ML031250249

Radioactive Effluent Release Report & Offsite Dose Calculation Manual PLA-5618, Procedure Change Process Form Through Bases B 3.11.4.3

ML031250249
Person / Time
Site:	Susquehanna
Issue date:	04/30/2003
From:	Shriver B Susquehanna
To:	Office of Nuclear Reactor Regulation
References
PLA-5618
Download: ML031250249 (178)

Text

PROCEDURE CHANGE PROCESS FORM PCAF NO. 203-4

.2?) 2. PAGE 1 OF 7

3. PROC. NO. ODCM-QA-008 REV. 4

4.

FORMS REVISED R

, -RR_,

R R-,

R.,

R

5.

PROCEDURE TITLE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

6.

REQUESTED CHANGE PERIODIC REVIEW i

NO LI YES INCORPORATE PCAFS L NO l

YES

1. 2002-1698 REVISION

[]

PCAF 3

DELETION J (CHECK ONE ONLY)

7.

SUMMARY

OF/ REASON FOR CHANGE MED The change being made is the addition of the Nuclear Emergency Planning g&obP tehRECOMMENDED REVIEWS" section on the procedure cover page and deletion of Plant Op6 tionsPFie6 v

Committee (PORC) from the "RECOMMENDED REVIEWS" section of the cover page>PORyeview of all 0DCM revisions is required per ODCM-QA-002 (ODCM REVIEW AND REVISION CO WTROL).

This change to ODCM-QA-008 is an administrative correction and d~ao ndcrease the level of effluent control or the accuracy and/or reliability of dose calculations or etpoin,'determinations as required by 1 OCFR20.1 302, 40C FR1 90, 1 OCFR50.36a and 1 OCFR50 CniudL

8. DETERMINE COMMITTEE REVIEW REQUIREM T

(Refer to Section 6.1.4)

PORC REVIEW REQ'D?

0 Q

S

9.

PORCMTG#

iS BLOCKS 11 THRU 16 ARE ON PAGEOEF FORM'

17.

Francis J. Hickey I

312 4/03

18. COMMUNICATION OF CHANGE REQUIRED?

PREPARER MF~

AE 0N IYES (TYPE)______

(Print or Type)

SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS

19.

CONDUCTED OADR AND TECHNICAL REVIEW UNLESS OTHERWISE S /

V 0

DOCUMENTED IN BLOCK 16 OR ATTACHED REVIEW FORMS.

RO CamOSrkESUERVSO 3

CROSS DISCIPUNE REVIEW (IF REQUIRED) HAS BEEN COMPLETED SPONSIBLEUPBY SIGNATURE IN BLOCK 16 OR ATTACHED REVIEW FORMS.

20.

N/A FUM APPROVAL DATE

21. RESPONSIBLE APPROVER ENTER NIA IF FUM HAS APPROVAL AUTHORITY N/A INITIALS DATE MAR 2 l

FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)

DOM IMENT CNMTRAL SERVICES

- SSES

'U PROCEDURE CHANGE PROCESS FORM

1.

PCAF NO. 2003-7

12. PAGE 2 OF 7 I,

13. PROC. NO. ODCM-QA-008 REV. 4 II

11. This question documents the outcome of the 50.59 and 72.48 Reiew required by NDAP-QA-0726. E ll a, b, c or d must be checked 'YES' and the appropriate form attached or referenced.

a. This change is an Administrative Correction for which 50.59 and 72.48 are not 3 YES 3

N/A applicable.

b. This change is a change to any surveillance, maintenance or administrative

[

YES 3 N/A procedure for which 50.59 and 72.48 are not applicable.

c. This change is bounded by a 50.59/72.48 Screen/Evaluation, therefore, no new E YES W

N/A 50.59172.48 Evaluation is required.

Screen/Evaluation No.

d. 50.59 and/or 72.48 are applicable to this change and a 50.59/72.48 LI YES 3 N/A Screen/Evaluation is attached.

12. This change is consistent with the FSAR or an FSAR change is required.

3 YES Change Request No.

13. Should this change be reviewed for potential effects on Training Needs or Material?

D YES NO If YES, enter an Action Item @ NIMS/Action/Gen Work Mech/PICN

14. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722?

0 YES 3 NO

15. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per

[

YES 3

NO NDAP-OA-0320? (SICT/E form does not need to be attached.)

16. Reviews may be documented below or by attaching Document Review Forms NDAP-QA-0101-1.

REVIEWED BY WITH DATE REVIEW NO COMMENTS QADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS

• IST**

OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (5)

Required for changes to Section XI Inservice Test Acceptance Criteria.

Aek FORM NDAP-QA-0002-8, Rev. 8, Page 2 of 2 (Electronic Form)

PAGEJdF

.O PROCEDURE COVER SHEET IPPL SUSQEHIANNA, LLC I NUCLEAR DEPARTMENT PROCEDURE

-RADIOLOGICAL ENVIRONMENTAL ODCM-QA-008 MONITORING PROGRAM Revision 4 Page 1 of 78 QUALITY CLASSIFICATION:

APPROVAL CLASSIFICATION:

0 QA Program 0 Non-QA Program 0 Plant l Non-Plant El Instruction EFFECTIVE DATE:

o AOD; PERIODIC REVIEW FREQUENCY:

NWA PERIODIC REVIEW DUE DATE:

N/A RECOMMENDED REVIEWS:

Nuclear BneRgKcy Planing Procedure Owner Francis J. Hickey Responsible Supervisor Chemistry Support Supeivisor - SSES Responsible FUM:

Chemistry Supervisor-SSES Responsible Approver Vice President - Nuclear Operations I

F C

I FORM NDAP-QOA0002-1, Rev. 3, Page 1 of 1

ODCM-QA-008 Revision 4 Page 2of78 PROCEDURE REVISION

SUMMARY

TITLE:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1. Replace milk sampling location I 0D3 with location 122B2 in Attachments B and C. This change is-in response to the result of an annual surveillance that evaluated the dose potentials of dairy farms in the vicinity of the SSES for any airborne activity that might be released from the SSES. This surveillance determined that location 12B2 has a significantly greater dose potential than 1 0D3.

2. Added Attachment I to provide an explanation of the regulatory basis for Equations 1-4.

3. Added Regulatory Guide 1.109 as Reference 3.1.

4. Added references to Attachment I in Sections 6.1.1, 6.1.2, and 6.1.3.

5. Deleted "12G1" from Attachment B. This is not and never has been a required monitoring location. It is not listed in Attachment C.

6. Update the description of monitoring location 2B3 from "Durabond Corporation" to 6Leggett

& Platt."

The changes to ODCM-QA-008 above have been determined to not decrease the level of effluent control or the accuracy and/or reliability of dose calculations or setpoint determinations as required by 10CFR20.1302, 40CFR190, 10CFR50.36a, and 10CFR50, Appendix I.

PAGL~'

F Revision 4 Page 3of 78 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 2.0 POUCY/DISCUSSION 4

2.1 Monitoring Program 4

2.2 Census Program 5

2.3 Interlaboratory Comparison Program 6

2.4 Dose Computations 6

3.0 REFERENCES

6 4.0 RESPONSIBILmES 7

4.1 Chemistry Support Supervisor - SSES 7

l 4.2 Chemistry Support Personnel 7

F 5.0 DEFINITIONS 7

6.0 PROCEDURE 8

6.1 Dose Computations 8

7.0 RECORDS 10 ATTACHMENTS ATTACHMENT PAGE A

Environmental Monitoring Locations within One Mile of SSES 11 B

Environmental Monitoring Locations Greater Than One Mile from SSES 12 C

Operational Radiological Environmental Monitoring Program 13 D

REMP Dose Factors forAduit Age Group 16 E

REMP Dose Factors forTeen Age Group 32 F

REMP Dose Factors for Child Age Group 48 G - REMP Dose Factors for Infant Age Group 64 H

REMP Dose Factors for Shoreline/Sediment Total Body and Skin Dose 72 I

Consolidated Dose Calculations '

75

ODCM-QA-008 Revision 4 Page 4 of 78 1.0 PURPOSE The purpose of this procedure is to provide the methodology and parameters used to determine doses to the public resulting from inhalation, ingestion, and direct shine from radiologically contaminated environmental sampling media based on measured activity concentrations in those media. This procedure also describes the Radiological Environmental Monitoring Program (REMP), which includes the annual land use census survey and interlaboratory comparison program.

This procedure constitutes part of the SSES Offsite Dose Calculation Manual (ODCM),

which is a licensing basis document.

2.0 POLICY/DISCUSSION 2.1 Monitoring Program 2.1.1 The results of the Radiological Environmental Monitoring Program are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from station operation.

- 2.1.2 Environmental samples shall be collected and analyzed (as a minimum) according to Attachment C at locations shown in Attachments A and B in order to meet the requirements of TR Table 3.11.4.1-1. Comparisons to the Reporting Levels-of TR Table 3.11.4.1-2 are conducted in accordance with procedure ST-099-003. Analytical techniques used shall ensure that the detection capabilities in TR Table 3.11.4.1-3 are achieved.

2.1.3 Sampling specified in Attachment C shall be performed with a maximum allowable extension not to exceed 25 percent of the specified interval.

More restrictive tolerances may be imposed by implementing procedures.

2.1.4 Program changes may be proposed based on operational experience.

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, an effort shall be made to complete corrective action prior to the end of the next sampling period. All program changes and deviations from the sampling schedule shall be documented in the next Annual Radiological Environmental Operating Report.

I-ODCM-QA-008 Revision 4 Page 5 of 78 2.1.5 An Annual Radiological Environmental Operating Report shall be prepared and submitted to the NRC prior to May 15 of each year in accordance with Technical Specification 5.6.2. The report shall include summaries, interpretations and analyses of trends of the results of the Radiological Environmental Monitoring Program (including any monitoring not conducted in accordance with TR Table 3.11.4.1-1) for the reporting period. A comparison, as appropriate, of sample analysis results with pre-operational studies, operational controls and results reported in previous reports shall be included. An assessment of environmental impacts of plant operation shall be made. The material provided shall be consistent with the objectives contained in the ODCM and 1 OCFR50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period at the locations specified in the ODCM as well as the summary and tabulation of results presented in the format of the table in the Radiological Assessment Branch Technical Position, Rev. 1, November 1979. The results of the Land Use Census and the Interlaboratory Comparison Program are included as well as corrective-actions for analyses with results which are outside the control limits specified in the Interlaboratory Comparison Program. Detected radionuclides which are not the result of plant effluents must be included in the report.

At least two maps, including one near the Site Boundary, showing monitoring/sampling locations that are keyed to table(s) providing distances and directions from the plant centerline shall also be included.

In the event that some individual results are not available for inclusion with the report, the report shall note and explain the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

2.1.6 Special Reports shall be prepared and submitted to the NRC in accordance with the TROs of the specific sections of the Technical Requirements Manual.

2.2 Census Program 2.2.1 Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two direction sectors with the highest predicted D/Q's in lieu of the garden census.

Specifications for broad leaf vegetation sampling in TR Table 3.11.4.1-1, Item 4C shall be followed, including analysis of control samples. -

2.2.2 If a land use census identifies a location(s) with a higher average annual deposition rate (D/Q) than a current indicator location, the following shall apply:

ODCM-QA-008 Revision 4 Page 6 of 78

a.

If the D/Q is at least 20 percent greater than a previously high D/Q, the new location shall be added to the program within 30 days of documented identification of sampling feasibility. The indicator location having the lowest D/Q may be dropped from the program after October 31 of the year in which the land use census was conducted.

b.

If the D/Q is not 20 percent greater than the previously highest D/Q, direction, distance, and D/Q will be considered in deciding whether to replace one of the existing sample locations. If applicable, replacement shall be within 30 days of documented decision making.

2.2.3 Any evaluations of possible location replacement should include the past history of the location, availability of sample, milk production history, and other applicable environmental conditions. New locations for dose calculations or environmental monitoring shall be reported in the Annual Effluent and Waste Disposal Report.

2.2.4 A land use census will be conducted at least once per calendar year by a door-to-door or aerial survey, by consulting local agricultural authorities, or by any combination of these methods.

2.3 Interlaboratory Comparison Program 2.3.1 The laboratories providing radioanalytical services for the station's Radiological Environmental Monitoring Program (REMP) shall participate in an Interlaboratory Comparison Program (ICP).

2.3.2 Analysis results which are obtained as part of an ICP that are not within acceptance limits established by the ICP shall be investigated by the laboratory responsible for the analysis. Corrective action appropriate for the findings of the investigation shall be taken. Investigation findings and corrective actions taken shall be described in the Annual Radiological Environmental Operating Report.

2.4 Dose Computations 2.4.1. When doses to members of the public are to be determined from REMP sample analysis results reported above LLD, doses should be added across sampling media for the same exposure pathways (airborne or waterbome), if available, to maximize the result for a particular age group and organ.

3.0 REFERENCES

3.1 Regulatory Guide 1.109, Rev. 1, October, 1977, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with IOCFR50, Appendix I.

UULA.IVI-UA4-UUJ PAGL A' D 7 Revision 4

-Page 7of 78 l

3.2

-.RTable3.11.4.1-1,RadiologicalEnvironmentalMonitoringProgram 3.3 TR Table 3.11.4.1-2, Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.4 TR Table 3.11.4.1-3, Detection Capabilities for Environmental Sample Analysis 3.5 TS 5.6.2, Annual Radiological Environmental Operating Report 3.6 1 OCFR50, Appendix I, Numerical Guides for Design Objectives and limiting Conditions for Operation to Meet the Criterion "As Low as is Reasonably Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents 3.7 40CFR141, National Primary Drinking Water Regulations 3.8 Regulatory Guide 4.8, December 1975-Environmental Technical Specifications for Nuclear Power Plants 3.9 Branch Technical Position to NRC Reg. Guide 4.8, Rev. 1, November 1979 3.10 ORP/SID 72-2 Environmental Radioactivity Surveillance Guide 3.11 NEPM-QA-1 014, Radiological Environmental Monitoring Program

• 3.12 ST-0994003, Performance of REMP Quarterly Surveillance 3.13 PP&L Calculation EC-ENVR-1 027, SSES REMP Dose Factor Calculations:

C. R. 96-1310 4.0 RESPONSIBILITIES 4.1 Chemistry SuDport SuDervisor-SSES P

C 4.1.1 Is responsible for appointing and supervising Chemistry Support A

personnel.

F 4.2 Chemistry SuDDort Personnel 4.2.1 Have the primary responsibility for developing the REMP and ensuring AF proper conduct of the REMP.

5.0 DEFINMONS 5.1 LLD - Lower Limit of Detection, the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95 percent probability with only a 5 percent probability of

.M.

falsely concluding that a blank observation represents a 'real signal.

1.5~

ODCMQA-008 PAGF L O Ago Revision 4 Page8of78 5.2

- REMP - Radiological Environmental Monitoring Program.

5.3 MEMBER(S) OF THE PUBLIC - Shall include all persons who are not occupationally associated with the plant This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant 6.0 PROCEDURE 6.1 Dose Computations P

6.1.1 Chemistry Support Personnel shall determine annual doses to members A

of the public from ingestion of radioactive material for various pathways, F

age groups and organs according to the methodology developed in EC-ENVR-1 027:

DREMPMG =DFCALCANO *RESRIEW

• FSAMP (Eq. 1) where:

DREMPw1N

=

Annual dose from ingestion, as determined from REMP sample result (mremlyear). Refer to Attachment I for the regulatory basis of the calculation of DREMPIp.

DFCALcN<G =

Dose rate factor for ingestion pathway; mrem-liter/pCi-yr for liquid samples; mrem-kg/pCi-yr for solid samples (Attachments D through G).

RESREMp

=

REMP sample result pCi/liter for water or milk samples; pCi/kg for vegetable, fruit, meat or fish samples.

FsA

=

Correction factor for the fraction of year represented by the sampling period (for cases where only periodic or seasonal sampling is conducted).

P 6.1.2 Chemistry Support Personnel shall determine annual doses to members A

of the public from inhalation of radioactive material for various pathways, F

age groups and organs according to the methodology developed in EC-ENVR-1 027:

DREMPMM = DFCALCwNH

• RESRStEP 'FsAmp (Eq. 2)

m var vvlrir~v PAGfL7-F 7 _

Revision 4 Page 9 of 78 where:

DREmP4

= Annual dose to organs or total body from inhalation, as determined from REMP sample result (mrem/yr).

Refer to Attachment I for the regulatory basis of the calculation of DpEMPmwNj DFcALcAmH =

Dose rate factor for inhalation pathway (mrem-m3/pCi-yr) (Attachments D through G).

RESRBW = REMP sample result: pCVmO for air samples corrected for absorption efficiency of filter media.

P 6.1.3 Chemistry Support Personnel shall determine annual dosesto members I A of the public from exposure to contaminated sediment for total body and F

skin dose, forvarious age groups according to the methodology developed in EC-ENVR-1 027:

Dmpfn =DFcALcfm

• RES^wp FsAF (Eq. 3)

D REMP/SKI = DFCLC/sm RESpwp IFsAmp (Eq. 4) where:

lDur.m

= Annual total body dose, as determined from REMP I.

sample result (mrern'yr). Refer to Attachment I for the regulatory basis of the calculation of DREwfm.

DREMP/SKN

=

Annual skin dose, as determined from REMP sample result (mremfyr). Refer to Attachment I for the regulatory basis of the calculation of DREMPJSKN.

RESREMP

=

REMP sample result pCVkg sediment.

DFcALcJTD

=

Total body dose rate factor from sediment (mrem-kgfpCi-yr) (Attachment H).

DFc/s 0

Skin dose rate factor from sediment (mrem-kgfpCi-yr) (Attachment H).

F.;AMP

=

Correction factor for the fraction of year represented by the sampling period (for cases where only periodic or seasonal sampling is conducted).

ODCM-QA-008 Revision 4 Page 10 of 78 7.0 RECORDS None.

odam-qa-008(26)

I Attachment A ODCM-QA-008 Revision 4 Page 11 of 78 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF SSES

~

.GOULD ISLAND NORTH 1(

2 4

14S

-Is I

13 z'=<

g'z SIT It Il/

\\

/;

0I\\

T'I:

BOUNT T

/

AIR g

SURFACE WATER T

THEOLMllKESMTI~

DO6(ETRY Page 1 of 1

d -

Attachment B ODCM-QA-008 Revision 4 Page 12 of78 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN ONE MILE FROM SSES

-I 1

13 12 GGI

~p AMI e

DR1W4G WATER OW FOOD

&6 SEDEMENT T

THERIOLUNLNEXT DlOMMERY Pag 1 o Page I of I

0 Attachment C ODCM-QA-008 Revision 4 Page 13 of 78 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathways and/or Sample Number of Samples and Locations*

Sampling and Collection Frequency Type and Frequency of Analysis Airborne Radioiodine and Particulates*

12S1 0.4 mi WSW West Building Laboratory 12E1 4.7 mi WSW Berwick Hospital 3S2 0.5 mi NE SSES Backup Met.

Tower South of Towers Club 13S6 0.4 mi W

Former Laydown Area, West of Confer's Lane 6G1 13.5 mni ESE Freeland Substation' 8G1 12.2 mi. SSE PPL System Facilities' Center, Humbolt Industrial Park Continual sampler operation with sample collection weekly.

V4 7Tii./cr-r Radioiodine Canister:

analyze weekly for 1-131.'

Particulate Sample:

Analyze for gross beta radioactivity following filter change. Perform isotopic analysis on composite sample ly location) quarterly.

Direct Radiation IS2 0.2 rni N

Perimeter Fence IDS 4.0mi N

Mocanaqua Sewage Treatment Plant 2S3 0.2 mi NNE Perimeter Fence 2B3 1.3 mi NNE Leggett & Platt 2F1 5.9 mi NNE St. Adalberts Cemetery 3S4 0.3 mi NE Perimeter Fence 3E1 4.7 mi NE Webb Residence-Lilly Lake 4S3 0.2 nil ENE West of SSES APF 4E2 4.7 mi ENE Ruckles Hill & Pond Hill Roads Intersection 4G1 14 mi ENE Crestwood Industrial Parke 5S7 0.3 mi E

Perimeter Fence 5E2 4.5 mi E

Bloss Farm 6S4 0.2 mi ESE Perimeter Fence 6A4 0.6 mi ESE Restaurant 6E1 4.7 mi ESE St. James Church Quarterly Gamma Dose: Quarterly.

Page 1 of 3

Attachment C OOCM-QA-008 Revision 4 Page 14 of 78 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathways and/or Samp e Number of Samples and Locations*

Sampling and Collection Frequencv Type and Frequency of Analysis 6S9 0.2 mi ESE Perimeter Fence 7S6 0.2 mi SE Perimeter Fence 7E1 4.2 mi SE Harwood Transmission Line Pole #2 7G1 14 mi SE PPL Hazleton Complex' 8S2 0.2 mi SSE Perimeter Fence 8B2 1.4 mi SSE LaWall Residence 8D3 4.0 mi SSE Mowry Residence 9S2 0.2 mi S

Security Fence 9D4 3.6 mi S

Country Folk Store IOS1 0.4 mi SSW Post South of Switching Station IODI 3.0 mi SSW Ross Ryman Farm 11S3 0.3 mi SW Security Fence I lEI 4.7 mi SW Thomas Residence 12S3 0.4 mi WSW Perimeter Fence 12E1 4.7 mi WSW Berwick Hospital 12G1 15 mi WSW PPL Bloomsburg Service Center' 13S2 0.4 mi W

Perimeter Fence 13E4 4.1 mi W

Kessler Farm 14S5 0.5 mi WNW Beach Grove Rd. &

Confer's Lane Intersection 14B3 1.3 mi WNW Moskaluk Residence 15F!

5.4 mi NW Zawatski Farm 15S5 0.4 mi NW Perimeter Fence 16S1 0.3 mi NNW Perimeter Fence 16S2 0.3 mi NNW Perimeter Fence 16F1 7.8 NNW Hidlay Residence Quarterly Gamma Dose: Quarterly.

Waterborne Surface Drinking 2S7 Cooling Tower Blowdown discharge line Monthly composite (restricted area)f 6S6 river water intake line' 6S7 Cooling Tower Blowdown discharge line (STP)"

12H2 DanvilleWaterCompany(Approximately Monthlycomposite' 30 miles downstream)

Gamma isotopic analysis. Composite tritium analysis at least quarterly.

Gross beta and gamma isotopic analyses monthly. Composite for trntiuni analysis at least quarterly.

Page 2 of 3

I Attachment C ODCM-QA-008 Revision 4 Page 15 of 78 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathways and/or Sample Number of Samples and Locations*

Sampling and Collection Frequency Type and Frequency of Analysis Sediment from Shoreline I -Milk**

7B 1.2 mi SE Bell Bend 12B2. 1.7 mi WSW Berger Farm IOGI 14.0 mi. SSW Davis Farm' 10D2 3.1 mi. SSW Ray Ryman Farm IODI 3.0 mi. SSW R&C Ryman Farm Outfall area 2H Falls, Pa' (Approximately 30 mi NNE)

Semi-annually Semi-monthly when animals are on pasture, monthly otherwise Gamma isotopic analysis semi-annually.

Gamma isotopic and 1-131 analysis of each sample.

Fish and Invertebrates Semi-annually. One sample' from each of two recreationally

- important species from any of the following families: bullhead

- catfish, sunfish, pikes, or perches.

Gamma isotopic on edible portions.

Food Products IIDI 3.3 mi SW ZehnerFarm(vegetable)

At time of harvest Gamma isotopic on edible portions.

12F7 83 mi WSW Lupini Farm (vegetable)

The location of samples and equipment were designed using the guidance in the Branch Technical Position to NRC Reg.

Guide 4.8, Rev. 1,Nov. 1979, Reg. Guide48.1975 and ORP/SID 72-2 Environmental RadioactivitySurveillance Guide.

Therefore, the airborne sampler locations were based upon X/Q and/or D/Q.

If a milk sample is unavailable for more than two sampling periods from one or more of the locations, a vegetation sample shall be substituted until a suitable milk location is evaluated. Such an occurrence will be documented in the REMP annual report.

a The charcoal sampler cartridges used in the airborne radioiodine-sampling program are designed and tested by the manufacturer to assure a high q-uality of radioiodine capture. A certificate from the manufacturer is supplied and retained with each batch of cartridges certifying the percent reduction of radioiodine versus air flow rate through the cartridge.

b Gross beta activity calculations will be performed in accordance with the procedures of the designated REMP analysis laboratory.

Control sample location.

d Two-week composite if calculated doses due to consumption of water exceed one millirem per year. In these cases, 1-131 analyses will be performed.

The sample collector will determine the species based upon availability, which may vary seasonally and yearly.

r A sample from either or both locations 2S7 and 6S7 will be collected and analyzed according to the required frequencies.

Page 3 of 3

Attachment D ODCM-QA-008 Revision 4 Page 16 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: MILK SAMPLE (Page 1 of 2) mrem-liter/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E+00 3.25E-05 3.25E-05 3.25E-05 3.25E-05 3.25E-05 3.25E-05 C-14 8.80E-04 1.76E-04 1.76E-04 1.76E-04 1.76E-04 1.76E-04 1.76E-04 Na-24 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 P-32 5.43E-02 3.38E-03 2.10E-03 0.OOE+00 0.00E+00 0.00E+00 6.11 E-03 Cr-51 0.OOE+00 0.00E+00 7.84E-07 4.69E-07 1.73E-07 1.04E-06 1.97E-04 Mn-54 0.00E+00 1.41 E-03 2.69E-04 0.00E+00 4.20E-04 0.00E+00 4.32E-03 Mn-56 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 8.51E-04 5.88E-04 1.37E-04 0.00E+00 0.00E+00 3.28E-04 3.37E-04 Fe-59 1.30E-03 3.07E-03 1.18E-03 0.00E+00 0.00E+00 8.56E-04 1.02E-02 Co-58 0.00E+00 2.26E-04 5.08E-04 0.OOE+00 0.00E+00 0.00E+00 4.59E-03 Co-60 0.00E+00 6.63E-04 1.46E-03 0.00E+00 0.00E+00 0.OOE+00 1.25E-02 Ni-63 4.03E-02 2.79E-03 1.35E-03 0.OOE+00 0.00E+00 0.00E+00 5.83E-04 Ni-65 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.49E-03 4.75E-03 2.15E-03 0.00E+00 3.17E-03 0.00E+00 2.99E-03 Zn-69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Rb-86 0.QOE+00 6.07E-03 2.83E-03 0.OOE+00 0.00E+00 0.00E+00 1.20E-03 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Sr-89 9.29E-02 0.00E+00 2.67E-03 0.00E+00 0.OOE+00 0.00E+00 1.49E-02 Sr-90 2.35E+00 0.00E+00 5.77E-01 0.00E+00 0.OOE+00 0.OOE+00 6.79E-02 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Y-90 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 4.27E-05 0.00E+00 1.14E-06 0.OOE+00 0.00E+00 0.OOE+00 2.35E-02 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Zr-95 9.22E-06 2.96E-06 2.00E-06 0.00E+00 4.64E-06 0.00E+00 9.37E-03 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Nb-95 1.85E-06 1.03E-06 5.54E-07 0.00E+00 1.02E-06 0.OOE+00 6.26E-03 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1 of 16

Attachment D ODCM-QA-008 Revision 4 Page 17 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: MILK SAMPLE (Page 2 of 2) mrem-liter/pCI-vr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 5.54E-05 O.OOE+00 2.39E-05 O.OOE+00 2.11 E-04 O.OOE+00

-6.46E-03 Ru-105 O.OOE+O0 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 Ru-106 8.49E-04 O.OOE+OO 1.07E-04 O.OOE+00 1.64E-03 O.OOE+00 5.50E-02 Ag-11 Om 4.93E-05 4.56E-05 2.71 E-05 O.OOE+00 8.97E-05 O.OOE+00 1.86E-02 Te-125m 8.11 E-04 2.94E-04 1.09E-04 2.44E-04 3.30E-03 O.OOE+00 3.24E-03 Te-127m 2.07E-03 7.41 E-04 2.53E-04 5.30E-04 8.42E-03 O.OOE+00 6.95E-03 Te-127 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 Te-129m 3.42E-03 1.28E-03 5.41 E-04 1.18E-03 1.43E-02 O.OOE+00 1.72E-02 Te-129 9.34E-06 3.51 E-06 2.28E-06 7.17E-06 3.93E-05 O.OOE+00

- 7.05E406 Te-131rm O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-I32 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 1.09E-03 1.55E-03 8.90E-04 5.09E-01 2.66E-03 O.OOE+00 4.10E-04 1-132 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 1,92E-02 4.58E-02 3.74E-02 O.OOE+00 1.48E-02 4.92E-03 8.01E-04 Cs-136 1.82E-03 7.17E-03 5.16E-03 O.OOE+00 3-.99E-03 5.47E-04 8.15E-04 Cs-137 2.47E-02 3.38E-02 2.21 E-02 O.OOE+00 1.15E-02 3.81 E-03 6.54E-04 Cs-138 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-1 39 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 5.65E-03 7.09E-06 3.70E-04 0.OOE+00 2.41 E-06 4.06E-06 1.1 6E-02 Ba-141 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00O Ba-1 42 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 2.78E-06 1.88E-06 2.13E-07 O.OOE+00 8.73E-07 O.OOE+00 7.19E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 1.51 E-04 6.29E-05 8.08E-06 O.OOE+00 3.73E-05 O.OOE+00 5.09E-02 Pr-143 2.57E-06 1.03E-06 1.28E-07 O.OOE+00

-5.96E-07 O.OOE+00 1.1 3E-02 Pr-144 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 1.72E-06 1.99E-06 1.19E-07 O.OOE+00 1.16E-06 O.OOE+00 9.54E-03 W-187 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 2 of 16

Attachment D ODCM-QA-008 Revision 4 Page 18 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: LEAFY VEG. SAMPLE (Page 1 of 2) mrem-kgtpCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 6.72E-06 6.72E-06 6.72E-06 6.72E-06 6.72E-06 6.72E-06 C-14 1.82E-04 3.64E-05 3.64E-05 3.64E-05 3.64E-05 3.64E-05 3.64E-05 Na-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 P-32 1.1 8E-02 7.32E-04 4.55E-04 0.OOE+00 0.00E+00 0.00E+00 1.32E-03 Cr-51 0.Q0E+00 0.OOE+00 1.66E-07 9.92E-08 3.66E-08 2.20E-07 4.1 8E-05 Mn-54 0.00E+00 2.92E-04 5.57E4-5 0.00E+00 8.68E-05 0.00E+00 8.94E-04 Mn-56 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 1.76E-04 1.22E-04 2.83E-05 0.00E+00 0.00E+00 6.78E-05 6.97E-05 Fe-59 2.73E-04 6.43E-04 2.46E-04 0.00E+00 0.00E+00 1.80E.04 2.14E-03 Co-58 0.00E+00 4.72E-05 1.06E-04 0.00E+00 0.00E+00 0.00E+00 9.57E-04 Co-60 0.002+00 1.37E-04 3.02E-04 0.OOE+00 0.00E+00 0.OOE+00 2.57E-03 NI-63 8.32E-03 5.77E-04 2.79E-04 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Ni-65 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Zn-65 3.09E-04 9.83E-04 4.44E-04 0.00E+00 6.57E-04 0.00E+00 6.19E-04 Zn-69 0.OOE+00 -

0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00

,E Br-84 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 -

0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.30E-03 6.06E-04 0.00E+00 0.00E+00 0.00E+00 2.57E-04 Rb-88 0:00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+O0 0.00E+00 O.OOE+00 Rb-89 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-89 1.94E-02 0.00E+00 5.58E404 0.00E+00 O.OOE+00 O.OOE+00 3.12E-03 Sr-90 4.85E-01 0.00E+00 1.19E-01 0.00E+00 0.00E+00 0.00E+00 1.40E-02 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Y-91 8.92E-06 0.00E+00 2.38E-07 0.00E+00 0.00E+00 0.00E+00 4.91 E-03 Y-92 0.002E00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.92E-06 6.17E-07 4.18E-07 0.00E+00 9.69E-07 0.00E+00 1.96E-03 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 3.90E-07 2.17E-07 1.17E-07 0.00E+00 2.15E-07 0.00E+00 1.32E-03 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 JI I

I 1-1-1 Page 3 of 16

Attachment D ODCM-QA-008 Revision 4 Page 19 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: LEAFY VEG. SAMPLE (Page 2 of 2) mrem-kg/pCi-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00' 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103

--1.16E-05.

O.OOE+00 5.01 E-06 O.OOE+00 4.44E-05 O.OOE+00 1.36E-03 Ru-1 05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+0O O.OOE+00 Ru-106 1.76E-04 O.OOE+00 2.22E-05 O.OOE+00 3.39E-04 O.OOE+OO 1.14E-02 Ag-11 Om 1.Q2E-05 9.45E-06 5.61 E-06 O.OOE+0O 1.86E-05 O.OOE+00 3.85E-03 Te-125m 1.69E-04.

6.14E-05 2.27E-05 5.1 OE-05 6.89E O.OOE+OO 6.77E Te-127m 4.31 E-04 1.54E-04 5.25E-05 1.1OE-04 1.75E-03 O.OOE+00 1.44E-03 Te-127 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00

-O.OOE+00 0.00E+00

.Te-129m 7.21 E-04 2.69E-04 1.14E-04 2.48E-04 3.01 E-03 0.00E+O0

- 3.63E-03

-Te-129 1.97E-06 7AOE-07 4.80E-07 1.51 E-06 8.28E-06 0.00E+00 1A9E-06 Te-131m-O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00.

O.OOE+00

-0.00E+00.

O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

- 0.00E+00

- 0.00E+00 1-131 2.442E04 3A9E-04 2.00E-04 1.14E-01

.5.99E-04

- 0.00E+00 9.22E-05 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00+00 O.OOE++00 0.00E+00

-0.00E+00 1-133 O.OOE+00 r

O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 1-134 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 3.98E-03 9.46E-03 7.74E-03 O.OOE+00 3.06E-03 1.02E-03 1.66E Cs-136 3.95-04 1.56E-03

- 1.12E-03 O.OOE+00 8.68E-04' 1.19E-04 1.77E-04 Cs-137 5.10E-03 6.98E-03 4.57E-03 O.OOE+00 2.37E-03 7.87E-04 1.35E-04 Cs-138

- O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-139 O.OOE+00

--O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 1.23E - 1.55E 8.06E-05 O.oOE+00 5.26E-07 8.85E-07 2.53E-03 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 -

O.OOE+00

• Ba-142 O.OOE+00 O.OOE+00

- O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 5.86E-07 3.97E-07 4.50E-08 O.OOE+00 1.84E-07 O.OOE+00 1.52E-03 Ce-143

-0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00

-0.00E+00 Ce-144 3.12E-05 1.30E-05

- 1.67E-06 O.OOE+00 7.73E-06 O.OOE+00

- 1.05E-02 Pr-143 -

5.59E-07 2.24E-07 2.77E-08 O.OOE+00 1.30E-07 O.OOE+00 2.45E-03 Pr-144 O.OE+00 0.00E+00 O.OOE+00 O.OOE+00 -

O.OOE+00 0.03E+00 O.OOE+00 Nd-147 3.78E-07 4.37E-07 2.61E-08 O.OOE+00 2.55E-07

- O.OOE+00 2.10E-03 W-187 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00

-O.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 4 of 16

Attachment D ODCM-QA-008 Revision 4 Page 20 of 78 _

REMP DOSE FACTORS FOR ADULT AGE GROUP: FRUIT SAMPLE (Page 1 of 2) mrem-kg/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 5.41 E-05 5.41 E-05 5.41 E-05 5.41 E-05 5.41 E-05 5.41 E-05 C-14 1.48E-03 2.95E-04 2.95E-04 2.95E-04 2.95E-04 2.95E-04 2.95E-04 Na-24 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 P-32 5.47E-03 3.40E-04 2.11 E-04 O.OOE+00 O.OOE+00 O.OOE+00 6.14E-04 Cr-51 O.OOE+00 O.OOE+00 3.08E-07 1.84E-07 6.79E-08 4.09E-07 7.75E-05 Mn-54 O.OOE+00 2.08E-03 3.97E-04 O.OOE+00 6.19E-04 O.OOE+00 6.37E-03 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 1.37E-03 9.47E-04 2.21 E-04 O.OOE+00 O.OOE+00 5.28E-04 5.43E-04 Fe-59 8.89E-04 2.09E-03 8.01 E-04 O.OOE+00 O.OOE+00 5.84E-04 6.96E-03 Co-58 O.OOE+00 2.15E-04 4.83E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.36E-03 Co-60 O.OOE+00 1.09E-03 2.40E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.05E-02 Ni-63 6.75E-02 4.68E-03 2.26E-03 O.OOE+00 O.OOE+00 O.OOE+00 9.76E-04 Ni-65 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Cu-64 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn-65 2.12E-03 6.75E-03 3.05E-03 O.OOE+00 4.52E-03 O.OOE+00 4.25E-03 Zn-69 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rr-RA n nnF+Onl n nnF+nn n nnr 1Ann n nnrAnn n nnr Llnn n nnE-n In nF~f rnn Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.0OE+00 1.18E-03 5.50E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.33E-04 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00

.O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 7.03E-02 0.00E+00 2.02E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-02 Sr-90 3.93E+00 O.OOE+00 9.63E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-01 Sr-91 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Y-91 3.60E-05.

O.OOE+00 9.63E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.98E-02 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-93 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 8.26E-06 2.65E-06 1.79E-06 O.OOE+00 4.15E-06 O.OOE+00 8.39E-03 Zr-97 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Nb-95 9.88E-07 5.49E-07 2.95E-07 O.OOE+00 5.43E-07 0.OOE+00 3.33E-03 Mo-99 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 5 of 16

Attachment D ODCM-QA-008 Revision 4 Page 21 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: FRUIT SAMPLE (Page 2 of 2) mrem-kg/pCi-yr NUCUDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Ru-103 3.34E-05 O.OOE+00 1.44E-05 O.OOE+00 1.28E-04 O.OOE+00 3.90E-03 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-106 1.28E-03 O.OOE+00 1.62E-04 O.OOE+00 2.47E-03 0.00E+00 8.27E-02 Ag-110m 7.04E-05 6.52E-05 3.87E-05 O.OOE+00 1.28E-04 O.OOE+00 2.66E-02 Te-125m 6.80E-04 2.46E-04 9.11 E-05 2.05E-04 2.77E-03 O.OOE+00 2.72E-03 Te-127m 2.40E-03 8.59E-04 2.93E-04 6.14E-04 9.76E-03 O.OOE+00 8.06E-03 Te-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Te-129m 1.73E-03 6.47E-04 2.74E-04 5.96E-04 7.24E-03 O.OOE+00 8.73E-03 Te-129 4.74E-06 1.78E-06 1.15E-06 3.63E-06 1.99E-05 O.OOE+00 3.57E-06 Te-131m O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-I 31 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 Te-1 32 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 1.23E-05 1.75E-05 1.01E-05 5.75E-03 3.01 E-05 O.OOE+00 4.63E-06 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00-O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 3.06E-02 7.28E-02 5.95E-02 O.OOE+00 2.36E-02 7.82E-03 1.27E-03 Cs-136 1.44E-04 5.67E-04 4.08E-04 O.OOE+00 3.15E-04 4.32E-05 6.44E-05 Cs-137 4.13E-02 5.65E-02 3.70E-02 O.OOE+00 1.92E-02 6.37E-03 1.09E-03 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-1 39 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 4.09E-04 5.13E-07 2.68E-05 O.OOE+00 1.74E-07 2.94E-07 8.41 E-04 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00.

