03 3.1M+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.ME+06 . CE 143 4.7M+01 3.1M+04 3.60E*00 0.00E+00 9.20E+00 0.00E+00 1.NE+05 CE 144 2.7M

• 05 1.14E+05 1.5M +04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 Pt.143 1.7EE+02 6.6M*01 8.84E+00 0.00E*00 2.48E+01 0.00E+00 9.41E+04 Pe 144 0.00E *00 0.00E*00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E*00 ND 147 .1.0M +02 1.09E*02 6.65E+00 0.00E+00 4.19E*01 0.00E+00 6.88E*04

              .                ' W 187        7.30E+03 5.0M +03 1,75E+03 0.00E+00 0.00E+00 0.00E+00 2.98E*05 NP 239       S.48E*01. 4.90E*00 2.77E*00 0.00E+00 9. TIE *00 0.00E+00 1.42E+05 Cormrsion f actors are in mitt of upere meter.orem/yr per tCl/sec for att tuctie'as except 113 which is in mits of orem/yr per LCl/ctbic meter.
      +-

l t i i UNT-005-014 Revision 0 Attachment 6.10 (12 of 12) 177

                                                                                                                                       'l

LIQUID WASTE MANAGEMENT SYSTEM EFFLUENT SOURCES- ,

                                                                                              'AND RELEASE PATHWAYS'AND POINTS                                                                                                 -

SOURCES SYSTEnrS -

                                                                                                                                                                                           '                      ftELE ASE PATMarAvs    (~

mod POssTS tasft OnAssigActa ,,,,g, - eastt fAset t cvCS OC3 Tm a ,,g g C I- M WR j{ CC3 SARE TA8M . g agg SCIRC ACO 8 I 4 80suC ace COECfMTRAff h 90tC ACO ggqggy,9,g7gg ColettegAft 85CM820E IR.OCK 840 3 g 9r IETE" l C Asc A Cr j( I CNM" M 3y )( j(j( RAmat0se g "I" l WALW LEAst OFFS l OL MPMta?OR lJk e, eue. - - gygmsgo p Pets-stE-De2 P g c4tf CASit "pt47 ruft STOItAM II

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• ggg,gyan OrSTR9JT8088 >

twSMcASp(P t At$eRY StjMS g "- - g P4tf-84E-OS* ? g BLOCK 190 4 g

       <0beTAbdNAftO SSgt$             bI                                                       =J

_ g , 50ps?AAdBtAff0 SHOWERS [ 47 waoet 9 CPS l LAtJbeRY DrSCpWIG I ~ TApots M rtita l% pui,, y, I ' A A86 O A A80 8 ," Tf*MA'C TRAfESFER if j I DrSG M r R10safiOBI I STRUCIURE

                                                                                                                       -                                                                      neosofon         I l

3' opeCE TMfr' C00Lesc Pate-sIE-io00 I' ~ ' ColdPCBENT Assue.sssty COOLego 9(At et? C00Lesc COesposENT I tuo weeta$ + toeta A Ase S 9 C00Lesc 10ete 9 Jt g ' j^ PutPS A Age S * , A"8 I

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                                                                                                                                                                       ,,                            mesesse                EttvCR mer ST(Alf M9EGA104                                                                                                                                                l OL0000ess D(Af                                                                                            '.e                                                 g (zCHA01C(4 A Af6 9

[ > I . l UNT-005-014 Revision 0 Attaciunent 6.11 (I of 2)  ;

                                                                                                                                                                                                                                       ~

178 4

n . _ _ _ _ _ _ _ LIQt4D WASTE MANAG2?fENT SYSTEM EFFLUENT SOURCES _ AND RELEASE PATHWAYS AND POINTS , (cont'd)

                                                                                                          'STSTEMS                                                               Rf1FASE FATMWAYS AfeO ynggryg SOtfRCES e
                                                                .                                                                                                              g I                                                                  i R.AS
                                                            '                                                       E                                                                                                                             j YtmBINE BU11.DINC                                                     e                                        TW                                                                                                                                  ;

FtIIOlt tHtAINS AND e 1 INMSTt!AL WASTE StWS il 9 e IMMSTRIAL ggmy pggg WI AN At'ToatAfic e WASTE 4 A AND B -e MrMITOR g Sol.ATf0N TALVF.S 8 9 Stw NO. I PR!4-f RE4778 9

                                                                                                        #                                                      OfL SFFAFATOR
                                                                                                                                                                              '       ""                        40 AAFFWT-i r                       ip                            ogg' stpARAtpa                                       I'AI"       '*
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                                                                                                               ~

Plf TANK ASST. WE SYSTFM 8 e I"L e Stw PL9FS -e e WASTE SUMP w A g,3 , g NO. 2 9 e IP $ ) e RAR w WASTF g

                                                                                    '                                                                                         g DRY (X10 LING g

TodE:S A AND ppm-tRE-6775 S StWS g g t l, IL DRY MING ggy ptyg ,p g g y r MANt?AL 39)f.AT1HN YA3 TFS tgyrg gen, g a ggg 7 g g 3 UMP RADIATION 40 APPENT pe1NITOR I CA!EAL PRM-tRE-6776 l, 8 DRY CDOLifeC StW PtWS 1, TOWER NO, 2 M C  ?  ? MAWA!, IW.ATIOlt TALVES g Agg g g o I I*As j ] M WASTF , 8 TANFS UNT-005-014 Revision 0 At.tachment 6.11 (2 of 2)

                                                                                              ,179
                                                                                                                                                                                       - '  ' ~ -" '
                                                                                                                                                                                                       ' ' ' ' '  ~ - -  " ' ' -' ' ' ~ '
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                                                                                                                                                                                                                 ,~

GASEOUS EFFLUENT 50URCES, GASEOUS WASTE MANAGEMENT ~ SYSTEM EFFLUENT SOURCES AND EXHAUST RELEASE POINTS l

                                                                                                                                   ,m,,,                                                                              RELEASE FotNTS s cRCEs                                                  ,                                                                 _

I

                                                                                                                 ^                                                               AUTO-ISOLAT10N TALvE I   QetS CAS DECAT CAS SURCE NEADER                                                                                                                                                               I l   TAM S: FLA$N TANK.

• WASTE CAS CAS DECAT WOLUME CTRL TAME. CAS BORtc i,CID CONTR9. SF ' TANK ]gm FTLTER 4 COMPRESSORS A AND 5

                                                                                                                                       -*            TAMS.A.B AND C g           O        O     ',

QUENC3 TAM. REACT 0g RADIATION MD41 TON g

                                  ^                                  -.

DRAI2 TAM. SAMLING Jl FFM-IPE-0MS I CCNT. TENT READER ~ i STSTEM. EQt!tF. DRA1't

• pg, ,3

                                                    $N                                                                                                                                                            i I

st.s/Cvs vrNT. syst. vuf CAs CottECTION READER I L18tS VENT CPS COLLECT. b H ' 1P I READE2. RAbt0-CMEW  ? 8 IJL90RATORY. COUNTINC N TAM ON W W 9 REACTOR AVE CONTAINMENT FRM-13E-et00.35 g RCOM.TALVE CALLERT. FURCE w DECON ARTA AND ROOM. SLDC. TENTitJLTION g PRM-IRE-0100.25 , SANFLE LASORATORT iP d it d f 2 EIHST $ g 9- PLANT STACK 2 SET J> 7 g g

• yag j g--

y r

                                                                                  ^

y u t AUTO ISot.ATION TALTE g ,

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                                                                                                                                                                        -                                         s RGE. ANNULUS NECAT1TE FRES$URE       '                                      h   -                   m sT 25"                        ,,t,T,";h,,         ,

I sT m M sm ,,2C. _ ,, e i : _. M s VENTItATION STSTEM Y $ . g . n I

                                                               ,                                                                                                                                                  g RAD 1ATTON I

AtT!D-19 TIOM TALVES ' FM E MA110 CONDENSER EVAC. LOCAL l EI M CEAND STEAM CONDENSER , Rb 5 .L Tst EVACUATION FUMFS. A AND R t (40' ElfT) t s

                                                                                                                                                                                                                  ,8 MAIN CONDENSER ETA.UAft0M                 7       g                         g,gg .                                                                                            g FUHFS. A AND 5                                                                                                                                                         E e

FUEL ILANDLINC SUllDIEC rrEt sTOR4ct F00t. h **Disnow nwrms a RErurtNC CANAL, Cast 2 stT 70 DRAIN FRM-IRE-5107A t 1 PRif-IRE-51078  : sTO ACE AmEA. rUtt. 1 v .Ut.T. Cast DECON.