0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 1.35E-06 9.16E-07 1.04E-07 O.OOE+00 4.25E-07 O.OOE+00 3.50E-03 Ce-143 O.OOE+00 O.OOE+00 0.00E+00 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 2.19E-04 9.16E-05 1.18E-05 O.OOE+00 5.44E-05 O.OOE+00 7.41 E-02 Pr-143 2.23E-07 8.93E-08 1.10E-08 O.OOE+00 5.16E-08 O.OOE+00 9.76E-04 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 7.41 E-08 8.56E-08 5.12E-09, O.OOE+00 5.01 E-08 0.00E+00 4.11 E-04 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 6 of 16

Attachment D ODCM-QA-008 Revision 4 Page 22 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: MEAT SAMPLE (Page 1 of 2) mrem-kglpCI-yr NUCLIDE- -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E+00 1.15E-05 1.15E-05 1.15E-05 1.15E-05 1.15E-05 1.15E-05 C-14 3.12E-04 6.25E-05 6.25E-05 6.25E-05 6.25E-05 6.25E-05 6.25E-05 Na-24 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 P-32 8.05E-03 5.00E-04 3.11 E-04 0.OOE+00 0.00E+00 0.00E+00 9.05E-04 Cr-51 0.00E+00 0.00E+00 1.77E-07 1.06E-07 3.91 E-08 2.35E-07 4.46E-05 Mn-54 0.OOE+00 4.81 E-04 9.18E-05 0.00E+00 1.43E-04 0.00E+00 1.47E-03 Mn-56 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Fe-55 2.98E-04 2.06E-04 4.80E-05 0.OOE+00 0.00E+00 1.1 5E-04 1.1 8E-04 Fe-59 3.50E-04 8.22E-04 3.15E-04 0.00E+00 0.00E+00 2.30E-04 2.74E-03 Co-58 0.00E+00 6.74E-05 1.51 E-04 0.00E+00 0.00E+00 0.00E+00 1.37E-03 Co-60 0.00E+00 2.34E-04 5.15E-04 0.00E+00 0.OOE+00 0.00E+00 4.39E-03 Ni-63 1.43E-02 9.91 E-04 4.79E-04 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Zn-65 5.03E-04 1.60E-03 7.23E-04 0.00E+00 1.07E-03 0.00E+00 1.01 E-03 Zn-69 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.10E-03 5.14E-04 0.00E+00 0.00E+00 0.00E+00 2.18E-04 Rb-88 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 2.58E-02 0.00E+00 7.39E-04 0.00E+00 0.00E+00 0.00E+00 4.13E-03 Sr-90 8.33E-01 0.00E+00 2.04E-01 0.00E+00 0.00E+00 0.00E+00 2.41 E-02 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 1.22E-05 0.00E+00 3.27E-07 0.00E+00 0.00E+00 0.00E+00 6.74E-03 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 2.69E-06 8.64E-07 5.85E-07 0.00E+00 1.36E-06 0.00E+00 2.74E-03 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.61E-07 2.56E-07 1.38E-07 0.00E+00 2.53E-07 0.00E+00 1.56E-03 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 7 of 16

Attachment D ODCM-QA-008 Revision 4 Page 23 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: MEAT SAMPLE (Page 2 of 2) mrem-kg/pCI-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 Ru-103 1.43E-05 0.OOE+OO 6.16E-06 O.OOE+OO 5.46E-05 O.OOE+O0 1.67E-03 Ru-105 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Ru-106 2.91 E-04 O.OOE+00 3.69E-05 O.OOE+00 5.63E-04 O.OOE+00 1.89E-02 Ag-11 Om 1.67E-05 1.54E-05 9.15E-06 O.OOE+O0 3.03E-05 O.OOE+O0 6.29E-03 Te-125m 2.32E-04 8.41 E-05 3.1 E-05 6.98E-05

-9.44E-04 O.OOE+O0 9.27E-04 Te-127m 6.56E-04 2.34E-04 7.99E-05 1.68E-04 2.66E-03 O.OOE+00 2.20E-03

- Te-127 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+O0 O.OOE+0O Te-129m 8.37E-04 3.12E-04 1.33E-04 2.88E-04 3.50E-03 O.OOE+O0 4.22E-03 Te-129 2.29E-06 8.59E-07 5.57E-07 1.75E-06 9.61 E-06 O.OOE+O0 1.73E-06 Te-l 31 m O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+O0

^Te-131 O.OOE+00 O.OOE+0O O.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 0.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-131 8.16E-05 1.17E-04 6.69E-05 3.82E-02 2.OOE-04 O.OOE+00 3.08E-05 1-132 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 1-134 O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+OO O.OOE+00 O.OOE+OO O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+O0 Cs-134 6.72E-03 1.60E-02 1.31 E-02 O.OOE+OO 5.17E-03 1.72E-03 2.80E-04 Cs-136 2.50E-04 9.86E-04 7.1OE-04 O.OOE+0O 5.49E-04 7.52E-05 1.12E-04 Cs-137 8.76E-03 1.20E-02 7.84E-03 O.OOE+O0 4.06E-03 1.35E-03 2.32E-04 Cs-138 0.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+OO O.OOE+00 O.OOE+OO O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O 0.OOE+00 0.OOE+OO Ba-140 7.55E-04 9.49E-07 4.95E-05 O.OOE+00 3.23E-07 5.43E-07 1.56E-03 Ba-141 O.OOE+O0 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 6.72E-07 4.55E-07 5.16E-08 O.OOE+00 2.11 E-07 O.OOE+00 1.74E-03 Ce-143 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO Ce-144 5.1tE-05 2.14E-05 2.74E-06 O.OOE+00 1.27E-05 O.OOE+00 1.73E-02 Pr-143 3.64E-07 1.46E-07 1.80E-08 O.OOE+00 8.43E-08 O.OOE+00 1.59E-03 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 Nd-147 1.96E-07 2.26E-07 1.35E-08 O.OOE+00 1.32E-07 O.OOE+00 1.09E-03 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Page 8 of 16

Attachment D ODCM-QA-008 Revision 4 Page 24 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: FISH SAMPLE (Page 1 of 2)

N mrem-kg/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E+00 2.20E-06 2.20E-06 2.20E-06 2.20E-06 2.20E-06 2.20E-06 C-14 5.96E-05 1.19E-05 1.19E-05 1.19E-05 1.19E-05 1.19E-05 1.19E-05 Na-24 1.18E-05 1.18E-05 1.18E-05 1.18E-05 1.18E-05 1.18E-05 1.18E-05 P-32 3.86E-03 2.40E-04 1.49E-04 0.00E+00 0.00E+00 0.00E+00 4.34E-04 Cr-51 0.00E+00 0.00E+00 5.45E-08 3.26E-08 1.20E-08 7.23E-08 1.37E-05 Mn-54 0.00E+00 9.58E-05 1.83E-05 0.00E+00 2.85E-05 0.00E+00 2.93E-04 Mn-56 0.OOE+00 3.81 E-09 6.76E-10 0.OOE+00 4.84E-09 0.00E+00 1.22E-07 Fe-55 5.77E-05 3.99E-05 9.30E-06 0.00E+00 0.00E+00 2.22E-05 2.29E-05 Fe-59 8.97E-05 2.11 E-04 8.08E-05 0.00E+00 0.OOE+00 5.89E-05 7.03E-04 Co-58 0.OOE+00 1.55E-05 3.47E-05 0.00E+00 0.00E+00 0.00E+00 3.14E-04 Co-60 0.00E+00 4.49E-05 9.91 E-05 0.00E+00 0.OOE+00 0.00E+00 8.44E-04 NI-63 2.73E-03 1.89E-04 9.16E-05 0.00E+00 0.OOE+00 0.OOE+00 3.95E-05 Ni-65 1.51 E-08 1.96E-09 8.93E-10 0.00E+00 0.00E+00 O.O0E+00 4.96E-08 Cu-64 0.00E+00 4.72E-07 2.22E-07 0.00E+00 1.19E-06 0.00E+00 4.02E-05 Zn-65 1.01 E-04 3.22E-04 1.46E-04 0.00E+00 2.16E-04 0.00E+00 2.03E-04 Zn-69 3.58E-15 6.85E-15 4.76E-16 0.00E+00 4.45E-15 0.00E+00 1.03E-15 Br-83 0.OOE+00 0.00E+00 8.01 E-10 0.00E+00 0.00E+00 0.OOE+00 1.15E-09 Br-84 0.00E+00 0.OOE+00 2.72E-20 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Br-85 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 -

0.00E+00 0.OOE+00 0.00E+00 Rb-86 0.00E+00 4.27E-04 1.99E-04 0.00E+00 0.00E+00 0.00E+00 8.42E-05 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Rb-89 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 6.38E-03 0.00E+00

.1.83E-04 0.00E+00 0.00E+00 0.00E+00 1.02E-03 Sr-90 1.59E-01 0.00E+00 3.91 E-02 O.OOE+00 0.00E+00 0.00E+00 4.60E-03 Sr-91 2.07E-05 0.00E+00 8.35E-07 0.00E+00 0.00E+00 0.00E+00 9.84E-05 Sr-92 9.74E-08 0.00E+00 4.21 E-09 0.00E+00 0.00E+00 0.00E+00 1.93E-06 Y-90 1.56E-07 0.00E+00 4.18E-09 0.00E+00 0.00E+00 0.00E+00 1.65E-03 Y-91m 3.78E-18 0.00E+00 1.47E-19 0.OOE+00 0.OOE+00 0.OOE+00 1.11E-17 Y-91 2.93E-06 0.OOE+00 7.82E-08 0.00E+00 0.00E+00 0.00E+00 1.61 E-03 Y-92 1.62E-10 0.00E+00 4.72E-12 O.00E+00 0.OOE+00 0.00E+00 2.83E-06 Y-93 1.08E-08 0.00E+00 2.99E-10 0.00E+00 O.00E+00 0.00E+00 3.44E-04 Zr-95 6.32E-07 2.03E-07 1.37E-07 0.00E+00 3.18E-07 0.00E+00 6.42E-04 Zr-97 1.32E-08 2.66E-09 1.22E-09 0.00E+00 4.02E-09 0.00E+00 8.24E-04 Nb-95 1.28E-07 7.12E-08 3.83E-08 0.OOE+00 7.04E-08 0.00E+00 4.32E-04 Mo-99 0.00E+00 7.04E-05 1.34E-05 0.00E+00 1.59E-04 0.00E+00 1.63E-04 Tc-99m 3.27E-10 9.25E-10 1.18E-08 0.00E+00 1.40E-08 4.53E-10 5.47E-07 J

Page 9 of 16

Attachment D ODCM-QA-008 Revision 4 Page 25 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: FISH SAMPLE (Page 2 of 2) mrem-kg/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-1 03 3.82E-06 O.OOE+00 1.64E-06 O.OOE+00 1.A6E-05 O.OOE+00 4.46E-04 Ru-105 7.63E-09 O.OOE+00 3.01 E-09 O.OOE+00 9.86E-08 O.OOE+00 4.67E-06 Ru-106 5.76E-05 O.OOE+00 7.29E-06 O.OOE+00 1.1 IE-04 O.OOE+00

'3.73E-03 Ag-11Om 3.35E-06 3.1 OE-06 1.84E-06 O.OOE+00 6.09E-06 O.OOE+00 1.26E-03 Te-125m 5.56E-05 2.01 E-05 7.45E-06 1.67E-05 226E-04 O.OOE+00 2.22E-04 Te-127m 1.41 E-04 5.05E-05 1.72E-05 3.61 E-05 5.74E-04 0.00E+00 4.74E-04 Te-127 3.90E-07 1.40E-07 8.44E-08 2.89E-07 1.59E-06 O.OOE+00 3.08E-05 Te-129m 2.37E-04 8.83E-05 3.74E-05

- 8.13E-05 9.87E-04 O.OOE+00 1.19E-03 Te-129 6.46E-07 2.43E-07 1.57E-07 4.96E-07 2.72E-06 O.OOE+00 4.88E-07 Te-131 m 2.09E-05 1.02E-05 8.50E-06 1.62E-05 1.03E-04 O.OOE+00 1.01E-03 Te-131 2.05E-24 O.OOE+00 0.00E+00 1.69E-24 8.98E-24 O.OOE+00 O.OOE+00 Te-132 4.28E-05 2.77E-05 2.60E-05 3.06E-05 2.67E-04 O.OOE+00 1.31E-03 1-130 4.1 3E-06 1.22E-05 4.81 E-06 1.03E-03 1.90E-05 O.OOE+00 1.05E-05 1-131 8.01 E-05 1.15E-04 6.57E-05 3.76E-02 1.97£-04 O.OOE+00 3.02E-05 1-132 3.08E-09 8.24E-09 2.88E-09 2.88E-07 1.31 E-08 O.OOE+00 1.55E-09 1-133 1.34E-05 2.33E-05 7.11 E-06 3A3E-03 4.07E-05 O.OOE+00 2.10E-05 1-134 1.33E-14 3.61 E-14 1.29E-14 6.25E-13 5.73E-14 O.OOE+00 3.14E-17 1-135 7.51 E-07 1.97E-06 7.26E-07 1.30E-04 3.15E-06 O.OOE+00 2.222E-06 Cs-134 1.-OE03 3.11 E-03 2.54E-03 O.OOE+00 1.OOE-03 3.34E-04 5.43E-05 Cs-136 1.30E-04 5.12E-04 3.69E-04 O.OOE+00 2.85E-04 3.90E-05 5.82E-05 Cs-137 1.67E-03 2.29E-03 1.50E-03 O.OOE+00 7.77E-04 2.58E-04 4A3E-05 Cs-138 4.25E-20 8.40E-20 4.16E-20 O.OOE+00 6.17E-20 6.1 OE-21 O.OOE+00 Ba-139 1.27E-11 9.03E-15 3.71 E-1 3 O.OOE+00 8.44E-15 5.12E-15 225E-11 Ba-140 4.04E-04 5.07E-07 2.65E-05 0.00E+00 1.72E-07 2.90E-07 8.31 E-04 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 33A7E-08 1.75E-08 4.62E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.28E-03 La-142 7.85E-14 3.57E-14 8.89E-15 O.OOE+00 O.OOE+00 O.OOE+00 2.61 E-1 0 Ce-141 1.92E-07 1.30E-07 1.48E-08 O.OOE+00 6.04E-08 O.OOE+00 4.97E-04 Ce-143 2.09E-08 1.55E-05 1.71 E-09 O.OOE+00 6.81 E-09 O.OOE+00 5.78E-04 Ce-144 1.02E-05 4.27E-06 5.49E-07 O.OOE+00 2.53E-06 O.OOE+00 3.46E-03 Pr-143 1.84E-07 7.36E-08 9.1 OE-09 O.OOE+00 4.25E-08 O.OOE+0O 8.04E-04 Pr-144 O.0OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO 0.0OE+00 O.OOE+00 Nd-147 1.24E-07 1.43E-07 8.58E-09 0.00E+00 8.38E-08 O.OOE+00 6.88E-04 W-187 1.08E-06 9.OOE-07 3.14E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.95E-04 Np,239 1.86E-08 1.83E-09 1.01E-09 O.OOE+00 5.71E-09 O.OOE+00 3.75E-04 Page 1 0 of 16

Attachment D ODCM-QA-008 Revision 4 Page 26 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: DRINKING WATER (Page 1 of 2) mrem-liter/pCi-yr I

NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LI H-3 0.OOE+00 7.66E-05 7.66E-05 7.66E-05 7.66E-05 7.66E-05 7.66E-05 C-14 2.07E-03 4.15E-04 4.15E-04 4.15E-04 4.15E-04 4.15E-04 4.15E-04 Na-24 7.13E-04 7.13E-04 7.13E-04 7.13E-04 7.13E-04 7.13E-04 7.13E-04 P-32 1.38E-01 8.55E-03 5.32E-03 0.OOE+00 0.OOE+00 0.00E+00 1.55E-02 Cr-51 0.00E+00 0.00E+00 1.92E-06 1.15E-06 4.22E-07 2.54E-06 4.82E-04 Mn-54 0.00E+00 3.33E-03 6.36E-04 0.00E+00 9.92E-04 0.00E+00 1.02E-02 Mn-56 0.00E+00 3.33E-06 5.92E-07 0.00E+00 4.23E-06 0.00E+00 1.06E-04 Fe-55 2.01 E-03 1.39E-03 3.23E-04 0.OOE+00 0.OOE+00 7.74E-04 7.95E-04 Fe-59 3.14E-03 7.39E-03 2.83E-03 0.00E+00 0.00E+00 2.06E-03 2.46E-02 CO-58 0.00E+00 5.41 E-04 1.21 E-03 0.00E+00 0.00E+00 0.00E+00 1.1OE-02 Co-60 0.OOE+00 1.56E-03 3.44E-03 0.00E+00 0.00E+00 0.00E+00 2.93E-02 Ni-63 9.49E-02 6.58E-03 3.18E-03 0.OOE+00 0.00E+00 0.OOE+00 1.37E-03 Ni-65 1.42E-05 1.85E-06 8.42E-07 0.00E+00 0.00E+00 0.00E+00 4.68E-05 Cu-64 0.00E+00 3.16E-05 1.48E-05 0.00E+00 7.96E-05 0.00E+00 2.69E-03 Zn-65 3.53E-03 1.12E-02 5.07E-03 0.00E+00 7.51 E-03 0.00E+00 7.07E-03 Zn-69 9.68E-10 1.85E-09 1.29E-10 0.00E+00.

1.20E-09 0.00E+00 2.78E-10 Br-83 O.OOE+00 0.00E+00 9.04E-07 0.00E+00 0.00E+00 0.00E+00 1.30E-06

,_E Br-84 0.U00+uu U.U00+00 6.00E-12 0.00E+00 0.00E+00 0.OOE+00 4.71 E-17 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 0.00E+00 1.51 E-02 7.04E-03 0.00E+00 0.00E+00 0.00E+00 2.98E-03 Rb-88 0.00E+00 3.11E-17 1.65E-17 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 2.86E-19 2.01E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 2.23E-01 0.00E+00 6.41 E-03 0.00E+00 0.00E+00 0.00E+00 3.58E-02 Sr-90 5.53E+00 0.00E+00 1.36E+00 0.00E+00 0.00E+00 0.00E+00 1.60E-01 Sr-91 1.72E-03 0.00E+00 6.96E-05 0.00E+00 0.00E+00 0.00E+00 8.21 E-03 Sr-92 7.29E-05 0.002+00 3.15E-06 0.00E+00 0.00E+00 0.00E+00 1.44E-03 Y-90 6.17E-06 0.00E+00 1.65E-07 0.00E+00 0.00E+00 0.00E+00 6.54E-02 Y-91m 2.95E-12 0.00E+00 1.14E-13 0.00E+00 0.00E+00 0.00E+00 8.68E-12 Y-91 1.02E-04 0.00E+00 2.74E-06 0.00E+00 0.00E+00 0.00E+00 5.63E-02 Y-92 5.88E-08 0.00E+00 1.72E-09 0.00E+00 0.00E+00 0.00E+00 1.03E-03 Y-93 8.59E-07 0.00E+00 2.37E-08 0.00E+00 0.00E+00 0.00E+00 2.72E-02 Zr-95 2.21E-05 7.08E-06 4.79E-06 0.00E+00 1.11 E-05 0.00E+00 2.24E-02 Zr-97 7.50E-07 1.51 E-07 6.92E-08 0.00E+00 2.28E-07 0.00E+00 4.69E-02 Nb-95 4.50E-06 2.50E-06 1.34E-06 0.00E+00 2.47E-06 0.00E+00 1.52E-02 Mo-99 0.00E+00 2.77E-03 5.28E-04 0.00E+00 6.28E-03 0.00E+00 6.43E-03 Tc-99m 4.53E-08 1.28E-07 1.63E-06 0.00E+00 1.94E-06 6.27E-08 7.57E-05

-l/

-1 Page 11 of 16

Attachment D ODCM-QA-008 Revision 4 Page 27 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: DRINKING WATER (Page 2 of 2) mrem-literlpCi-yr NUCLIDE-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 1.08E-22 1.56E-22 1.53E-21 O.OOE+00 2.81 E-21 7.98E-23 O.OOE+00 Ru-1 03 1.34E-04 O.OOE+00 5.77E-05 O.OOE+00' 5.11 E-04 O.OOE+00 1.56E-02 Ru-1 05 1.73E-06 0.00E+00 6.82E-07.

O.OOE+00 2.23E-05, O.OOE+00 1.06E-03 Ru-106 2.01 E-03 0.OOE+00, 2.54E-04 O.OOE+00 3.87E-03 O.OOE+00 1.30E-01 Ag-1I0m 1.17E-04 1.08E-04 6.41E-05 O.OOE+00

' 2.12E-04 O.OOE+00 4.40E-02, Te-125m 1.94E-03 7.05E-04 2.61 E-04 5.85E-04 7.91E-03 O.OOE+00 7.76E-03 Te-127m 4.93E-03 1.76E-03 6.00E-04 1.26E-03 2.00E-02 O.OOE+00 1.65E-02 Te-127 3.30E-05 1.18E-05 7.14E-06 2.44E-05 1.34E-04 O.OOE+00 2.60E-03 Te-129m 8.31 E-03 3.10E-03 1.31 E-03 2.85E-03 3.47E-02 O.OOE+00 4.18E-02 Te-129 2.27E-05 8.53E-06 5.53E-06 1.74E-05 9.54E-05 O.OOE+00 1.71E-05 Te-131m 9.57E-04 4.68E-04 3.90E-04 7.41 E-04 4.74E-03 O.OOE+00 4.65E-02 Te-131 3.20E-14 1.34E-14 1.01E-14 2.63E-14 1.40E-13 O.OOE+O 4.53E-15.

Te-132 1.65E-03 1.07E-03 1.00E-03 1.18E-03 1.03E-02 O.OOE+O0; 5.06E-02 1-130 2.82E-04 8.31 E-04 3.28E-04 7.04E-02 1.30E-03 O.OOE+00 7.15E-04 1-131 2.91 E-03 4.16E-03 2.38E-03 1.36E+00 7.13E-03 O.OOE+00 1.10E-03 1-132 3.98E-06 1.07E-05 3.73E-06 3.73E-04 1.70E-05

-O.OOE+00 2.00E-06 1-133 6.95E-04 1.21 E-03 3.69E-04 1.78E-01 2.11 E-03 O.OOE+00 1.09E-03 1-134 5.97E-09 1.62E-08 5.81 E-09 2.81 E-07 2.58E-08 O.OOE+00 1.41 E-11 1-135 9.19E-05 2.41 E-04 8.88E-05

-1.59E-02 3.86E-04 O.OOE+

0 00 2.72E-04 Cs-134 4.54E-02 1.08E-01 8.83E-02 O.OOE+00

.3.50E-02 1.16E-02 1.89E-03 Cs-1 36 4.63E-03 1.83E-02 1.32E-02 O.OOE+00 1.02E-02 1.39E-03 2.08E-03 Cs-1 37 5.82E-02 7.96E-02 5.21 E-02 O.OOE+00 2.70E-02 8.98E-03 1.54E-03 Cs-138 7.72E-12 1.52E-11 7.55E-12 0.00E+00

,1.12E-11 1.11E-12 6.50E-17 Ba-139 1.77E-07 1.26E-10 5.17E-09 O.OOE+00

- 1.18E-10 7.14E-11 3.13E-07 Ba-140 1.44E-02 1.81 E-05 9.45E-04 O.OOE+00 6.16E-06 1.04E-05.

2.97E-02 Ba-141 4.97E-17 3.76E-20 1.68E-18 O.OOE+00 3.50E-20 2.13E-20 O.OOE+00 Ba-142 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 1.48E-06 7.48E-07 1.98E-07 0.00E+00 O.OOE+00 O.OOE+00 5.49E-02 La-142 5.05E-10 2.30E-10 5.72E-11 O.OOE+00 O.OOE+00 O.OOE+00 1.68E-06 Ce-141 6.76E-06 4.57E-06 5.19E-07 O.OOE+00

.2.12E-06 O.OOE+00 1.75E-02 Ce-143 9.36E-07 6.92E-04 7.66E-08 O.OOE+00 3.05E-07 O.OOE+00 2.59E-02 Ce-144 3.56E-04 1.49E-04 1.91E-05 O.OOE+00 8.82E-05 O.OOE+00 1.20E-01 Pr-143 6.55E-06 2.63E-06

,3.24E-07 O.OOE+00 1.52E-06 O.OOE+00 2.87E-02 Pr-144 6.67E-21 2.77E-21 3.39E-22 O.OOE+00 1.56E-21 0.O0E+0O O.OOE+00 Nd-147 4.45E-06 5.14E-06 3.08E-07 O.OOE+00 3.01 E-06 O.OOE+00 2.47E-02 W-187 5.30E-05 4.43E-05 1.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.45E-02 Np-239 7.50E-07 7.37E-08 4.06E-08 O.OOE+00 2.30E-07 O.OOE+00 1.51E-02 Page 12 of 16

Attachment D ODCM-QA-008 Revision 4 Page 28 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 1 of 2) mrem-m3/pCi-yr NUCLIDE-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.00 E+00 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 C-14 1.82E-02 3.41 E-03 3.41 E-03 3.41 E-03 3.41 E-03 3.41 E-03 3.41E-03 Na-24 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 1.21E+01 7.05E-01 4.58E-01 0.00E+00 0.00E+00 0.00E+00 7.90E-01 Cr-51 0.OOE+00 0.OOE+00 3.13E-04 1.86E-04 7.14E-05 4.51E-02 1.04E-02 Mn-54 0.OOE+00 4.38E-02 6.97E-03 0.OOE+00 1.09E-02 1.55E+00 8.56E-02 Mn-56 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Fe-55 2.54E-02 1.75E-02 4.07E-03 0.00E+00 0.OOE+00 7.44E-02 6.23E-03 Fe-59 2.39E-02 5.64E-02 2.14E-02 0.00E+00 0.00E+00 2.06E+00 3.82E-01 Co-58 0.00E+00 2.48E-03 3.24E-03 0.00E+00 0.00E+00 1.45E+00 1.66E-01 Co-60 0.OOE+00 1.17E-02 1.50E-02 0.00E+00 0.OOE+00 6.07E+00 2.90E-01 NI-63 4.32E-01 3.15E-02 1.45E-02 0.00E+00 0.00E+00 1.79E-01 1.34E-02 Ni-65 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Zn-65 3.69E-02 1.17E-01 5.30E-02 0.00E+00 7.85E-02 9.83E-01 6.08E-02 Zn-69 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.OOE+00 7.36E-01 3.21 E-01 0.00E+00 0.OOE+00 0.00E+00 9.06E-02 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 5.68E-01 0.00E+00 1.63E-02 0.00E+00 0.00E+00 2.62E+00 6.54E-01 Sr-90 9.95E+01 0.00E+00 6.11 E+00 0.00E+00 0.00E+00 9.63E+00 7.24E-01 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Y-91m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Y-91 7.94E-01 0.OOE+00 2.13E-02 0.OOE+00 0.00E+00 2.93E+00 6.61 E-01 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Zr-95 1.76E-01 5.64E-02 3.82E-02 0.00E+00 8.88E-02 2.90E+00 2.46E-01 Zr-97 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 3.47E-02 1.93E-02 1.04E-02 0.00E+00 1.91 E-02 1.24E+00 2.56E-01 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 13 of 16

Attachment D ODCM-QA-008 Revision 4 rnl-nf 1t 07f h'-'

REMP DOSE FACTORS FOR ADULT AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 2 of 2) e-vur to mrem-m 3lpCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

-O.OOE+00 O.OOE+00 Ru-103 3.41 E-03 O.OOE+O0 1.47E-03 O.OOE+00 1.30E-02 1.13E+00 2A7E-01 Ru-105 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 0O.OOE+00 O.OOE+00 Ru-106 7.53E-02 O.OOE+00 9.50E-03 O.OOE+00 1.46E-01 1.02E+01 9.94E-01 Ag-11 Om 1.23E-02 1.13E-02 6.75E-03 O.OOE+00 2.23E-02 5.26E+00 3.43E-01 Te-125m 5.89E-03 2.73E-03 8.06E-04 1.81 E-03 2.14E-02 5.41E-01 1.22E-01 Te-127mr 1.69E-02 7.71E-03 2.1OE-03 4.39E-03 6.12E-02 1.28E+00 2.OOE-01 Te-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-129m 2.50E-02 1.20E-02 4.06E-03 8.82E-03 9.37E-02 2.97E+00 9.82E-01 Te-129 1.28E-07 6.13E-08 3.18E-08 9.99E-08 4.80E-07 4.96E-03 4.02E-04 Te-131rm O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.0E+00 O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+0O 1-131 1.29E+00 1.83E+00 1.05E+00 6.09E+02 3.13E+00 O.OOE+00 3.21E-01 1-132

.002E+00-O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 3.89E-01 8.84E-01 7.59E-01 O.OOE+00 3.00E-01 1.02E-01 1.08E-02 Cs-136 4.32E-01 1.62E+00 1.22E+00 i

-O.OOE+00 9.47E-01 1.33E-01 1.29E-01 Cs-137 4.80E-01 6.23E-01 4.29E-01 O.OOE+00 2.23E-01 7.54E-02 8.42E-03 Cs-1 38 O.OOE+00 0.002+00 0.002000 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 Ba-139 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ba-140 4.63E-01 5.81 E-04 3.04E-02 O.OOE+00 1.98E-04

.1.51 E+01 2.59E+00 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+O0 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 5.27E-02 3.58E-02 4.04E-03 O.OOE+00 1.66E-02 9.57E-01 3.18E-01 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 3.84E+00 1.60E+00 2.06E-01 O.OOE+00 9.48E-01 8.69E+00 9.12E-01 Pr-143 9.64E-02 3.86E-02 4.78E-03 0.00E+00 2.22E-02 2.89E+00 2.06E+00 Pr-144 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Nd-147 9.39E-02 1.09E-01 6.50E-03 O.OOE+00 6.34E-02 3.93E+00 3.08E+00 W-187 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+0020 0.OOE+00 0.0+0 O.OOE+00 O.OOE+000 O.OOE+00 Page 14 of 16

I Attachment D ODCM-QA-008 Revision 4 Page 30 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: INHALATION - WEEKLY SAMPLING (Page 1 of 2) mrem-m 3/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.26E-03 1.26E-03 1.26E-03 1.26E-03 1.26E-03 1.26E-03 C-14 1.82E-02 3.41 E-03 3.41 E-03 3.41E-03 3.41 E-03 3.41 E-03 3.41 E-03 Na-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 1.56E+00 9.14E-02 5.93E-02 0.00E+00 0.00E+00 0.00E+00 1.02E-01 Cr-51 0.00E+00 0.00E+00 1.09E-04 6.50E-05 2.49E-05 1.57E-02 3.62E-03 Mn-54 0.00E+00 3.99E-02 6.35E-03 0.00E+00 9.92E-03 1.41 E+00 7.80E-02 Mn-56 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 2.46E-02 1.70E-02 3.95E-03 0.00E+00 0.OOE+00 7.23E-02 6.05E-03 Fe-59 1.24E-02 2.93E-02 1.11 E-02 0.00E+00 0.00E+00 1.07E+00 1.99E-01 CO-58 0.00E+00 1.64E-03 2.14E-03 0.00E+00 0.00E+00 9.60E-01 1.1OE-01 Co-60 0.00E+00 1.15E-02 1.48E-02 0.00E+00 0.00E+00 5.98E+00 2.85E-01 Ni-63 4.32E-01 3.14E-02 1.45E-02 0.00E+00 0.00E+00 1.78E-01 1.34E-02 Ni-65 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 3.27E-02 1.04E-01 4.70E-02 0.00E+00 6.96E-02 8.73E-01 5.40E-02 Zn-69 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 U.0u0+uu U.0U0+0U 0.00E+00 0.00E+00 0.00E+00 0.00E+OO n-om^+nn Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.54E-01 6.71 E-02 0.00E+00 0.00E+00 0.00E+00 1.90E-02 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 3.19E-01 0.00E+00 9.15E-03 0.00E+00 0.00E+00 1.47E+00 3.67E-01 Sr-90 9.92E+01 0.00E+00 6.10E+00 0.00E+00 0.00E+00 9.60E+00 7.22E-01 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 m 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 4.82E-01 0.00E+00 1.29E-02 0.00E+00 0.00E+00 1.78E+00 4.01 E-01 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 Zr-95 1.11E-01 3.57E-02 2.42E-02 0.00E+00 5.63E-02 1.84E+00 1.56E-01 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.51 E-02 8.38E-03 4.51 E-03 0.00E+00 8.29E-03 5.41 E-01 1.11E-01 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J

-z Page 15 of 16

Attachment D ODCM-QA-008 Revision 4 Page 31 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: INHALATION - WEEKLY SAMPLING (Page 2 of 2)

_ _mrem-m3/pCi-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+O0 0.00E+00 O.OOE+00 Ru-103 1.63E-03 O.OOE+00 7.00E-04 O.OOE+00 6.20E-03 5.37E-01 1.17E-01 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Ru-106 6.96E-02 O.OOE+00 8.78E-03 O.OOE+00 1.34E-01 9A2E+00 9.18E-01 Ag-1I Om 1.09E-02 1.01E-02 6.00E-03 O.OOE+00 1.99E-02 4.68E+00 3.05E-01 Te-125m 3.56E-03 1.65E-03 4.87E-04 1.09E-03 1.29E-02 3.27E-01 7.37E-02 Te-127m 1.29E-02 5.90E-03 1.60E-03 3.36E-03 4.68E-02 9.82E-01 1.53E-01 Te-127 O.OOE+00.