    **EA                            rCEt nANot.tNC etDC                             -

ErNST h  !~ tDCALEINST FAN EIEAUSTS. A AND 9 l o t Etrv) 9 Attachmerat 6.12 (I of I) UNT-005-014 Revision C

                                                                                                               . 180

RADIOLOGICAL EWIRONMENT MONITORING PROGRAM 4..

                                                                                          ~

Sample Tyg Location Analysis. Frequency Volume N/A. TLD A-2,'B-1, C-1, D-2,'E-1, TLD* Quarterly.. F-2, G-2, H-2, J-2, K-1, ,~ L-1, M-1, N-1,.P-1, Q-1,. R-1, A-5, B-4,.:D-5, E-5 F-4, G-4,.H-6,-P-6, Q R-6, F-9, G-9, E-15, J-15 E-30 Radiciodine and APP-1, APQ-1, APG-1, Gross beta, I-131 Weekly 285m3 /wk APC-1, APE-30 . y isotopic D Quaterly composite 3700 m 3/qtr' Particulates y isotopic, H-3 ']uarterly 4 liters Ground Water GWJ-1 Drinking Water # DWG-2, DWE-5 , DWP-7 H-3 . Quarterly composite Homogeneous Gross beta, y isotopic Monthly composite 4 liters I-131 8 Semi-monthly.composi_te . C SWG-2, SWE-5 , SWP-7 H Quarterly composite Homogeneous . Surface Water y isotopic Monthly composite 4 liters Shoreline Sediment SHWE-3, SHWJ-1 y isotopic - Semi-annually 2 kilograms - Milk MKE-4, MKQ-5, MKQ-45, MKQ-1 y isotopic, I-131 Semi-monthly / monthly 4 liters Fish FH-1, FH-2' y isotopic In season or . 50 grams semi-annually

• Food Products
• y isotopic At' harvest time l 500 grams Broad leaf BLQ-1, BLB-1, BLK-15 y isotopic, I-131 Monthly 500. grams When milk samples not collected
• Irrigated Food Pathway does not exist. However, food products grown within the site boundary are. .

sampled and analyzed. Attachment 6.13 (1 of-2)

                                                                                     ~

UNT-005-014 Revision 0 l 181 t

                                                                                             .._.i__,.__.-   .._-..E_._.               - - - - -

                                                                                                     ~

RADIOLOGICAL ENVERONMENTAL MONITORING FROGRAM (Continued) , 1

a. One or more instrument, such as a pressurized ion chamber, for measuring and recordin~g dose rate continuously may be used in place of, or in addition to, integrating dosimeters. A TLD is considered one phosphor, two or more phosphors in a packet are considered two or more dosimeters. Geographical limitations affect siting of l dosimeters.

b. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of contro%. samples, gamma isotopen analysis shall be performed on the individual samples. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

c. Drinking Water and Surface Water samples are identical samples.

d. The downs ~tream sample is beyond the mixing zone.

e. A composite sample will contain aliquots of sample taken proportional to the quantity of flowing liquid that results in a specimen representative of the liquid flow.

f. Ground water samples shall be taken wP :n this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

g. This analysis will begperformed when the dose calculated for the consumption of water is greater than 1 mrem per year as calculated for maximum organ and age group. ,

h. Milk will be collected semimonthly when animals are on pasture, monthly otherwise. If milk sampling is not performed, broad leafy vegetation will be sampled.

i. Striped mullet, gizzard shad, freshwater drum, and catfish will be collected. If they are not available, .

substitute species will be collected and identified in reporting. l

j. One sample of each principal class of food products will be sampled in an area irrigated by water in which

                               ~

plant wastes have been inadvertently discharged. If harvest occurs more than once a year, sampling shall be perforced during each discrete harvest. If harvesting occurs continuously, sampling shall be monthly. Tuberous and root products will be sampled when available. UNT-005-014 Revision 0 Attachment 6.13 (2 of 2', 182 h

                                                                                                        .- - - 'u.__m

a SAMPLE LOCATION TABLE. ,

     ..                                                                                           ~

LOCATION- LOCATION MILES FROM. SECTOR NUMBER- ' DESCRIPTION PLANT DIRECTION DIRECT RADIATION (TLD)

            -A-2                   (Eastbank) On fence enclosure surrounding                  1.1                   N water tower west of Little Gypsy opposite Etinenne St. Access from River Road (LA 628).- The TLD's are located on the (S) fence opposite the entrance gate to the-water tower.