O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Te-129m 1.05E-02 5.02E-03 1.70E-03 3.70E-03 3.93E-02 1.25E+00 4.12E-01 Te-129 5.35E-08 2.57E-08 1.33E-08 4.19E-08 2.01 E-07 2.08E-03 1.69E-04 Te-131m 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+002 Te-131 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00

.Te-132 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 1-130 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 1-131 2.52E-02 3.58E-02 2.05E-02 1.19E+01 6.13E-02 O.OOE+00 6.28E-03 1-132 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 1-135 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Cs-1 34 3.74E-01 8.51 E-01 7.30E-01 O.OOE+00 2.88E-01 9.79E-02 1.04E-02 Cs-136 4.69E-02 1.76E-01 1.33E-01 O.OOE+00 1.03E-Of 1.44E-02 1.40E-02 Cs-137 4.79E-01 6.21 E-01 4.28E-01

.O.OOE+00 222E-01 7.52E-02 8.40E-03 Cs-1 38 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Ba-I 39 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Ba-140 4.72E-02 5.93E-05 3.1 OE-03 O.OOE+00 2.02E-05 1.54E+00 2.64E-01 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00

.O.OOE+00 0.00E+00 O.OOE+00 0.00E+00

,Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Ce-141 2.15E-02 1.46E-02 1.65E-03 0.00E+00 6.75E-03 3.90E-01 129E-01

-Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Ce-144 3.46E+00 1.44E+00 1.86E-01 0.OOE+OO 8.55E-01 7.84E+00 8.23E-01 Pr-143 1.12E-02 4.49E-03 5.55E-04 O.OOE+00 2.58E-03 3.36E-01 2.39E-01 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Nd-147 6.58E-03 7.60E-03 4.55E-04 O.OOE+00 4.44E-03 2.75E-01 2.16E-01 W-187 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Np-239 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Page 16 of 16

Attachment E ODCM-QA-008 Revision 4 Page 32 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: MILK (Page 1 of 2) mrem-liter/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 4.24E-05 4.24E-05 4.24E-05 4.24E-05 4.24E-05 4.24E-05 C-14 1.62E-03 3.25E-04 3.25E-04 3.25E-04 3.25E-04 3.25E-04 3.25E-04 Na-24 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 P-32 1.00E-01 6.21 E-03 3.88E-03 0.OOE+00 0.00E+00 0.00E+00 8.42E-03 Cr-51 0.00E+00 0.00E+00 1.37E-06 7.61 E-07 3.00E-07 1.96E-06 2.30E-04 Mn-54 0.00E+00 2.35E-03 4.66E-04 0.00E+00 7.01 E-04 0.OOE+00 4.82E-03 Mn-56 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 1.51 E-03 1.07E-03 2.50E-04 0.00E+00 0.00E+00 6.79E-04 4.63E-04 Fe-59 2.28E-03 5.31 E-03 2.05E-03 0.00E+00 0.OOE+00 1.68E-03 1.26E-02 Co-58 0.00E+00 3.81 E-04 8.79E-04 0.00E+00 0.00E+00 0.OOE+00 5.26E-03 Co-60 0.00E+00 1.12E-03 2.53E-03 0.00E+00 0.00E+00 0.00E+00 1.46E-02 Ni-63 7.08E-02 5.OOE-03 2.40E-03 0.002+00 0.OOE+00 0.00E+00 7.96E-04 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Cu-64 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 2.29E-03 7.95E-03 3.71 E-03 0.00E+00 5.09E-03 0.00E+00 3.37E-03 Zn-69 O.00E+00-0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Br-85 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 -

0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.11E-02 5.20E-03 0.00E+00 0.00E+00 0.OOE+00 1.64E-03 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 0.00E+00 Sr-89 1.71 E-01 0.00E+00 4.90E-03 0.00E+00 0.00E+00 0.00E+00 2.04E-02 Sr-90 3.32E+00 0.00E+00 8.20E-01 0.00E+00 0.00E+00 0.00E+00 9.32E-02 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 7.85E-05 0.00E+00 2.11 E-06 0.OOE+00 0.00E+00 0.00E+00 3.22E-02 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.61 E-05 5.09E-06 3.50E-06 0.00E+00 7.48E-06 0.00E+00 1.17E-02 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 3.16E-06 1.75E-06 9.65E-07 0.00E+00 1.70E-06 0.00E+00 7.50E-03 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1 of 16

Attachment E ODCM-QA-008 Revision 4 Page 33 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: MILK (Page 2 of 2) mrem-iterlpCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY

- LUNG GI-LLI Tc-101 O.OOE+OO 0.00E+0 O.OOE+OO O.OOE+OO 0.0OE+00 O.OOE+00 O.OOE+00 Ru-1 03 9.85E-05 O.OOE+00 4.21 E-05 0.00E+00 3A7E-04 O.OOE+00 8.23E-03 Ru-1 05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-106 1.56E-03 O.OOE+00 1.97E-04 O.OOE+00 3.01 E-03 O.OOE+00 7.49E-02 Ag-11 Omr 8.t5E-05 7.72E-05 4.69E-05 O.OOE+00 1.47E-04 O.OOE+00 2.17E-02 Te-125m 1.50E-03 5.39E-04 2.00E-04 4.18E-04 O.OOE+00 O.OOE+00 4.41E-03 Te-1 27m 3.82E-03 1.35E-03 4.54E-04 9.08E-04 1.55E-02 O.OOE+00 9.52E-03 Te-127 O.OOE+00 O.OOE+00 O.OOE+00

- O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 Te-129m 6.26E-03 2.32E-03 9.90E-04 2.02E-03 2.62E-02 O.OOE+00 2.35E-02 Te-129

-1.72E-05 6.41E-06 4.1 8E-06 1.23E-05 7.22E-05 0.00E+00 9.40E-05 Te-131 m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O 0.00E+00 O.OOE+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1-131 1.97E-03 2.76E-03 1.48E-03 8.05E-01 4.75E-03 O.OOE+00 5.45E-04 1-132 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 3.34E-02 7.87E-02 3.65E-02 0.00E+00 2.50E-02 9.54E-03 9.78E-04 Cs-136 3.09E-03 1.22E-02 8.17E-03 O.OOE+00 6.62E-03 1.04E-03 9.79E-04 Cs-137 4.48E-02 5.96E-02 2.08E-02 O.OOE+00 2.03E-02 7.88E-03 8A8E-04 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00

-O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 1.02E-02 1.25E-06 6.57E-04 0.002+00 4.24E 8.40E-06 1.57E-02 Ba-141 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 La-142

-,0.00E+00

.002+00 0.002+00

-0.002+00 0.002+00 0.002+00 0.002+00 Ce-141 5.10E-06 3.40E-06 3.91E - O.OOE+00 1.60E-06 O.OOE+00 9.74E-03 Ce-143 0.00E+00 O.OOE+00 O.OOE+00 0.002+00 -

O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 2.77E-04 1.15E-04 1.49E-05 O.OOE+00 6.85E-05 O.OOE+00 6.97E-02 Pr-143 4.732-06 1.89E-06 2.35E-07 O.OOE+00 1.1 OE-06 0.00E+00 1.56E-02 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 3.31 E-06 3.60E-06 2.15E-07 O.OOE+00 2.11 E2-06 O.OOE+00 1.30E-02 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 2 of 16

Attachment E ODCM-QA-008 Revision 4 Page 34 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: LEAFY VEG. SAMPLES (Page 1 of 2) mrem-kg/pCI-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 4.45E-06 4.45E-06 4.45E-06 4.45E-06 4.45E-06 4.45E-06 C-14 1.71 E-04 3.41 E-05 3.41 E-05 3.41 E-05 3.41 E-05 3.41 E-05 3.41 E-05 Na-24 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 P-32 1.10E-02 6.84E-04 4.28E-04 0.00E+00 0.00E+00 0.00E+00 9.28E-04 Cr-51 0.00E+00 0.00E+00 1.47E-07 8.19E-08 3.23E-08 2.11 E-07 2.48E-05 Mn-54 0.00E+00 2.47E-04 4.90E-05 0.00E+00 7.38E-05 0.OOE+00 5.07E-04 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00

-Fe-55 1.59E-04 1.12E-04 2.62E-05 0.OOE+00 0.OOE+00 7.13E-05 4.87E-05 Fe-59 2.43E-04 5.67E-04 2.19E-04 0.00E+00 0.00E+00 1.79E-04 1.34E-03 Co-58 0.00E+00 4.04E-05 9.32E-05 0.00E+00 0.00E+00 0.00E+00 5.57E-04 Co-60 0.00E+00 1.18E-04 2.66E-04 0.00E+00 0.00E+00 0.00E+00 1.54E-03 Ni-63 7.43E-03 5.25E-04 2.52E-04 0.00E+00 0.OOE+00 0.00E+00 8.36E-05 Ni-65 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 Zn-65 2.41 E-04 8.38E-04 3.91 E-04 0.00E+00 5.36E-04 0.00E+00 3.55E-04 Zn-69 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Rb-86 0.OOE+00 1.21 E-03 5.67E-04 0.00E+00 0.00E+00 0.00E+00 1.78E-04 Rb-88 0.00E+00 0.00E+00 0.00E+00

.0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 1.82E-02 0.00E+00 5.22E-04 0.00E+00 0.00E+00 0.00E+00 2.17E-03 Sr-90 3.49E-01 0.OOE+00 8.61 E-02 0.00E+00 0.OOE+00 0.00E+00 9.79E-03 Sr-91 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Sr-92 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.00E+00-0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 8.34E-06 0.00E+00 2.24E-07 0.00E+00 0.OOE+00 0.00E+00 3.42E-03 Y-92 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Y-93 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.71 E-06 5.40E-07 3.71 E-07 0.00E+00 7.94E-07 0.00E+00 1.25E-03 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 3.38E-07 1.88E-07 1.03E-07 0.OOE+00 1.82E-07 0.00E+00 8.03E-04 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 3 of 16

Attachment E ODCM-QA-008 Revision 4 Page 35 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: LEAFY VEG. SAMPLES (Page 2 of 2) mrem-kg/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE400 O.OOE+00 Ru-103 1.05E-05 O.OOE+00 4.50E-06 O.OOE+00 3.71 E-05 O.OOE+00 8.79E-04 Ru-105 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-1 06 1.64E-04 O.OOE+0O 2.07E-05 O.OOE+00 3.17E-04 O.OOE+00 7.88E-03 Ag-11Om 8.59E-06 8.13E-06 4.94E-06 O.OOE+00 1.55E-05 O.OOE+00 2.28E-03 Te-125m 1.59E-04 5.73E-05 2.12E-05 4.44E-05 O.OOE+00 O.OOE+00 4.69E-04 Te-127m 4.04E-04 1.43E-04 4.80E-05 9.60E-05 1.64E-03 O.OOE+00 1.01 E-03 Te-127 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 Te-129m 6.71 E-04 2.49E-04 1.06E-04

.2.16E-04 2.81 E-03 O.OOE+00 2.52E-03

- Te-129 1.84E-06 6.87E-07 4.48E-07 1.32E-06 7.73E-06 O.OOE+O0 1.01E-05 Te-131 m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 1-131 2.25E-04 3.16E-04 1.70E-04 9.21 E-02 5A3E-04 O.OOE+00 6.24E-05 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Cs-134 3.51 E-03 8.27E-03 3.84E-03 O.OOE+00 2.63E-03 1.00E-03 1.03E-04 Cs-136 3.42E-04 1.35E-03 9.04E-04 O.OOE+00 7.33E-04

.1.16E-04 1.08E-04 Cs-137 4.70E-03 6.26E-03 2.18E-03 O.OOE+00 2.13E-03 8.27E-04 8.90E-05 Cs-138 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 1.13E-03 1.38E-07 7.28E-05 O.OOE+00 4.69E-07 9.31 E-07 1.74E-03 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00, O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Ce-141 5.47E-07 3.65E-07 4.19E-08 O.OOE+00 1.72E-07 O.OOE+00 1.04E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 2.92E-05 1.21E-05 1.57E-06 O.OOE+00 7.21 E-06 O.OOE+00 7.33E-03 Pr-143 5.23E-07 2.09E-07 2.60E-08 0.002E+00 1.21 E-07 O.OOE+00 1.72E-03 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 3.70E-07 4.02E-07 2.41 E-08 O.OOE+00 2.36E-07 O.OOE+00 1.45E-03 W-187 O.OOE+00 O.OOE+00 O.OOE+00 -

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO Np-239 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+OO O.OOE+00 Page 4 of 16

Attachment E ODCM-QA-008 Revision 4 Page 36 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: FRUIT SAMPLES (Page 1 of 2) mrem-kg/pCi-yr NUCLIDi-BONE iVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 6.62E-05 6.62E-05 6.62E-05 6.62E-05 6.62E-05 6.62E-05 C-14 2.56E-03 5.12E-04 5.12E-04 5.12E-04 5.12E-04 5.12E-04 5.12E-04 Na-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 P-32 9.47E-03 5.87E-04 3.67E-04 0.00E+00 0.00E+00 0.OOE+00 7.96E-04 Cr-51 0.00E+00 0.00E+00 5.05E-07 2.81 E-07 1.1 E-07 7.22E-07 8A9E-05 Mn-54 0.00E+00 3.25E-03 6.45E-04 0.00E+00 9.71 E-04 0.00E+00 6.67E-03 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Fe-55 2.28E-03 1.62E-03 3.77E-04 0.00E+00 O.00E+00 1.03E-03 7.01 E-04 Fe-59 1.46E-03 3.40E-03 1.31 E-03 0.00E+00 0.00E+00 1.07E-03 8.04E-03 Co-58 0.00E+00 3.40E-04 7.84E-04 0.00E+00 0.OOE+00 0.00E+00 4.69E-03 Co-60 0.00E+00 1.73E-03 3.90E-03 0.00E+00 0.00E+00 0.00E+00 2.26E-02 Ni-63 1.11 E-01 7.87E-03 3.78E-03 0.00E+00 0.00E+00 0.00E+00 1.25E-03 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Zn-65 3.06E-03 1.06E-02 4.96E-03 0.00E+00 6.80E-03 0.OOE+00 4.50E-03 Zn-69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Br-84 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Br-85 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.02E-03 9.50E-04 0.00E+00 0.OOE+00 0.00E+00 2.99E-04 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Sr-89 1.22E-01 0.OOE+00 3.49E-03 0.00E+00 0.00E+00 0.00E+00 1 A5E-02 Sr-90 5.21 E+00 0.00E+00 1.29E+00 0.00E+00 0.00E+00 0.00E+00 1.46E-01 Sr-91 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 Sr-92 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Y-90 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Y-91 m 0.00E2+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Y-91 6.22E-05 0.00E+00 1.67E-06 0.00E+00 0.00E+00 0.OOE+00 2.55E-02 Y-92 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.36E-05 4.28E-06 2.94E-06 0.00E+00 6.28E-06 0.00E+00 9.87E-03 Zr-97 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Nb-95 1.58E-06 8.77E-07 4.83E-07 0.00E+00 8.50E-07 0.00E+00 3.75E-03 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00__

0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Page 5 of 16

Attachment E ODCM-QA-008 Revision 4 Page 37 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: FRUIT SAMPLES (Page 2 of 2) mrem-kglpCI-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY

-LUNG GI-LLI Tc-101

'O.OOE+O0 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-1 03 5.58E-05 O.OOE+00 2.39E-05 O.OOE+00 1.97E-04 O.OOE+00 4.66E-03 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-106 2.21 E-03 0.00E+00 2.78E-04 O.OOE+0O

-4.25E-03 O.OOE+00 1.06E-01 Ag-11Om 1.09E-04 1.03E-04 6.29E-05 O.OOE+OO 1.97E-04 O.OOE+00 2.91 E-02 Te-125m 1.18E-03 4.24E-04 1.57E-04 3.29E-04 O.OOE+00 O.OOE+00 3.48E-03 Te-127m 4.16E-03 1.48E-03 4.95E-04 9.89E-04 1.69E-02 O.OOE+00 1.04E-02 Te-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-129m 2.98E-03 1.11 E-03 4.71 E-04 9.61 E-04 1.25E-02 O.OOE+00 1.122-02,

- Te-129 8.19E-06 3.05E-06 1.99E-06 5.85E-06 3.44E-05 O.OOE+00 4.48E-05 Te-131m O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+002 1-131 2.09E-05 2.93E-05 1.57E-05 8.54E-03 5.04E-05

, O.OOE+00 5.79E-06 1-132 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00O 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00.

Cs-134 4.09E-02 1.17E-01 5.45E-02 O.OOE+00 3.73E-02 1 A2E-02 14A6E Cs-136 2.30E-04 9.03E-04 6.07E-04 O.OOE+00 4.92E-04 7.75E-05 7.27E-05 Cs-137 7.032-02 9.35E-02 3.26E-02

'O.OOE+00 3.18E-02 1.24E-02 1.33E-03 Cs-138 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-1 39 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 6.92E-04

'8A8E-08 4A6E-05 O.OOE+00 2.88E-07

-5.71 E-07 1.07E-03 Ba-141 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 2.33E-06 1.56E-06 1.79E-07 O.OOE+00

7.32E-07 O.OOE+OO 4.45E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 3.79E-04 1.57E-04 2.04E-05 O.OOE+00 9.36E-05 O.OOE+00

-9.52E-02 Pr-143 3.84E-07 1.53E-07 1.91 E-08 O.OOE+00 8.92E-08 O.OOE+OO 1.26E-03 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 O.0E+00 Nd-147 1.34E-07 14A6E-07 8.72E-09 O.OOE+00 8.55E-08 O.OOE+00 5.25E-04 W-187

-O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00

-O.OOE+00 Page 6 of 16

Attachment E ODCM-QA-008 Revision 4 Page 38 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: MEAT SAMPLES (Page 1 of 2) mrem-kg/pCi-yr NUCLID.E BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.OOE+00 6.87E-06 6.87E-06 6.87E-06 6.87E-06 6.87E-06 6.87E-06 C-14 2.64E-04 5.28E-05 5.28E-05 5.28E-05 5.28E-05 5.28E-05 5.28E-05 Na-24 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 P-32 6.80E-03 4.21 E-04 2.64E-04 O.OOE+00 O.OOE+00 0.OOE+00 5.72E-04 Cr-51 0.00E+00 0.OOE+00 1.42E-07 7.88E-08 3.11 E-08 2.03E-07 2.38E-05 Mn-54 O.OOE+00 3.67E-04 7.28E-05 0.OOE+00 1.09E-04 0.OOE+00 7.52E-04 Mn-56 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-55 2.42E-04 1.72E-04 4.01 E-05 0.OOE+00 0.OOE+00 1.09E-04 7.43E-05 Fe-59 2.80E-04 6.53E-04 2.52E-04 0.OOE+00 0.OOE+00 2.06E-04 1.54E-03 CO-58 0.OOE+00 5.19E-05 1.20E-04 0.OOE+00 0.OOE+00 O.OOE+00 7.16E-04 Co-60 0.OOE+00 1.81 E-04 4.08E-04 0.OOE+00 0.OOE+00 O.OOE+00 2.36E-03 Ni-63 1.15E-02 8.12E-04 3.90E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.29E-04 Ni-65 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Cu-64 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Zn-65 3.54E-04 1.23E-03 5.73E-04 O.OOE+00 7.86E-04 0.OOE+00 5.20E-04 Zn-69 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-83 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-84 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-85 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Rb-86 0.00E+00 9.21 E-04 4.33E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.36E-04 Rb-88 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-89 0.OOE+00 0 OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 2.17E-02 0.OOE+00 6.23E-04 O.OOE+00 0.00E+00 0.OOE+00 2.59E-03 Sr-90 5.39E-01 0.OOE+00 1.33E-01 0.OOE+00 O.OOE+00 0.OOE+00 1.51 E-02 Sr-91 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-92 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Y-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Y-91 1.03E-05 0.00E+00 2.76E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.23E-03 Y-92 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-93 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zr-95 2.16E-06 6.80E-07 4.68E-07 0.OOE+00 1.00E-06 0.OOE+00 1.57E-03 Zr-97 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Nb-95 3.60E-07 2.OOE-07 1.1OE-07 0.OOE+00 1.93E-07 0.0OE+00 8.54E-04 MO-99 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Tc-99m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Page 7 of 16

Attachment E ODCM-QA-008 Revision 4 Page 39 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: MEAT SAMPLES (Page 2 of 2) mrem-kglpCI-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002E+00, Ru-103 1.17E-05

-O.OOE+00

. 4.98E-06 O.OOE+00 4.11E-05' O.OOE+00 9.73E-04 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00.

O.OOE+00 Ru-106 2.45E-04 O.OOE+ 00 3.09E-05 O.OOE+00 4.73E-04 O.OOE+00 1.18E-02 Ag-110m 1.26E-05 1.19E-05 7.26E-06 O.OOE+00 2.28E-05 O.OOE+00 3.35E-03 Te-125m 1.96E-04 7.06E-05 2.62E-05 5.48E-05 O.OOE+00 O.OOE+00 5.78E-04 Te-127m 5.53E-04 1.96E-04 6.58E-05 1.32E-04 2.24E-03 O.OOE+00 1.38E-03 Te-127 O.OOE+00 O.OOE+00 0.OOE+OO.OOE+O O

O.OOE+00 O.OOE+00 O.OOE+00

,Te-129m 7.01 E-04 2.60E-04 1.1E-04 2.26E-04 2.93E-03 0.OOE+00 2.63E-03 TeA129 -

1.93E-06 7.19E-07 4.69E-07 1.38E-06 8.09E-06 O.OOE+OO 1.05E-05 Te-131 m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

,Te-131 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

-Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 6.78E-05 9.49E-05 5.1 OE-05 2.77E-02 1.63E-04 O.OOE+00 1.88E-05 1-132 O.OOE+00 0.002+00 0.00E+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 5,34E-03 1.26E-02 5.83E-03 O.OOE+00 3.99E-03 1.53E-03 1.56E-04 Cs-136 1.95E-04 7.66E-04 5.15E-04 O.OOE+00 4.17E-04 6.57E-05 6.17E-05 Cs-137 7.27E-03 9.67E-03 3.37E-03 O.OOE+00 3.29E-03 1.28E-03 1.38E-04 Cs-138 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 6.24E-04 7.65E-08 4.02E-05 O.OOE+00 2.59E-07 5.14E-07 9.63E-04 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE00 O.OOE+00 O.OOE+00 Ce-141 5.64E-07 3.77E-07 4.33E-08 O.OOE+00 1.77E-07 0.OOE+00 1.08E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 4.31 E-05 1.78E-05 2.32E-06 O.OOE+00 1.06E O.OOE+00 1.08E-02 Pr-143 3.06E-07 1.22E-07 1.52E-08 O.OOE+00 7.11 E-08 O.OOE+00 1.01 E-03 Pr-144 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Nd-147 1.73E-07 1.88E-07 1.12E-08 O.OOE+00 1.10E-07 O.OOE+00 6.77E-04 W-187 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 8 of 16

I Attachment E ODCM-QA-008 Revision 4 Page 40 of 78 p

REMP DOSE FACTORS FOR TEEN AGE GROUP: FISH SAMPLES (Page 1 of 2) mrem-kg/pCI-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 O.OOE+00 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 C-14 6.50E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 Na-24 1.21 E-05 1.21E-05 1.21E-05 1.21 E-05 1.21 E-05 1.21 E-05 1.21 E-05 P-32 4.21 E-03 2.61 E-04 1.63E-04 O.OOE+00 O.OOE+00 O.OOE+00 3.54E-04 Cr-51 0.00E+00 O.OOE+00 5.62E-08 3.12E-08 1.23E-08 8.02E-08 9.44E-06 Mn-54 O.OOE+00 9.42E-05 1.87E-05 O.OOE+00 2.81 E-05 O.OOE+00 1.93E-04 Mn-56 O.OOE+00 3.99E-09 7.09E-10 O.OOE+00 5.05E-09 O.OOE+00 2.63E-07 Fe-55 6.04E-05 4.28E-05 9.99E-06 O.OOE+00 O.OOE+00 2.72E-05 1.85E-05 Fe-59 9.25E-05 2.16E-04 8.33E-05 O.OOE+00 O.OOE+00 6.81 E-05 5.1 OE-04 Co-58 O.OOE+00 1.54E-05 3.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.12E-04 Co-60 O.OOE+00 4.49E-05 1.01E-04 O.OOE+00 O.OOE+00 O.OOE+00 5.85E-04 Ni-63 2.83E-03 2.OOE-04 9.60E-05 O.OOE+00 O.OOE+00 O.OOE+00 3.18E-05 Ni-65.

1.63E-08 2.08E-09 9.48E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-07 Cu-64 O.OOE+00 4.97E-07 2.34E-07 O.OOE+00 1.26E-06 O.OOE+00 3.85E-05 Zn-65 9.19E-05 3.19E-04 1.49E-04 O.OOE+00 2.04E-04 O.OOE+00 1.35E-04 Zn-69 3.90E-15 7.42E-15 5.19E-16 O.OOE+00 4.85E-15 O.OOE+00 1.37E-14 Br-83 O.OOE+00 O.OOE+00 8.71 E-10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 2.87E-20 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 4.59E-04 2.16E-04 O.OOE+00 O.OOE+00 O.OOE+00 6.80E-05 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 6.94E-03 O.OOE+00 1.99E-04 O.OOE+00 O.OOE+00 O.OOE+00 8.27E-04 Sr-90 1.33E-01 O.OOE+00 3.28E-02 O.OOE+00 O.OOE+00 O.OOE+00 3.73E-03 Sr-91 2.24E-05 O.OOE+00 8.92E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.02E-04 Sr-92 1.05E-07 O.OOE+00 4.49E-09 O.OOE+00 O.OOE+00 O.OOE+00 2.68E+04 Y-90 1.69E-07 O.OOE+00 4.55E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.39E-03 Y-91m 4.09E-18 O.OOE+00 1.56E-19 O.OOE+00 O.OOE+00 O.OOE+00 1.93E-16 Y-91 3.18E-06 O.OOE+00 8.52E-08 O.OOE+00 0.00E+00 O.OOE+00 1.30E-03 Y-92 1.76E-10 O.OOE+00 5.10E-12 O.OOE+00 O.OOE+00 O.OOE+00 4.83E-06 Y-93 1.18E-08 O.OOE+00 3.24E-10 O.OOE+00 O.OOE+00 O.OOE+00 3.61 E-04 Zr-95 6.52E-07 2.06E-07 1.41 E-07 O.OOE+00 3.02E-07 O.OOE+00 4.75E-04 Zr-97 1.42E-08 2.80E-09 1.29E-09 O.OOE+00 4.25E-09 O.OOE+00 7.59E-04 Nb-95 1.29E-07 7.15E-08 3.94E-08 O.OOE+00 6.93E-08 0.00E+00 3.06E-04 Mo-99 O.OOE+00 7.50E-05 1.43E-05 O.OOE+00 1.72E-04 O.OOE+00 1.34E-04 Tc-99m 3.35E-10 9.35E-10 1.21E-08 O.OOE+00 1.39E-08 5.19E-10 6.14E-07 Page 9 of 16

Attachment E ODCM-QA-008 Revision 4 Adh Page 41 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: FISH SAMPLES (Page 2 of 2) mrem-kglpCi yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+OO O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 4.01 E-06 O.OOE+00 1.71E-06 O.OOE+00 1 A1 E-05 O.OOE+00 3.35E-04

- Ru-105 8.23E-09 O.OOE+00 3.19E-09 O.OOE+00 1.04E-07 O.OOE+00 6.64E-06 Ru-106 6.26E-05 O.OOE+00 7.89E-06 O.OOE+00 1.21 E-04 O.OOE+00 3.00E-03 Ag-11 Om 3.27E-06 3.10E-06 1.88E-06 O.OOE+00 5.90E-06 O.OOE+00 8.70E-04 Te-125m 6.06E-05 2.18E-05 8.09E-06 1.69E-05 O.OOE+00 O.OOE+00 1.79E-04 Te-127m 1.54E-04 5.45E-05 1.83E-05 3.66E-05 6.23E-04 0.00E+00 3.83E-04 Te-127 4.27E-07 1.51 E-07 9.18E-08 2.94E-07 1.73E-06 O.OOE+00 3.29E-05 Te-129m 2.55E-04 9.48E-05 4.04E-05 8.24E-05 1.07E-03 O.OOE+00 9.59E-04 Te-1 29 7.02E-07 2.62E-07 1.71E-07 5.02E-07 2.95E-06 O.OOE+00 3.84E-06 Te-131rm 2.24E-05 1.08E-05 8.97E-06 1.62E-05 1.12E-04 O.OOE+00 8.63E-04 Te-131 2.21 E-24 0.00E+00 O.OOE+00

'- 1.71 E-24 9.68E-24 O.OOE00 O.OOE+00 Te-132 4.51 E-05 2.86E-05 2.69E-05 3.01 E-05 2.74E-04 O.OOE+00 9.05E-04.

1-130 4.29E-06 1.24E-05 4.96E-06 1.01 E-03 1.91 E-05 O.OOE+00 9.54E-06 1-131 8.59E-05 1.20E-04 6.46E-05 3.51 E-02 2.07E-04 O.OOE+00 2.38E-05 132 3.23E-09 8.44E-09 3.03E-09 2.84E-07 1.33E-08 O.OOE+00 3.68E-09 1-133 1.45E-05 2.45E-05 7.48E-06 3.42E-03 4.30E-05 O.OOE+00 1.86E-05 1-134 1.39E-14 3.69E-14 1.33E-14 6.15E-13 5.82E-14 O.OOE+00 4.86E-16 1-135 7.88E-07 2.03E-06 7.52E 1.30E-04

-3.20E-06 O.OOE+00 2.25E-06 Cs-134 1.34E-03 3.15E-03 1.46E-03 O.OOE+00 1.OOE-03 3.82E-04 3.92E-05 Cs-136 1.30E-04

-5.13E-04

-3.45E-04 0O.OOE+00 2.79E-04(

4.40E-05 4.13E-05 Cs-137 1.79E-03

'.2.38E-03

-8.30E-04 O.OOE+00 8.11 E-04 3.15E-04 3.39E-05 Cs-I 38 4.56E-20 8.75E-20-,

4.37E-20 O.OOE+00 6.46E-20 7.52E-21 3.97E-23 Ba-139 1.38E-11 9.74E 4.03E-13 O.OOE+00 9.18E-15 6.71 E-15 1.23E-10 Ba-140 4.30E-04 5.27E-08 2.77E-05 O.OOE+00 1.79E-07 3.55E-07 6.64E-04 Ba-141 O.OOE+00

.0O0+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+000' O.OOE+00 O.OOE+00 La-140 3.68E-08 1.81 E-08 4.81 E-09 O.OOE+00 0.002E+00 O.OOE+00 1.042-03' La-142 8.36E-14 3.71 E-14 9.25E-15 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-09 Ce-141

-2.08E-07'

- 1.39E-07 1.60E-08 O.OOE+00 6.55E-08' O.OOE+00 3.98E-04 Ce-143 2.27E-08 1.65E-05 1.85E-09 O.OOE+00 7A12E-09 O.OOE+00 4.97E-04 Ce-144 1.11E-05 "4.60E-06 5.97E-07 O.OOE+00 2.75E-06 O.OOE+00 2.79E-03 Pr-143 1.99E-07 ---

7.95E-08 9.91 E-09 O.OOE+00 4.62E-08 O.OOE+00 6.55E-04 Pr-144 O.OOE+00 O.OOE+00 "O.OOE+00

'O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 1 A1 E-07 1.53E-07

'9.18E-09 O.OOE+00 9.00E-08 O.OOE+00 5.53E-04 W-187 1.16E-06 9.47E-07 3.32E-07 "O.OOE+00 O.OOE+00 O.OOE+00

' 2.56E-04 Np-239 2.10E-08 1.98E-09 1.1 OE-09 O.OOE+00 621E-09 O.OOE+00 3.18E-04 Page 10 of 16

Attachment E

'ODCM-QA-008 Revision 4 Page 42 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: DRINKING WATER (Page 1 of 2) mrem-literlpCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 5.41 E-05 5.41 E-05 5.41 E-05 5.41 E-05 5.41 E-05 5.41E-05 C-14 2.07E-03 4.14E-04 4.14E-04 4.14E-04 4.14E-04 4.14E-04 4.14E-04 Na-24 6.74E-04 6.74E-04 6.74E-04 6.74E-04 6.74E-04 6.74E-04 6.74E-04 P-32 1.37E-01 8.51 E-03 5.33E-03 0.00E+00 0.00E+00 0.00E+00 1.15E-02 Cr-51 0.00E+00 0.00E+00 1.81 E-06 1.01 E-06 3.97E-07 2.59E-06 3.05E-04 Mn-54 0.00E+00 3.01 E-03 5.96E-04 0.OOE+00 8.97E-04 0.00E+00 6.16E-03 Mn-56 0.OOE+00 3.20E-06 5.69E-07 0.00E+00 4.05E-06 0.00E+00 2.11 E-04 Fe-55 1.93E-03 1.37E-03 3.19E-04 0.00E+00 0.00E+00 8.67E-04 5.91 E-04 Fe-59 2.97E-03 6.93E-03 2.68E-03 0.OOE+00 0.OOE+00 2.19E-03 1.64E-02 Co-58 0.00E+00 4.93E-04 1.14E-03 0.00E+00 0.00E+00 0.00E+00 6.80E-03 Co-60 0.00E+00 1.43E-03 3.23E-03 0.00E+00 0.00E+00 0.00E+00 1.87E-02 Ni-63 9.03E-02 6.37E-03 3.06E-03 0.00E+00 0.00E+00 0.OOE+00 1.01 E-03 Ni-65 1.41 E-05 1.80E-06 8.20E-07 0.00E+00 0.00E+00 0.00E+00 9.76E-05 Cu-64 0.00E+00 3.05E-05 1.43E-05 0.00E+00 7.71 E-05 0.00E+00 2.36E-03 Zn-65 2.93E-03 1.02E-02 4.75E-03 0.OOE+00 6.52E-03 0.00E+00 4.31 E-03 Zn-69 9.65E-10 1.84E-09 1.29E-10 O.OOE+00 1.20E-09 0.OOE+00 3.39E-09 Br-83 0.00E+00 0.00E+00 9.02E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.OOE+00 0.00E+00 5.81 E-12 O.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.002+00 Rb-86 0.00E+00 1.49E-02 7.01E-03 0.00E+00 0.00E+00 0.OOE+00 2.21 E-03 Rb-88 0.00E+00 3.06E-17 1.63E-17 0.00E+00 0.00E+0d 0.00E+00 2.62E-24 Rb-89 0.OOE+00 2.74E-19 1.94E-19 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 2.23E-01 0.00E+00 6.38E-03 0.00E+00 0.00E+00 0.OOE+00 2.65E-02 Sr-90 4.23E+00 0.00E+00 1.05E+00 0.OOE+00 0.00E+00 0.00E+00 1.19E-01 Sr-91 1.71E-03 0.00E+00 6.82E-05 0.OOE+00 0.00E+00 0.00E+00 7.78E-03 Sr-92 7.23E-05 0.00E+00 3.08E-06 0.OOE+00 0.00E+00 0.00E+00 1.84E-03 Y-90 6.14E-06 0.00E+00 1.65E-07 0.OOE+00 0.00E+00 0.00E+00 5.06E-02 Y-91m 2.93E-12 0.00E+00 1.12E-13 0.00E+00 0.00E+00 0.00E+00 1.38E-10 Y-91 1.02E-04 0.00E+00 2.73E-06 0.00E+00 0.00E+00 0.OOE+00 4.18E-02 Y-92 5.89E-08 0.00E+00 1.70E-09 0.00E+00 0.OOE+00 0.00E+00 1.62E-03 Y-93 8.57E-07 0.00E+00 2.35E-08 0.00E+00 0.00E+00 0.00E+00 2.62E-02 Zr-95 2.09E-05 6.59E-06 4.53E-06 0.OOE+00 9.69E-06 0.00E+00 1.52E-02 Zr-97 7.39E-07 1.46E-07 6.73E-08 0.00E+00 2.22E-07 0.00E+00 3.96E-02 Nb-95 4.15E-06 2.30E-06 1.27E-06 0.00E+00 2.23E-06 0.00E+00 9.85E-03 Mo-99 0.00E+00 2.71 E-03 5.17E-04 0.OOE+00 6.20E-03 0.002+00 4.86E-03 Tc-99m 4.25E-08 1.19E-07 1.542-06 0.00E+00 1.77E-06 6.58E-08 7.79E-05 Page 11 of 16

Attachment E ODCM-QA-008 Revision 4 Page 43 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: DRINKING WATER (Page 2 of 2) mrem-literlpCi-yr NUCLIDE BONE

LIVER T.BODY THYROID

KIDNEY, LUNG GI-LLI Tc-101 1.07E-22 1.53E-22 1.50E-21

- O.OOE+00 2.76E-21 9.30E-23 O.OOE+0O Ru-103 1.29E-04 0.00E+00 5.51E-05 O.OOE+00 4.54E-04 O.OOE+O0 1.08E-02 Ru-105 1.71 E-06 O.OOE+00 6.63E-07 O.OOE+0O 2.15E-05 0.00E+00 1.38E-03 Ru-1 06 2.00E-03 O.OOE+00 2.52E-04 O.OOE+00 3.85E-03 O.OOE+O0 9.58E-02 Ag-1 I Om 1.04E-04 9.88E-05 6.01 E-05 O.OOE+00 1.88E-04 O.OOE+O0 2.78E-02 Te-125m 1.94E-03 7.OOE-04 2.60E-04 5.42E-04 O.OOE+00 O.OOE+00 5.73E-03 Te-127m 4.92E-03 1.74E-03 5.85E-04 1.17E-03 1.99E-02 O.OOE+00 1.23E-02 Te-127 3.31 E-05 1.1 7E-05 7.12E-06 2.28E-45 1.34E-04 O.OOE+00 2.56E-03 Te-129m 8.23E-03 3.05E-03 1.30E-03 2.66E-03 3.44E-02 O.OOE+00 3.09E-02 Te-129 2.26E-05 8.43E-06 5.50E-06 1.62E-05 9.49E-05 O.OOE+00 1.24E-04 Te-131m 9.43E-04 4.52E-04 3.77E-04 6.80E-04 4.72E-03 O.OOE+00 3.63E-02 Te-131 3.17E-14 1.31 E-14 9.90E-15 2.44E-14 1.39E-13 O.OOE+00 2.60E-15 Te-132 1.60E-03 1.01 E-03 9.54E-04 1.07E-03 9.72E-03 O.OOE+00 3.21E-02 1-130 2.68E-04 7.75E-04 3.10E-04 6.32E-02 1.19E-03 O.OOE+00 5.96E-04 1-131 2.86E-03 4.00E-03 2.15E-03 1.17E+00 6.89E-03 O.OOE+00 7.91E-04 1-132 3.82E 1.OOE-05 3.59E-06 3.37E-04 1.58E-05 O.OOE+00 4.36E-06 1-133 6.87E-04 1.17E-03 3.56E-04 1.63E-01 2.04E-03 O.OOE+00 8.82E-04 1-134 5.75E-09 1.52E-08 5.47E-09 2.54E-07 2.40E-08 O.OOE+00 2.01E-10 1-135 8.84E-05 2.27E-04 8A3E-05 1.46E 3.59E-04 O.OOE+00 2.52E-04 Cs-134 427E-02 1.OOE-01 4.66E-02 O.OOE+00 3.19E-02 1.22E-02 1.25E-03 Cs-136 4.27E-03 1.68E-02 1.13E-02 O.OOE+00 9.14E-04 1.44E-03 1.35E-03 Cs-137 5.71 E-02 7.60E-02 2.65E-02 0.OOE+00 2.59E-02 1.00E-02

• 1.08E-03 Cs-138 7.58E-12 1A6E-11 7.28E212 O.OOE+00 1.07E-11 1.25E-12 6.60E-15 Ba-139 1.77E-07 1.24E-10 5.15E-09 O.OOE+00 1.17E-10 8.57E-11 1.58E-06 Ba-140 1.41 E-02 1.73E-06 9.08E-04 O.OOE+00 5.86E-06 1.16E-05 2.17E-02 Ba-141 4.95E-17 3.70E-20 1.65E-18 O.OOE+00 3.43E-20 2.53E-20 1.06E-22 Ba-142 0.00E+O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 1.44E-06 7.09E-07 1.89E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.07E-02 La-142 4.93E-10 2.19E-10 5.46E-11 O.OOE+00 O.OOE+00 O.OOE+00 6.67E-06 Ce-141 6.71 E-06 4.48E-06 5.15E-07 O.OOE+00 2.11 E-06 O.OOE+00 1.28E-02 Ce-143 9.31 E-07 6.78E-04 7.57E-08 O.OOE+00 3.04E-07 O.OOE+00 2.04E-02 Ce-144 3.55E-04 1.47E-04 1.91 E-05 O.OOE+00 8.76E-05 O.OOE+00 8.91 E-02 Pr-143 6.51 E-06 2.60E-06 3.24E-07 O.OOE+00 1.51 E-06 O.OOE+O 2.14E-02 Pr-144 6.66E-21 2.72E-21 3.37E-22 O.OOE+00 1.56E-21 O.OOE+00 7.34E-24 Nd-147 4.64E-06 5.04E-06 3.02E-07 O.OOE+00 2.96E-06 O.OOE+00 1.82E-02 W-187 5.25E-05 4.28E-05 1.50E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.16E-02 Np,239 7.75E-07 7.31 E-08 4.06E-08 O.OOE+0 2.29E-07 0.OE+00 1.18E-02 Page 12 of 16

Attachment E ODCM-QA-008 Revision 4 Page 44 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 1 of 2) mrem-m3 /pCI-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU l

H-3 O.OOE+OO 1.28E-03 1.28E-03 1.28E-03 1.28E-03 1.28E-03 1.28E-03 C-14 2.60E-02 4.87E-03 4.87E-03 4.87E-03 4.87E-03 4.87E-03 4.87E-03 Na-24 O.OOE+OO O.OOE+0O O.OOE+0O O.OOE+O0 O.OOE+OO O.OOE+0O O.OOE+O0 P-32 1.73E+01 1.OOE+00 6.55E-41 O.OOE+00 O.OOE+00 O.OOE+00 8.49E-01 Cr-51 0.OOE+O0 O.OOE+00 4.23E-04 2.35E-04 9.62E-05 6.56E-02 9.39E-03 Mn-54 O.OOE+00 5.66E-02 9.29E-03 O.OOE+O0 1.41 E-02 2.20E+00 7.39E-02 Mn-56 O.OOE+OO O.OOE+OO O.OOE+0O O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 3.45E-02 2.46E-02 5.72E-03 0.00EE+00 O.OOE+00 1.28E-01 6.60E-03 Fe-59 3.23E-02 7.51 E-02 2.91 E-02 O.OOE+OO O.OOE+00 3.1 OE+00 3.62E-41 Co-58 O.OOE+00 3.24E-03 4.34E-03 O.OOE+OO 0.OOE+O0 2.1 OE+O0 1.49E-01 Co-60 O.OOE+OO 1.54E-02 2.02E-02 0.00E+00 O.OOE+OO 8.86E+00 2.63E-01 Ni-63 5.81 E-01 4.35E-02 1.98E-02 0.OOE+00 O.OOE+00 3.07E-01 1.42E-02 Ni-65 O.OOE+O0 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+O0 Cu-64 O.OOE+00 O.OE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+OO O.OOE+O0 Zn-65 4.39E-02 1.52E-41 7.10E-02 O.OOE+00 9.83E-02 1.41 E+0O 5.31 E-02 Zn-69 O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+O0 O.OOE+00 O.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00 Br-84 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+00 Rb-86 0.OOE+00 1.04E+00 4.57E-01 O.OOE+0O O.OOE+0O O.OOE+00 9.63E-02 Rb-88 O;OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+0O 0.OOE+06 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 8.12E-01 O.OOE+00 2.33E-02 0.OOE+00 O.OOE+OO 4.52E+00 6.94E-41 Sr-90 1.08E+02 O.OOE+O0 6.70E+O0 O.OOE+00 O.OOE+00 1.65E+01 7.67E-41 Sr-91 O.OOE+O0 0.OOE+OO O.OOE+O0 0.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00 Sr-92 0.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+OO O.OOE+00 O.OOE+OO Y-90 O.OOE+O0 O.OOE+00 0.OOE+0O O.OOE+O0 O.OOE+0O O.OOE+O0 O.OOE+00 Y-91m O.OOE+00 O.OOE+0O O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.13E+00 0.OOE+00 3.04E-02 O.OOE+0O O.OOE+00 5.04E+00 7.02E-41 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-93 O.OOE+OO 0.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+0O O.OOE+0O O.OOE+00 Zr-95 2.39E-01 7.51 E-02 5.17E-02 O.OOE+O0 1.1OE-01 4.41 E+00 2.44E-01 Zr-97 O.OOE+OO O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+0O O.OOE+OO O.OOE+00 Nb-95 4.57E-02 2.54E-02 1.40E-02 O.OOE+00 2.46E-02 1.85E+00 2.39E-01 Mo-99 O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Tc-99m O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

)

Page 13 of 16

Attachment E ODCM-QA-008 Revision 4 Page 45 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 2 of 2) mrem-m 3l/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LL TcI01 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ru-103 4.70E-03 O.OOE+00 2.OOE-03 O.OOE+00 1.66E-02 1.75E+00 2.43E-01 Ru-105 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Ru-106 1.07E-01 O.OOE+00 1.35E-02 O.OOE+00 2.07E-01 1.75E+01 1.05E+00 Ag-11 Om 1.57E-02 1.49E-02 9.07E-03 O.OOE+00 2.84E-02, 7.66E+00 3.1OE-01 Te-25m 8A2E-03 3.86E-03 1.15E-03 2.42E-03 0.OOE+00 9.25E-01 1.29E-01 Te-127m 2.41 E-02 1.09E-02 2.92E-03 5.86E-03 8.74E-02 2.21 E+00 2.13E-01 Te-127 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Te-129m 3.57E-02 1.69E-02 5.76E-03 1.17E-02 1.33E-01 5.06E+0o 1.04E+00 Te-129 1.82E-07 8.65E-08 4.51 E-08 1.33E-07 6.81 E-07 8.45E-03 4.14E-03 Te-1 31 m O.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Te-131 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Te-132 0.OE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00

'0.OE+00 0.00E+00 1-130 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 1-131 1.81 E+00 2.51 E+00 1.35E+00 7.48E+02 4.29E+00 0.OOE+00 3.31 E-01 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 1-134 -

O.OOE+00 0.00E+00 0.00E+00 O.OOE+00

'O.OOE+00 0.OOE+00 0.OOE+00 1-135 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Cs-134 5.-24E-01 1.18E+00 5.72E-01 0.OOE+00 3.91 E-01 1.53E-01 1.02E-02 Cs-136 5.70E-01 2.14E+00

- 1.51 E+00 O.OOE+00 1.22E+0O 1.96E-01 1.20E-01 Cs-137 6.72E-01 8.50E-01 3.12E-01 0.OOE+00 3.05E-01 1.21 E-01 8.50E-03 Cs-138 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 Ba-139 0.OE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ba-140 6.49E-01 7.95E-04 4.17E-02 O.OOE+00 2.70E-04 2.41 E+01 2.71 E+00 Ba-141 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Ba-142 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 La-142 O.OOE+00 -

0.OE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ce-141

- 7.51 E-02 5.02E-02 5.74E 0.OE+00 2.35E-02 1.62E+00 3.34E-01 Ce-143 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Ce-144 5A6E+00 2.26E+00 2.93E-41 0.OOE+00 1.35E+00 1.49E+01 9.66E-41 Pr-143 1.38E-01 5.47E-02 6.82E-03 O.OOE+00 3.18E-02 4.98E+00 2.20E+00 Pr-144 O.OOE+00-0.OOE+00, O.OOE+00 0.OOE+00 0.OOE+00 O.ODE+00 O.OOE+00 Nd-147 1.40E-01

-1.53E-01 9.14E-03 O.OOE+00 8.95E-02 6.63E+00 3.25E+00 W-187 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 Page 14 of 16

Attachment E ODCM-QA-008 Revision 4 Page 46 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP: INHALATION - WEEKLY SAMPLING (Page 1 of 2) mrem-m 3/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 C-14 2.60E-02 4.87E-03 4.87E-03 4.87E-03 4.87E-03 4.87E-03 4.87E-03 Na-24 O.OOE+00 O.OOE+00 O.OOE++00 0.00E+00 O.OOE+O O.OOE+O0 O.OOE+00 P-32 2.24E+00 1.30E-01 8.48E-02 0.OOE+00 O.OOE+00 O.OOE+00 1.10E-01 Cr-51 O.OOE+00 O.OOE+00 1.48E-04 8.18E-05 3.35E-05 2.29E-02 3.27E-03 Mn-54 O.OOE+00 5.15E-02 8.47E-03 O.OOE+00 1.28E-02 2.00E+00 6.73E-02 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 3.35E-02 2.39E-02 5.56E-03 O.OOE+00 O.OOE+00 1.24E-01 6.41 E-03 Fe-59 1.68E-02 3.90E-02 1.51 E-02 O.OOE+00 O.OOE+00 1.61 E+00 1.88E-01 Co-58 O.OOE+00 2.14E-03 2.87E-03 O.OOE+00 O.OOE+00 1.39E+00 9.85E-02 Co-60 O.OOE+00 1.51 E-02 1.99E-02 O.OOE+00 O.OOE+00 8.73E+00 2.60E-01 Ni-63 5.80E-01 4.34E-02 1.98E-02 O.OOE+00 O.OOE+00 3.07E-01 1.42E-02 Ni-65 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 0.OOE+00 Cu-64 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn-65 3.89E-02 1.35E-01 6.30E-02 O.OOE+00 8.73E-02 1.25E+00 4.71 E-02 Zn-69 O.OOE+00 -

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 0.00E+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Rb-86 O.0OE+00 2.17E-01 9.57E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.01 E-02 Rb-88 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 o.00E+06 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 4.56E-01 O.OOE+00 1.31 E-02 O.OOE+00 O.OOE+00 2.53E+00 3.89E-01 Sr-90 1.08E+02 O.OOE+00 6.68E+00 O.OOE+00 O.OOE+00 1.65E+01 7.65E-01 Sr-91 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Y-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Y-91 6.89E-01 O.OOE+00 1.84E-02 O.OOE+00 O.OOE+00 3.06E+00 4.26E-01 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-93 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 1.5tE-01 4.76E-02 3.27E-02 O.OOE+00 7.00E-02 2.79E+00 1.55E-01 Zr-97 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-95 1.99E-02 1.11 E-02 6.07E-03 0.00E+00 1.07E-02 8.05E-01 1.04E-01 Mo-99 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Page 15 of 16

Attachment E ODCM-QA-008 Revision 4 Page 47 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP:INHALATION - WEEKLY SAMPLING (Page 2 of 2) mrem-mS/pCi-yr NUCLIDE.

BONE UVER T.BODY

-THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Ru-103 2.24E-03 O.OOE+00 9.53E-04 O.OOE+00 7.90E-03 8.33E-01 1.16E-01 Ru-105 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+0O Ru-106 9.91 E-02 O.OOE+00 1.25E-02 O.OOE+00 1.92E-01 1.62E+01 9.66E-01 Ag-110m 1.40E-02 1.32E-02 8.07E-03 O.OOE+00 2.53E-02 6.82E+00 2.75E-01 Te-125m 5.09E-03 2.34E-03 6.96E-04 1.46E-03 O.OOE+OO 5.59E-01 7.82E-02 Te-127m 1.84E-02 8.34E-03 2.23E-03 4.48E-03

' 6.68E-02 1.69E+00 1.63E-01 Te-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-129m 1.50E-02 7.08E-03 2.42E-03 4.92E-03 5.58E-02 2.12E+00 4.35E-01 Te-129 7.63E-08 3.63E-08 1.89E-08 5.57E-08 2.85E-07 3.54E-03 1.74E-03 Te-131m 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00O-1-130 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 1-131 3.54E-02 4.91 E-02 2.64E-02 14A6E+01 8.40E-02 O.OOE+00 6.49E-03 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 0.00E+00 1-133 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 0.OOE+00 O.OOE+00 O.OOE+00

-O.OOE+00

-O.OOE+00 O.OOE+OO O.OOE+00 Cs-134 5.04E-01 1.13E+00 5.51 E-01 O.OOE+00 3.76E-01 1.47E-01 9.79E-03 Cs-136 6:.19E-02 2.33E-01 1.64E-01 O.OOE+00 1.33E-01 2.14E-02 1.31 E-02 Cs-137 6.71E-01 8.48E-01 3.11 E-01 O.OOE+00 3.04E-01 1.21 E-01 8.48E-03 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-1 39 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 6.61E-02 8.1OE-05 4.26E-03 0.00E+00 2.76E-05 2.46E+00 2.77E-01 Ba-141 O.OOE+00 O.0OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 3.06E-02 2.04E-02 2.34E-03 0.OOE+00-9.57E-03 6.61 E-01 1.36E-01 Ce-143 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 4.93E+00 2.04E+00 2.65E-01 O.OOE+00 1.22E+00 1.35E+01 8.71E-01 Pr-143 1.60E-02 6.35E-03 7.92E-04 ~O.OOE+00 3.69E-03 5.78E-01 2.55E-01 Pr-144 O.OOE+00 O.OOE+00

, 0.00E+00 0.00E+00 O.OOE+00 O.OE+00 O.OOE+00 Nd-147 9.81 E-03 1.07E-02 6.40E-04 O.OOE+00 6.27E-03 4.64E-01 228E-01 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 0.002+00 Page 16 of 16

Attachment F ODCM-QA-008 Revision 4 Page 48 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: MILK (Page 1 of 2) mrem-liter/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 6.70E-05 6.70E-05 6.70E-05 6.70E-05 6.70E-05 6.70E-05 C-14 3.99E-03 7.99E-04 7.99E-04 7.99E-04 7.99E-04 7.99E-04 7.99E-04 Na-24 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 P-32 2.47E-01 1.16E-02 9.52E-03 O.OOE+00 O.OOE+00 O.OOE+00 6.83E-03 Cr-51 O.OOE+00 O.OOE+00 2.79E-06 1.55E-06 4.24E-07 2.83E-06 1.48E-04 Mn-54 O.OOE+00 3.52E-03 9.36E-04 O.OOE+00 9.86E-04 O.OOE+00 2.95E-03 Mn-56 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 Fe-55 3.79E-03 2.01 E-03 6.23E-04 O.OOE+00 O.OOE+00 1.14E-03 3.72E-04 Fe-59 5.28E-03 8.54E-03 4.25E-03 O.OOE+00 O.OOE+00 2.48E-03 8.89E-03 Co-58 O.OOE+00 5.82E-04 1.78E-03 O.OOE+00 O.OOE+00 O.OOE+00 3.40E-03 Co-60 O.OOE+00 1.74E-03 5.14E-03 O.OOE+00 O.OOE+00 O.OOE+00 9.66E-03 Ni-63 1.78E-01 9.50E-03 6.04E-03 O.OOE+00 O.OOE+00 O.OOE+00 6.40E-04 Ni-65 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cu-64 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn-65 4.50E-03 1.20E-02 7.45E-03 O.OOE+00 7.55E-03 O.OOE+00 2.1 OE-03 Zn-69 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Br-84 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.002+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Rb-86 0.90E+00 2.05E-02 1.26E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.32E-03 Rb-88 OOOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+06 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 4.24E-01 O.OOE+00 1.21 E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.64E-02 Sr-90 5.61 E+00 O.OOE+00 1.42E+00 O.OOE+00 O.OOE+00 O.OOE+00 7.56E-02 Sr-91 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91m O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.94E-04.

O.OOE+00 5.19E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.582-02 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-93 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 3.75E-05 8.23E-06 7.33E-06 O.OOE+00 1.18E-05 O.OOE+00 8.59E-03 Zr-97 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-95 7.14E-06 2.78E-06 1.99E-06 O.OOE+00 2.61 E-06 0.00E+00 5.14E-03 Mo-99 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I--

Page 1 of 16

Attachment F ODCM-QA-008 Revision 4 Page 49 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: MILK (Page 2 of 2) mrem-liter/pCi-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY

LUNG, GI-LU Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 Ru-1 03 2.33E-04 O.OOE+00 8.95E-05 O.OOE+00 5.86E-04 O.OOE+00

- 6.02E-03 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ru-1 06 3.85E-03 O.OOE+00 4.80E-04 O.OOE+00 5.19E-03 O.OOE+00 5.98E-02

--Ag-110m 1.77E-04 1.19E-04 9.55E-05 O.OOE+00 2.23E-04 O.OOE+00 1.42E-02 Te-125m 3.67E-03 9.96E-04 4.90E-04 1.03E-03 O.OOE+00 O.OOE+00 3.54E-03 Te-127m 9A2E-03 2.53E-03 1.12E-03' 2.25E-03 2.68E-02 O.OOE+00 7.62E-03 Te-127 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Te-129m 1.54E-02 4.31 E-03 2.39E-03 4.97E-03 4.53E-02 O.OOE+00 1.88E-02 Te-129 4.24E-05 1.18E-05 1.01E-05 3.03E-05 1.24E-04 O.OOE+00 2.64E-03

--Te-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-1 31 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132

' O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 4.78E-03 4.80E-03 2.73E-03 1.59E+00 7.89E-03 O.OOE+00 4.28E-04 1-132 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 7.71 E-02 1.26E-01 2.67E-02 O.OOE+00 3.92E-02 1.41E-02 6.82E-04 Cs-136 6.98E-03 1.92E-02 1.24E-02 O.OOE+00 1.02E-02 1.52E-03 6.74E-04 Cs-137 1.08E-01 1.03E-01 1.52E-02 O.OOE+00 3.37E-02 1.21 E-02 6.47E-04 Cs-138 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 2A6E-02 2.16E-05 1.44E-03 O.OOE+00 7.02E-06 1.29E-05 1.25E-02 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 -

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 1.26E-05 6.26E-06 9.30E-07 0.002+00 2.74E-06 O.OOE+00 7.81 E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00

-Ce-144 6.83E-04 2.14E-04 3.65E-05 O.OOE+00 1.19E-04 O.OOE+00 5.58E-02 Pr-143 1.17E-05 3.52E-06 5.81 E-07 O.OOE+00 1.90E-06

, O.OOE+00 1.26E-02 Pr-1M44 O.OOE+00 O.OOE+00 O.OOE+00, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147.

8.11E-06 6.57E-06 5.09E-07 O.OOE+00 3.61 E-06 O.OOE+00 1.04E-02 W-1 87 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 2 of 16

Attachment F ODCM-QA-008 Revision 4 Page 50 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: LEAFY VEG. (Page 1 of 2) mrem-kg/pCi-yr NUCLIDE.

BONE LVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 O.OOE+00 5.28E-06 5.28E-06 5.28E-06 5.28E-06 5.28E-06 5.28E-06 C-14 3.1 5E-04 6.29E-05 6.29E-05 6.29E-05 6.29E-05 6.29E-05 6.29E-05 Na-24 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 P-32 2.04 E-02 9.56E-04 7.88E-04 O.OOE+00 O.OOE+00 O.OOE+00 5.65E-04 Cr-51 0.OOE+O0 O.OOE+O0 2.26E-07 1.25E-07 3.42E-08 2.29E-07 1.20E-05 Mn-54 O.OOE+00 2.78E-04 7.39E-05 O.OOE+00 7.78E-05 O.OOE+00 2.33E-04 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 2.99E-04 1.58E-04 4.91 E-05 O.OOE+00 O.OOE+00 8.96E-05 2.94E-05 Fe-59 4.22E-04 6.84E-04 3.40E-04 O.OOE+OO O.OOE+00 1.98E-04 7.12E-04 Co-58 0.00E+00 4.63E-05 1.42E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.70E-04 Co-6O O.OOE+00 1.37E-04 4.05E-04 O.OOE+00 0.002+00 O.OOE+00 7.62E-04 Ni-63 1.40E-02 7.49E-04 4.76E-04 O.OOE+00 O.OOE+00 O.OOE+00 5.04E-05 Ni-65 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cu-64 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn-65 3.55E-04 9.46E-04 5.89E-04 O.OOE+00 5.96E-04 O.OOE+00 1.66E-04 Zn-69 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 O.OOE+00 0.0OE+00 0.002E+00 O.OOE+00 O.OOE+00 RA nl nnFln n nnF I

n nn Z

A

..^E Dr-o'4 U.UMt+UU I

U.UE+Wruu I

u.uuO+Ou U.UUIOO+O O.OoE+oo n-nf=j+no n nnF 4 nn Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Rb-86 0.QOE+00 1.68E-03 1.03E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.08E-04 Rb-88 0:OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+06 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 3.39E-02 O.OOE+00 9.67E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.31E-03 Sr-90 4.42E-01 0.00E+00 1.12E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.95E-03 Sr-91 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.55E-05 O.OOE+00 4.14E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.06E-03 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-93 O.OOE+00 O.OOE+00 O.OOE+O0 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 2.98E-06 6.56E-07 5.84E-07 O.OOE+00 9.39E-07 O.OOE+00 6.84E-04 Zr-97 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 Nb-95 5.74E-07 2.23E-07 1.60E-07 O.OOE+00 2.1 OE-07 O.OOE+00 4.13E-04 Mo-99 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

/

Page 3 of 16

Attachment F ODCM-QA-008 Revision 4 Page 51 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: LEAFY VEG. (Page 2 of 2) mrem-kglpCi-yr NUCUDE BONE LIVER T.BODY THYROID' KIDNEY LUNG GI-LU l

To101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO Ru103 1.87E-05 O.OOE+00 7.1 BE-06 O.OOE+00 4.70E-05 O.OOE+00 4.83E-04 R0105 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Ru-106 3.04E-04 O.OOE+00 3.79E-05 O.OOE+00 4.10E-04 O.OOE+00 4.72E-03 Ag-11Om 1.40E-05 9.44E-06 7.55E-06 O.OOE+00 1.76E-05 O.OOE+O0 1.12E-03 Te-125m 2.93E-04 7.94E-05 3.91 E-05 8.22E-05 O.OOE+00 O.OOE+00 2.83E-04 Te-127m 7.47E-04 2.01 E-04 8.86E-05 1.79E-04 2.13E-03 O.OOE+00 6.05E-04 Te-127 O.OOE0 +00 O

.OO E+OOE+.OOE+O O

O.OOE+00 O.OOE+0200 O.OOE+00 Te-129m 1.24E-03 3.46E-04 1.93E-04 4.OOE-04 3.64E-03 O.OOE+00 1.51E-03 Te-129 3.41 E-06 9.53E-07 8.10E-07 2.43E-06 9.98E-06 O.OOE+00 2.12E-04 Te-131 m O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 -

O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1-130 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 4.1 OE-04 4.13E-04 2.34E-04 1.36E-01 6.77E-04 O.OOE+00 3.67E-05 1-132 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00

-O.OOE+00 O.OOE+00 0.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Cs-1 34 6:08E03 9.97E-03 2.1 OE-03 O.OOE+00 3.09E-03 1.11 E03 5.38E-05 Cs-136 5.80E-04 1.59E-03 1.03E-03 O.OOE+00 8.49E-1.27E-04 5.60E-05 Cs-137 8.50E-03 8.14E-03 1.20E-03 O.OOE+00 2.65E-03 9.54E-04 5.1 OE-05 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-1 39 0.002+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 2.05E-03 1.79E-06 1.19E-04 O.OOE+00 5.84E-07 1.07E-06 1.04E-03 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 1.01 E-06 5.04E-07 7.48E-08 O.OOE+00 2.21 E-07 O.OOE+00 6.29E-04 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 5.39E-05 1.69E-05 2.88E-06 O.OOE+00 9.36E-06 O.OOE+00 4.41 E-03 Pr-143 ^

9.71E-07 2.92E-07 4.82E-08 O.OOE+00 1.58E-07 O.OOE+00 1.05E-03 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.CDE+00 O.OOE+00 Nd-147 6.81 E-07 5.52E-07 4.27E-08 O.OOE+00 3.03E-07 0.00E+00 8.74E-04 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 6

Np-239 O.OOE+00 O.OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Page 4 of 16

- Attachment F ODCM-QA-008 Revision 4 Page 52 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: FRUIT (Page 1 of 2) mrem-kglpCI-yr NUCLIDE -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.05E-04 1.05E-04 1.05E-04 1.05E-04 1.05E-04 1.05E-04 C-14 6.29E-03 1.26E-03 1.26E-03 1.26E-03 1.26E-03 1.26E-03 1.26E-03 Na-24 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 2.34E-02 1.09E-03 9.OOE-04 0.00E+00 0.00E+00 0.00E+00 6.46E-04 Cr-51 0.00E+00 0.00E+00 1.03E-06 5.72E-07 1.56E-07 1.05E-06 5.47E-05 Mn-54 0.00E+00 4.87E-03 1.30E-03 0.00E+00 1.37E-03 0.00E+00 4.09E-03 Mn-56 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Fe-55 5.73E-03 3.04E-03 9.42E-04 0.00E+00 0.00E+00 1.72E-03 5.63E-04 Fe-59 3.38E-03 5.47E-03 2.72E-03 0.00E+00 0.00E+00 1.59E-03 5.69E-03 Co-58 0.00E+00 5.20E-04 1.59E-03 0.OOE+00 0.00E+00 0.00E+00 3.03E-03 Co-60 0.00E+00 2.69E-03 7.94E-03 0.00E+00 0.00E+00 0.00E+00 1.49E-02 Ni-63 2.79E-01 1.50E-02 9.51 E-03 0.00E+00 O.OOE+00 0.00E+00 1.01 E-03 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Cu-64 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 6.01 E-03 1.60E-02 9.96E-03 0.00E+00 1.01E-02 0.OOE+00 2.81 E-03 Zn-69 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.002+00 0.00E+00 Br-83 0.00E+OU 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00

^.

Br-85 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 Rb-86 0.00E+00 3.75E-03 2.31 E-03 0.00E+00 0.00E+00 0.OOE+00 2.41 E-04 Rb-88 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+06 0.00E+00 0.OOE+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 3.01 E-01 0.00E+00 8.61 E-03 0.00E+00 0.00E+00 0.00E+00 1.17E-02 Sr-90 8.80E+00 0.002+00 2.23E+00 0.00E+00 0.00E+00 0.00E+00 1.192-01 Sr-91 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 1.54E-04 0.OOE+00 4.11E-06 0.00E+00 0.00E+00 0.00E+00 2.05E-02 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.15E-05 6.92E-06 6.16E-06 0.OOE+00 9.91 E-06 0.00E+00 7.22E-03 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 3.57E-06 1.39E-06 9.94E-07 0.00E+00 1.31 E-06 0.00E+00 2.57E-03 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 0.002+00 Page 5 of 16

Attachment F ODCM-QA-008 Revision 4 Aft Page 53 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: FRUIT (Page 2 of 2) mrem-kg/pCi-yr NUCUDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ru-1 03 1.32E-04 O.OOE+00 5.08E-05 0.00E+00 3.33E-04 O.OOE+00 3.42E-03 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-1 06 5.43E-03 0.OOE+00 6.78E-04 O.OOE+00 7.34E-03 O.OOE+00 8.45E-02 Ag-110m 2.3-7E-04 1.60E-04 128E-04 O.OOE+00 2.98E-04 O.OOE+00 1.91 E-02 Te-125m 2.89E-03 7.84E-04 3.86E-04 8.12E-04 O.OOE+00 O.OOE+00 2.79E-03 Te-127m 1.03E-02 2.76E-03 1.22E-03 2.45E-03 2.93E-02 O.OOE+00 8.31 E-03 Te-127 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Te-129m 7.34E-03 2.05E-03 1.14E-03 2.37E-03 2.16E-02 O.OOE+00 8.96E-03 Te-129 2.02E-05 5.64E-06 4.80E-06 1.44E-05 5.91E-05 0.00E+00 1.26E-03 Te-131m O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Te-1 31 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-1 32 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 1-131 5.07E-05 5.10E-05.

2.90E-05 1.69E-02 8.37E-05 O.OOE+00 4.54E-06 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.02E+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-1 34 1.15E-01 1.89E-01 3.99E-02 O.OOE+00 5.86E-02 2.10E-02 1.02E-03 Cs-136 5:18E404 1.42E-03 9.22E-04 O.OOE+00 7.59E-04 1.13E-04 5.01E-05 Cs-137 1.69E-01 1.62E-01 2.39E-02 O.OOE+00 5.28E-02 1.90E-02 1.02E-03 Cs-1 38 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 1.67E-03 1.47E-06 9.76E-05 O.OOE+00 4.77E-07 8.73E-07 8.47E-04 Ba-141 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 5.74E-06 2.86E-06 4.25E-07 O.OOE+00 1.26E-06 O.OOE+00 3.57E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 9.34E-04 2.93E-04 4.99E-05.

O.OOE+00 1.62E-04 O.OOE+00 7.642-02 Pr-143 9.51 E-07 2.86E-07 4.72E-08 O.OOE+00 1.55E-07 O.OOE+00 1.03E-03 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Nd-147 3.29E-07 2.66E-07 2.06E-08 O.OOE+00 1.46E-07 O.OOE+00 4.22E-04 W-187 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002E+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 6 of 16

I Attachment F ODCM-QA-008 Revision 4 Page 54 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: MEAT (Page 1 of 2) mrem-kg/pCi-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 8.30E-06 8.30E-06 8.30E-06 8.30E-06 8.30E-06 8.30E-06 C-14 4.96E-04 9.92E-05 9.92E-05 9.92E-05 9.92E-05 9.92E-05 9.92E-05 Na-24 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 1.28E-02 6.00E-04 4.94E-04 0.00E+00 0.00E+00 0.OOE+00 3.54E-04 Cr-51 0.00E+00 0.00E+00 2.21 E-07 1.23E-07 3.36E-08 2.24E-07 1.17E-05 Mn-54 0.00E+00 4.20E-04 1.12E-04 0.00E+00 1.18E-04 0.00E+00 3.52E-04 Mn-56 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 4.65E-04 2.47E-04 7.64E-05 0.00E+00 0.00E+00 1.39E-04 4.57E-05 Fe-59 4.96E-04 8.02E-04 4.00E-04 0.00E+00 0.00E+00 2.33E-04 8.35E-04 Co-58 0.00E+00 6.07E-05 1.86E-04 0.00E+00 0.OOE+00 0.00E+00 3.54E-04 Co-60 0.00E+00 2.15E-04 6.35E-04 0.00E+00 0.OOE+00 0.00E+00 1.19E-03 Ni-63 2.20E-02 1.18E-03 7.50E-04 0.00E+00 0.00E+00 0.00E+00 7.95E-05 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.002+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Zn-65 5.31 E-04 1.41 E-03 8.79E-04 0.00E+00 8.91 E-04 0.00E+00 2.48E-04 Zn-69 0.00E+00 0.00E+00 0.00E+00.

0.OOE+00 0.OOE+00 0.00E+00 0.002+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rrn nnFa n

n ne n nne nn I

I_

010lu U.UVCt-UU I

U.UUrtuU I

0.00E+00 U.UUE+00 0 00E+00 n nnF=+nn n nnr-nn Br-85 0.00E+00 0.002+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.90E+00 1.312-03 8.04E-04 0.00E+00 0.00E+00 0.00E+00 8.41 E-05 Rb-88 0;00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 4.11 E-02 0.00E+00 1.17E-03 0.00E+00 0.00E+00 0.00E+00 1.59E-03 Sr-90 6.96E-01 0.00E+00 1.76E-01 0.00E+00 0.00E+00 0.00E+00 9.38E-03 Sr-91 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 1.95E-05 0.00E+00 5.21 E-07 0.00E+00 0.00E+00 0.00E+00 2.59E-03 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.83E-06 8.42E-07 7.49E-07 0.00E+00 1.21E-06 0.00E+00 8.78E-04 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.21 E-07 2.42E-07 1.73E-07 0.00E+00 2.27E-07 0.00E+00 4.47E-04 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J

Page 7 of 16

Attachment F ODCM-QA-008 Revision 4 Page 55 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: MEAT (Page 2 of 2) mrem-kglpCi-yr I

NUCUDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+0O O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+O0 O.OOE+00 Ru-1 03

- 2.11 E-05 O.OOE+00 8.1 OE-06 0.OOE+OO 5.30E-05 O.OOE+0O 5.45E-04 Ru-105 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+O0 Ru-1 06 4.62E-04 0.OOE+00 5.76E-05 O.OOE+00 6.24E-04 0.OOE+00 7.19E-03 Ag-110m 2.09E-05 1.41 E-05 1.13E-05 O.OOE+00 2.63E-05 O.OOE+0O 1.68E-03 Te-125m 3.68E-04 9.98E-05 4.91 E-05 1.03E-04 O.OOE+00 O.OOE+00 3.55E-04 Te-127m 1.04E-03 2.81 E-04 1.24E-04 2.49E-04 2.97E-03 O.OOE+OO 8A5E-04 Te-127 O.OOE+00 0.OOE+00 0.OOE+OO O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+O0 Te-129m 1.32E-03 3.69E-04 2.05E-04 4.26E-04 3.88E-03 O.OOE+0O 1.61 E-03 Te-129 3.64E-06 1.02E-06 8.63E-07 2.59E-06 1.06E-05 O.OOE+00 2.26E-04

--Te-131 m O.OOE+00.

0.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00

-0.OOE+00 O.OOE+00

, Te-131 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+0O Te-132 O.OOE+O0 O.OOE+00 O.OOE+O0 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+OO 1-130 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+0O O.OOE+00 0.OOE+0O O.OOE+O0 1-131 1.26E-04 1.26E-044 7.19E-05 4.18E-02 2.08E-04 0.OOE+O0 1.13E-05 1-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 1-133 O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+OO 1-135 O.OOE+00

--O.OOE+00 O.OOE+OO O.OOE+OO -

O.OOE+0O O.OE+0 O.OOE+0E Cs-1 34 9.42E-03 1.55E-02 3.26E-03 O.OOE+00 4.79E-03 1.72E-03 8.33E-05 Cs-136 3-.36E-04 9.24E-04 5.98E-04 O.OOE+00 4.92E-04 7.34E-05 3.25E-05 Cs-137

-1.34E-02 1.28E-02 1.89E-03 O.OOE+00 4.18E-03 1.50E-03 8.03E-05 Cs-1 38 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 p.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+O0 Ba-140 1.15E-03 1.01E-06 6.73E-05 O.OOE+00 3.29E-07 6.02E-07 5.84E-04 Ba-141 0.OOE+00 O.OOE+O0 -

0.00E+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+OO Ba-142 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+OO 0.OOE+O0 O.OOE+O0 La-140 O.OOE+OO O.OOE+O0 0.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+0O La-142 0.OOE+00

-O.OE+OO O.OOE+O-O.OOE+OO O.OOE+OO O.OOE+O

.OOE+O0 Ce-141 1.06E-06 5.30E-07 7.87E-08, O.OOE+00 2.32E-07 O.OOE+00 6.61E-04 Ce-143 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Ce-144 8.12E-05 2.55E-05 4.33E-06 O.OOE+00 1.41 E-05 O.OOE+00 6.64E-03 Pr-143 5.80E-07 1.74E-07 2.88E-08 O.OOE+OO 9.43E-08 O.OOE+00 6.25E-04 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+OO O.OOE+OO Nd-147 3.24E-07 2.62E-07

- 2.03E-08 O.OOE+O0 1.44E-07 O.OOE+OO 4.15E-04_/

W-187 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00

,.OOE+00 FO.OOE+00 O.OOE+O0/

Np-239 O.OOE+00 I - O.OOE+00 I O.OOE+00 I

O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+OV

-I h I

&I Page 8 of 16 i

Attachment F ODCM-QA-008 Revision 4 Page 56 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: FISH (Page 1 of 2) mrem-kg/pCi-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.40E-06 1.40E-06 1.40E-06 1.40E-06 1.40E-06 1.40E-06 C-14 8.35E-05 1.67E-05 1.67E-05 1.67E-05 1.67E-05 1.67E-05 1.67E-05 Na-24 1.32E-05 1.32E-05 1.32E-05 1.32E-05 1.32E-05 1.32E-05 1.32E-05 P-32 5.42E-03 2.54E-04 2.09E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E-04 Cr-51 O.OOE+OO O.OOE+OO 5.99E-08 3.32E-08 9.08E-09 6.07E-08 3.18E-06 Mn-54 O.OOE+OO 7.37E-05 1.96E-05 O.OOE+OO 2.07E-05 O.OOE+OO 6.18E-05 Mn-56 O.OOE+OO 3.64E-09 8.21 E-10 O.OOE+OO 4.40E-09 O.OOE+OO 5.27E-07 Fe-55 7.93E-05 4.21 E-05 1.30E-05 O.OOE+OO O.OOE+OO 2.38E-05 7.79E-06 Fe-59 1.12E-04 1.81 E-04 9.04E-05 O.OOE+OO O.OOE+OO 5.26E-05 1.89E-04 Co-58 O.OOE+OO 1.23E-05 3.76E-05 O.OOE+OO O.OOE+OO O.OOE+OO 7.17E-05 Co-60 O.OOE+OO 3.65E-05 1.08E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.02E-04 Ni-63 3.71 E-03 1.99E-04 1.26E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.34E-05 Ni-65 2.08E-08 1.96E-09 1.14E-09 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E-07 Cu-64 O.OOE+OO 4.56E-07 2.76E-07 O.OOE+OO 1.1OE-06 O.OOE+OO 2.14E-05 Zn-65 9.43E-05 2.51 E-04 1.56E-04 O.OOE+OO 1.58E-04 O.OOE+OO 4.41 E-05 Zn-69 5.01E-15 7.23E-15 6.69E-16 O.OOE+OO 4.39E-15 O.OOE+OO 4.56E-13 Br-83 O.OOE+OO O.OOE+OO 1.12E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l_

Br-84 O.OOE+OO O.OOE+OO 3.40E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.45E-04 2.74E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E-05 Rb-88 O:OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 8.98E-03 O.OOE+OO 2.57E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.48E-04 Sr-90 1.17E-01 O.OOE+OO 2.97E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E-03 Sr-91 2.87E-05 O.OOE+OO 1.09E-06 O.OOE+OO O.OOE+OO O.OOE+OO 6.35E-05 Sr-92 1.34E-07 O.OOE+OO 5.39E-09 O.OOE+OO O.OOE+OO O.OOE+OO 2.55E-06 Y-90 2.1 9E-07 O.OOE+OO 5.86E-09 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E-04 Y-91m 5.22E-18 O.OOE+OO 1.90E-19 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E-14 Y-91 4.1OE-06 O.OOE+OO 1.10OE-07 O.OOE+OO O.OOE+OO O.OOE+OO 5.47E-04 Y-92 2.26E-10 O.OOE+OO 6.47E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.53E-06 Y-93 1.52E-08 O.OOE+OO 4.16E-10 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E-04 Zr-95 7.92E-07 1.74E-07 1.55E-07 O.OOE+OO 2.49E-07 O.OOE+OO 1.82E-04 Zr-97 1.80E-08 2.60E-09 1.54E-09 O.OOE+OO 3.74E-09 O.OOE+OO 3.94E-04 Nb-95 1.52E-07 5.93E-08 4.23E-08 O.OOE+OO 5.57E-08 O.OOE+OO 1.1OE-04 Mo-99 O.OOE+OO 7.13E-05 1.76E-05 O.OOE+OO 1.52E-04 O.OOE+OO 5.90E-05 Tc-99m 4.02E-10 7.88E-10 1.31 E-08 O.OOE+OO 1.14E-08 4.OOE-10 4.48E-07 Page 9 of 16

Attachment F ODCM-QA-008 Revision 4 Page 57 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: FISH (Page 2 of 2) mrem-kg/pCI-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-1 01 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 Ru-103 4.96E-06 0.00E+00 1.91 E-06 0.00E+00 1.25E-05 0.00E+00 1.28E-04 Ru-105 1.05E-08 0.00E+00 3.81 E-09 0.00E+00 9.23E-08 0.00E+00 6.85E-06 Ru-106 8.06E-05 0.00E+00 1.01E-05 0.00E+00 1.09E-04 0.002+00 1.25E-03 Ag-l Om 3.71 E-06 2.50E-06 2.00E-06 0.OOE+00 4.67E-06 0.OOE+00 2.98E-04 Te-125m 7.77E-05

2. 1 E-05 1.04E-05 2.18E-05 0.OOE+00 0.00E+00 7.50E-05 Te-127m 1.98E-04 5.33E-05 2.35E-05 4.74E-05 5.65E-04 0.00E+00 1.60E-04 Te-127 5.48E-07 1.48E-07 1.18E-07 3.80E-07 1.56E-06 0.00E+00 2.14E-05 Te-129m 3.29E-04 9.19E-05 5.11 E-05 1.06E-04 9.67E-04 0.00E+00 4.01 E-04 Te-129 9.06E-07 2.53E-07 2.15E-07 6.46E-07

-2.65E-06 0.00E+00 5.64E-05 Te-131m 2.85E-05 9.87E-06 1.05E-05 2.03E-05

-9.55E-05 0.00E+00 4.00E-04 Te-131 2.84E-24 0.00E+00 0.00E+00 2.17E-24 8.59E-24 0.00E+00 1.49E-23 Te-132 5.63E-05 2.49E-05 3.01 E-05 3.63E-05 2.31 E-04 0.00E+00 2.51 E-04 1-130 5.24E-06 1.06E-05 5.46E-06 1.17E-03 1.58E-05 0.00E+00 4.96E-06 1-131 1.09E-04 1.10E-04 6.22E-05 3.62E-02 1.80E-04 0.00E+00 9.75E-06 1-132 3.99E-09 7.33E-09 3.37E-09 3.40E-07 1.12E-08 0.00E+00 8.62E-09 1-133 1.84E-05 2.27E-05 8.59E-06 4.22E-03 3.78E-05 0.00E+00 9.15E-06 1-134 1.72E-14 3.20E-14 1.47E-14 7.36E-13 4.89E-14 0.00E+00 2.12E-14 1-135 9.75E-07 1.75E-06 8.30E-07 1.55E-04 2.69E-06 0.00E+00 1.34E-06 Cs-134 1.61 E-03 2.65E-03 5.58E-04 0.00E+00 8.20E-04 2.94E-04 1.43E-05 Cs-136 1.54E-04 4.23E-04 2.74E-04 0.00E+00 2.25E-04 3.36E-05 14A9E-05 Cs-137 2.26E-03 2.16E-03 3.19E-04 O.OOE+00 7.04E-04 2.53E-04

• 1.35E-05 Cs-1 38 5.77E-20 8.03E-20 5.09E-20 0.00E+00 5.65E-20 6.08E-21 3.70E-20 Ba-139 1.78E-11 9.49E-15 5.15E-13 0.00E+00 8.29E-15 5.58E-15 1.03E-09 Ba-140 5.43E-04 4.76E-07 3.17E-05 0.00E+00 1.55E-07 2.84E-07 2.75E-04 Ba-141 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Ba-142 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 La-140 4.61 E-08 1.61 E-08 5.43E-09 0.00E+00

-0.00E+00 0.00E+00 4.49E-04.