B-1 (Eastbank)'On fence anclosing the 0.8 NNE transmission tower 0.3 miles west (up-river)

                                                     ~

from Little Gyspy. Access from River Road - (LA 628). TLD's are located at SW corner of fence enclosure. C-1 (Eastbank) On fence enclosing.the Little 0.8 NE Gyspy Cooling' Water Intake. Access is ' from. River Road (LA 628) across from Little Gyps'y Power Station entrance, i TLD's are on the south side (inside) of s the Cooling Water Intake fence enclosure, ' directly opposite the entrance gate. 1 D-2 (Eastbank) Located approximately 0.3 miles 1.1 ENE east of Little Gypsy Power. Station. Access fromsRiver Road (LA 628) near the west end of;the Bonne Carre Spillway, TLD's are on the fence at the West entrance to the spillway (located on' levee). - E-1 (Westbank) Located on utility pole along 0.2 E River Road (LA 18) approximately 0.3 miles east of'Waterford 3 plant entrance. Access from LA 18. TLD's are on the third utility pole east of the construction entrance road, s F-2 (Westbank) Located on fence enclosure 1.1 ESE surrounding the LP&L substation on LA 3142. Access from LA 3142 approximately l 0.2 miles south of LA 18. TLD's are on-the southeast corner of the fence enclosure. -! l

                                                                                                                                        .l

I UNT-005-014 Revision 0 Attachment 6.'14 (1 of 7) l-183

i

                                                    ~

SAMPLE LOCATION TABLE (Continued) LbCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT- , DIRECTION G-2 (Westbank) Located on utility pole on 1.2 SE East side.of LA 3142 near Witco entrance , gate (Next to Union Carbide Star Plant.  ! Gate 3).4_ Access from LA 3142 approximately.  ; O.2 miles north of railroad overpass.  ! 1 H-2 (Westbank) Located on fence enclusre 1.2 SSE

                                                         .      to shall road off of LA 3142. Access from                                             1 LA 3142 sourth of railroad overpass on east i

side of LA 3142., TLD's are on the south side of the' gate for shell road. (Just south of Texaco pipeline station). J-2 (Westbank) Located on northeast corner of 1.3 S fence enclosing Texaco valve station south of LA 3127. Access from LA 3127, approxmiately 0.6 miles. west of LA 3127/3142 intersection.

                                                      'K-1       (Westbank) Located b'e hind " Private Road"        1.0               .SSW SIGN AT Gate 8 en' trance off of LA 3127.                   .                            i
                                                               ' Access from LA 3127, approximately 1.3      .                                .           l miles. west of LA 3127/3142 intersection.
                                                                '(Gate 8 is'the access to the Waterf.ord 3                                          '

switchyard station).

                                                      'L-1     -(Westbank) Located.behind " Private Road"           1.0'               SW sign at LP&L Gate 9 entrance off of LA 3127, approxistely 1.6 miles west of LA 3127/3142 intersection. (Gate 9 is                                          ,

an access road for Waterford 3). H-1 (Westbank) Located on south gate into 0.7 WSW-the Waterford I and 2 fuel oil storage tank enclosure. Access is either thru LP&L Gate 8, Gate 9 off of LA 3127, the , shell access road from LA 18 between Waterford 3, or thru the Waterford 1 and - 2 access road. N '(Westbank) Located behind the "No- 0.9 W Trespassing" sign'off on-Short Street, in Killona, just south of the Killona *

                                                                . Elementary Schoo1~.

UNT-005-014 -Revision 0 Attachment 6.14 (2 of 7) 184

                                     .          SAMPLE LOCATION T'ABLt (Continued)

LOCATION LOCATION MllIS FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION P-1 (Westbank) Located on Short Street, TLD 0.8 WNW is on fence at air sample station APP-1. Q-1 (Westbank) Located on fence enclosing air 0.8 NW sample station approximately 0.5 miles west of Waterford 1 and 2 on River Road (LA 18). R-1 (Westbank) Located on fence enclosure for 0.5 NNW Waterford I and 2 Cooling Water Intake-Structure. Access is from River Road (LA 18) opposite Waterford 1 and 2. TLD's are on the southwest corner of fence. A-5 (Eastbank) Located on utility pole just 4.5 N east of the Shady Nook Trailer Park on Hwy 61 in Laplace. TLDis are on second utility pole east of trailer park on north side of Hwy 61..(eastern end of Laplace). B-4 (Eastbank) Located on utility pole just 3.8 NNE east of shell access road to South Central Bell transmission tower on south side of - Hwg 61. Transmission tower, is just east of Weigh Station at St. John /St. Charles Parish line. TLD's are on first utility pole east of access road. D-5 (Eastbank) Located on fence gate on shell 4.2 ENE access road to Big 3 Chemical Plant. Shell access road'is approximately 0.1 miles west of Hwy 61/48 intersection (at

         ,                       black and yellow gate). TLD's are on fence gate 0.1 miles north on shell access road from Hwy 61.                                                       .

E-5 (Eastbank) Located on the Norco Substation 4.2 E . fence enclosure. Access from River Road (LA 48) onto Wesco St. (adjacent to Norco Shell Chemical Plant), take Wesco St. to the dead end. TLD's are located on sixth fence post south of the north substation gate. UNT-005-014 Revision 0 . Attachment 6.14 (3 of 7) 185

SAMPLE LOCATION TABLI (Continued) LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT , DIRECTION F-4 (Westbank) Located'on utility pole behind 3.5 ESE blonde brick house on Aquarius St. in Hahnville. Access from River Road (LA 18) and turn onto Oak St. Follow Oak St. to Hickory St., turn right on Hickory St. and follow to Aquarius St. and turn.left. Blonde brick house is second house on right (west) side of Aquarius St. heading south. G-4 (Westbank) Located on railroad sign 3.2 SE no.rthwest side of LA 3160/ railroad track in'tersection. Access from either LA 3127 ' or River Road (LA 18) onto LA 3160. H-6 (Westbank) Located on a road 5.7 SSE sign on the southwest side of the second canal bridge east of LA 3160 along LA 3127. P-6 (Westbank) Located on utility pole at 5.5 WNW southwast corner of LA 640/ railroad track intersection. Utility pole is just west of LA.640 and east of radio transmission tower. Q-5 (Westbank) Located on fence post 5.0 NW surrounding (green) river marker on. levee just east of Edgard. Fence post is located along River Road (LA "

18) across from the Webre's house.

R-6 (Eastbank) Located'on fence enclosing 5.3 NNW LP&L Laydown Yard on LA 3223 in Laplace.

       .       Access from Hwy 61 onto Elm St. (LA 3223),

take Elm St. to the northeast corner of LA 3223/ railroad intersection. TLD's ara located on the southeast corner of fence urclosure. F-9 (Eastbank) Loca'ed on entrance gate 8.2 ESE to Destrehan Substation. Access from River Road (LA 48), approximate 0.3 miles cast of Luling-Destrehan Ferry, onto Destrehan Road (west of Bunge Corp. Grain Elevator), and proceed to substation gate. UNT-005-014 Revision 0 Attachment 6.14 (4 of 7) 186

SAMPLE LOCATION TABLE (Continued) LOCATION LOCATION MILES FROM SECTOR NUMBER DESCRIPTION PLANT DIRECTION' G-9 (Westbank) Located on back fence of 8.1 SE LP&L District Office in Luling. Access via Ellington St. from either River Road (LA 18); or Second or Third S. from Paul Mallard Rd. (LA 52) to Ellington St.

         . E-15'                                         -(Eastbank) Located on Kenner Substation                                                       11.8                E fence enclosure. Access from either River Road (LA 48) or liwy 61, turn onto Alliance Ave. TLD's are located on the north side of the fence enclosure, near a light pole.

J-15 (Westbank) Located on fence enclosure 12.0 b surrounding LP&L switchyard at LA 631/11wg 90 intersection in Des Allemands. TLD's are on the~ northwest corner of fence. Access from LA 631 via shell road. E-30* (Westb'ank) Located on fence at LP&L 27.0 E General Office or Delaronde St. in Algiers. TLD's Are on the fence, facing the Mississippi River, in the passageway to the transformer shop. Airborne APP-1 (Westbank) Lo'cated in soybean field 0.8 WNW at northwest corner of Short St. in Killona.