La-142 1.06E-13 3.36E-14 1.05E-14 0.00E+00 0.00E+00 0.00E+00 6.678-09 Ce-141 2.68E-07 1.34E-07 1.99E-08 0.00E+00 5.86E-08 0.00E+00 1.67E-04 Ce-143 2.91 E-08 1.58E-05 2.29E-09 0.00E+00 6.63E-09 0.00E+00 2.31 E-04 Ce-144 1A3E-05 4.49E-06 7.64E-07 0.00E+00 2.48E-06 O.OOE+00 1.17E-03 Pr-143

- 2.58E-07 7.74E-08 1.28E-08 0.00E+00 4.19E-08 0.00E+00 2.78E-04 Pr-144 0.00E+00

- 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Nd-147 1.81 E-07 1.A6E-07 1.13E-08 0.00E+00 8.03E-08 O.OOE+00 2.32E-04 W-1 87 1.47E-06 8.72E-07 3.91 E-07 0.00E+00 0.00E+00 0.00E+00 1.23E-04 Np-239 2.70E-08 1.94E-09 1.36E-09 0.00E+00 5.60E-09 0.00E+00 1.43E-04 Page 10 of 16

Attachment F ODCM-QA-008 Revision 4 Page 58 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: DRINKING WATER (Page 1 of 2) mrem-literlpCi-yr NUCLIDE BONE IVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E+00 1.04E-04 1.04E-04 1.04E-04 1.04E-04 1.04E-04 1.04E-04 C-14 6.17E-03 1.23E-03 1.23E-03 1.23E-03 1.23E-03 1.23E-03 1.23E-03 Na-24 1.70E-03 1.70E-03 1.70E-03 1.70E-03 1.70E-03 1.70E-03 1.70E-03 P-32 4.11 E-01 1.92E-02 1.58E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-02 Cr-51 O:OOE+0O O.OOE+00 4.48E-06 2.49E-06 6.80E-07 4.54E-06 2.38E-04 Mn-54 O.OOE+00 5.45E-03 1.45E-03 O.OOE+00 1.53E-03 O.OOE+00 4.57E-03 Mn-56 O.OOE+00 6.77E-06 1.53E-06 O.OOE+00 8.18E-06 O.OOE+00 9.81 E-04 Fe-55 5.86E-03

3. 1 E-03 9.64E-04 O.OOE+00 O.OOE+00 1.76E-03 5.76E-04 Fe-59 8.35E-03 1.35E-02 6.73E-03 O.OOE+00 O.OOE+00 3.92E-03 1.41E-02 Co-58 O.OOE+00 9.14E-04 2.80E-03 O.OOE+00 O.OOE+00 O.OOE+00 5.33E-03 Co-60 O.OOE+00 2.70E-03 7.95E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.49E-02 NI-63 2.74E-01 1.47E-02 9.33E-03 O.OOE+00 O.OOE+00 O.OOE+00 9.89E-04 Ni-65 4.17E-05 3.93E-06 2.29E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.81 E-04 Cu-64 O.OOE+00 6.49E-05 3.92E-05 O.OOE+00 1.57E-04 O.OOE+00 3.05E-03 Zn-65 6.98E-03 1.86E-02 1.16E-02 O.OOE+00 1.17E-02 O.OOE+00 3.26E-03 Zn-69 2.87E-09 4.15E-09 3.84E-10 O.OOE+00 2.52E-09 O.OOE+00 2.62E-07 Br-83 O.OOE+00 O.OOE+0O 2.69E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 1.59E-1 1 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 -

O.OOE+00 O.OOE+00 0.OOE+00 Rb-86 0.00E+00 3.35E-02 2.06E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.16E-03 Rb-88 O.OOE+O0 6.83E-17 4.74E-17 O.OOE+00 O.OOE+OOd O.OOE+00 3.35E-18 Rb-89 O.OOE+0O 5.84E-19 5.19E-19 O.OOE+00 O.OOE+00 O.OOE+00 5.09E-21 Sr-89 6.69E-01 O.OOE+00 1.91 E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.59E-02 Sr-90 8.67E+00 O.OOE+00 2.20E+00 O.OOE+00 O.OOE+0O O.OOE+00 1.17E-01 Sr-91 5.10E-03 O.OOE+00 1.93E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-02 Sr-92 2.14E-04 O.OOE+00 8.58E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.05E-03 Y-90 1.84E-05 O.OOE+00 4.93E-07 O.OOE+00 O.OOE+00 O.OOE+00 5.24E-02 Y-91m 8.67E-12 O.OOE+00 3.16E-13 O.OOE+00 O.OOE+00 O.OOE+00 1.70E-08 Y-91 3.05E-04 O.OOE+00 8.16E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.07E-02 Y-92 1.75E-07 O.OOE+00 5.01 E-09 0.00E+00 O.OOE+00 O.OOE+00 5.06E-03 Y-93 2.55E-06 O.OOE+00 7.01 E-08 O.OOE+00 O.OOE+00 O.OOE+00 3.81E-02 Zr-95 5.88E-05 1.29E-05 1.15E-05 O.OOE+00 1.85E-05 O.OOE+00 1.35E-02 Zr-97 2.18E-06 3.15E-07 1.86E-07 O.OOE+00 4.52E-07 O.OOE+00 4.77E-02 Nb-95 1.14E-05 4.42E-06 3.16E-06 O.OOE+00 4.16E-06 O.OOE+00 8.18E-03 Mo-99 O.OOE+00 5.98E-03 1.48E-03 O.OOE+00 1.28E-02 O.OOE+00 4.95E-03 Tc-99m 1.18E-07 2.32E-07 3.84E-06 O.OOE+00 3.37E-06 1.18E-07 1.32E-04 Page 11 of 16

Attachment F ODCM-QA-008 Revision 4 Page 59 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: DRINKING WATER (Page 2 of 2) mrem-liter/pCi-yr NUCLIDE.

BONE

LIVER, T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 3.19E-22 3.34E-22 4.23E-21 O.OOE+00 5.70E-21 1.77E-22 1.06E-21 Ru-103 3.70E-04 O.OOE+00 1.42E-04 O.OOE+00 9.30E-04 O.OOE+00 9.55E-03 Ru-105 5.05E-06 O.OOE+00 1.83E-06 O.OOE+00 4.44E-05 O.OOE+00 3.30E-03 Ru-106 5.96E-03 O.OOE+00 7.44E-04 O.OOE+00 8.05E-03 O.OOE+00 9.27E-02 Ag-11Om 2.7-5E-04 1.85E-04 1.48E-04 O.OOE+00 3.45E-04 O.OOE+00 2.21E-02 Te-1 25m 5.78E-03 1.57E-03 7.71 E-04 1.62E-03 O.OOE+00 O.OOE+OO 5.58E-03 Te-127m 1.47E-02 3.96E-03 1.74E-03 3.51 E-03 4.19E-02 O.OOE+00 1.19E-02 Te-127 9.87E-05 2.66E-05 2.12E-05 6.83E-05 2.81 E-04 O.OOE+00 3.86E-03 Te-129m 2.46E-02 6.86E-03 3.82E-03 7.92E-03 7.22E-02 O.OOE+00 3.00E-02 Te-129 6.76E-05 1.89E-05 1.61E-05 4.83E-05 1.98E-04 O.OOE+00 4.21E-03 Te-131 m 2.78E-03 9.62E-04 1.02E-03 1.98E-03 9.31 E-03 O.OOE+00 3.90E-02 Te-131 9.43E-14 2.87E-14 2.80E-14 7.21 E-14 2.85E-13 O.OOE+00 4.95E-13 Te-132 4.63E-03 2.05E-03 2.48E-03 2.99E-03 1.90E-02 O.OOE+00 2.06E-02 1-130 7.60E-04 1.54E-03 7.91E-04 1.69E-01 2.29E-03 O.OOE+00 7.18E-04 1-131 8.40E-03 8.45E-03 4.80E-03 2.79E+00 1.39E-02 0.00E+00 7.52E-04 1-132 1.1 OE-05 2.02E-05 9.27E-06 9.35E-04 3.08E-05 O.OOE+00 2.37E-05 1-133 2.02E-03 2.50E-03 9.47E-04 4.65E-01 4.17E-03 O.OOE+00 1.01 E-03 1-134 1.65E-08 3.06E-08 141AE-08 7.05E-07 4.69E-08 0.00E+00 2.03E-08 1-135 2.54E-04 4.56E-04 2.16E-04

-4.04E-02 7.00E-04 0.00E+00 3.48E-04 Cs-134 1.19E-01 1.96E-01 4.13E-02 O.OOE+00 6.07E-02 2.18E-02 1.06E-03 Cs-136 1.1 7E-02 3.21 E-02 2.08E-02 O.OOE+00 1.71 E-02 2.55E-03 1.13E-03 Cs-137 1.67E-01 1.60E-01 2.36E-02 O.OOE+00 5.20E-02 1.87E-02 1.00E-03 Cs-138 2.23E-11 3.10E-11 1.96E-11 O.OOE+00 2.18E-11 2.34E-12 14A3E-11 Ba-139 5.27E-07 2.81 E-10 1.53E-08 O.OOE+00 2.46E-10 1.65E-10 3.04E-05 Ba-140 4.12E-02 3.61 E-05 2.41 E-03 o.OOE+00 1.18E-05 2.15E-05 2.09E-02 Ba-141 1.48E-16

- 8.26E-20 4.80E-18 O.OOE+00 7.15E-20 4.86E-19 8.41 E-17 Ba-142 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-140 4.19E-06 1.46E-06 4.94E-07 O.OOE+00 0.00E+00 O.OOE+00 4.08E-02 La-142 1.44E-09,

4.60E-10 1.44E-10 O.OOE+00 O.OOE+00 O.OOE+00 9.12E-05 Ce-141 2.00E-05 9.99E-06 1 A8E-06 O.OOE+00 4.38E-06 0.00E+00 1.25E-02 Ce-143 2.77E-06 1.50E-03 2.18E-07 O.OOE+00 6.30E-07 0.002+00 2.20E-02 Ce-144 1.06E-03 3.32E-04 5.65E-05 O.OOE+00 1.84E-04 O.OOE+00 8.66E-02 Pr-143 1.95E-05 5.87E-06 9.69E-07 O.OOE+00 3.18E-06 0.00E+00 2.11 E-02 Pr-144 2.002-20 6.18E-21 1.00E-21 O.OOE+00 3.27E-21 0.00E+00 1.33E-17 Nd-147 1.38E-05 1.12E-05 8.65E-07 O.OOE+00 6.13E-06 O.OOE+00 1.77E-02 W-187 1.54E-04 9.14E-05 4.1 OE-05 O.OOE+00 O.OOE+00 0.00E+00 1.28E-02 Np-239 2.31 E-06 1.66E-07 1.17E-07 O.OOE+00 4.80E-07 O.OOE+00 1.23E-02 Page 12 of 16

Attachment F ODCM-QA-008 Revision 4 Page 60 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 1 of 2) mrem-m 3/ICI-vr NUCLIDE-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 O.OOE+OO 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 C-14 3.59E-02 6.73E-03 6.73E-03 6.73E-03 6.73E-03 6.73E-03 6.73E-03 Na-24 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO P-32 2.38E+01 1.05E+00 9.03E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.86E-01 Cr-51 O.OOE+OO O.OOE+OO 4.83E-04 2.68E-04 7.61 E-05 5.32E-02 3.39E-03 Mn-54 O.OOE+OO 4.75E-02 1.05E-02 O.OOE+OO 1.11 E-02 1.74E-02 2.53E-02 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE-0O O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 4.89E-02 2.60E-02 8.02E-03 O.OOE+OO O.OOE+OO 1.15E-01 2.96E-03 Fe-59 4.20E-02 6.79E-02 3.39E-02 O.OOE+OO O.OOE+OO 2.58E+00 1.44E-01 Co-58 O.OOE+OO 2.77E-03 4.94E-03 O.OOE+OO O.OOE+OO 1.73E+00 5.37E-02 Co-60 O.OOE+OO 1.34E-02 2.30E-02 O.OOE+OO O.OOE+OO 7.18E+00 9.78E-02 Ni-63 8.22E-01 4.63E-02 2.80E-02 O.OOE+OO O.OOE+OO 2.75E-01 6.33E-03 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO O.OOE+OO O.OOE+Oo 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Zn-65 4.84E-02 1.29E-01 8.OOE-02 O.OOE+OO 8.13E-02 1.13E+00 1.86E-02 Zn-69 O.OOE+00-O.OOE+OO O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO Rr12 n nnF~nn n

In

-f nnn nn.

nn n

I

^_

D1 W.wwV I

%/.%/uc-uu I

u.uuc+~uu I

u.Uut+uu O.OOE+OO O.OOE+OO n nnc:.&nn Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOEE+O O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.08E+OO 6.23E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E-02 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+0 O.OOE+OO O.OOE+00 Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.12E+OO O.OOE+OO 3.22E-02 O.OOE+OO O.OOE+OO 4.03E+00 3.13E-01 Sr-90 1.0 IE+02 O.OOE+OO 6.46E+OO O.OOE+OO O.OOE+OO 1.48E+01 3.44E-01 Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-92 O.OOE+OO O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oO Y-91m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1.57E+OO O.OOE+OO 4.19E-02 O.OOE+OO O.OOE+OO 4.51 E+OO 3.16E-01 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 3.1 fE-01 6.85E-02 6.06E-02 O.OOE+OO 9.76E.02 3.66E+00 1.OOE-01 Zr-97 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nb-95 5.79E-02 2.26E-02 1.61 E-02 O.OOE+OO 2.12E-02 1.51 E+00 9.12E-02 Mo-99 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tc-99m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO lO.OOE+OO Page 13 of 16

Attachment F ODCM-QA-008 Revision 4 Am Page 61 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 2 of 2)

_mrem-m3Ipci-yr NUCLIDE.

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 Ru-103 6.24E-03 O.OOE+OO 2AOE-03 O.OOE+00 1.57E-02 1 A8E+00 1.OOE-01 Ru-105 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 Ru-106 1.48E-01 O.OOE+00 1.84E-02 O.OOE+00 2.OOE-01 1.56E+01 4.68E-01 Ag-1 Om 1.91 E-02 1.29E-02 1.04E-02 O.OOE+00 2A12E-02 6.21 E+00 1.14E-01 Te-125m 1.16E-02 4.01 E-03 1.58E-03 3.322-03 O.OOE+00 8.23E-01 5.83E-02 Te-127m 3.32E-02 1.14E-02 4.04E-03 8.11 E-03 8.51 E-02 1.98E+00 9.54E-02 Te-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Te-129m 4.92E-02 1.75E-02 7.80E-03 1.62E-02 1.29E-01 4.51 E+00 4.66E-01

,Te-129 2.50E-07 8.96E-08 6.11 E-08 1.83E-07 6.58E-07 7.52E-03 6.53E-02 Te-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Te-1 31 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+O0 0.00E+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1-131 -

2.46E+00 2.46E+00 1.39E+00 8.30E+02 4.03E+00 O.OOE+00 1.45E-01 1-132 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Cs-134

-6.79E-01 1.06E+00

. 2.34E-01 O.OOE+00 3.45E-01 1.26E-01 4.01E-03 Cs-136 7.20E-01 1.89E+00 1.28E+00 O.OOE+00 1.06E+06 1.61E-01 4.62E-02 Cs-137 9.09E-01 8.27E-01 1.29E-01 O.OOE+00 2.83E-01 1.04E-01 3.63E-03 Cs-138 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140

-8.77E-01 7.68E-04

- 5.13E-02 O.OOE+00 2.50E-04 2.07E+01 1.21E+00 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00

-La-140 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00

-O.OOE+00 O.OOE+00 O.OOE+00 La-142 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 1.04E-01 5.17E-02 7.67E-03

~O.OOE+00 2.26E-02 1.44E+00 1.50E-01 Ce-143 O.OOE+00 0.00E+00 O.OOE+ 00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 7.57E+00 2.37E+00 4.04E-01 O.OOE+00 1.31 E+00 1.34E+01 4.34E-01 Pr-143 1.90E-01 5.72E-02 9.41 E-03 O.OOE+00.

3.09E-02 4.46E+00 1.OOE+00 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 1.93E-01 1.56E-01 1.21 E-02 O.OOE+00 8.57E-02 5.85E+00 1 A6E+00 W-187 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.002+00 Page 14 of 16

Attachment F ODCM-QA-008 Revision 4 Page 62 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: INHALATION -WEEKLY SAMPLING (Page 1 of 2) mrem-m3/pCi.yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03

(>14 3.59E-02 6.73E-03 6.73E-03 6.73E-03 6.73E-03 6.73E-03 6.73E-03 Na-24 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 P-32 3.09E+00 1.35E-01 1.17E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.00E-02 Cr-51

-O.OOE+00 O.OOE+00 1.68E-04 9.33E-05 2.65E-05 1.85E-02 1.18E-03 Mn-54 O.OOE+00 4.33E-02 9.58E-03 O.OOE+00 1.01 E-02 1.59E-02 2.31 E-02 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 4.75E-02 2.52E-02 7.79E-03 O.OOE+00 O.OOE+00 1.11 E-01 2.87E-03 Fe-59 2.18E-02 3.53E-02 1.76E-02 O.OOE+00 O.OOE+00 1.34E+00 7.46E-02 Co-58 O.00E+00 1.83E-03 3.27E-03 O.OOE+00 O.OOE+00 1.14E+00 3.56E-02 Co-60 O.OOE+00 1.32E-02 2.27E-02 O.OOE+00 O.OOE+00 7.08E+00 9.63E-02 NI-63 8.21 E-01 4.63E-02 2.80E-02 O.OOE+00 O.OOE+00 2.75E-01 6.33E-03 Ni-65 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cu-64 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Zn-65 4.30E-02 1.14E-01 7.10E-02 O.OOE+00 7.21 E-02 1.01 E+00 1.65E-02 Zn-69 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00.

Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 O.OOE+00 O.OOE+000 0.00E

/

Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.26E-01 1.30E-01 O.OOE+00 O.OOE+00 O.OOE+00 9.10E-03 Rb-88 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.0OE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 6.29E-01 O.OOE+00 1.81 E-02 O.OOE+00 0.00E+00 2.26E+00 1.75E-01 Sr-90 1.01E+02 O.OOE+00 6.44E+00 O.OOE+00 O.OOE+00 1.48E+01 3.43E-01 Sr-91 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-92 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Y-91m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 9.53E-01 O.OOE+00 2.54E-02 O.OOE+00 O.OOE+00 2.74E+00 1.92E-01 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-93 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 1.97E-01 4.34E-02 3.84E-02 O.OOE+00 6.19E-02 2.32E+00 6.34E-02 Zr-97 O.OOE+00 O.OOE+00 0.00E+00 O.02+00 O.OOE+00 O.OOE+00 O.OOE+00 Nb-95

• 2.52E-02 9.83E-03 7.02E-03 O.OOE+00 9.24E-03 6.58E-01 3.97E-02 Mo-99 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tc-99m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 15 of 16

Attachment F ODCM-QA-008 Revision 4 Page 63 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: INHALATION - WEEKLY SAMPLING (Page 2 of 2) mrem-m3/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI Tc-101 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Ru-1 03-2.97E-03 O.OOE+00 1.14E-03 O.OOE+00 7A8E-03 7.04E-01 4.76E-02 Ru-105 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Ru-106 1.37E-01 O.OOE+00 1.70E-02 0.00E+00 1.85E-01 1.44E+01 4.32E401 Ag-I1 Om 1.70E-02 1.15E-02 9.23E-03 O.OOE+00 2.14E-02 5.53E+00 1.01E-01 Te-125m 7.02E-03

- 2.43E-03 9.53E-04 2.01 E-03 O.OOE+00 4.98E-01 3.52E-02 Te-127m 2.54E-02 8.74E-03 3.09E-03 6.20E-03 6.51 E-02 1.51 E+00 7.30E-02 Te-127 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Te-129m 2.06E-02 7.36E-03 3.27E-03 6.80E-03 5.41 E-02 1.89E+00

-1.95E-01 Te-129 1.05E-07 3.76E-08

- 2.56E-08 7.68E-08 2.76E-07 3.15E-03 2.74E-02 Te-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Te-131 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Te-132

-.O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 1-130 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 4.81 E-02 4.81 E-02 2.73E-02 1.62E+01 7.88E-02 O.OOE+00 2.84E-03 1-132 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00, O.OOE+00 O.OOE+00 O.OOE+00 1-133 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 6.53E-01 1.02E+00 2.25E-01 O.OOE+00 3.31 E-01 1.21 E-01 3.86E-03 Cs-136 7.83E 2.06E-01 1 AOE-01 O.OOE+00-1.15E-01 1.75E-02 5.03E-03 Cs-137 9.07E-01 8.25E-01 1.28E-01 O.OOE+00.

2.82E-01 1.04E-01 3.62E-03 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

- O.OOE+00 Ba-139 0.00E+00

'O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 8.95E-02 7.83E-05 5.23E-03 O.OOE+00 2.55E-05 2.11 E+00 1.23E-01 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Ba-142 0.00E+00 0.00E+200 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 La-140 0.00E+00 0.002E+00 0.002E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+Ob La-142

. O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-14.1 4.23E-02 2.11 E-02 3.12E-03 O.OOE+00 9.21 E-03 5.86E-01 6.10E02 Ce-143 0.002+E+

00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 ^

6.83E+00

-2.13E+00 3.65E-01 O.OOE+00

^ 1.18E+00 1.21E+01

- 3.92E-01 Pr-143

.2.21 E-02

^ 6.64E-03 1.09E-03 O.OOE+00 3.59E-03 5.18E-01 1.16E-01 Pr-144 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Nd-147 1.35E-02 1.09E-02 8.49E-04 O.OOE+00 6.00E-03 4.09E-01 1.02E-01 W-187 ^

O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Np-239 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 16 of 16

Attachment G ODCM-QA-008 Revision 4 Page 64 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: MILK (Page 1 of 2) mrem-liter/pCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.02E-04 1.02E-04 1.02E-04 1.02E-04 1.02E-04 1.02E-04 C-14 7.82E-03 1.67E-03 1.67E-03 1.67E-03 1.67E-03 1.67E-03 1.67E-03 Na-24 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 5.09E-01 2.99E-02 1.97E-02 0.00E+00 0.00E+00 0.00E+00 6.89E-03 Cr-51 0.00E+00 0.00E+00 4.43E-06 2.89E-06 6.31 E-07 5.62E-06 1.29E-04 Mn-54 0.00E+00 6.54E-03 1.48E-03 0.00E+00 1.45E-03 0.00E+00 2.40E-03 Mn-56 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Fe-55 4.58E-03 2.96E-03 7.91 E-04 0.00E+00 0.OOE+00 1.45E-03 3.76E-04 Fe-59 9.85E-03 1.72E-02 6.78E-03 0.OOE+00 0.00E+00 5.09E-03 8.22E-03 Co-58 0.OOE+00 1.16E-03 2.91 E-03 0.00E+00 0.00E+00 0.OOE+00 2.90E-03 Co-60 0.00E+00 3.56E-03 8.41 E-03 0.OOE+00 0.00E+00 0.00E+00 8.47E-03 Ni-63 2.09E-01 1.29E-02 7.26E-03 0.00E+00 0.00E+00 0.00E+00 6.43E-04 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Zn-65 6.04E-03 2.07E-02 9.55E-03 0.00E+00 1.00E-02 0.00E+00 1.75E-02 Zn-69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.21 E-02 2.57E-02 0.00E+00 0.00E+00 0.00E+00 1.33E-03 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+O00 0.00E+00 0.OOE+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 8.06E-01 0.00E+00 2.31 E-02 0.00E+00 0.00E+00 0.00E+00 1.66E-02 Sr-90 6.10E+00 0.00E+00 1.55E+00 0.00E+00 0.00E+00 0.00E+00 7.62E-02 Sr-91 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 3.64E-04 0.00E+00 9.70E-06 0.00E+00 0.00E+00 0.00E+00 2.61 E-02 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 6.65E-05 1.62E-05 1.15E-05 0.00E+00 1.75E-05 0.00E+00 8.07E-03 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 1.33E-05 5.49E-06 3.17E-06 0.00E+00 3.93E-06 0.00E+00 4.63E-03 MO-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 0.00E+00 0.00E+00 Page 1 of 8

Attachment G ODCM-QA-008 Revision 4 Page 65 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: MILK (Page 2 of 2) mrem-IiterIpCi-yr NUCLIDE..

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Ru-103 4.71 E-04 O.OOE+00 1.58E-04 0.00E+00 9.81 E-04 O.OOE+00 5.73E-03 Ru-1 05 0.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-106 7.92E-03 O.OOE+00 9.90E-04 O.OOE+00 9.37E-03 O.OOE+00 6.02E-02 Ag-11Om 3.27E-04 2.39E-04 1.58E-04 O.OOE+00 3.41 E-04 O.OOE+00 1.24E-02 Te-125m 7.51 E-03 2.51 E-03 1.01 E-03 2.53E-03 O.OOE+00 O.OOE+00 3.58E-03 Te-127m 1.91 E-02 6.32E-03 2.31E-03 5.51 E-03 4.69E-02 O.OOE+00 7.69E-03 Te-127 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-129m 3.17E-02 1.09E-02 4.88E-03 1.22E-02 7.92E-02 O.OOE+00 1.89E-02 Te-129 8.99E-05 3.10E-05 2.10E-05 7.54E-05 2.24E-04 O.OOE+OO 7.19E-03 Te-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+0O 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-131 9.97E-03 1.17E-02 5.17E-03 3.86E+00 1.37E-02 0.00E+00 4.19E-04 1-132 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 1.24E-01 2.32E-01 2.34E-02 O.OOE+00 5.96E-02 2.44E-02 6.29E-04 Cs-136 1.36E-02 4.01 E-02 1.50E-02 O.OOE+00 1.60E-02 3.27E-03 6.09E-04 Cs-137 1.72E-01 2.02E-01 1 A3E-02 O.OOE+00 5.41 E-02 2.19E-02 6.30E-04 Cs-138 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-1 39 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-140 5.06E-02 5.06E-05 2.61 E-03 O.OOE+00

'1.20E-05 3.11 E-05 1.24E-02 Ba-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 La-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ce-141 2.49E-05 1.52E-05 1.79E-06 O.OOE+00 4.68E-06 O.OOE+00 7.84E-03 Ce-143 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.002+00 0.002+00 Ce-144 9.79E-04 4.01 E-04 5.48E-05 O.OOE+00 1.62E-04 0.00E+O0 5.62E-02 Pr-143 2.42E-05 9.06E-06 1.20E-06 0.00E+00 3.37E-06 0.002E+O 1.28E-02 Pr-144 0.00E+O0 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Nd-147 1.61 E-05 1.65E-05 1.01 E-06 0.002+00 6.37E-06 O.OOE+00 1.05E-02 W-187 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.002+00 O.OOE+00 Np-239 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 2 of 8

Attachment G ODCM-QA-008 Revision 4 Page 66 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: DRINKING WATER (Page 1 of 2) mrem-literlpCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E+00 1.02E-04 1.02E-04 1.02E-04 1.02E-04 1.02E-04 1.02E-04 C-14 7.82E-03 1.67E-03 1.67E-03 1.67E-03 1.67E-03 1.67E-03 1.67E-03 Na-24 1.91 E-03 1.91 E-03 1.91E-03 1.91 E-03 1.91 E-03 1.91 E-03 1.91 E-03 P-32 5.48E-01 3.22E-02 2.12E-02 0.00E+00 0.00E+00 0.00E+00 7.41 E-03 Cr-51 0.00E+00 0.OOE+00 4.60E-06 3.00E-06 6.55E-07 5.83E-06 1.34E-04 Mn-54 0.00E+00 6.56E-03 1.49E-03 0.00E+00 1.45E-03 0.00E+00 2A.1 E-03 Mn-56 0.00E+00 1.07E-05 1.85E-06 0.OOE+00 9.22E-06 0.00E+00 9.74E-04 Fe-55 4.59E-03 2.96E-03 7.92E-04 0.OOE+00 0.OOE+00 1.45E-03 3.76E-04 Fe-59 1.01E-02 1.76E-02 6.94E-03 0.00E+00 0.00E+00 5.21 E-03 8.42E-03 Co-58 0.OOE+00 1.18E-03 2.95E-03 0.00E+00 0.00E+00 0.00E+00 2.95E-03 Co-60 0.00E+00 3.56E-03 8.41 E-03 0.00E+00 0.00E+00 0.00E+00 8.48E-03 Ni-63 2.09E-01 1.29E-02 7.26E-03 0.00E+00 0.00E+00 0.00E+00 6.43E-04 Nk65 5.72E-05 6.47E-06 2.94E-06 0.00E+00 0.00E+00 0.OOE+00 4.93 E-04 Cu-64 0.00E+00 1.04E-04 4.83E-05 0.00E+00 1.77E-04 0.00E+00 2.14E-03 Zn-65 6.06E-03 2.08E-02 9.59E-03 0.00E+00 1.01 E-02 0.00E+00 1.76E-02 Zn-69 3.96E-09 7.13E-09 5.31 E-10 0.OOE+00 2.96E-09 0.00E+00 5.82E-07 Br-83 0.00E+00 0.00E+00 3.69E-06 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Br-84 O.OOE+00 0.00E+00 1.99E-11 0.OOE+00 0.00E+00 0.00E+00 O.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Rb-86 0.00E+00 5.51 E-02 2.72E-02 0.OOE+00 0.00E+00T 0.OOE+00 1.41E-03 Rb-88 0.00E+00 1.16E-16 6.35E-17 0.00E+00 0.00E+00 0.00E+00 1.13E-16 Rb-89 0.00E+00 9.23E-19 6.36E-19 0.00E+00 0.OOE+00 0.00E+00 3.14E-19 Sr-89 8.23E-01 0.00E+00 2.36E-02 0.00E+00 0.00E+00 0.00E+00 1.69E-02 Sr-90 6.10E+00 0.00E+00 1.55E+00 0.00E+00 0.00E+00 0.00E+00 7.62E-02 Sr-91 6.87E-03 0.00E+00 2.49E-04 0.00E+00 0.OOE+00 0.00E+00 8.14E-03 Sr-92 2.94E-04 0.00E+00 1.09E-05 0.00E+00 0.00E+00 0.00E+00 3.17E-03 Y-90 2.52E-05 0.00E+00 6.75E-07 0.00E+00 0.00E+00 0.OOE+00 3.48E-02 Y-91 m 1.19E-11 0.00E+00 4.06E-13 0.00E+00 0.00E+00 0.00E+00 3.97E-08 Y-91 3.71 E-04 0.00E+00 9.87E-06 0.00E+00 0.00E+00 0.00E+00 2.66E-02 Y-92 2.41 E-07 0.00E+00 6.77E-09 0.00E+00 0.00E+00 0.00E+00 4.60E-03 Y-93 3.52E-06 0.00E+00 9.59E-08 0.00E+00 0.00E+00 0.00E+00 2.78E-02 Zr-95 6.76E-05 1.65E-05 1.17E-05 0.00E+00 1.78E-05 0.00E+00 8.21 E-03 Zr-97 2.99E-06 5..12E-07 2.34E-07 0.00E+00 5.16E-07 0.00E+00 3.27E-02 Nb-95 1.37E-05 5.65E-06 3.27E-06 0.00E+00 4.05E-06 0.OOE+00 4.77E-03 Mo-99 0.00E+00 9.89E-03 1.93E-03 0.00E+00 1.48E-02 0.00E+00 3.26E-03 Tc-99m 1.59E-07 3.28E-07 4.23E-06 0.00E+00 3.53E-06 1.72E-07 9.53E-05 Page 3 of 8

Attachment G ODCM-QA-008 Revision 4 Page 67 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: DRINKING WATER (Page 2 of 2) mrem-liter/pCi-yr NUCUDE BONE LIVER T.BODY THYROID KIDNEY LUNG Gl-LLI Tc-101 4.38E-22 5.52E-22 5.46E-21 O.OOE+OO 6.56E-21 3.01 E-22 9.38E-20 Ru-103 4.84E-04 O.OOE+O0 1.62E-04 O.OOE+O0 1.01 E-03 O.OOE+OO 5.89E-03 Ru-105 6.89E-06 O.00E+00 2.32E-06 O.OOE+O0 5.07E-05 O.OOE+O0 2.74E-03 Ru-1 06 7.95E-03 O.OOE+00 9.92E-04 O.OOE+OO 9.40E-03 O.OOE+O0 6.03E-02

- Ag-11 Om 3.28E-04 2.40E-04 1.59E-04 O.OOE+00 3.43E-04 O.OOE+0O 1.24E-02 Te-125m 7.64E-03 2.56E-03 1.03E-03 2.57E-03 O.OOE+O0 O.OOE+00 3.64E-03 Te-127m 1.92E-02 6.38E-03 2.33E-03 5.56E-03 4.74E-02 O.OOE+0O 7.76E-03 Te-127 1.36E-04 4.54E-05 2.91 E-05 1.1OE-04 3.31 E-04 O.OOE+00 2.85E-03 Te-129m 3.27E-02 1.12E-02 5.03E-03 1.25E-02 8.17E-02 O.OOE+00 1.95E-02 Te-129 9.28E-05 3.20E-05 2.17E-05 7.77E-05 2.31 E-04 O.OOE+00 7.41 E-03 Te-131m 3.80E-03 1.53E-03 1.26E-03 3.1 OE-03 1.05E-02 O.OOE+00 2.58E-02 Te-131 1.29E-13 4.78E-14 3.63E-14 1.15E-13 3.31 E-13 O.OOE+00 5.22E-12 Te-132 6.17E-03

-3.06E-03 2.85E-03 4.51 E-03 1.91 E-02 O.OOE+OO 1.13E-02 1-130 1.o IE-03 2.22E-03 8.92E-04 2.49E-01 2.44E-03 O.OOE+00 4.76E-04 1-131 1.13E-02 1.34E-02 5.88E-03 4.39E+00 1.56E-02 O.OOE+O0 4.77E-04 1-132 1.47E-05 2.99E-05 1.06E-05 1.40E-03 3.34E-05 O.OOE+O0 2.42E-05 1-133 2.77E-03 4.03E-03 1.18E-03 7.32E-01 4.73E-03 O.OOE+00 6.81 E-04 1-134 2.21 E-08 4.54E-08 1.61 E-08 1.06E-06 5.07E-08 O.OOE+00 4.69E-08 1-135 3.41 E-04 6.79E-04 2.48E-04 6.08E-02 7.57E-04 O.OOE+00 2.46E-04 Cs-1 34 1.24E-01 2.32E-01 2.34E-02 O.OOE+00 5.97E-02 2.45E-02 6.30E-04 Cs-136 1.48E-02 4.34E-02 1.62E-02 O.OOE+O0 1.73E-02 3.54E-03 6.59E-04 Cs-137 1.72E-01 2.02E-01 1.43E-02 O.OOE+00 5.41 E-02 2.19E-02 6.30E-04 Cs-138 3.04E-11 4.94E-11 2.40E-11 O.OOE+O0 2A7E-11 3.85E-12 7.90E-11 Ba-139 7.25E-07 4.81 E-10 2.1 OE-08 O.OOE+OO 2.89E-10 2.91 E-10 4.59E-05 Ba-140 5.49E-02 5A9E-05 2.83E-03 O.OOE+O0 1.30E-05 3.37E-05 1.35E-02 Ba-141 2.03E-16 1.39E-19 6.40E-18 O.OOE+00 8.36E-20 8.45E-20 2.48E-15 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.52E-24 La-140 5.66E-06 2.23E-06 5.74E-07 O.OOE+OO O.OOE+O0 O.OOE+00 2.62E-02 La-142 1.96E-09 7.20E-10 1.72E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.22E-04 Ce-141 2.57E-05 1.57E-05 1.84E-06 O.OOE+O0 4.83E-06 O.OOE+00 8.1 OE-03 Ce-143 3.80E-06 2.52E-03 2.87E-07 0.OOE+00 7.34E-07 O.OOE+O0 1.47E-02 Ce-144 9.82E-04 4.02E-04 5.50E-05 O.OOE+0O 1.62E-04 O.OOE+OO 5.64E-02 Pr-143 2.62E-05 9.78E-06 1.30E-06 O.OOE+OO 3.63E-06 O.OOE-+00 1.38E-02 Pr-144 2.74E-20 1.06E-20 1.38E-21 O.OOE+O0 3.85E-21.

O.OOE+O0 4.94E-16 Nd-147 1.77E-05 1.82E-05 1.1 IE-06 O.OOE+00 7.OOE-06 O.OOE+O0 1.15E-02 W-187 2.1 OE-04 1.46E-04 5.05E-05 O.OOE+00 O.OOE+00 O.OOE+0O 8.59E-03 Np-239 3.16E-06 2.83E-07 1.60E-07 O.OOE+00 5.64E-07 O.OOE+O0 8.17E-03 Page 4 of 8

Attachment G ODCM-QA-008 Revision 4 Page 68 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP:INHALATION - QUARTERLY SAMPLING (Page 1 of 2) mrem-m3IpCi-yr NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG Gl-LU H-3 0.00E+00 6.51E-04 6.51E-04 6.51 E-04 6.51 E-04 6.51E-04 6.51 E-04 C-14 2.65E-02 5.31E-03 5.31 E-03 5.31 E-03 5.31 E-03 5.31E-03 5.31 E-03 Na-24 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 P-32 1.86E+01 1.03E+00 7.08E-01 0.00E+00 0.00E+00 0.00E+00 1.47E-01 Cr-51 0.OOE+00 0.00E+00 2.80E-04 1.80E-04 4.14E-05 4.02E-02 1.12E-03 Mn-54 0.00E+00 2.80E-02 5.51E-03 0.00E+00 5.51E-03 1.11 E+00 7.81 E-03 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Fe-55 2.04E-02 1.21 E-02 3.44E-03 0.00E+00 0.00E+00 8.98E-02 1.13E-03 Fe-59 2.76E-02 4.78E-02 1.93E-02 0.00E+00 0.00E+00 2.06E+00 5.03E-02 Co-58 0.00E+00 1.91 E-03 2.84E-03 O.00E+00 0.00E+00 1.21 E+00 1.74E-02 Co-60 0.00E+00 8.15E-03 1.20E-02 0.00E+00 0.00E+00 4.58E+00 3.24E-02 Ni-63 3.39E-01 2.05E-02 1.16E-02 0.00E+00 0.00E+00 2.09E-01 2.42E-03 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 2.20E-02 7.12E-02 3.54E-02 O.00E+00 3.70E-02 7.36E-01 5.85E-02 Zn-69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.OOE+00 Br-83 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Br-84 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0-.OOE+00 1.04E+00 4.80E-01 0.00E+00 0.00E+00 0.00E+00 1.65E-02 Rb-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 Sr-89 7.43E-01 0.00E+00 2.13E-02 O.00E+00 0.00E+00 3.79E+00 1.20E-01 Sr-90 4.1 OE+01 0.00E+00 2.60E+00 0.00E+00 0.00E+00 1.13E+01 1.31 E-01 Sr-91 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-92 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Y-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-91 1.01E+00 0.00E+00 2.69E-02 O.00E+00 0.00E+00 4.21 E+00 1.21 E-01 Y-92 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-93 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.89E-01 4.57E-02 3.33E-02 0.00E+00 5.09E-02 2.87E+00 3.56E-02 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Nb-95 3.86E-02 1.58E-02 9.32E-03 0.00E+00 1.16E-02 1.18E+00 3.12E-02 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 0.002+00 0.002+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.002+00 J

0.00E+00

-I I

Page 5 of 8

Attachment G ODCM-QA-008 Revision 4 Page 69 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: INHALATION - QUARTERLY SAMPLING (Page 2 of 2) mrem-m 31pCi-yr NUCUDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Ru-103 4.50E-03 O.OOE+00 1.52E-03 O.OOE+00 9.48E-03 1.23E+00 3.60E-02 Ru-1 05 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+OO O.OOE+00 Ru-106 9.46E-02 O.OOE+00 1.19E-02 O.OOE+00 1.16E-01 1.26E+01 1.78E-41 Ag-1 Om 1.13E-02 8.20E-03 5.67E-03 O.OOE+0O 1.24E-02 4.16E+00 3.75E-02 Te-125m 8.21 E-03 3.43E-03 1.14E-03 2.80E-03 O.OOE+00 7.70E-41 2.23E-02 Te-127m 2.23E-02 9.23E-03 2.77E-03 6.51 E-03 5.01 E-02 1.75E+00 3.65E-02 Te-127 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 Te-129m 3.62E-02 1.56E-02 5.71 E-03 1.40E-02 8.15E-02 4.31 E+OO 1.77E-01 Te-129 2.02E-07 8.90E-08 4.81E-08 1.73E-07 4.49E-07 7.68E-03 6.75E-02 Te-131m O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Te-1 31 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+00 Te-1 32 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+O0 O.OOE+O0 1-130 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO 1-131 3.79E-02 4.44E-02 1.96E-02 1A8E+01 5.18E-02 O.OOE+O0 1.06E-03 1-132 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-135 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 4.13E-01 7.33E-01 7.77E-02 O.OOE+00 1.99E-Ot 8.31 E-02 1.39E-03 Cs-136 5.34E-01 1.49E+00 5.85E-01 O.OOE+00 6.24E-01 1.30E-01 1.58E-02 Cs-137 5.50E-01 6.14E-01 4.56E-02 O.OOE+00 1.73E-01 7.15E-02 1.34E-03 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Ba-139 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 Ba-140

-6.64E-01 6.64E-04 3.44E-02 0.00E+00 1.59E-04 1.89E+01 4.55E-01

- Ba-141 O.OOE+OO 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ba-142 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00O La-140 O.OOE+00 O.OOE+OO 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 La-142 0.OOE+00 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+O0 Ce-141 7.33E-02 4.41 E-02 5.26E-03 O.OOE+00 1.39E-02 1.37E+00 5.70E-02 Ce-143 O.OOE+00 O.OOE+O0 0.OOE+00 O.OOE+00

--O.OOE+00 O.OOE+00 O.OOE+O0 Ce-144 3.57E+00 1.35E+00 1.97E-41 O.OOE+00 6.01 E-01 1.1OE+01 1.66E-01 Pr-143 1.44E-01 5.39E-02 7.20E-03 O.OOE+00 2.03E-02 4.46E+00 3.84E-01 Pr-144 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Nd-147 IA1E-01 1.45E-01 8.91 E-03 O.OOE+OO 5.61 E-02 5.74E+00 5.56E-01 W-187 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 Np-239 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Page 6 of 8

Attachment G

. ODCM-QA-008 Revision 4 Page 70 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: INHALATION - WEEKLY SAMPLING (Page 1 of 2) mrem-m3/pCi-yr NUCLIDE BONE LIVER T.1BODY THYROID KIDNEY LUNG GI-LU H-3 O.OOE+O0 6.47E-04 6.47E-04 6.47E-04 6.47E-04 6.47E-04 6.47E-04 C-14 2.65E-02 5.31 E-03 5.31 E-03 5.31 E-03 5.31 E-03 5.31 E-03 5.31 E-03 Na-24 O.OOE+0O O.OOE+OO 0.OOE+00 O.OOE+00

.OOE+OO O.OOE+O0 O.OOE+0O0 P-32 2.41 E+00 1.33E-01 9.17E-02 O.OOE+00 O.OOE+00 O.OOE+O0 1.91 E-02 Cr-51 O.OOE+00 O.OOE+0O 9.76E-05 6.28E-05 1.44E-05 1.40E-02 3.90E-04 Mn-54 O.OOE+O0 2.55E-02 5.02E-03 O.OOE+O0 5.02E-03 1.01 E+OO 7.11 E-03 Mn-56 O.OOE+OO O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 Fe-55 1.98E-02 1.18E-02 3.34E-03 O.OOE+00 O.OOE+00 8.72E-02 1.1OE-03 Fe-59 1.43E-02 2.48E-02 1.OOE-02 O.OOE+O0 0.OOE+OO 1.07E+00 2.62E-02 Co-58 O.OOE+OO 1.26E-03 1.88E-03 O.OOE+00 O.OOE+00 8.04E-01 1.15E-02 Co-60 0.OOE+O0 8.03E-03 1.18E-02 O.OOE+00 O.OOE+00 4.51 E+00 3.20E-02 NI-63 3.39E-01 2.04E-02 1.16E-02 O.OOE+O0 O.OOE+OO 2.09E-01 2.42E-03 Ni-65 0.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+0 Cu-64 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+OO Zn-65 1.95E-02 6.32E-02 3.14E-02 O.OOE+O0 3.28E-02 6.53E-01 5.19E-02 Zn-69 O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 Br-83 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+0O O.OOE+00 O.OOE+O0 Br-84 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+OO O.OOE+O0 Br-85 0.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Rb-86 O.OOE+00 2.17E-01 1.OOE-01 O.OOE+0O O.OOE+00 O.OOE+0 3.46E-03 Rb-88 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+0O 0.OOE+0O O.OOE+0O O.OOE+0 Rb-89 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+OO O.OOE+0O O.OOE+O0 O.OOE+00 Sr-89 4.17E-01 O.OOE+OO 1.20E-02 O.OOE+00 O.OOE+00 2.13E+00 6.71 E-02 Sr-90 4.09E+01 O.OOE+O0 2.59E+0O O.OOE+00 O.OOE+00 1.12E+01 1.31 E-01 Sr-91 O.OOE+00 O.OOE+0O O.OOE+0O O.OOE+OO O.OOE+0 O.OOE+O0 O.OOE+OO Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Y-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+OO O.OOE+00 Y-91m O.OOE+0O O.OOE+0O O.OOE+0O O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+OO Y-91 6.13E-01 O.OOE+00 1.63E-02 0.OOE+0

0. OOE+00 2.55E+00 7.33E-02 Y-92 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+O0 O.OOE+O0 Y-93 O.OOE+0O O.OOE+OO O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+00 Zr-95 1.20E-01 2.89E-02 2.11 E-02 O.OOE+O0 3.23E-02 1.82E+00 2.25E-02 Zr-97 0.OOE+00 O.OOE+00 0.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+OO O.OOE+OO Nb-95 1.68E-02 6.89E-03 4.05E-03 O.OOE+OO 5.06E-03 5.13E-01 1.36E-02 MI-99 O.OOE+OO O.OOE+00 O.OOE+0O 0.OOE+0O 0.OOE+O0 O.OOE+00 O.OOE+OO Tc-99m O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+OO Page 7 of 8

Attachment G ODCM-QA-008 Revision 4 Page 71 of 78 REMP DOSE FACTORS FOR INFANT AGE GROUP: INHALATION - WEEKLY SAMPLING (Page 2 of 2) mrem-m3lpCI-yr NUCUDE..

- BONE L UVER T.BODY THYROID KIDNEY LUNG GI-LU Tc-101 O.OOE+OO 0.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+0O Ru-103 2.14E-03 O.OOE+00 7.22E-04 O.OOE+00 4.51 E-03 5.87E-01 1.71 E-02 Ru-105 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 0.OOE+OO O.OOE+OO O.OOE+00 Ru-106 8.74E-02 O.OOE+00 1.09E-02 O.OOE+O0 1.07E-01 1.16E+01 1.65E-01 Ag-I0m 1.01 E-02 7.29E-03 5.05E-03 O.OOE+0O 1.10E-02 3.70E+00 3.34E-02 Te-125m 4.96E-03 2.07E-03 6.86E-04 1.69E-03 O.OOE+0O 4.66E-01 1.35E-02 Te-127m 1.70E-02 7.06E-03 2.12E-03 4.98E-03 3.84E-02 1.34E+00 2.79E-02 Te-127 O.OOE+00 O.OOE+0O

- O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 Te-129m 1.52E-02 6.55E-03 2.39E-03 5.88E-03 3.42E-02 1.81 E+0O 7.42E-02 Te-129 8.47E-08

-3.73E-08 2.02E-08 7.25E-08 1.88E-07 322E-03 2.83E-02 Te-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+O0 Te-131 -

O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 Te-132 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-130 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 1-131 3.79E-02 4.44E-02 1.96E-02' 1.48E+01 5.18E-02

-O.OOE+O0 1.06E-03 1-132 O.OOE+OO -

O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+00

-O.OOE+O0 O.OOE+00 1-133 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 1-134 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 1-135 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 Cs-134 3.97E-01 7.05E-01 7.47E-02 O.OOE+00 1.91E-01 7.99E-02 1.34E-03 Cs-136 5.81 E-02 1.62E-01 6.36E-02 O.OOE+0O 6.78E-O0 1 A1 E-02 1.72E-03 Cs-137 5.49E-01 6.12E-01 4.55E-02 O.OOE+0O 1.72E-01 7.13E-02 1.33E-03 Cs-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O Ba-I 39 O.OOE+O0 O.OOE+00 0.OOE+00 O.OOE+0O O.OOE+00 0.OOE+00 O.OOE+00 Ba-140 6.77E-02 6.77E-05 3.50E-03 O.OOE+O0 1.62E-05 1.93E+00 4.64E-02 Ba-141 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+O0 O.OOE+00 Ba-142 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+O0 La-140 O.OOE+00 O.OOE+00 0.OOE+0O

.O.OOE+00 O.OOE+0O O.OOE+O0 O.OOE+O0 La-142 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 Ce-141 2.99E-02 1.80E-02 2.14E-03 O.OOE+00 5.66E-03 5.57E-01 2.32E-02 Ce-143 O.OOE+0O O.OOE+O0 O.OOE+OO O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 Ce-144 3.22E+00 1.22E+00 1.78E-01 O.OOE+O0 5.42E-01 9.93E+00 1.50E-01 Pr-143 1.67E-02

• 6.26E-03 8.35E-04 O.OOE+00 2.36E-03 5.17E-01 4A5E-02 Pr-144 O.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Nd-147 9.90E-03 1.01 E-02 6.23E-04 O.OOE+00 3.93E-03 4.02E-01 3.89E-02 W-187 O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+O0 0.OOE+0O O.OOE+00 O.OOE+OO Np-239 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+OO Page 8 of 8

Attachment H ODCM-QA-008 Revision 4 Page 72 of 78 REMP DOSE FACTORS FOR ADULT AGE GROUP: SHORELINE/SEDIMENT TOTAL BODY AND SKIN DOSE

)

mrem-K~gPI-Yr NUCLIDE T.BODY SKIN NUCLIDE T.BODY SKIN H-3 O.OOE+00 O.OOE+00 Ru-103 6.91 E-07 8.06E-07 C-14 O.OOE+00 O.OOE+00 Ru-105 8.64E-07 9.79E-07 Na-24 4.80E-06 5.57E-06 Ru-1 06 2.88E-07 3.46E-07 P-32 O.OOE+00 O.OOE+00 Ag-i 1 Om 3.46E-06 4.03E-06 Cr-51 4.22E-08 4.99E-08 Te-125m 6.72E-09 9.22E-09 Mn-54 1.11E-06 1.31 E-06 Te-127m 2.11 E-10 2.50E-10 Mn-56 2.11E-06 2.50E-06 Te-127 1.92E-09 2.1 E-09 Fe-55 O.OOE+00 O.OOE+00 Te-129m 1.48E-07 1.73E-07 Fe-59 1.54E-06 1.80E-06 Te-129 1.36E-07 1.61 E-07 Co-58 1.34E-06 1.57E-06 Te-131 m 1.61 E-06 1.90E-06 Co-60 3.26E-06 3.84E-06 Te-131 4.22E-07 4.99E-04 Ni-63 O.OOE+00 O.OOE+00 Te-132 3.26E-07 3.84E-07 Ni-65 7.1 OE-07 8.26E-07 1-130 2.69E-06 3.26E-06 Cu-64 3.05E-07 3.26E-07 1-131 5.38E-07 6.53E-07 Zn-65 7.68E-07 8.83E-07 1-132 3.26E-06 3.84E-06 Zn-69 O.OOE+00 O.OOE+0O 1-133 7.1OE-07 8.64E-07 Br-83 1.23E-08 1.79E-08 1-134 3.07E-06 3.65E-06 Br-84 2.30E-06 2.69E-06 1-135 2.30E-06 2.69E-06 Br-85 O.OOE+00 O.OOE+00 Cs-1 34 2.30E-06 2.69E-06 Rb-86 1.21 E-07 1.38E-07 Cs-136 2.88E-06 3.26E-06 Rb-88 6.72E-07 7.68E-07 Cs-1 37 8.06E-07 9.41 E-07

-Rb-89 2.88E-06 3.46E-06 Cs-1 38 4.03E-06 4.61E-06 Sr-89 1.08E-10 1.25E-10 Ba-139 4.61 E-07 5.18E-07 Sr-90 O.OOE+00 O.OOE+00 Ba-140 4.03E-07 4.61 E-07 Sr-91 1.36E-06 1.59E-06 Ba-141 8.26E-07 9.41 E-07 Sr-92 1.73E-06 1.92E-06 Ba-142 1.52E-06 1.73E-06 Y-90 4.22E-10 4.99E-10 La-140 2.88E-06 3.26E-06 Y-91m 7.30E-07 8.45E-07 La-142 2.88E-06 3.46E-06 Y-91 4.61 E-09 5.18E-09 Ce-141 1.06E-07 1.1 9E-07 Y-92 3.07E-07 3.65E-07 Ce-1 43 4.22E-07 4.80E-07 Y-93 1.09E-07 1.50E-07 Ce-144 6.14E-08 7.1 OE-08 Zr-95 9.60E-07 1.11 E-06 Pr-143 O.OOE+00 O.OOE+00 Zr-97 1.06E-06 1.23E-06 Pr-144 3.84E-08 4.42E-08 Nb-95 9.79E-07 1.1 5E-06 Nd-147 1.92E-07 2.30E-07 Mo-99 3.65E-07 4.22E-07 W-187 5.95E-07 6.91 -07 Tc-99m 1.84E-07 2.11E-07 Np-239 1.82E-07 2.11 -07 Ane

-Q 7

r

)

Ic-lI I

5.1E-u0 I

5.76E407 Page 1 of 3

Attachment H ODCM-QA-008 Revision 4

_~

Page 73 of 78 REMP DOSE FACTORS FOR TEEN AGE GROUP:SHORELINEISEDIMENT TOTAL BODY AND SKIN DOSE mrem-kglpCI-yr NUCLIDE T.BODY SKIN NUCLIDE T.BODY SKIN H-3 0.O0E+00 0.O0E+00 Ru-103 3.86E-06 4.50E-06 C-14 0.OOE+00 O.OOE+00 Ru-1 05 4.82E-06 5.47E-06 Na-24 2.68E-05 3.11 E-05 Ru-1 06 1.61 E-06 1.93E-06 P-32 O.OOE+00 0.OOE+00 Ag-l Om 1.93E-05 2.25E-05 Cr-51 2.36E-07 2.79E-07 Te-125m 3.75E-08 5.15E-08 Mn-54 6.22E-06 7.29E-06

-Te-127m 1.18E-09 1.39E-09 Mn-56 1.18E-05 1.39E-05 Te-127 1.07E-08 1.18E-08 Fe-55 O.OOE+00 O.OOE+00 Te-129m 8.25E-07 9.65E-07 Fe-59 8.58E-06

-1.01 E-05 Te-1 29 7.61 E-07 9.OOE-07 Co-58 7.50E-06 8.79E-06 Te-131m 9.OOE-06 1.06E-05 Co-60 1.82E-05 2.14E-05 Te-131 2.36E-06 2.79E-03 Ni-63 0.OOE+00 0.OOE+00 Te-132 1.82E-06 2.14E-06 Ni-65 3.97E-06 4.61 E-06 1-130 1.50E-05 1.82E-05 Cu-64 1.70E-06 1.82E 1-131 3.OOE-06 3.64E-06 Zn-65 4.29E-06 4.93E-06 1-132 -

1.82E-05 2.14E-05 Zn-69 O.OOE+00 0.OOE+00 1-133 3.97E-06 4.82E-06 Br-83 6.86E-08 9.97E-08 1-134 1.72E-05 2.04E-05 Br-84 1.29E-05 1.50E-05 1-135 1.29E-05 1.50E-05 Br-85 0.OOE+00 O.OOE+00 Cs-134.

1.29E-05 1.50E-05 Rb-86 6.75E-07 7.72E-07 Cs-1 36 1.61 E-05 1.82E-05

- Rb-88 3.75E-06 4.29E-06 Cs-I137 4.50E-96 5.25E-06 Rb-89 1.61 E-05 1.93E-05 Cs-138 2.25E-05 2.57E-05 Sr-89 6.OOE-10 6.97E-10

• Ba-139 2.57E 2.89E-06 Sr-90 0.OOE+00 0.OOE+00 Ba-140 2.25E-06 2.57E-06 Sr-91 7.61 E-06 8.90E-06 Ba-141 4.61 E-06 5.25E-06 Sr-92 9.65E-06 1.07E Ba-142 8.47E-06 9.65E-06 Y-90 2.36E-09 2.79E-09 La-140 1.61E-05 1.82E-05 Y-91m 4.07E-06 4.72E-06 La-142 1.61E-05 1.93E-05 Y-91 2.57E-08 2.89E-08 Ce-141 5.90E-07 6.65E-07 Y-92 1.72E-06

-2.04E-06 Ce-143 2.36E-06 2.68E-06 Y-93 6.11 E-07 8.36E-07 Ce-144 3.43E-07 3.97E-07 Zr-95 5.36E-06 6.22E-06 Pr-1 43

-0.OOE+00 0.00E+00 Zr-97 5.90E-06 6.86E-06 Pr-144 2.14E-07 2.47E-07 Nb-95 5.47E-06 6.43E-06 Nd-1 47,

1.07E-06 1.29E-06 Mo-99 2.04E-06 2.36E-06 W-187 3.32E-06 3.86E-06 Tc-99m 1.03E-06 1.1 8E-06 Np-239 1.02E-06 1.18E-06 aAi f

V^c ni IC-IUI Z.Ot-Uo I

3.LLZ-iJ Page 2 of 3

I Attachment H ODCM-QA-008 Revision 4 Page 74 of 78 REMP DOSE FACTORS FOR CHILD AGE GROUP: SHORELINEISEDIMENT TOTAL BODY AND SKIN DO5.

mrem-kg/pCi-yr NUCLIDE T.BODY SKIN NUCLIDE T.BODY SKIN H-3 O.00E+OO 0.00E+00 Ru-103 8.06E-07 9.41 E-07 C-14 0.00E+00 O.OOE+00 Ru-105 1.01 E-06 1.14E-06 Na-24 5.60E-06 6.50E-06 Ru-1 06 3.36E-07 4.03E-07 P-32 0.OOE+00 0.00E+00 Ag-i1 Om 4.03E-06 4.70E-06 Cr-51 4.93E-08 5.82E-08 Te-125m 7.84E-09 1.08E-08 Mn-54 1.30E-06 1.52E-06 Te-127m 2.46E-10 2.91 E-10 Mn-56 2.46E-06 2.91 E-06 Te-127 2.24E-09 2.46E-09 Fe-55 0.00E+00 0.00E+00 Te-129m 1.72E-07 2.02E-07 Fe-59 1.79E-06 2.11 E-06 Te-129 1.59E-07 1.88E-07 Co-58 1.57E-06 1.84E-06 Te-131m 1.88E-06 2.22E-06 Co-60 3.81 E-06 4.48E-06 Te-1 31 4.93E-07 5.82E-04 Ni-63 0.00E+00 0.00E+00 Te-132 3.81E-07 4.48E-07 Ni-65 8.29E-07 9.63E-07 1-130 3.14E-06 3.81 E-06 Cu-64 3.56E-07 3.81 E-07 1-131 6.27E-07 7.62E-07 Zn-65 8.96E-07 1.03E-06 1-132 3.81 E-06 4.48E-06 Zn-69 0.00E+00 0.00E+00 1-133 8.29E-07 1.01 E-06 Br-83 1.43E-08 2.08E-08 1-134 3.58E-06 4.26E-06 Br-84 2.69E-06 3.14E-06 1-135 2.69E-06 3.14E-06 Br-85 0.00E+00 0.00E+00 Cs-134 2.69E-06 3.14E-06 Rb-86 1.41 E-07 1.61 E-07 Cs-136 3.36E-06 3.81 E-06 Rb-88 7.84E-07 8.96E-07 Cs-137 9.41 E-07 1.1OE-06 Rb-89 3.36E-06 4.03E-06 Cs-1 38 4.70E-06 5.38E-06 Sr-89 1.25E-10 1.46E-10 Ba-139 5.38E-07 6.05E-07 Sr-90 0.00E+00

• 0.00E+00 Ba-140 4.70E-07 5.38E-07 Sr-91 1.59E-06 1.86E-06 Ba-141 9.63E-07 1.10E-06 Sr-92 2.02E-06 2.24E-06 Ba-142 1.77E-06 2.02E-06 Y-90 4.93E-10 5.82E-10 La-140 3.36E-06 3.81 E-06 Y-91 m 8.51 E-07 9.86E-07 La-142 3.36E-06 4.03E-06 Y-91 5.38E-09 6.05E-09 Ce-141 1.23E-07 1.39E-07 Y-92 3.58E-07 4.26E-07 Ce-143 4.93E-07 5.60E-07 Y-93 1.28E-07 1.75E-07 Ce-144 7.17E-08 8.29E-08 Zr-95 1.12E-06 1.30E-06 Pr-143 0.00E+00 0.00E+00 Zr-97 1.23E-06 1.43E-06 Pr-144 4.48E-08 5.15E-08 Nb-95 1.14E-06 1.34E-06 Nd-147 2.24E-07 2.69E-07 Mo-99 4.26E-07 4.93E-07 W-187 6.94E-07 8.06E-07 Tc-99m 2.15E-07 2.46E-07 Np-239 2.13E-07 2.46E-07 Tc-101 I

6.05E-07 6.72E-07 I

I I Page 3 of 3

Attachment I ODCM-QA-008 Revision 4 Page 75 of 78 CONSOLIDATED DOSE CALCULATIONS Equations 1 - 4 in Section 6.0 of ODCM-QA-008 consolidate the methodology of Regulatory Guide (RG) 1.109 (Ref. 3.1). Equations 1, 3, and 4 are related to -

Equation A-1 of Appendix A to Revision 1 of RG 1.109. This equation is a generalized equation for calculating the radiation dose to man via liquid effluent pathways. Equation A-1 is expressed as follows:

Raw = CoUwDDawi Where

Rap, is the annual dose to organ j of an individual of age group a from nuclide i via pathway p, in mrern/yr Cal is the concentration of nuclide i in the media of pathway p, in pCi/I, pCi/kg, or pCVM3; Uap is the exposure time or intake rate (usage) associated with pathway p for age group a, in hr/yr or kg/yr (as appropriate); and D8 p,,

is the dose factor, specific to age group a, radionuclide i, pathway p, and organ j. It represents the dose due to the intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in sediment, in mrem per hr/pCi per m2.

Cip of Equation A-1 corresponds to the RESREMP, and Raip corresponds to DREMPANG, DREMP[JB, and DREMPISKIN of Equations 1, 3, and 4.

The major differences between Equation A-1 and Equations 1, 3 and 4 of Section 6.0 of ODCM-QA-008 are as follows:

1.

As shown in EC-ENVR-1 027 (Ref. 3.13), the dose factors (DCALCANG, DCA~wB, and DCALC/SKIN) of Equations 1, 3, and 4 in Section 6.0 of ODCM-QA-008 incorporate both the usage factor, Up, and the dose factor, DaIg found in equation A-1 from RG 1.109.

2.

DcALcrm, & DCALCSKIN of Equations 3 and 4 from the ODCM have been modified by an assumed areal density (80 kg/rM2) for the first two inches of sediment to accommodate activity concentrations for sediment expressed in pCi/kg.

3.

In addition to the variables already discussed, all three of the ODCM equations incorporate the variable FsAmp to account for consumption periods (e.g., water and fish) or exposure times (shoreline sediment) less than one year. This is necessary because the dose factors, Dwq,, from RG 1.109 used by EC-ENVR-1 027 for the derivation of DCALCANG, DcALcr.B, & DCALC/SKJN are based on continuous intakes or I Pagel of4

Attachment I ODCM-QA-008 Revision 4 Page 76 of 78 exposures over a one-year period. However, activity concentrations for REMP samples may represent consumption or exposure periods of a week, two weeks, a month, a quarter, or in exceptional cases periods of other duration less than one year.

4.

As shown in EC-ENVR-1027, the dose factors of Equation 1 for certain media monitored by the REMP, such as monthly composited drinking water samples, incorporate an additional factor not included in Equation A-1. This additional factor calculates the dose from activity concentrations that might be consumed at the midpoint of the compositing period rather than the end of the period.

Equation 1 in Section 6.0 of ODCM-QA-008 may also be used to determine doses associated with the airborne exposure pathway resulting from the ingestion of such foods as milk, fruits, and vegetables. The use of Equation 1 for this purpose is similar to the intended use of Equation C-13 in Appendix C of RG 1.109 (Ref. 3.1). Equation C-13 is expressed as follows:

Da (r, 0) = D F lhaa C

fCon(r, 9) + U. C. (r, 0) + U. C[ (r, 9) + U0)f C. (r,9)]

Where D,a(r,9) is the annual dose to organ j of an individual of age group a from the dietary intake of atmospherically released radionuclides, in mrem/yr for sector Oat distance r.

C, is the concentration of nuclide i in produce, milk, meat or leafy vegetables, in pCi/l or pCi/kg for sector Oat distance r, Ua are the ingestion rates of produce, milk, meat, or leafy vegetables, respectively for individuals in age group a, in I/yr or kg/yr (as appropriate);

DFIV.

is the dose conversion factor for the ingestion of nuclide i, organ j and age group a, in mrem/pCi; and fg, are fractions that may be assumed to represent the portion of the total of that food product that is radiologically contaminated which is consumed during the period of interest.

C, of Equation C-1 3 corresponds to the RESREMP, and DFIIa corresponds to DREMPANG, of Equation 1 as it applies to food products containing radionuclides from the airborne pathway.-

The major differences between Equation C-13 and Equation 1 of Section 6.0 of ODCM-QA-008 are as follows:

I Page2of4

0 Attachment I ODCM-QA-008 Revision 4 Page 77 of 78

1.

Equation C-13 was formulated to calculate the total dose from the consumption of various foods (produce, milk, meat, and leafy vegetables) and radionuclides simultaneously, whereas Equation 1 is intended to calculate the doses separately for each item of food and each radionuclide.

2.

Equation C-13, similar to Equation A-1 discussed above, states usage factors and other factors for ingestion separately while equation 1 has incorporated these factors into the dose factors presented in the tables of Attachments D through H of ODCM-QA-008. This is shown in EC-ENVR-1027 (Ref. 3.13)

3.

In addition to the variables already discussed for Equation C-13, Equation 1 of the ODCM incorporates the variable FsAmp to account for consumption periods (e.g.,

milk and produce) less than one year. This is necessary because the dose factors, DFIff8, from RG 1.109 used by EC-ENVR-1 027 for the derivation of DCALCANG are based on continuous intakes over a one year period. -However, -

activity concentrations for REMP samples may represent consumption or exposure periods of a week, two weeks, a month, a quarter, or in exceptional cases periods of other duration less than one year.

Equation 2 in Section 6.0 of ODCM-QA-008 may also be used to determine doses associated with the inhalation of radionuclides. The use of Equation 2 for this purpose is similar to the intended use of Equation C-4 in Appendix C of RG 1.109 (Ref. 3.1).

Equation C4 is expressed as follows:

A X

Dja(r,90)=RaZXI(rO)DFAYa Where Dpa is the annual dose in mremlyr associated with inhalation of all radionuclides, to organ j of an individual in age group a Re is the inhalation rate in m3lyr for the appropriate age group x,(r,9) is the annual average ground-level concentration of nuclide i in air in sector 0 at distance r, in pCi/M3 DFAp is is the dose conversion factor for the inhalation of nuclide i, organ j and age group a, in mrem/pCi; Xt of Equation CA corresponds to the RESREMP, and DFA#a corresponds to DREMPnNH, Of Equation 2 as it applies to the inhalation of air containing radionuclides.

The major differences between Equation C4 and Equation 2 of Section 6.0 of ODCM-QA-008 are as follows:

I Page3of4

Attachment I ODCM-QA-008 Revision 4 Page 78 of 78

1.

Equation C-4 was formulated to calculate the total dose from inhalation of multiple radionuclides at different concentrations simultaneously, whereas Equation 2 is intended to calculate the doses separately for each radionuclide and concentration.

2.

Equation C-4 states breathing rates for inhalation separately, while Equation 2 has incorporated these into the dose factors presented in the tables of Attachments D through H of ODCM-QA-008. This is shown in EC-ENVR-1027 (Ref. 3.13)

3.

In addition to the variables already discussed for equation CA4, Equation 2 of the ODCM incorporates the variable FSAMP to account for consumption inhalation periods less than one year. This is necessary because the dose factors, DFAq, from RG 1.109 used by EC-ENVR-1 027 for the derivation of DcAJCANH is based on continuous inhalation over a one-year period. However, activity concentrations for REMP air samples may represent inhalation periods of a week, a quarter, or in exceptional cases periods of other duration less than one year.

4.

As shown in EC-ENVR-1027, the dose factors of Equation 2 incorporate an additional factor not included in Equation C4. This additional factor calculates the dose from activity concentrations that might be consumed at the midpoint of a quarterly compositing period rather than the end of the period.

I Page 4 of 4

PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC 1 NUCLEAR DEPARTMENT PROCEDURE DOSE ASSESSMENT POLICY STATEMENTS ODCM-QA-009 Revision 2 Page I of 11 QUALITY CLASSIFICATION:

APPROVAL CLASSIFIAtJi ON:

Z QA Program El Non-QA Program E

Plant No6-Plant El Instructio EFFECTIVE DATE:

__x_______

PERIODIC REVIEW FREQUENCEQ, A_

N/A PERIODIC REVIEW DUE A N/A RECOMMENDED REVIEWS:

tzl Nuclear Emergeny g

P ProcedurePiq n Francis J. Hickey Re e Supervisor Chemistry Support Supervisor - SSES Responsible FUM:

Chemistry Supervisor - SSES Responsible Approver Vice President - Nuclear Operations FORM NDAP-QA-0002-1, Rev. 3, Page 1 of 1

ODCM-QA-009 Revision 2 Page 2 of 11 PROCEDURE REVISION

SUMMARY

TITLE:

DOSE ASSESSMENT POLICY STATEMENTS The revision provides direction regarding identification of radionuclides in the sewage treatment plant waste !flGdge and or liquid effluent. The revision provides clarification in order to evaluate the impact of non-SSES generated isotopes identified in the sewage treatment plant sludge and liquid effluent relative to liquid effluent regulatory compliance and the disposition of sewage treatment plant sludge. The revision does not change any limits or analyses. Thus, Revision 2 of ODCM-QA-009 maintains the level of radioactive effluent control required pursuant to I OCFR20.1302, 40CFR1 90, 1 OCFR50.36a and Appendix I to 1 OCFR50 and does not impact the accuracy or reliability of efflpent, dose, or setpoint calculations.

In addition, these changes (1) do not alter the conduct of the radiological environmental monitoring program; (2) do not change radiological environmental monitoring activities; and (3) do not change-the information to be included in the Annual Radiological Environmental Operating or Radioactive Effluent Release Reports.

Incorporated PCAF 2002-1697, and added Nuclear Emergency Planning as a recommended reviewer.

UUL;)M-L2A-UUY Revision 2 Page 3 of 11 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 4

2.0 POLICY/DISCUSSION 4

2.1 Evaluation and Monitoring Criteria for Effluent Pathways 4

2.2 Low-Level Radioactivity in the Sewage Treatment Plant 5

3,0 REFERENCES 6

4.0 RESPONSIBILITIES 7

4.1 Chemistry Supervisor - SSES 7

5.0 DEFINITIONS 6.0 PROCEDURE 8

^

7.0 RECORDS 8

ATTACHMENTS ATTACHMENT PAGE A

Systems Classified as Insignificant Effluent Pathway 9

B Systems Classified as Significant Effluent Pathway 10 C

Systems with NRC l/E Bulletin 80-10 Applicability 11

ODCM-QA-009 Revision 2 Page 4 of 11 1.0 PURPOSE The purpose of this procedure is to state dose and effluent policy statements that are not directly associated with any other section of the ODCM.

This procedure constitutes part of the SSES Offsite Dose Calculation Manual (ODCM) which is a licensing basis document.

2.0 POLICY/DISCUSSION 2.1 Evaluation and Monitoring Criteria for Effluent Pathways 2.1.1 Potential effluent pathways will be evaluated on a case-by-case basis.

The evaluation will include identification of systems which are normally non-radioactive (as described in the FSAR) but could possibly become radioactive through interfaces with radioactive systems (

Reference:

NRC IE Bulletin No. 80-10). The evaluation will determine the significance of any potential effluent pathways and extent of sampling and/or monitoring required. The frequency of sampling or monitoring will be determined based on the potential for contamination, the potential for inadvertent, releases, the potential levels of contamination and releases, and the potential impact on station offsite doses.

2.1.2 Results of sampling and/or evaluation will be used to classify systems into one of the following categories:

a.

Not an Effluent Pathway

b.

Insignificant Effluent Pathway

c.

Significant Effluent Pathway

d.

Systems with NRC l/E Bulletin 80-10 Applicability Listings of systems classified as Insignificant or Significant Effluent Pathways or have 80-10 applicability are provided in Attachments A, B, and C, respectively.

2.1.3 Certain holding tanks for liquids and/or sludges that are not physically connected to radioactively contaminated systems also could become radioactively contaminated if they were to receive and concentrate radioactive materials from undetectable to detectable levels. All such tanks/vessels that receive/collect materials that have been in the station's Radiologically Controlled Areas, that allow these materials to contact liquids, and from which the liquid contents of the tanks could be released to the environment should be considered as 80-10 systems.

ODCM-QA-009 Revision 2 Page 5 of 11 All 80-10 systems shall be sampled and analyzed for radioactivity periodically in accordance with station procedures. If an 80-10 system becomes radioactively contaminated, a Condition Report (CR) shall be initiated. Further use of the system shall be evaluated and documented in Operability Assessments in response to the CR.

Compensatory measures, if any, shall be subject to 50.59 screening and/or evaluation.

If the resolution of the Condition Report is to continue operation of the system as contaminated (i.e., muse-as-is"), this shall require the performanrce of a 50.59 and 72.48 screening and/or evaluation.

2.1.4 Positively detected radioactive material in samples collected from all airborne and waterbome offsite release pathways will be reported in the Annual Effluent and Waste Disposal Report.

2.2 Low-Level Radioactivity in the Sewage Treatment Plant (STP) 2.2.1 Sewage processing facilities, such as the SSES sewage treatment plant, can under certain unusual conditions become contaminated with licensee generated radioactive materials (NRC IN 88-22).

2.2.2 Sewage treatment plant sludge is typically shipped to, and disposed of at, an offsite facility. The following guidelines have been established to support the disposal of sewage treatment sludge:

a.

Sludge collected for disposal at an offsite facility should be sampled and analyzed to environmental LLD criteria, to quantify any radioactivity present above natural background levels prior to free release.

b.

When sludge is determined to be contaminated with radionuclides generated from SSES operations, which have half-lives sufficiently long to make hold-up for decay impractical, the following options should be considered:

(1)

Dispose of the sludge as low level radioactive waste.

(2)

Obtain a special permit pursuant to the requirements of 10 CFR 20.2002.

c.

The sewage treatment plant liquid effluent should be sampled monthly for radioactivity.

2.2.3 A common source term for radionuclides identified in the STP is when individuals who work on-site have been subjected to the medical administration of radio-pharmaceuticals for diagnostic or therapeutic purposes. In these cases, normal biological elimination processes can

I' UUL;M-UA-UUY Revision 2 Page 6 of 1 1 easily result in levels of radioactivity in sewage treatment plant solutions and suspensions that are within the detection capabilities of the associated sampling and analysis program. Naturally occurring background radioisotopes and weapons testing fallout radioisotopes may also be identified in STP effluents or sludge. The radionuclides referenced above (naturally occurring, weapons testing fallout, medical) can be eliminated from consideration (regarding radioactive liquid effluent compliance or free release of sludge) once a determination has been made and documented that the source of the radionuclides is not due to SSES operations (i.e., licensee byproduct material).

3.0 REFERENCES

3.1 10CFR20.2002, Method for Obtaining Approval of Proposed Disposal Procedures 3.2 10CFR20 Appendix B, Annual Limits on Intake (ALls) and Derived Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage 3.3 1 OCFR50 Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low as is Reasonably Achievable" for Radioactive Material in Light-water Cooled Nuclear Power Reactor Effluents 3.4 10CFR50.59, Changes, Tests, and Experiments 3.5 NRC IE Bulletin No. 80-10, Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment 3.6 FSAR Section 11.2, Liquid Waste Management Systems 3.7 FSAR Section 11.3, Gaseous Waste Management Systems 3.8 ODCM-QA-003, Effluent Monitor Setpoints 3.9 PP&L Calculation EC-ENVR-1008, Unmonitored Release Analysis: Systems Identified in PLI-77223 3.10 Safety Evaluation NL-92-007, Operation of LLRWHF at SSES 3.11 Safety Evaluation NL-95-001, Refueling Outage Decay Heat Removal and Tie-In of the SDHR Temporary Cooling Equipment 3.12 Safety Evaluation NL-95-015, Operation of the Sewage Treatment Plant with Sludge Activity Above Environmental LLDs

ODCM-QA-009 Revision 2 Page 7 of 11 3.13 PLI-77223, Letter from D. L. Hagan to K. E. Shank, "Potential Unmonitored Release Assessment" 3.14 NDAP-QA-1180, Radiological Effluent Monitoring and Control A.