               .APQ-1                                           (Westbank) Located at northwest corner                                                       0.8                 NW of soybean field on east side of Killona.                                                                              -

Access from River Road (LA 18) approxim-ately 0.6 miles east of LA 18/3141 intersection. APG-1 (Westbank) Located at the north side 0.5 SE of the Secondary Meterological Tower.

               -APC-1                                           (Eastbank) Located inside the Little Gypsy                                                   0.8                  NE Cooling Water Intake Structure fence enclosure.

UNT-005-014 Revision 0 Attachment 6.14 (5 of 7) i 187 l i _ _ _ _ _ _ _ _ _ _

O SAMPLE LOCATION TABLE (Continued) LbCATION LOCATION MILES FROM SECTOR KUMBER DESCRIPTION PLANT DIRECTION APE-30* (Westbank) Located o 'n the roof of the 27.0 E LP&L General Office building on Delaronde St. in Algiers. Broad Leaf BLQ-1 (Westbank) Located between LA 18 and 0.8 NW soybean field on eastern edge Killona, near air sample station APQ-1. BLB-1 (Eastbank) Located at wooded area at the 0.8 NNE southwestern corner of the LP&L Little i Gypsy plant along River Road.  ! I BLK-15* (Westbank) Located 3.5 miles SSW of 15.0 SSW i Des Allemands on Hvy. 90. ' Ingestion Milk' MKE-4 (Westbank) Located 0.8 miles west of the 4.0 E Time Saver in Hahnville off of River Road. KKQ-5 (Westbank) Located at the Webre's house, 5.0 NW

,           just across LA 18 from river marker, at the eastern end of Edgard.

MKQ-45* (Eastbank) Located off of I-12 in Denham 52 NV Springs. Take LA 3002 s.outh of LA 1034 then right to LA 1032. Turn left and go to farm 1 mile on the right. MKQ-1 (Westbank) 1.0 miles west of Waterford 3 1.0 NW at the corner of River Road and Post Street ' in Killona. UNT-005-014 Revision 0 Attachment' 6.14 (6 of 7) 188

l e 1 SAMPLE LOCATION TABLE (Continued) l 1 LOCATION LOCATION MILES FROM SECTOR  ; NUMBER DESCRIPTION PLANT DIRECTION  ! l Fish TH-1* Upstream of the plant intake structure. N/A N/A , 1 TH-2 Downstream of the plant intake structure. N/A N/A Waterborne G0J-1 (Westbank) Located at 40 Arpent Canal 0.3 S south of the plant. Access from LA 3127 through LP&L Gate 8.. The canal is northwest of the shell access road /. ' railroad track intersection. DWG-2 (Westbank) Located at the Union Carbide 2.0 ESE SWG-2 drinking water canal. Access from LA 3142 through Gate 28. SHWE-3 (Westbank) Located at the Foot Ferry 3.0 E Landing off of LA 18'in Taft. SHWJ-1 (Westbank). Located at 40 arpent canal 1.0 S south of plant. Access thru LP&L gate 8 off of LA 3127. - DWE-5 (Eastbank) Located at the St. Charles 4.5 E SWE-5 Parish Waterworks off of River' Road (LA 48) near New Sarpy. DWP-7* (Westbank) Located at the St. John Parish 6.5 WNW . SWP-7*. Waterworks off of LA 18'in Edgard.

• DENOTES CONTROL LOCATIONS -

N/A - Not Applicable for this sampling location. UNT-005-014 Revision 0 Attachment 6.14 (7 of 7) 189

                                                                                                                                                                   .i

. SECTOR ~ AND' ZONE DESIGNATORS FOR. RADIOLOGICAL SAMPLING. -- . .AND MONITORI.NG POINTS i SECTOR NOMENCLATURE ZONE NOMENCLATURE CENTERLINE OF SECTOR , . l IN DEGREES TRUE NORTH 22 \' , - MILES FROM -  ; I FROM FACILITY SECTOR FACILITY ZONE i 0 & 360 *A .N - ~ 0-1 1 22\ B NNE 1-2 2 i ! 45 ~C NE 2-3 3 67\ D ENE 3-4 4 . 90 E E 4-5 .5 ~