3.15 NRC Generic Letter No. 91-18, Revision 1; Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions, October 8, 1997 3.16 Condition Report #95876 3.17 Unit I and Unit 2 Technical Requirements Manual 3.18 PLI-86027, Insignificant Pathway - Noble Gas Entrained in Liquid Effluent 3.19 Condition Report #457463 and Action Request #457461 3.20 NRC IN 88-22 4.0 RESPONSIBILITIES 4.1 Chemistry Supervisor - SSES 4.1.1 Ensures adequacy and correctness of dose and effluent policy statements.

4.1.2 Ensures effluent pathways are properly evaluated based on calculations or other appropriate methods.

5.0 DEFINITIONS 5.1 Insignificant Effluent Pathway - Evaluation and/or periodic sampling demonstrate that the pathway may contain radioactive effluents, however, these effluents may not be reasonably expected to exceed 10 times the appropriate unrestricted area EC value (fractional ECs summed when appropriate) listed in Table 2 of Appendix B to 10 CFR 20. A release pathway which falls in this category will be sampled periodically.

5.2 ECL - Effluent Concentration Limit as defined in 1 OCFR20, Appendix B.

5.3 Not An Effluent Pathway - Realistic evaluation (e.g., engineering design, system operation, radionuclide inventory) demonstrates that the pathway has no potential for release of radioactive material. Although not required, periodic sampling may at times be performed to confirm the result of the evaluation.

ODCM-QA-009 Revision 2 Page 8 of 11 5.4 Significant Effluent Pathway - Evaluation and/or periodic sampling demonstrate

-that the pathway may contain radioactive effluents, and these effluents may be reasonably expected to exceed 10 times the appropriate unrestricted area EC value (fractional ECs summed when appropriate) listed in Table 2 of Appendix B to 10 CFR 20. Significant Effluent Pathways are not always sampled

.- 'continuously. They will be sampled and/or monitored continuously except where TRO Action Statements allow something different. Monitoring will occur in accordance with TR requirements.

5.5 80-10 Systems are those systems considered as non-radioactive (or described as non-radioactive in the FSAR), which could become radioactive through interfaces with radioactive systems (a non-radioactive system that could become contaminated due to leakage, valving errors, or other operating conditions in the radioactive systems). These normally non-radioactive systems are considered 80-10 Systems in accordance with NRC IE Bulletin 80-10 if they have both a potential for radioactive contamination and a release pathway to the

- environment Monitoring systems or sample analysis must be capable of detecting the Effluent Lower Limits of Detection (LLDs) referenced in the TRM.

6.0 PROCEDURE Chemistry Support shall perform dose calculations as required to support classification of effluent pathways. Use may be made of incoming requests for revision of the ODCM, or other relevant information that may be received from Nuclear Engineering or other PPL Susquehanna, LLC groups.

7.0 RECORDS None.

Attachment A ODCM-QA-009 Revision 2 Page 9 of 11 SYSTEMS CLASSIFIED AS INSIGNIFICANT EFFLUENT PATHWAY SYSTEM NO.

DESCRIPTION' REFERENCE, 037B Condensate Storage and Transfer I

b37D Refueling Storage and Transfer I

048 RFPT Lube Oil 1

095

. H2 Seal Oil

.'I 093 Main Turbine Lube Oil 1

099D Sewage Treatment Plant 2

040 Batch Lube Oil Tank 3

Noble Gas Entrained In Liquid Effluent 4

Notes:

1.

PP&Lu Calculation EC-ENVR-1008

2.

Sewage treatment plant is designed to be operated as a non-radioactive system.

Classification as an Insignificant Effluent Pathway is in accordance with Safety Evaluation NL-95-015

3.

PLI-77223

4.

PLI-86027 dated July 24, 1998, Insignificant Effluent Pathway - Noble Gas Entrained in Liquid Effluent Page 1 of I

Attachment B ODCM-QA-009 Revision 2 Page 10 of 11 IT CS SYSTEMS CLASSIFIED AS SIGNIFICANT EFFLUENT PATHWAY SYSTEM NO.

DESCRIPTION'.

- REFERENCE 069 Liquid Waste Management Systems 1

068 Solid Radwaste Processing Systems 3

072 Offgas System 2

012F Unit 1 and Unit 2 Reactor Building Vents 2

01 2B Unit I and Unit 2 Turbine Building Vents 2

070 Standby Gas Treatment System Vent 2

Notes:

1. SSES FSAR Chapter 11.2

2. SSES FSAR Chapter 11.3

3. SSES FSAR Chapter 11.4 I

Page 1 of I

Attachment C ODCM-QA-009 Revision 2 Page 11 of 11 SYSTEMS WITH NRC I/E BULLETIN 80-10 APPLICABILITY SYSTEM NO.

DESCRIPTION "i REFERENCE -

011 Service Water (F/P HTX Discharge) 1 016 RHR Service Water 1

018 Instrument Air 1

019 Service Air 1

022 Makeup Demineralizers 027 Station Auxiliary Boiler/Auxiliary Steam I

Oil Shutdown Decay Heat Removal Service Water 3

042 Circulating Water 054 Emergency Service Water 1

086 Low Level Radwaste Handling Facility 2

Notes:

1. PLI-77223

2. Safety Evaluation NL-92-007, Rev. 2, Operation of LLRWHF at SSES

3. Safety Evaluation NL-95-001, Rev. 2 Page 1 of 1

Liquid Effluents Concentration 3.11.1.1 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.1 Liquid Effluents Concentration TRO 3.11.1.1 APPLICABILITY:

The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See FSAR Section 2.1.1.3) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.

At all times.

ACTIONS CONDITION REQWIRED ACTION COMPLETION TIME A. Concentration of Al.

Restore the concentration Immediately radioactive material to within the above released in liquid limits effluents to UNRESTRICTED AREAS (See FSAR Section 2.1.1.3) exceeds the limits specified in TRO 3.11.1.1 SUSQUEHANNA - UNIT 1 3.11-1 EFFECTIVE DATE 8/31/1998

Liquid Effluents Concentration 3.11.1.1 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.11.1.1-1. The results of pre-release analyses shall be used with the calculational methods and parameters in the ODCM to assure that the concentration at the point of release is maintained within the limits of TRO 3.11.1.1 Prior to each release TRS 3.11.1.1.2 Post release analyses of samples composited According to from batch releases shall be performed in the 0DCM accordance with Table 3.11.1.1-1. The results of the previous post-release analyses shall be used with the calculational methods and parameters in the ODCM to assure that the concentrations at the point of release were maintained within the limits of TRO 3.11.1.1 SUSQUEHANNA - UNIT I 3.11-2 EFFECTIVE DATE 8/31/1998

Liquid Effluents Concentration 3.11.1.1 TABLE 3.11.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (gCi/ml)

Batch Waste Prior to Prior to Principal Gamma 5E-7 Release Tanks Release release Emitters Each Batch Each Batch I-131 1E-6 Prior to 31 days Dissolved and 1E-5 Release

-Entrained Gases One Batch per (Gamma Emitters) month Prior to 31 days H-3 1E-5 Release Composite"a>

Each Batch Gross Alpha 1E-7 Prior to 92 days Sr-89. Sr-90 5E-8 Release Composite")

Each Batch Fe-55 1E-6

"' Minimum frequency for initiation of required analysis.

SUSQUEHANNA - UNIT 1 3.11-3 EFFECTIVE DATE 8/31/1998

Liquid Effluents Dose 3.11.1.2 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.2 Liquid Effluents Dose TRO 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each reactor unit to UNRESTRICTED AREAS shall be limited:

a.

During any calendar quarter 1.5 mrems to the total body to 5 mrems to any organ.

to less than or equal to and to less than or equal AND

b.

During any calendar year to mrems to the total body and 10 mrems to any organ.

less than or equal to 3.0 to less than or equal to APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose from Al. Prepare and submit a Within 30 days the release of Special Report to the radioactive materials Commission in liquid effluents exceeding any of the above limits N

11-j SUSQUEHANNA - UNIT I 3.11-4 EFFECTIVE DATE 8/31/1998

Liquid Effluents Dose 3.11.1.2 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.1.2.1 Determine cumulative dose contributions 31 days from liquid effluents for the current calendar quarter and the current calendar year in accordance with methodology and parameters in the ODCM SUSQUEHANNA - UNIT 1

3. 11-5 EFFECTIVE DATE 8/31/1998

Liquid Waste Treatment System I

3.11.1.3 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.3 Liquid Waste Treatment System TRO 3.11.1.3 APPLICABILITY:

The appropriate portions of the Liquid Radwaste Treatment System, as described in the ODCM, shall be OPERABLE.

Appropriate portions of the Liquid Waste Treatment System shall be used to reduce the radioactive materials in liquid effluent, prior to their discharge, when projected doses due to liquid effluent releases from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Liquid effluent Al. Prepare and submit a 30 days releases being Special Report to the discharged without Commission treatment and in excess of the TRO limit.

SUSQUEHANNA - UNIT 1 3.11-6 EFFECTIVE DATE 8/31/1998

Liquid Waste Treatment System 3.11 1.3 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.1.3.1 Project doses due to liquid releases from 31 days, each reactor unit to UNRESTRICTED AREAS in accordance with the methodology and parameters in the ODCM.

TRS 3.11.1.3.2 ------------------ NOTE-------------------

Not required to be performed if the liquid radwaste system has been utilized to process radioactive liquid during the previous 92 days Demonstrate the Liquid Radwaste (LRW) 92 days Treatment System OPERABLE by operating LRW Treatment System equipment for at least 10 minutes.

SUSQUEHANNA - UNIT I 3.11-7 EFFECTIVE DATE 8/31/1998

Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation TRO 3.11.1.4 The Radioactive Liquid Radwaste Effluent Monitoring Instrumentation channels shown in Table 3.11.1.4-1 shall be OPERABLE with their setpoints established in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of TRO 3.11.1.1.

APPLICABILITY:

At all times.

ACTIONS

---

NOTE---------------------------------------

1. Separate condition entry is allowed for each channel

2. The provisions of TRO 3.0.4 are not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Suspend the release of Immediately radioactive liquid radioactive liquid effluent monitoring effluents monitored by instrumentation the affected channel alarm/trip channels OR setpoint less A.2 Declare the channel Immediately conservative than the inoperable limits allowed by TRO 3.11.1.1__ _

(continued)

)

SUSQUEHANNA - UNIT 1 3.11-8 EFFECTIVE DATE 8/31/1998

Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Liquid Radwaste B.1 Analyze at least two Prior to releases are necessary independent samples in initiating each and Effluent Line accordance with TRO release.

Gross Radioactivity 3.11.1.1 Monitoring AND Instrumentation inoperable.

B.2 Independently determine Prior to release rates for samples initiating each analyzed per Action B.1 release.

AND B.3 Perform and independently Prior to verify discharge valve initiating each lineup release.

AND B.4 Restore monitoring 14 days instrumentation l

C. Liquid Radwaste C.1 Maintain at least one Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of releases are not in isolation valve closed securing from progress and the Gross between each-source of release or Radioactivity release and-the liquid discovery of Monitoring radwaste discharge valve.

inoperable instrumentation is instrument.

inoperable because the inoperable channel is caused by a discharge valve interlock in an off-normal condition or not functioning.

v (continued)

SUSQUEHANNA - UNIT 1 3.11-9 EFFECTIVE DATE 8/31/1998

Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Liquid Radwaste D.1 Estimate Flow Rate.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> releases are necessary during releases.

and Effluent Line or AND Cooling Tower Blowdown D.2 Restore Monitoring 30 days Flow Monitoring Instrumentation.

Instrumentation inoperable.

E. Liquid Radwaste E.1 Maintain at least one Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of releases are not in isolation valve closed, securing release progress and cooling between each source of or discovery of tower blowdown flow release and the liquid inoperable monitoring radwaste discharge valve. instrument.

instrumentation is inoperable because the inoperable channel is a discharge valve interlock in an off-normal condition or not functioning.

F. Required Action and F.1 -------- NOTE----------

Associated Completion Only applicable to Time of Conditions B.

Condition B C, D, or E not met.

Suspend release of Immediately radioactive effluents via this pathway AND F.2 Explain why the In the next inoperability was not Annual corrected in a timely Radioactive manner Effluent Release Report per TS Section 5.6 SUSQUEHANNA - UNIT 1

3. 11-10 EFFECTIVE DATE 8/31/1998

Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 TECHNICAL REQUIREMENT SURVEILLANCE

---

NOTE---------------------------------

Refer to Table 3.11.1.4-1 to determine which TRSs apply for each Monitoring Function.

SURVEILLANCE FREQUENCY TRS 3.11.1.4.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 3.11.1.4.2 Perform CHANNEL CHECK including a source Prior to check.

commencing release TRS 3.11.1.4.3 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.11.1.4.4 Perform CHANNEL CALIBRATION 24 months SUSQUEHANNA - UNIT 1

3. 11-11 EFFECTIVE DATE 8/31/1998

Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 TABLE 3.11.1.4-1 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS

1.

GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line 1

TRS 3.11.1.4.2 TRS 3.11.1.4.3 TRS 3.11.1.4.4

2.

FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1

TRS 3.11.1.4.1"(

TRS 3.11.1.4.3 TRS 3.11.1.4.4-

b. Cooling Tower Blowdown 1

TRS 3.11.1.4.1(")

TRS 3.11.1.4.3 TRS 3.11.1.4.4

(" Only required when performing batch releases.

SUSQUEHANNA - UNIT I 3.11-12 EFFECTIVE DATE 8/31/1998

Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 3.11 Radioactive Effluents 3.11.1 Liquid Effluents 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation TRO 3.11.1.5 APPLICABILITY:

The Radioactive Liquid Process Monitoring Instrumentation channels shown in Table 3.11.1.5-1 shall be OPERABLE with their setpoints established in accordance with the ODCM to ensure'the alarm will occur prior to exceeding the limits of TRO 3.11.1.1.

As specified in Table 3.11.1.5-1.

ACTIONS N

---

NOTE---------------------------------------

1. Separate condition entry is allowed for each channel

2. The provisions of TRO 3.0.4 are not applicable CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Suspend the release of Immediately Radioactive Liquid liquid effluents Process Monitoring monitored by the affected Instrumentation channel alarm/trip channels OR setpoint less A.2 Declare the channel Immediately conservative than the inoperable limits allowed by TRO 3.11.1.1.

(continued)

SUSQUEHANNA - UNIT 1 3.11-13 EFFECTIVE DATE 9/01/1998

[

Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Radioactive Liquid B.1.1 Suspend the release of 'Immediately Process Monitoring liquid effluents Instrumentation monitored by the otherwise inoperable.

affected channel.

OR B.1.2 Analyze grab samples Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for isotopic activity

-when the to the required LLDs associated for liquid effluents pathway is in (Table 3.11.1.1-1).

service AND B.2 Restore monitoring 30 days instrumentation C. Required Action and C.1 Explain why the In the next Associated Completion inoperability was not Annual Time of Conditions B corrected in a timely Radioactive not met.

manner Effluent Release Report per TS Section 5.6 D. RHR Heat Exchanger to D.1 Analyze grab samples from Prior to be drained to the the RHR Heat Exchanger draining RHR spray pond.

for isotopic activity to Heat Exchanger the required LLDs for to the spray liquid effluents (Table pond.

3.11.1.1-1).

I I

SUSQUEHANNA - UNIT 1 3.11-14 EFFECTIVE DATE 9/01/1998 I

Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 TECHNICAL REQUIREMENT SURVEILLANCE

---

NOTE-------------------------------------

Refer to Table 3.11.1.5-1 to determine which TRSs apply for each Monitoring Function.

SURVEILLANCE FREQUENCY TRS 3.11.1.5.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 3.11.1.5.2 Perform a Source Check 31 days TRS 3.11.1.5.3 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.11.1.5.4 Perform CHANNEL CALIBRATION 24 months SUSQUEHANNA - UNIT I 3.11-15 EFFECTIVE DATE 9/01/1998 l

Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 TABLE 3.11.1.5-1 RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION N

REQUIRED SURVEILLANCE FUNCTION CHANNELS APPLICABILITY REQUIREMENTS GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

1. Service Water System Effluent Line 1

(a)

TRS 3.11.1.5.1 TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4

2. Supplemental Decay Heat Removal 1

(a)

TRS 3.11.1.5.1 Service Water TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4

3. RHR Service Water System Effluent 1/Loop (b)

TRS 3.11.1.5.1 Line.

TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4 (a) System aligned through Fuel Pool Cooling Heat Exchanger. Alignment change between Service Water System Effluent Line and Supplemental Decay Heat Removal Service Water is not considered to be a change in the applicable condition.

(b) At all times SUSQUEHANNA - UNIT I

3. 11-16 EFFECTIVE DATE 9/01/1998 l

Dose Rate 3.11.2.1 3.11 Radioactive Effluents 3.11.2 Gaseous Effluents 3.11.2.1 Dose Rate TRO 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents to areas at and beyond the SITE BOUNDARY (See FSAR Section 2.1.1.3) shall be limited to the following:

I.

For Noble Gases:

A.

Less than or equal to 500 mrems/yr to the total body, and B.

Less than or equal to 3000 mrems/yr to the skin AND II.

For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days A.

Less than or equal to 1500 mrem/yr to any organ (Inhalation pathways only.)

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate(s) exceed A.1 Restore the release rate Immediately the above limits to within the above limits SUSQUEHANNA - UNIT 1 3.11-17 EFFECTIVE DATE 8/31/1998

'lo Dose Rate 3.11.2.1 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.2.1.1 Determine the dose rate due to noble See ODCM gases in gaseous effluents.

TRS 3.11.2.1.2 The dose rate due to iodine-131, iodine-See Table 133, tritium, and all radionuclides in 3.11.2.1-1 particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.11.2.1-1 SUSQUEHANNA - UNIT 1 3.11-18 EFFECTIVE DATE 8/31/1998

Dose Rate 3.11.2.1 TABLE 3.11.2.1-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS Sampling Minimum Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Analysis DtcionL)

Frequency (11Ci/ml)

A, Containment Purge Prior to each purge Prior to each Principal Noble 1E-4 Grab Sample purge Gas Gamma Emitters H-3 1E-6 B. Reactor Building 31 days")

31 days")

Principal Noble 1E-4 Vents. Turbine Grab Sample Gas Gamma Emitters Building Vents.

and SGTS H-3 1E-6 Continuouscb) Iodine 7 days(c)

I-131 IE-12 Cartridge Sample I-133 lE-10 Continuous(b) 7 days")

Principal lE-11 Particulate Gamma Particulate sample Emitters I-131 Continuous(b) 92 days Gross Alpha lE-11 Particulate Sample ComPosite Continuous(b) 92 days Sr-89. Sr-90 lE-11 Particulate sample Camposite(d)

Continuous(b)

Noble Gas Noble Gases, Gross 1E-6 Monitor Beta or Gamma (Xe-133 equivalent)

" If the iodine or particulate monitoring channel(s) is (are) inoperative, noble gas analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15X of the RATED THERMAL POWER within a 1-hour period.

(b The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with TROs 3.11.2.1.

3.11.2.2. and 3.11.2.3.

(c) Samples shall be changed at 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.

If the iodine or particulate monitoring channel(s) is (are) inoperative. 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 THERMAL POWER change exceeding 15X of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. and analyses 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 S 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.

(

Minimum frequency for initiation of required analysis.

SUSQUEHANNA - UNIT I

3. 11-19 EFFECTIVE DATE 8/31/1998

Dose - Noble Gases 3.11.2.2 3.11 Radioactive Effluents 3.11.2 Gaseous Effluents 3.11.2.2 Dose - Noble Gases TRO 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See FSAR Section 2.1.1.3) shall be limited to the following:

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 for gamma radiation and less than or for beta radiation.

or equal to 10 mrads equal to 20 mrads APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated air A.1 Prepare and submit a 30 days dose exceeds the Special Report to the limits.

Commission TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.2.2.1 Determine the cumulative dose contributions 31 days for the current calendar quarter and current calendar year for these sources in accordance with the methodology and parameters in the ODCM SUSQUEHANNA - UNIT I 3.11-20 EFFECTIVE DATE 8/31/1998

Dose - Iodine, Tritium, and Radionuclides in Particulate Form 3.11.2.3 3.11 Radioactive Effluents 3.11.2 Gaseous Effluents 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form TRO 3.11.2.3 The dose to a 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 released, from each reactor unit, to areas at and beyond the SITE BOUNDARY 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:

to any organ.

Less than-or equal to 15 mrems APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated dose A.1 Prepare and submit a 30 days from the release Special Reportnto the exceeds the limits.

Commission.,

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.2.3.1 Determine the cumulative dose contributions 31 days for the current calendar quarter and current calendar year for these sources in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT I 3.11-21 EFFECTIVE DATE 8/31/1998

LML GASEOUS RADWASTE TREATMENT SYSTEM I 3.11.2.4 3.11 Radioactive Effluents 3.11.2 -

Gaseous Effluents 3.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM I

TRO 3.11.2.4 APPLICABILITY:

The GASEOUS RADWASTE TREATMENT SYSTEM shall be OPERABLE and in operation.

When the main condenser air ejector (evacuation) system is in operation.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

GASEOUS RADWASTE A.1 Restore GASEOUS 7 days TREATMENT SYSTEM RADWASTE TREATMENT inoperable.

SYSTEM to OPERABLE status.

B.

Required Action and B.1 Prepare and submit a 30 days associated Completion Special Report to the Time not met.

Commission.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.2.4.1 Verfy GASEOUS RADWASTE TREATMENT 92 days SYSTEM to be in operation.

SUSQUEHANNA - UNIT 1 TRM /3.11-22 EFFECTIVE DATE 04/02/2002

VENTILATION EXHAUST TREATMENT SYSTEM l 3.11.2.5 3.11 Radioactive Effluents 3.11.2 - Gaseous Effluents 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM I

TRO 3.11.2.5-The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM, as described in the Offsite Dose Calculation Manual (ODCM),

shall be OPERABLE.

NOTES Appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when projected doses due to gaseous effluent releases from either reactor unit to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day period.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

VENTILATION EXHAUST A.1 Restore VENTILATION 31 days TREATMENT SYSTEM EXHAUST TREATMENT inoperable.

SYSTEM to OPERABLE status.

B.

Required Action and B.1 Prepare and submit a 30 days Associated Completion Special Report to the Time of Condition A Commission.

not met.

OR Gaseous waste being discharged without treatment and in excess of TRO limits.

SUSQUEHANNA - UNIT 1 TRM /3.11-23 EFFECTIVE DATE 04/0212002

VENTILATION EXHAUST TREATMENT SYSTEM I 3.11.2.5 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.2.5.1 Perform dose projection due to gaseous 31 days releases from each reactor unit to areas at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

TRS 3.11.2.5.2

-DENTE Not required if the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days:

Verify VENTILATION EXHAUST TREATMENT 92 days SYSTEM is OPERABLE by operating the system 210 minutes.

SUSQUEHANNA - UNIT 1 TRM /3.11-24 EFFECTIVE DATE 04/02/2002

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 3.11 Radioactive Effluents 3.11.2 Gaseous Effluents 3.11.2.6 Radioactive Gaseous Effluent Monitoring.Instrumentation TRO 3.11.2.6 APPLICABILITY:

The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.11.2.6-1 shall be OPERABLE with their setpoints established in accordance with the ODCM to ensure that the limits of Requirement 3.11:2.1 are not exceeded.

According to Table 3.11.2.6-1 ACTIONS

---

NOTE---------------------------------------

1. Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gaseous A.1 Suspend the release of Immediately effluent monitoring radioactive gaseous instrumentation effluents monitored by channel alarm/trip the affected channel setpoint less OR conservative than OR required to ensure A.2 Declare the channel-Immediately that the limits of inoperable Requirement 3.11.2.1 are not exceeded (continued)

SUSQUEHANNA - UNIT 1 3.11-25 EFFECTIVE DATE 9/01/1998

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 ACTIONS (continued)

CONDITION d

REQUIRED ACTION COMPLETION TIME B. Reactor Building B.1 Take grab samples Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Ventilation System while release is Noble Gas Activity in progress.

Monitor low range AND channel inoperable B.2 Analyze grab samples for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> isotopic activity to the of grab sample required LLDs for principal noble gas gamma emitters (Table 3.11.2.1-1).

AND B.3 Restore monitoring 30 days instrumentation.

C. Reactor Building C.1 Ensure samples are Continuously Ventilation System collected with auxiliary while release is Iodine Monitor or sampling equipment as in progress.

Particulate Monitor required by Table inoperable 3.11.2.1-1 AND C.2 Restore monitoring 30 days instrumentation D. Reactor Building D.1 Estimate flow rate.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ventilation Monitoring while release is System Effluent System AND in progress Flow Rate Monitor or D.2 Restore monitoring 30 days Sampler Flow Rate isrmnain Monitor inoperable instrumentation.

(continued)

N SUSQUEHANNA - UNIT 1 3.11-26 EFFECTIVE DATE 9/01/1998 1

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Turbine Building E.1 Verify mechanical vacuum Immediately Ventilation System pump'is not in operation.

Noble Gas Activity AND Monitor low range channel inoperable E.2 Take grab samples.

Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ANDp bwhile release is AND

-in progress E.3 Analyze grab samples for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> isotopic activity to the after sample required LLDs for the principal noble gas gamma emitters (Table 3.11.2.1-1).

AND E.4 Restore monitoring 30 days instrumentation

.F.

Turbine Building F.1 Ensure samples are Continuously Ventilation System collected with auxiliary while release is Iodine Monitor or sampling equipment as in progress Particulate Monitor required by Table inoperable 3.11.2.1-1 AND F.2 Restore monitoring 30 days instrumentation-G. Turbine Building G.1 Estimate flow rate.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ventilation Monitoring AND while release is System Effluent System in progress.

Flow Rate Monitor or G.2 Restore monitoring 30 days Sampler Flow Rate instrumentation Monitor inoperable (continued)

SUSQUEHANNA - UNIT I

3. 11-27 EFFECTIVE DATE 9/01/1998 1

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Standby Gas Treatment H.1 Take grab samples.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> System Noble Gas AND while release is Activity Monitor low in progress.

range channel inoperable H.2 Analyze grab samples for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> isotopic activity to the of grab sample required LLDs for being taken.

principal noble gas gamma emitters (Table 3.11.2.1-1).

AND H.3 Restore monitoring 30 days instrumentation.

I. Standby Gas Treatment I.1 Ensure samples are Continuously System Iodine Monitor collected with auxiliary while releases or Particulate Monitor sampling equipment as are in progress inoperable required by Table 3.11.2.1-1.

AND I.2 Restore monitoring 30 days instrumentation.

J. SGTS Ventilation J.1 Estimate flow rate.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Monitoring System AND while release is Effluent flow rate in progress.

monitor or sample flow rate monitor Inoperable.

J.2 Restore monitoring 30 days Instrumentation.

(continued)

SUSQUEHANNA - UNIT.1 3.11-28 EFFECTIVE DATE 9/.01/1998 l

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. Required Actions and K.1 Explain why this In the next

- Completion Times not

-inoperability was not Annual met for Conditions B corrected in a timely Radioactive through J.

manner.

Effluents Release Report

.per TS Section 5.6.

TECHNICAL REQUIREMENT SURVEILLANCE NOTE-----------------------------------

Refer to Table 3.11.2.6-1 to determine which TRSs apply for each Monitoring Function.

SURVEILLANCE FREQUENCY TRS 3.11.2.6.1 Perform CHANNEL CHECK 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 3.11.2.6.2 Perform CHANNEL CHECK 7 days TRS 3.11.2.6.3 Perform Source Check 31 days TRS 3.11.2.6.4 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.11.2.6.5 Perform CHANNEL CALIBRATION 24 months SUSQUEHANNA - UNIT 1 3.11-29 EFFECTIVE DATE 9/01/1998

]

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TABLE 3.11.2.6-1 (Page 1 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS

1. REACTOR BUILDING VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor At all Times 1

TRS 3.11.2.6.1 (Low Range)

TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5

b. Iodine Monitor At all Times 1

TRS 3.11.2.6.2 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5

c. Particulate Monitor At all Times 1

TRS 3.11.2.6.2 TRS 3.11:2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5

d. Effluent System Flow Rate Monitor At all Times 1

TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5

e. Sampler Flow Rate Monitor At all Times 1

TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 (continued)

SUSQUEHANNA - UNIT 1 3.11-30 EFFECTIVE DATE 9/01/1998 I

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TABLE 3.11.2.6:1 (Page 2 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE

• FUNCTION APPLICABILITY CHANNELS REQUIREMENTS

2. TURBINE BUILDING VENTILATION MONITORING SYSTEM

a. Noble Gas Activity.Monitor At all Times 1

TRS 3.11.2.6.1 (Low Range)

TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5

b. Iodine Monitor At all Times 1

TRS 3.11.2.6.2 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5 c:

Particulate Monitor At all Times 1

TRS 3.11.2.6.2 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5

d. Effluent System Flow Rate Monitor At all Times 1

TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5

e. Sampler Flow Rate Monitor At all Times 1

TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 (continued)

SUSQUEHANNA - UNIT 1 3.11-31 EFFECTIVE DATE 9/01/1998 l

Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TABLE 3.11.2.6-1 (Page 3 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS

3. STANDBY GAS TREATMENT SYSTEM (STGS)

MONITOR

a. Noble Gas Activity Monitor During 1

TRS 3.11.2.6.1 (Low Range) operation of TRS 3.11.2.6.3 SGTS TRS 3.11.2.6.4 TRS 3.11.2.6.5

b. Iodine Monitor During 1

TRS 3:11.2.6.2 operation of TRS 3.11.2.6.3 SGTS TRS 3.11.2.6.4 TRS 3.11.2.6.5

c.

Particulate Monitor During 1

TRS 3.11.2.6.2 operation of TRS 3.11.2.6.3 SGTS TRS 3.11.2.6.4 TRS 3.11.2.6.5

d. Effluent System Flow Rate Monitor During 1

TRS 3.11.2.6.1 operation of TRS 3.11.2.6.4 SGTS TRS 3.11.2.6.5

e. Sampler Flow Rate Monitor During 1

TRS 3.11.2.6.1 operation of TRS 3.11.2.6.4 SGTS TRS 3.11.2.6.5 I

IIIfII I

II II I

II Cat e, o_

,73

~W

_A9-

)

SUSQUEHANNA - UNIT 1 3.11-32 EFFECTIVE DATE 9/o1/1998 I

Total Dose 3.11.3 3.11 Radioactive Effluents 3.11.3 Total Dose TRO 3.11.3 APPLICABILITY:

The annual (calendar year) 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.

At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated doses from A.1 Initiate actions to Immediately the release of calculate whether the radioactive materials TRO limits have been in liquid or gaseous exceeded effluents exceed twice the limits of Requi rements 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b B. TRO limits exceeded B.1 Prepare and submit a 30 days Special Report to the Commission SUSQUEHANNA - UNIT 1 3.11-33 EFFECTIVE DATE 8/31/1998

Ix-Total Dose 3.11.3 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.3.1 Determine the cumulative dose from liquid 31 days and gaseous effluents in accordance with the methodology and parameters in the ODCM TRS 3.11.3.2 Determine cumulative dose contributions 12 months from direct radiation from unit operation in accordance with the methodology and parameters in the ODCM SUSQUEHANNA - UNIT I 3.11-34 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 3.11 Radioactive Effluents 3.11.4 Radiological Environmental Monitoring 3.11.4.1 Monitoring Program TRO 3.11.4.1 APPLICABILITY:

The radiological environmental monitoring program shall be conducted as specified in Table 3.11.4.1-1.

At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Report and describe the Annually environmental events and any actions monitoring program not taken to prevent their being conducted as recurrence in the Annual specified in Table Radiological 3.11.4.1-1 Environmental Operating Report B. The average level of B.1 Prepare and submit a 30 days radioactivity over any Special Report to the calendar quarter as Commission the result of an individual radionuclide in plant effluents in a particular environmental exposure pathway in a particular environmental sampling medium, at a specified location exceeds the applicable reporting level of Table 3.11.4.1-2 i~curiu rIutu k

kCTI-L] nlueU SUSQUEHANNA - UNIT 1 3.11-35 EFFECTIVE DATE 8/31/1998

Monitoring Progrram 3.11.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. More than one of the C.1 Prepare and submit a 30 days radionuclides in Table Special Report to the 3.11.4.1-2 are Commission detected in a particular envi ronmental exposure pathway at a specified monitoring location and are the result of plant effluents AND The sum of the ratios of the quarterly average activity levels to their corresponding reporting levels of each detected radionuclide, from Table 3.11.4.1-2, is

Ž 1.0 (continued)

SUSQUEHANNA - UNIT I 3.11-36 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 ArTTnkl(Z (i-nntimnipd)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more D.1 Prepare and submit a 30 days Radionuclide(s) other Special Report to the than those in Table Commission 3.11.4.1-2 are detected in a particular environmental exposure pathway at a specified location and are the result of plant effluents AND The potential annual dose to a MEMBER OF THE PUBLIC from all detected radionuclides that are the result of plant effluents is greater than or equal to the calendar year limits of TROs 3.11.1.2, 3.11.2.2 and 3.11.2.3 E. The requirements for a Special Report per Conditions B. C, or D are met, but the radionuclides that are detected are not the result of plant effluents E.1 Report and discuss the Annually reasons for not attributing idei radionuclides to effluents in thi Radiological I

Environmental O0 Report ew A<77

,A 6'

Of t t

g' S/?

C 4

A<~

=4E

?

At r,,4 1

'E

lse,

., 4

-'e."',

"4d -

SUSQUEHANNA - UNIT 1 3.11-37 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Milk or fresh leafy

---

NOTE-----------

vegetable samples are The specific locations from unavailable from one which samples were or more of the sample unavailable may then be locations required by deleted from the monitoring Table 3.11.4.1-1 program.

F.1 Identify locations for 30 days obtaining replacement samples and add them to the radiological environmental monitoring program AND F.2 Identify the cause of Annually the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report SUSQUEHANNA - UNIT I 3.11-38 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.4.1.1 Collect the radiological environmental As required by monitoring samples pursuant to Table Table 3.11.4.1-1 3.11.4.1-1 TRS 3.11.4.1.2 Analyze samples pursuant to the As required by requirements of Table 3.11.4.1-1 with Table 3.11.4.1-1 equipment meeting the detection capabilities required by Table 3.11.4.1-3 TRS 3.11.4.1.3 Determine annual cumulative potential Annually dose contributions from radionuclides detected in environmental samples in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT I 3.11-39 EFFECTIVE DATE 8/31/1998

Monitoring Program TABLE 3.11.4.1-1 (Page 1 of 3)

I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY nF ANAIYSIS FREOUENCY flF ANAl VT

1. DIRECT RADIATION 40 routine monitoring stations with two or more dosimeters or with one instrument for measuring and recording dose rate continuously placed as follows:

Quarterly Ganma dose quarterly

1.

An inner ring of stations, one in each meteorological sector, in the general area of the SITE BOUNDARY

2.

An outer ring of stations, one in each meteorological sector, in the 3 to 9 mile range from the site

3.

The balance of the stations placed in special interest areas such as population centers, nearby residences,.schools. and in 1 or 2 areas to serve as control stations AIRBORNE Radioiodine and Particulates Samples from 5 locations

a. 1 sample from close to each of the 3 SITE BOUNDARY locations (in different sectors) with the highest calculated annual average groundlevel X/Q

b. 1 sample from the vicinity of the community having one of the highest calculated annual ground level X/Q

c.

1 sample from a control location, between 15 and 30 km distant and in the least prevalent wind direction of wind blowing from the plant Continual sampler operation with sample collection weekly, or more frequently if required by dust loading Radiolodine Cannister:

I-131 Analysis weekly Particulate Sampler:

Gross Beta radio activity analysfs following filter changed: Gamma isotopic analysis of composite (by location) quarterly (continued)

(')

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 control samples, gamma isotopic analysis shall be performed on the individual samples.

SUSQUEHANNA - UNIT 1 3.11-40 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 11 TABLE 3.11.4.1-1 CPage 2 of 3)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND EXPOSURE PATHWAY SAMPLES AND COLLECTION TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS FREQUENCY OF ANALYSIS

3.

WATERBORNE

a. Surface 1 sample upstream 1 sample downstream Composite sample over one-month period-

b. Ground Samples from 1 or 2 sources only if likely to be affected Quarterly

c.

Drinking 1 sample from each of 1 to 3 of the nearest water supplies that could be affected by its discharge 1 sample from a control location Composite sample over 2-week period when I-131 analysis is performed.

monthly composite otherwise Gamma isotopic analysis monthly.

Composite for tritium analyses quarterly Gamma isotopic and tritium analyses quarterly I-131 analysis on each composite when the dose calculated for the consumption of the water is greater than I mrem per year. Composite for gross beta and gamma isotopic analyses monthly.

Composite for tritium analyses quarterly Gamma isotopic analyses semiannually (continued)

d. Sediment from chrli no 1 sample from downstream area with existing or potential recreational value Semiannually aI IV l 111#

SUSQUEHANNA - UNIT 1 3.11-41 EFFECTIVE DATE 8/31/1998

I.

Monitoring Program 3.11.4.1 TABLE 3.11.4.1-1 (Page 3 of 3) p RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS

4.

INGESTION

a. Milk

a. Samples from milking animals in 3 locations within 5km from the plant having the highest dose potential. If there are none, then, 1 sample from milking animals in each of 3 areas between 5 and 8km distant where doses are calculated to be greater than 1 mrem per year.

1 sample from milking animals at a control location (between 15 and 30km from the plant preferably in the least prevalent direction for wind blowing from the plant).

b. 1 sample of each of two recreationally important species in vicinity of plant discharge area.

1 sample of same species in areas not influenced by plant discharge.

Semimonthly when animals are on

pasture, monthly at other times.

Gamma isotopic and 1-131 analysis semimonthly when animals are on pasture: monthly at other times.

b. Fish and/or Invertebrates Sample in season, or semiannually if they are not seasonal.

At time of harvest Gamma isotopic analysis on edible portions.

c.

Food Products

c.

1 sample of each principal class of food products from any area which is irrigated by water in which liquid plant wastes have been discharged.

Samples of 3 different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

1 sample of each of the similar broad leaf vegetation grown between 15 to 30km from the plant, preferably. in the least prevalent direction for wind blowing from the plant if milk sampling is not performed.

Gamma isotopic analysis on edible portions.

Monthly when available Monthly when available Gamma isotopic and 1-131 analysis.

Gamma isotopic and 1-131 analysis.

SUSQUEHANNA - UNIT 1 3.11-42 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 TABLE 3.11.4.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Particulate Fish Milk Food Products Analysis (pCi/l) or Gases (pCi/n3)

(pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

H-3 20.000"'a 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 4 0 0 (b)

I-131 2

0.9 3

100

'Cs-134 30 10 1.000 60 1,000 Cs-137 50 20 2.000 70 2.000 Ba-La-140 200 (b) 300 For drinking water samples.

This is 40 CFR Part 141 value.

If value of 30.000 pCi/l may be used.

'--'Total for parent and daughter.

no drinking water pathway exists. a SUSQUEHANNA - UNIT 1 3.11-43 EFFECTIVE DATE 8/31/1998

Monitoring Program 3.11.4.1 TABLE 3.11.4.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Water Airborne Fish Milk Food Sediments Analysis (pCi/1)

Particulate Or (pCi/kg, wet),

(pCi/D Products (pCi/kg.

Gas (pCi/n3)

(pCi/kg, dry) wet)

Gross Beta 4

0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1i(

0.07 1

60 Cs-134 15 0.05 130 15 60 150 S

Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15

") LLD for drinking water samples.

SUSQUEHANNA - UNIT 1 3.11-44 EFFECTIVE DATE 8/31/1998

Land Use Census 3.11.4.2 3.11 Radioactive Effluents 3.11.4 Radiological Environmental Monitoring 3.11.4.2 Land Use Census TRO 3.11.4.2 A land use census shall be conducted.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Land use census A.1 Identify the new As defined by identifies a location(s) in the next the Annual location(s) which Annual Radioactive Radioactive yields a calculated Effluent and Waste Effluent and dose or dose Disposal Report Waste Disposal commitment greater Report than the values currently being calculated in Requirement 3.11.2.3 B. Land use census B.1 Add the new location(s) 30 days identifies a to the radiological location(s) that environmental monitoring yields a calculated program dose or dose AND commitment (via the same exposure pathway)

B.2 Identify the new As defined in 20 percent greater location(s) in the next Annual than at a location Annual Radioactive Radioactive from which samples are Effluent Release Report Effluent Release currently being per TS Section 5.6 Report obtained in accordance with Requirement 3.11.4.1 SUSQUERANNA - UNIT 1

3. 11-45 EFFECTIVE DATE 8/31/1998

TV Land Use Census 3.11.4.2 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.4.2.1 Conduct the land use census 12 months SUSQUEHANNA - UNIT I 3.11-46 EFFECTIVE DATE 8/31/1998

Interlaboratory Comparison Program 3.11.4.3 3.11 Radioactive Effluents 3.11.4 Radiological Environmental Monitoring 3.11.4.3 Interlaboratory Comparison Program TRO 3.11.4.3 APPLICABILITY:

Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Analyses not being A.1 Report the corrective As required performed actions taken to prevent a recurrence to the Commission TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.11.4.3.1 Include a summary of the results obtained Annually as part of the above required Interlaboratory Comparison Program in the Annual Radiological Environmental Operating Report SUSQUEHANNA - UNIT I 3.11-47 EFFECTIVE DATE 8/31/1998

Liquid Effluents Concentration B 3.11.1.1 B 3.11.1.1 Liquid Effluents Concentration BASES TRO This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration levels specified in 10 CFR Part 20.1001 to 20.2402, Appendix B.

Table 2, Column 2. The requirement provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR part 50. This limitation provides reasonable 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 of Appendix I, 10 CFR 50, to a Member of the Public and (2) restrictions authorized by 10 CFR 20.1301(e). The concentration limit for dissolved or entrained noble gases is based upon the assumptions that Xe-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This requirement does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a). This requirement applies to -the release of radioactive materials in liquid effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the-lower limits of detection (LLDs). Detailed discussion of the LLD and the other detection limits can be found in Curie, L.A., "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements."

(References 2. 3. and 4)

This section of the TRM is also part of the ODCM (Reference 2).

Actions The Actions are defined to ensure proper corrective measures are taken in response to exceeding the TRO limits.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the parameters are maintained within the TRO limits. Table 3.11.1.1-1 defines Radioactive Liquid Waste Sampling and Analysis Program.

The lower limit of detection (LLD) is defined, for purposes of these Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, (continued)

SUSQUEHANNA - UNIT 1 B 3;11-1 EFFECTIVE DATE 8/30/98

Liquid Effluents Concentration B 3.11.1.1 B 3.11.1.1 Liquid Effluents Concentration BASES TRS above system background, that will be detected with 95%

(continued) probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.

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

LW) 4.66sA E

• V

• 2.22E6

• Y

• exp(-AA)

Where:

LLD is the a priori lower limit of detection as defined above (as microcuries per unit mass or volume).

sb 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 E6 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 plant effluents is the elapsed time between the midpoint of sample collection and 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.

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 to assure representative sampling.

(continued)

SUSQUEHANNA - UNIT 1 B 3.11-2 EFFECTIVE DATE 8/30/98

Liquid Effluents Concentration B 3.11.1.1 B 3.11.1.1 Liquid Effluents Concentration BASES TRS (continued)

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144.

The dissolved and entrained-gases (gamma emitters) for which the LLD specification applies-include the following radionuclides:

Kr-85, Kr-85m. Kr-87, Kr-88, Ar-41, Xe-133, Xe-133m, Xe-135, and Xe-135m.

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 accordance with the ODCM.

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 method of sampling employed results in a specimen that is representative of the liquids released over a period no longer than the Minimum Analysis Frequency.

The Minimum Analysis Frequency as listed for the Composite Samples shall mean the minimum frequency for initiation of the required analyses, not completion of the analyses and evaluation of the results. Since the analysis involves sending the samples to an offsite laboratory and performance of involved sample preparation and wet chemical analyses, there will be a delay between initiation of the analysis and receipt of the results.

The analysis initiation shall normally be done on a calendar month for the 31 day frequency or calendar quarter for a 92 day frequency.

REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

NUREG/CR-4007, September, 1984.

4. 10 CFR Part 20.

SUSQUEHANNA - UNIT I B 3.11-3 EFFECTIVE DATE 8/30/98

Liquid Effluents Dose B 3.11.1.2 B 3.11.1.2 Liquid Effluents Dose BASES TRO This requirement is *provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Technical Requirement for Operation implements the guides set forth in Section II.A of Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking-water that are in excess of the requirements of 40 CFR 141. The dose calculation methodology and parameters in the ODCM 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 equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents, are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of 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 Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. (References 2, 3, 4, and 5)

This section of the TRM is also part of the ODCM (Reference 2).

Actions 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 liquid effluents will be kept "as low as is reasonably achievable."

The Special Report to the Commission under Action A.1 shall (continued)

N SUSQUEHANNA - UNIT I B 3.11-4 EFFECTIVE DATE 8/30/98

Liquid Effluents Dose B 3.11.1.2 B 3.11.1.2 Liquid Effluents Dose BASES ACTIONS identify the cause(s) for exceeding the limit(s) and define the (continued) 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 specified limits. This Special Report shall also include the radiological impact on finished drinking water supplies at the nearest downstream drinking water source.-

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRO limits are maintained.

REFERENCES

1. Tech Spec 5.5.4 - Radioactive Effluent Controls program

2. Tech Spec 5.5.1 - Offsite Dose Calculation Manual

3. 10 CFR Part 20

4. Regulatory Guide 1.109, 'Calculation-of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977.

5. Regulatory Guide 1.113,' 'Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"

April 1977.

SUSQUEHANNA - UNIT 1 B 3.11-5 EFFECTIVE DATE 8/30/98

Liquid Waste Treatment System B 3.11.1.3 B 3.11.1.3 Liquid Waste Treatment System BASES TRO The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

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

This Requirement implements the requirements of 10 CFR Part 50.36a. General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 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 I, 10 CFR part 50, for liquid effluents. (Reference 3)

This section of the TRM is also part of the ODCM (Reference 2).

Actions The Actions are defined to ensure proper corrective, measures are taken in response to the inoperable components.

The Special Report to the Commission under Action A.1 shall include the following:

1.

Explanation of why liquid radwaste was being discharged 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.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the system is maintained OPERABLE. OPERABILITY is demonstrated by operating the liquid radwaste treatment system equipment for at least 10 minutes.

REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2. Technical Specification 5.5.1 - ODCM.

3. 10 CFR Part 50.

SUSQUEHANNA - UNIT 1 B 3.11-6 EFFECTIVE DATE 8/30/98

Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4 B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation BASES TRO The radioactive liquid effluent instrumentation are 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 in accordance with the procedures in the ODCM (Reference 2) to ensure that the alarm/trip will occur prior to exceeding the 10 times the concentration values specified in Appendix B, Table 2, Column 2 of 10CFR20.1001 - 10CFR20.2401 (Ref. 2). The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. (Reference 4)

OPERABILITY of the radiation monitoring instrumentation requires their alarm/trip setpoints set to ensure that the limits of Requirement 3.11.1.1 are not exceeded. The-alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters described in the ODCM.

OPERABILITY of the Liquid Radwaste Effluent Line gross radioactivity monitor includes the proper functioning of the discharge valve interlocks (sample pump low flow, high radiation alarm, and radiation monitor failure).

OPERABILITY of the Cooling Tower Blowdown flow rate measurement device includes the proper functioning of the Liquid Radwaste Effluent-Line discharge valve interlock (i.e. cooling tower blowdown low flow).

The Required Channels for each function in Table 3.11.1.4-1 are as follows:

(continued)

SUSQUEHANNA - UNIT 1 B 3.11-7 EFFECTIVE DATE 8/30/98

Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4 B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation BASES TRO (continued)

a. Liquid Radwaste Effluent rad monitor (Function 1.a) one instrument per station.

b. Liquid Radwaste Effluent flow rate (Function 2.a) one instrument per station.

c. Cooling Tower Blowdown flow rate (Function 2.b) one instrument per station.

It should be noted that the radioactive liquid waste stream is diluted in the Cooling Tower blowdown line prior to entering the Susquehanna River. The setpoint for this dilution water flow is 5000 gpm from the combination of the Unit 1 blowdown, Unit 2 blowdown flow, and Spray Pond Discharge.

Options exist to ensure the requirement of one OPERABLE Cooling Tower Blowdown flow Instrument per station is met as required by Table 3.11.1.4-1, Function 2.b. As long as any one of three instruments (Unit 1 Tower, Unit 2 Tower, Total Site Blowdown) are OPERABLE and alignment of HS-06443A and HSS-01503 on panel OC301 is such that the OPERABLE instrument(s) are in the circuit, then the TRM Requirement is met.

This section of the TRM is also part of the ODCM (Reference 2).

Actions The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.

Pump curves generated in situ may be used to estimate flow for Action D.1.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the monitoring instrumentation is maintained OPERABLE.

The TRSs shall be performed in accordance with the Technical Specification definition for the test with the following additional requirements:

The Liquid Radwaste Effluent Line radiation monitor CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any (continued)

SUSQUEHANNA - UNIT I B 3.11-8 EFFECTIVE DATE 8/30/98

Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4 BASES TRS (continued) of the following conditions exist:

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

2. Circuit failure. -

3. Instrument indicates a downscale failure.

The liquid Radwaste Effluent Line radiation monitor initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using-standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used in lieu of the reference standards associated with the initial calibration.

The Liquid Radwaste Effluent Line flow rate monitor and Cooling Tower Blowdown flow rate monitor CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3. 10 CFR Part 20

4. 10 CFR Part 50 SUSQUEHANNA - UNIT 1 B 3.11-9 EFFECTIVE DATE 8/30/98

ML Radioactive Liquid Process Monitoring Instrumentation B 3.11.1.5 B 3.11.1.5 Radioactive Liquid Process Aonitoring Instrumentation BASES TRO The radioactive liquid process 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 in accordance with the procedures in the ODCM (Reference 2) to ensure that the alarm/trip will occur prior to exceeding 10 times the concentration values specified in Appendix B. Table 2. Column 2 of 10CFR20.1001 - 20.2401 (Reference 3). The OPERABILITY and use of this instrumentation is consistent with the.requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. (Reference 4)

This section of the TRM is also part of the ODCM (Reference 2).

Actions The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.

If an RHR heat exchanger and its applicable RHRSW loop are in service there is a pathway from the heat exchanger to the spray pond. If the heat exchanger and RHRSW loop are not in service (i.e.. valved-out, RHRSW pump not running, or piping drained) then a pathway does not exist.

If there is no pathway, the requirement to perform grab sampling is not applicable when the RHR Service Water System Effluent Line Radiation Monitor has been declared inoperable.

The function of pumping down the RHR heat exchanger and RHRSW system piping to the Spray Pond provides a pathway for a release of potentially radioactively contaminated water. The RHRSW system is considered an 80-10 system because a pathway to the environment from this system exists through the Spray Pond and because the system, although normally not radioactively contaminated, has the potential for becoming radioactively contaminated in the event that a leak develops across an RHR heat exchanger. Therefore, grab samples must be collected periodically when the RHRSW system radiation monitor for a particular loop is inoperable (malfunctioning) and water from that loop of the system is being returned to the Spray Pond.

Also, grab samples must be collected prior to operations in which water from the RHRSW system will be drained to the Spray Pond.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.11-10 EFFECTIVE DATE 2/01/99

Radioactive Liquid Process Monitoring Instrumentation B 3.11.1.5 BASES (continued)

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the monitoring instrumentation is maintained OPERABLE.

Performance of the.CHANNEL CHECK ensures that a gross failure of the instrument has not occurred. A CHANNEL CHECK is normally a

-comparison of the parameter indicated on;one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same-value. Significant deviations between instrument channels could an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrument continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria, which are developed by the plant staff based on an investigation of a combination of the channel instrument uncertainties. may be used to support this parameter comparison and include indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit and does not necessarily indicate the channel is inoperable.

The TRSs shall be. performed in accordance with the Technical Specification definition for the test with the following additional requirements:

The CHANNEL 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. Instrument indicates a downscale failure. and

4. Instrument controls not set in operate mode.

(continued)

SUSQUEHANNA - UNIT I TRM / B 3.11-11 EFFECTIVE DATE 04/07/2000

1l Radioactive Liquid Process Monitoring Instrumentation B 3.11.1.5 BASES (continued)

TRS (continued)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used in lieu of the reference standards associated with the initial calibration.

REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3. 10 CFR Part 20

4. 10 CFR Part 50 SUSQUEHANNA - UNIT I TRM / B 3.11-11a EFFECTIVE DATE 04/07/2000

Dose Rate B 3.11.2.1 B 3.11.2.1 Dose Rate BASES TRO This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public either within or outside the Site Boundary, in excess of the design objectives of Appendix I to 10CFR50. It provides operational flexibility for releasing gaseous effluents while satisfying section II.B and II.C design objectives of Appendix I. For individuals who may at times be within the Site Boundary, the occupancy of the individual will usually be sufficiently low to compensate for any increase in atmospheric diffusion factor above that for the Site Boundary.

The specified release rate limits restrict, at all times, the corresponding dose rates above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrem/yr to the total body or to less than or equal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an individual via the inhalation pathway to less i

than or equal to 1500 mrem/yr. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20.

(Reference 3)

This Requirement applies to the release of gaseous effluents from all reactors at the site.

This section of the TRM is also part of the ODCM (Reference 2).

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.11-12 EFFECTIVE DATE 2/01/99

"U Dose Rate B 3.11.2.1 B 3.11.2.1 Dose Rate A

BASES Actions The Actions are defined to ensure proper corrective measures are taken in response to the limits being exceeded.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the dose rates are maintained within limits.

Dose rates are determined in accordance with the methodology and parameters of the ODCM.

Table 3.11.2.1-1 defines Radioactive Gaseous Waste Sampling and Analysis Program. The lower limit of detection (LLD) is defined, for purposes of these requirement, 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:

LLD =

4.66Sb E

• V

• 2.22E6

• Y

• exp(-XAt)

Where:

LLD is the a priori lower limit of detection as defined above (as microcuries per unit mass or volume),

Sb 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 E6 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 plant effluents is the elapsed time between the midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

(continued)

N SUSQUEHANNA - UNIT 1 TRM / B 3.11-13 EFFECTIVE DATE 2/01/99

Dose Rate B 3.11.2.1 B 3.11.2.1 Dose Rate BASES TRS The value of sb used in the calculation of the LLD for a (continued) detection system shall be-based on the actual,observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E,. V. Y.

and At shall be used in the calculation.

The principal gamma emitters for which -the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133. Xe-133m, Xe-135, Xe-135m and Xe-138 for gaseous emissions and Mn-54, Fe-59. Co-58, Co-60. Zn-65, Mo-99, Cs-134. Cs-137.

Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks which are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

The design of the systems for the sampling of particulates and iodines provide for sample nozzle entry velocities which are approximately isokinetic with instack air velocities.

Gaseous particulate and iodine samples are gathered continuously, with the sample size proportional to the stack emissions: a composite gaseous sample is a combination of all the particulate filters gathered in a sampling period.

Particulate or iodine sampling required to be in continuous service will be considered to remain and have been in continuous service when its service is interrupted for a time period not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per sampling period.

For particulate and iodine sampling, this is a small fraction of the normal minimum analysis frequency.

The minimum Analysis Frequency as listed for the Composite Samples shall mean the minimum frequency for initiation of the required analyses, not completion of the analysis and evaluation of the results. Since the analysis involves sending the samples to an offsite laboratory and performance of involved sample preparation and wet chemical analyses, there will be a delay between initiation of the analysis and receipt of the results.

The analysis initiation shall normally be done on a calendar quarter for a 92 cay frequency.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.11-14 EFFECTIVE DATE 11/01/1999

Dose Rate B 3.11.2.1 X

B 3.11.2.1 Dose Rate BASES REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls Program

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3. 10CFR Part 20 SUSQUEHANNA - UNIT 1 TRM / B 3.11-15 EFFECTIVE DATE 2/01/99

Dose Rate B 3.11.2.1 B 3.11.2.1 Dose Rate BASES REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls Program

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3. 10CFR Part 20 SUSQUEHANNA - UNIT I B 3.11-15 EFFECTIVE DATE 8/30/98

Dose - Noble Gases B 3.11.2.2 B 3.11.2.2 Dose - Noble Gases BASES TRO This requirement is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.

(Reference 5) The Technical Requirement for Operation implements the guides set forth in Section II.B of Appendix I.

This section of the TRM is also part of the ODCM (Reference 2).

Actions 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 will be kept "as low as is reasonably achievable".

The Special Report required under Action A.1 shall identify the cause(s) for exceeding the limit(s) and define 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.

TRS The TRSs 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 calculation established in the ODCM 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 Effluents 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. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

(References 2. 3 and 4)

(continued)

SUSQUEHANNA - UNIT 1 B 3.11-'16 EFFECTIVE DATE 8/30/98

Dose - Noble Gases B 3.11.2.2 B 3.11.2.2 Dose - Noble Gases BASES REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program

2. Technical Specification Spec 5.5.1 - Offsite Dose Calculation Manual

3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".

Revision 1,-October 1977.

4. 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.

5. 10 CFR Part 50.

SUSQUEHANNA - UNIT 1 B 3.11-17 EFFECTIVE DATE 8/30/98

Dose - Iodine, Tritium, and Radionuclides in Particulates Form B 3.11.2.3 B 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulates Form BASES TRO This requirement is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. (Reference 5)

This section of the TRM. is also part of the ODCM (Reference 2).

Actions 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 materials in gaseous effluents will be kept" as low as is reasonably achievable."

The Special Report required under Action A.1 shall identify the cause(s) for exceeding the limit(s) and define 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.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRO limits are maintained.

The ODCM calculational methods specified in the TRSs 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 ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents 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. These equations also provide for determining the actual (continued)

SUSQEHANA

-UNI 1

B3.1-18EFFETIV DAT 8/0/9 SUSQUEHANNA - UNIT 1 B 3.11-18 EFFECTIVE DATE 8/30/98

Dose -

Iodine, Tritium, and Radionuclides in Particulates Form Dose - Iodine, Tritium. and Radionuclides in Particulates Form B 3.11.2.3 B 3.11.2.3 Dose - Iodine, Tritium. and Radionuclides in Particulates Form BASES TRS doses based upon the historical average atmospheric conditions.

(continued) The release rate Requirements for iodine-131,'iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent on the existing radionuclide pathways to man in areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radio-nuclides, 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.

(References 2, 3 and 4)

REFERENCES

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3. Regulatory Guide 1.109. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977.

4.

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.

5. 10 CFR Part 50 SUSQUEHANNA - UNIT 1 B 3.11-19 EFFECTIVE DATE 8/30/98

U GASEOUS RADWASTE TREATMENT SYSTEM B 3.11.2.4 B 3.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM l.

BASES-TRO This TRO ensures that the GASEOUS RADWASTE TREATMENT SYSTEM is OPERABLE and in operation to reduce radioactive materials in gaseous waste prior to discharge when the main condenser air ejector (evacuation) system is in operation. This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept uas low as is reasonably achievable". This TRO implements the requirements 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 11.0 of Appendix I to 10 CFR Part 50. The limits governing the use of the system were specified as a suitable fraction of the dose design objectives set forth in Sections ll.B and I.C of Appendix I, 10 CFR Part 50, for gaseous effluents (Ref. 1).

This section of the TRM is part of the Offsite Dose Calculation Manual (Ref.

2) and implements the requirements of the Radiological Effluent Controls Program (Ref. 3).

ACTIONS The ACTIONS are defined to ensure proper corrective measures are taken in response to the inoperable components.

A.1 With the GASEOUS RADWASTE TREATMENT SYSTEM inoperable, action must be taken to restore it to OPERABLE status in order to maintain radioactive releases from the main condenser as low as reasonably achievable, and in compliance with regulatory requirements. The 7 day Completion Time is reasonable to perform repairs and to maintain radioactive release objectives.

B.1 If the Required Action and Completion Time of Condition A are not met, a Special Report must be prepared and submitted to the Commission. The 30 day Completion Time is reasonable for preparation of the report. The Special Report should include the following information:

1. Identification of the inoperable equipment or subsystems and the reason for 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.

(continued)

SUSQUEHANNA - UNIT I TRM / B 3.11-20 EFFECTIVE DATE 04/02/2002

GASEOUS RAD WASTE TREATMENT SYSTEM GASEOUS RADWASTE TREATMENT SYSTEM I B 3.11.2.4 B 3.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM I

BASES -

TRS The TRSs are performed at the specified Frequency to ensure that the GASEOUS RADWASTE TREATMENT SYSTEM is maintained OPERABLE. I TRS 3.11.2.4.1 This surveillance requires verification that the GASEOUS RADWASTE TREATMENT SYSTEM is in operation when the main condenser air ejector (evacuation) system is in operation. The Frequency of 92 days is appropriate considering the performance of monthly dose projections.

REFERENCES

1.

10 CFR Part 50 l

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

/

SUSQUEHANNA - UNIT I TRM / B, 3.11-20a EFFECTIVE DATE 04/02/2002

VENTILATION EXHAUST TREATMENT SYSTEM B 3.11.2.5 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM I

BASES-TRO This TRO ensures that the appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM, as described in the Offsite Dose Calculation Manual (ODCM) are OPERABLE at all times. The TRO is modified by a Note which requires that the appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive materials in gaseous waste prior to their discharge when projected doses due to gaseous effluent releases from either reactor unit to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day period. This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept was low as reasonably achievable'. This TRO implements the requirements 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 I.D of Appendix I to 10 CFR Part 50. The limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ll.B and Il.C of Appendix I, 10 CFR Part 50, for gaseous effluents (Ref. 1).

The VENTILATION EXHAUST TREATMENT SYSTEM is comprised of the following systems, as described in the ODCM:

The Unit 1 Reactor Building filtered exhaust system, including the following filters:

1 F216A,1 F216B, IF217A,1 F217B,1 F218A,1 F218B, 1F255A, IF255B 1 F257A, IF257B,1 F258A AND 1 F258B.

The Unit 2 Reactor Building filtered exhaust system, including the following filters:

2F216A, 2F216B, 2F217A, 2F217B, 2F218A, 2F218B, 2F255A, 2F255B 2F257A, 2F257B, 2F258A AND 2F258B.

The Unit 1 Turbine Building filtered exhaust system, including the following filters:

1F157A, 1F157B, 1F158A, and 1F158B.

The Unit 2 Turbine Building filtered exhaust system, including the following filters:

2F1 57A, 2F1 57B, 2F1 58A, and 2F1 58B.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.11-21 EFFECTIVE DATE 04/02/2002

VENTILATION EXHAUST TREATMENT SYSTEM I B 3.11.2.5 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM I

~BASES TRO (continued)

The Radwaste Building filtered exhaust system, including the following filters:

I OF355A and OF355B The Radwaste Degasifier exhaust system, including the following filters:

OF372, OF373 and OF374 The Radwaste Tank Vent exhaust system, including the following filters:

OF358 and 0F359.

The S&A Hot Shop exhaust system, including the following filters:

OF716.

The Control Structure Filter Unit exhaust system, including the following filters:

OF1 34, 0F135, 0F137, OF1 38, OF140, 0F141, OF1 43, and 0F144.

This section of the TRM is part of the ODCM (Ref. 2) and implements the requirements of the Radiological Effluent Controls Program (Ref. 3).

I I

I I

I ACTIONS The ACTIONS are defined to ensure proper corrective measures are taken in response to the, inoperable components. Dose evaluations are performed when evolutions occur which result in an effluent path to the environment with some level of degraded treatment. In effect, degraded treatment renders the monthly dose projection per TRS 3.11.2.5.1 questionable. The dose evaluation is an estimated projection under the degraded conditions.

Dose evaluations should be performed under the following conditions:

1. When bypassing a treatment system (a preliminary evaluation prior to bypassing the filter and a follow-up evaluation after the bypass);

I (continued)

SUSQUEHANNA -UNIT1I TRM /B 3.11-22 EFFECTIVE DATE 04/02/2002

VENTILATION EXHAUST TREATMENT SYSTEM B 3.11.2.5 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES -

ACTIONS (continued)

2. When placing an inoperable filter train in service (a preliminary evaluation prior to starting the system and a follow-up evaluation after the system is in service; and)

3.

If a surveillance on a treatment system fails while the filter is in service; and

4.

Any other event which results in degraded treatment.

The appropriate portion of the VENTILATION EXHAUST TREATMENT SYSTEM will be declared inoperable if any of the following conditions exist:

1. Failure of a surveillance test;

2.

Broken or non-functional component which prevents the system from being run (e.g. both 100% fans or one 50% fan in the system); or

3.

Bypass or degradation of system filtration in which effluent flow continues without full treatment.

A.1 With any portion of the VENTILATION EXHAUST TREATMENT SYSTEM inoperable, action must be taken to restore it to OPERABLE status. The 31 day Completion Time is a reasonable time frame to repair the inoperable components.

B.1 If the Required Action and Completion Time of Condition A are not met, or gaseous waste is being discharged without treatment and in excess of the TRO limits, a Special Report must be prepared and submitted to the Commission. The 30 day Completion Time is reasonable for preparation of the report. The Special Report should include the following information:

Io I'

1. Identification of the inoperable equipment or subsystems and the reason for 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.

I I

I (continued)

SUSQUEHANNA - UNIT 1 TRM / B3.11-23 EFFECTIVE DATE 04/02/2002

VENTILATION EXHAUST TREATMENT SYSTEM B 3.11.2.5 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES TRS The TRSs are performed at the specified Frequency to ensure that the VENTILATION EXHAUST TREATMENT SYSTEM is maintained OPERABLE.

TRS 3.11.2.5.1 This surveillance requires that a dose projection be performed in accordance with the methodology and parameters in the ODCM. The dose projection is performed based on the most recently available effluent data.

If t is known prior to performing the dose projection that a treatment system will be out of service, and if data exists which indicates how the lack of treatment will impact effluents, these factors will be considered when performing the dose projection. The 31 day Frequency is consistent with Reference 3.

TRS 3.11.2.5.2 This surveillance verifies that the VENTILATION EXHAUST TREATMENT SYSTEM is OPERABLE by operating the system Ž10 minutes. Operation of the system for at least 10 minutes provides sufficient time to verify the appropriate parameters are within their normal operating range. The Frequency of 92 days is appropriate considering the performance of monthly dose projections.

This TRS is modified by a Note which states that the TRS is not required to be performed if the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. This allowance is appropriate because actual processing of radioactive gaseous effluents demonstrates system OPERABILITY.

REFERENCES

1. 10CFR Part 50.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

I I

SUSQUEHANNA - UNIT 1 TRM / B 3.11-23a EFFECTIVE DATE 04/02/2002

Radioactive Gaseous Effluent Monitoring Instrumentation B 3.11.2.6 B 3.11.2.6-Radioactive Gaseous Effluent Monitoring Instrumentation BASES TRO The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM (Reference 2) to ensure that the alarm/trip will occur prior to exceeding the release rate limits corresponding to dose rates above background to a member of the public at or beyond the site boundary to

• 500 mrem/yr to the total body or to < 3000 mrem/yr to the skin.

These release rate limits also restrict the corresponding thyroid dose rate above background to a child via the inhalation pathway to

• 1500 mrem/yr. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. (References 3 and 4)

OPERABILITY requires their alarm/trip setpoints set to ensure that the limits of Requirement 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.

This section of the TRM is also part of the ODCM (Reference 2).

ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.

Low range Noble Gas channel readings from the local vent monitor may be used to meet the requirement for a Noble Gas grab sample and grab sample analysis.

Noble Gas release grab samples are not required to be taken when there are no releases via that pathway. Effluent flow is to be determined by vent flow instrumentation or by a vent flow estimate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Continuous sample collection shall be on the same basis as described in the Bases for TRO 3.11.2.1 Monitoring may be interrupted for up to 30 minutes to perform particulate filter/iodine cartridge changeout required by TRM Table 3.11.2-1 without entering the TRO ACTIONS.

(continued)

SUSQUEHANNA - UNIT I TRM / B 3.1 1-24 EFFECTIVE DATE 03/21/2003

Radioactive Gaseous Effluent Monitoring Instrumentation B 3.11.2.6 B. 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation BASES TRS The TRSs are defined to be performed at the specified Frequency to ensure that the monitoring instrumentation is maintained OPERABLE.

The TRSs shall be performed in accordance with the Technical Specification definition for the test with the following additional requirements:

The CHANNEL FUNCTIONAL TEST for all noble gas activity monitors, Iodine Monitors, and Particulate Monitors shall also demonstrate that 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, and

4.

Instrument controls not set in operate mode.

The initial CHANNEL CALIBRATION for all noble gas activity monitors, Iodine Monitors, and Particulate Monitors shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION.

sources that have been related to the initial calibration may be used in lieu of'reference standards associated with the initial calibration.

Particulate or iodine sampling required to be in continuous service will be considered to remain and have been in continuous service when its service is interrupted for a period of time not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per sampling period.- For particulate and iodine sampling.

this is a small fraction of the normal minimum analysis frequency.

REFERENC

1. Technical Specification 5.5.4 - Radioactive Effluent Controls ES program

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3.

10 CFR Part 20

4. 10 CFR Part 50 SUSQUEHANNA - UNIT 1 TRM / B 3.11-25 EFFECTIVE DATE 11/01/1999

1lo Total Dose B 3.11.3 B 3.11.3 Total Dose BASES TRO This Requirement is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 CFR 18525. The Requirement requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel 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 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190. the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Reference 3 Actions The Actions are defined to ensure proper corrective measures are taken when requirements are not met.

Calculations required by Action B.1 shall include direct radiation contributions from both reactor units and from outside storage tanks to determine whether the limits of this TRO have been exceeded.

(continued)

SUSQUEHANNA - UNIT 1 B 3.11-26 EFFECTIVE DATE 8/30/98

Total Dose B 3.11.3 B 3.11.3 Total Dose BASES (continued)

ACTIONS -

(continued)

The Special Report to be issued per Action B.1 shall *define the corrective action to be taken to reduce subsequent releases, to prevent recurrence of exceeding the above limits, and include the schedule for achieving conformance with the above limits.

This Special Report shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations 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 complete.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that requirements are implemented.-

TRS 3.11.3.1 cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with TROs 3.11.1.2, 3.11.2.2, and 3.11.2.3, The direct radiation dose is determined from the results of radiation monitoring with TLDs that is conducted by the SSES REMP. The REMP TLDs are processed quarterly. There is no requirement to show compliance with the 40CFR190 dose limits more frequently than an annual basis.

Demonstration of compliance with this dose limit considers the combined dose contributions from liquid and gaseous effluents and direct radiation.

REFERENCES

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3. 40 CFR 190 SUSQUEHANNA - UNIT I B 3.11-27

- EFFECTIVE DATE 8/30/98

UIL Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES TRO The radiological environmental monitoring program required by this Requirement provides representative measurements of radiation and of radioactive materials in those environmental exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Changes to the radiological environmental monitoring program specified in Table 3.11.4.1-1 may be made based on expected SSES operation and the results of radiological environmental monitoring during SSES operation.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).

The LLDs required by Table 3.11.4.1-3 are considered optimum for routine environmental measurements in industrial laboratories. 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.

Detailed discussion 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., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

(Reference 1)

This section of the TRM is also part of the ODCM (Reference 2).

Actions The Actions are-defined to ensure proper corrective measures are taken when requirements are not met.

(continued)

SUSQUEHANNA - UNIT 1 B 3.11-28 EFFECTIVE DATE 8/30/98

Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES (continued)

ACTIONS Per Action A.1, the Annual Radiological Environmental Operating (continued)- Report shall provide a description ofthe reasons for not conducting the program as required and the plans for preventing a recurrence.

The Special Report submitted per Action B.1 shall identify the cause(s) for exceeding the limit(s) and define 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 Requirements 3.11.1.2, 3.11.2.2 and 3.11.2.3.

Include revised figure(s) and table for the ODCM reflecting the new locations for obtaining samples per Action-F.1 in the next Annual Radioactive Effluent Release Report.

TRS The TRSs are defined to be performed at the specified frequency to ensure that the requirements are implemented. Monitoring samples collected per TRS 3.11.4.1.1 shall be from the specific locations given in the table and figure in the ODCM. (Reference 2)

Table 3.11.4.1-1 Sample Locations Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in this Table and in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (Reference 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 (continued)

SUSQUEHANNA - UNIT I B 3.11-29 EFFECTIVE DATE 8/30/98

Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES (continued)

TRS period. All deviations from the sampling schedule shall be (continued) documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

I 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. Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM-reflecting the new location(s).

Direct Radiation One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered 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.

Radioiodine and Particulates -

Sampling and Collection Frequency The charcoal cartridges used in the airborne radioiodine sampling conducted as part of the radiological environmental monitoring program are designed and tested by the manufacturer to assure a high efficiency in the capture of radioiodine.

Certificates from the manufacturer of the cartridges are provided with each batch of cartridges certifying the percent retention of the radiodine for stated air flows.

Radioiodine and Particulates -

Particulate Sample: Waterborne -

Surface, Ground, Sediment: Food Products Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

Waterborne - Surface The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in the discharge line.

(continued)

SUSQUEHANNA - UNIT I B 3.11-30 EFFECTIVE DATE 8/30/98

Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES (continued) _

TRS (continued)

Waterborne - Drinking - Sampling and Collection Frequency A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity 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 samples shall be collected at time intervals that are veryshort (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

Waterborne - Ground - Samples and Sample Locations Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

Drinking Water - I-131 Analyses Calculation of the dose projected from I-131 in drinking water to determine if I-131 analyses of the water are required shall be performed for the maximum organ and age group using the methodology and parameters of the ODCM.

Food Products - Sampling and Collection Frequency 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 tuborous and root food products.

Table 3.11.4.1-3 This list does not mean that only these nuclides considered. Other peaks that are identifiable at level together with those of the above nuclides, analyzed and reported in the Annual Radiological Operating report.

are to be 95% confidence shall also be Environmental Required detection capabilities for used-for environmental measurements 4.13. (Reference 4) thermoluminescent dosimeters are given in Regulatory Guide (continued)

SUSQUEHANNA - UNIT 1 B 3.11 EFFECTIVE DATE 8/30/98

Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES (continued)

TRS (continued)

The LLD is defined, for purpose of these Requirements, 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 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD =

4.66sb EeVe2.22.Y.exp(-AI&)

Where:

LLD is the a priori lower limit of detection as defined above (as picrocuries per unit mass or volume),

Sb is the standard deviation of the background counting rate or of the countingrate 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 is the number of disintegrations per minute per picrocurie, Y is the fractional radiochemical yield, when applicable, X 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 calculation.

of E, V, Y, and At should be used in the (continued)

SUSQUEHANNA - UNIT I B 3.11-32 EFFECTIVE DATE 8/30/98

Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES (continued)

TRS (continued It should be recognized that the LLD is defined as 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, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDS unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

REFERENCES

1. HASL Procedures Manual, HASL-300 (revised annually): Curie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem.

40, 586-93 (1968): and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975)Offsite Dose Calculation Manual.

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual

3.

NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

4. Regulatory Guide 4.13 SUSQUEHANNA - UNIT 1 B 3.11-33 EFFECTIVE DATE 8/30/98

Land Use Census B 3.11.4.2 B 3.11.4.2 Land Use Census BASES TRO The Land Use Census 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 50rn (500ft 2) producing broad leaf vegetation.

This Requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial survey or consulting with local agricultural authorities or any combination of these methods 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 500 square feet 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/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

(Reference 1 and 2)

Broad leaf vegetation sampling of at least three 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 3.11.4.1-1 item 4c shall be followed, including analysis of control samples.

This section of the TRM is also part of the ODCM (Reference 3).

Actions The Actions are defined to ensure proper corrective measures are taken in when requirements are not met.

(continued)

SUSQUEHIANNA - UNIT 1 B 3.11-34 EFFECTIVE DATE 8/30/98

Land Use Census B 3.11.4.2 B 3.11.4.2 Land Use Census BASES (continued)

ACTIONS (continued)

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 the monitoring program after October 31 of the year in which the land use census was conducted.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the requirements are implemented.

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.

REFERENCES 1

10 CFR Part 50 2

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

Revision 1, October 1977 3

Technical Specification 5.5.1 - Offsite Dose Calculation Manual SUSQUEHANNA - UNIT 1 B 3.11-35 EFFECTIVE DATE 8/30/98

Interlaboratory Comparison Program B 3.11.4.3 Interlaboratory Comparison Program B 3.

11.4.3 BASES TRO The Interlaboratory Comparison Program shall be accepted by the Commission.

The requirement for participation in an Interlaboratory 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 reasonably valid for the purpose of Section IV.B.2 of Appendix I to 10 CFR Part 50. (Reference 1)

This part of the TRM is also part of the ODCM (Reference 2)

Actions The Actions are defined to ensure proper corrective measures are

-taken in response to the detection of unacceptably large deviations (systematic biases) from known values for the quantities being measured.

The corrective actions taken to prevent a recurrence shall be reported to the Commission in the Annual Radiological Environmental Operating Report.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the requirements are implemented.

REFERENCES

1. 10 CFR Part 50

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual I

SUSQUEHANNA - UNIT 1 TRM / B 3.11-36 EFFECTIVE DATE 2/12/99