112 F ESE 5-6 6  !

135 G SE 6-7 '7 > 157 H or SSE' - 7-8 8 t 180 J S. ~ 8-9 9 - i 202 K SSW. 9-10 -10 l 225 L SW 10-15 15 . 247 M WSW 15-20 20  ; 270 N W 20-25 - 25 .; 292\ P - WNW 25-30 30 l 315 Q NW 30-35 35 *  ! 337 ~ R NNW 35 40 i 40-45 45 , 45-50 50  ; i 1 AREA SEGMENT - An area is identified by a Sector and Zone designator. Thus, area N-1 is that area which lies j between 348'3/4 and 11k degrees true north from the facility out'to a radius of 1 mile. Area e l G-4 would be that area between 123 3/4 to 146 k degrees and the 3- and 4-mile arcs from the facility. For Airborne, Ingestion- (milk), and Food Products pathways, the sector designator will be preceded by acronyms AP, MK, and FP, respectively. l

• The letters I and 0 have been omitted from these sector designators so.as to eliminate possible. confusion between .

l letters and numbers. 1 I  ! i

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UNT-0GS-014 Revision 0 Attachment 6.15 (1 of ' t)

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UNT-005-014 Revision'0 Attaclunent 6.16 (I of 1) 191

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REMP SAMPLING LOCATIONS -

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UNT-005-014 Revision 0 Attachnent 6.18 (1 of 1) 1

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t s SPECIFICATION CROSS REFERENCE TABLE Specification Methodology Section Requirement , Section ' 5.3.1 Liquid Effluent Concentration 5.3.5 6 5.3.6  ; 5.3.2 Dose due to Liquid Effluents 5.3.4 5.3.3 Dose Projections for Liquid Releases 5.3.7 5.4.1 Dose Rate Due to Noble Cases 5.4.5 6 5.4.8 5.4.1 Dose Rate Due to Iodine, Tritum 5.4.5 6 5.4.8 ' And Particulates with Half Lives Greater than Eight Days 5.4.2 Air Doses due to Noble Gases 5.4.6 5.4.3 Doses Due to Iodines, Tritium 5.4.7 and Particulates with Half-L'ives Greater than Eight Days. 5.4.4 Dose Projections for Gaseous Releases 5.4.9 5.5.1 Total Dose 5.5.2 4 5.6.1 Radioactive Liquid Effluent Monitoring 5.3.5 Channels Alarm / Trip Setpoints 5.6.2 Radioactive Gaseous Effluent 5.4.8 Monitoring Channels Alarm / Trip Setpoints 5.8.1 Radiological Envire.. mental 5.8.4 Monitoring Program 5.8.2 Interlaboratory Comparison Program 5.8.5 1 l 5.8.3 Land Use Census. 5.8.3 ) l UNT-005-014 Revision 0 Attachment 6.19 (1 of 1)  ! 194 l

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TECHNICAL SPECIFICATION CR'OSS REFERENCE TABLE e Specification Technical Specification Section Requirement Section 5.3.1 Liquid Effluent Concentration 3.11.1.1, 4.11.1,1.1, 4.11.1.1.2 5.3.2 Dose due to Liquid Effluents 3.11.1.2 & 4.11.1.2 5.3.3 Dose Projections for liquid Releases 3.11.1.3, 4.11.1.3.1 & 4.11.1.3.2 5.4.1 Dose Rate Due to Noble Gases 3.11.2.1,

                                                                            .4.11.2.1.1, 4.11.2.1.2 &
                                                                           .4.11.2.1.3 5.4.1                Dose kate Due to Iodine, Tritum                  3.11.2.1, And Particulates with Half Lives                4.11.2.1.1, Greater than Eight Days                          4.11.2.1.2 &

4.11.2.1.3 Sv4.2 Air Doses due to Noble Gases 3.11.2.2 & 4.11.2.2 5.4.3 Doses Due to Iodines, Tritium 3.11.2.3 & and Particulates with Half-Lives /. 11.2.3 Greater than Eight Days. 1 5.4.4 Dose Projections for Gaseous Releases 3.11.2.4, 4.11.2.4.1 & , 1 4.11.2.4.2 CNT-005-014 Revision 0 Attachment 6.20 (1 of 2) ) l 195

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